Text

Submittal of Cycle No. 24 Inservice Inspection Summary Report for Inservice Inspection and ASME Section Xl Repairs and Replacements
	ML092740722
Person / Time
Site:	Monticello
Issue date:	08/07/2009
From:	O'Connor T; Northern States Power Co, Xcel Energy
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	FOIA/PA-2010-0209, L-MT-09-078
	Download: ML092740722 (200)
	v • d • e

j& XcelEnergy" August 7, 2009 L-MT-09-078 10 CFR 50.55a U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Monticello Nuclear Generating Plant Docket 50-263 Renewed Facility Operating License No. DPR-22 Cycle No. 24 Inservice Inspection Summary Report for Inservice Inspection and ASME Section Xl Repairs and Replacements Pursuant to 10 CFR 50.55a and Subsection IWA, Paragraph IWA-6240 of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section Xl, 1995 Edition, with the 1996 Addenda, the Northern States Power Company - a Minnesota corporation (NSPM), submits the Cycle No. 24 Inservice Inspection (ISI)

Summary Report for ISI and ASME Section Xl Repairs and Replacements completed between April 28, 2007, to May 10, 2009.

Pursuant to ASME Section Xl, Subsection IWB, Paragraph IWB-3144(b), evaluation analysis results are being submitted for components that were accepted for continued service in accordance with IWB-3142.4.

This summary report also provides amended information to the previously submitted Cycle Nos. 21, 22, and 23 ISI Summary Reports, including supplemental NIS-1 Forms, an NIS-1 attachment, and supplemental NIS-2 Forms. provides a copy of the Cycle No. 24 Inservice Inspection Summary Report, which includes the above discussed changes.

Summarv of Commitments I

No new commitments or changes to any existing commitments are proposed by this letter.

2807 West County Road 75 9 Monticello, Minnesota 55362-9637 Telephone: 763.295.5151 9 Fax: 763.295.1454 Aý5L~ll tMgA

Document Control Desk L-MT-09-078 Page 2 of 2 that the foregoing is true and correct.

IOYCbnnor \

'resident, Monticello Nuclear Generating Plant tates Power Company - Minnesota Enclosure cc: Administrator, Region Ill, USNRC (2 copies of enclosure)

Project Manager, Monticello, USNRC (1 copy of enclosure)

Resident Inspector, Monticello, USNRC (1 copy of enclosure)

Mr. Joel Amato, Chief Boiler Inspector, State of Minnesota (1 copy of enclosure)

Mr. Paul Fisher, Hartford Insurance (1 copy of enclosure)

ENCLOSURE I NORTHERN STATES POWER COMPANY MONTICELLO NUCLEAR GENERATING PLANT DOCKET 50-263 INSERVICE INSPECTION

SUMMARY

REPORT CYCLE NO. 24 REFUELING OUTAGE

XceI Ener-gy-Xcel Energy, Inc.

Northern States Power Co. - Minnesota 414 Nicollet Mall Minneapolis, MN 55401 INSERVICE INSPECTION

SUMMARY

REPORT Monticello Nuclear Generating Plant Unit 1 2807 West County Road 75 Monticello, MN 55362 Commercial Service Date: June 30, 1971 Report Date: August 6, 2009

Monticello Nuclear Generating Plant Cycle 24 Summary Report Inservice Inspection 2009 Refueling Outage TABLE OF CONTENTS SECTIONS PAGES I. Summary 5 1.0 Introduction 2.0 Personnel 3.0 Examination Reports, Equipment, and Materials 4.0 Inspection Summary 5.0 Abbreviations II. NIS-1 Form for Cycle 24 2 III. NIS-2 Summary for Cycle 24 4 NIS-2 Forms for Cycle 24 119 IV. New NIS- 1 Form for Cycle 23 Supplemental Information 2 V. NIS-2 Form for Cycle 23 Supplemental Information 2 NIS-1 Attachment (Appendix A) 1 VI. New NIS- I Form for Cycle 22 Supplemental Information 2 VII. NIS-2 Form for Cycle 22 Supplemental Information 2 VIII. New NIS-1 Form for Cycle 21 Supplemental Information 2 IX. NIS-2 Form for Cycle 21 Supplemental Information 2 APPENDICES PAGES A. Class 1 and 2 Examinations Summary 17 (Sorted by Class, Category, and Item No.)

B. Reactor Vessel IVVI Examination Summary 9 C. System Pressure Test Summary 1 D. Snubber Functional Testing Summary 1 E. Engineering Evaluation per Subsection IWB-3142.4

1. CAP 01177677 Indications discovered in shroud support legs 16

" Condition Evaluation (01177677-02)

" Final Documentation of SIA Evaluation (sans vendor proprietary information) (01177677-02)

Monticello Nuclear Generating Plant Cycle 24 Summary Report Inservice Inspection 2009 Refueling Outage

1. Summary Page I of 5 1.0 Introduction This report encompasses all Inservice Inspection (ISI) activities performed during Unit 1 Cycle 24 of operation at Monticello Nuclear Generating Plant (MN GP).

Cycle 24 began April 28, 2007, immediately following completion of the 23rd refueling outage. This report also includes activities performed during the 24th refueling outage that began March 14, 2009 and concluded on May 10, 2009.

All examinations and tests for Cycle 24 were scheduled and conducted in accordance with the 4th Interval ISI Plan. The exams and tests were credited to the 2nd period of the 4th ISI Interval, as applicable.

Also included in this report is supplemental information for the Cycle 23 ISI Summary Report submitted in July 2007, the Cycle 22 ISI Summary Report submitted in July 2005, and the Cycle 21 Summary Report submitted in August 2003.

2.0 Personnel Visual and nondestructive examinations for inservice inspection (ISI) and preservice inspection (PSI) activities were performed by Nuclear Management Company (NMC) / Northern States Power Company of Minnesota (NSPM),

Lambert-MacGill-Thomas (LMT), International Quality Consultants (IQC), Inc.,

TEAM, and AREVA-NP. Hartford Steam Boiler Inspection & Insurance Co. of Connecticut (HSB-CT) provided the Authorized Inspection. Personnel certification records are maintained by NSPM.

3.0 Examination Reports, Equipment and Materials The examination reports listed in the attached appendices contain references to procedures, equipment, and materials used to complete specific examinations.

Records of the reports and referenced information are maintained by NSPM.

4.0 Inspection Summary In accordance with the 4th Interval ISI Plan and approved ISI Relief Request #1, Class I and 2 piping welds were examined using methodologies applicable to Risk-Informed ISI (RI-ISI). The remainder of the components and their supports were examined per the requirements set forth in American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI.

Monticello Nuclear Generating Plant Cycle 24 Summary Report Inservice Inspection 2009 Refueling Outage

1. Summary (continued) Page 2 of 5 Comprehensive in-vessel visual inspections (IVVI) of reactor vessel internal components were conducted to ensure continued integrity of the Reactor Pressure Vessel (RPV) internals. Additionally, enhanced visual inspections (EVT-1) were performed per the recommendations set forth in Boiling Water Reactor Vessel Internals Project (BWRVIP) guideline BWRVIP-03.

Examinations performed during Cycle 24 are listed in attached appendices. Code Case N-460, which allows a reduction of examination volume coverage <10% to be considered essentially 100%, was applied to exams where coverage was reduced due to interference or part geometry. These limitations are recorded on the examination reports.

Components with exam limitations that did not meet the required coverage requirements of essentially 100% will be included in a 10CFR50.55a request for relief under separate cover.

Results of the Class 1 and 2 ISI and PSI examinations, identified conditions, and corrective actions are noted and summarized in the attached appendices. Listed anomalies were either corrected, or an engineering evaluation was performed to accept "as-is" conditions.

Results of system pressure tests and snubber functional tests performed during Cycle 24 are summarized in attached appendices.

Repair-replacement activities for Cycle 24 were performed to the requirements of 4th ISI Interval Relief Request #7 which is based on ASME Section XI, 2001 Edition with no Addenda as approved by the Nuclear Regulatory Commission (NRC). A summary of the activities and copies of the NIS-2 forms are attached to this report in the applicable appendix.

Monticello Nuclear Generating Plant Cycle 24 Summary Report Inservice Inspection 2009 Refueling Outage

1. Summary (continued) Page 3 of 5 During Cycle 24, an audit of Cycle 23's ANII activities identified an editorial error on an NIS-2 form (2007-23-0070) and an editorial error on the NIS-1 Attachment (Appendix A) submitted previously with the Cycle 23 ISI Summary Report in July 2007. This condition was identified subsequent to submittal of the Cycle 23 ISI Summary Report. As part of the corrective action process, the corrected NIS-2 form and NIS- 1 Attachment are included in this Summary Report.

Additionally, a corrective action was written against an installed safety relief valve that was determined to contain a non-conforming weld condition on an internal component (RV-2-71H with topworks s/n 194). The condition was corrected by removal of the valve during the Cycle 24 outage under work order 344394. As part of the corrective action process, the applicable NIS-2 forms from Cycle 21 and 22 are resubmitted referencing the condition.

In conclusion, based on the results of the Cycle 24 ISI activities, the integrity of the plant systems has been adequately maintained.

Monticello Nuclear Generating Plant Cycle 24 Summary Report Inservice Inspection 2009 Refueling Outage I. Summary (continued) Page 4 of 5 5.0 List of Abbreviations The Summary Report Examination Appendices contains several abbreviations identified below (plant component identifiers, and standard Section XI identifiers are not included in list):

AUG Augmented Exam Program B- Bolt (plus number identifier)

BWRVIP Boiling Water Reactor Vessel and Internals Project CA Corrective Action CAP Corrective Action Process CE Condition Evaluation CRD Control Rod Drive CRDMs CRD Mechanisms D Long Seam Downstream of Circ Weld DC / EC Design / Engineering Change DS Downstream EDG Emergency Diesel Generator EFT Emergency Filtration Train EPU Extended Power Uprate EVT Enhanced Visual Examination EDG-ESW EDG Emergency Service Water ESW Emergency Service Water FSW EFT Emergency Service Water GEO Geometry / Geometric Reflector H- Hanger (plus number identifier)

HELB High Energy Line Break ISO ISI Isometric Drawing IVVI In-Vessel Visual Inspection LS Longitudinal Seam MS Main Steam MT Magnetic Particle Examination NC Non-Code Commitment Exam NRI No Reportable Indications OE Operating Experience Pump (plus number identifier)

PM Preventative Maintenance PMT Post-Maintenance Testing PSI Pre-Service Inspection PT Liquid Penetrant Examination PEI Program Engineering Instruction RCIC Reactor Core Isolation Cooling RF Refuel RFO Refueling Outage

Monticello Nuclear Generating Plant Cycle 24 Summary Report Inservice Inspection 2009 Refueling Outage

1. Summary (continued) Page 4 of 5 5.0 List of Abbreviations (continued)

RHR = Residual Heat Removal RHRSW = RHR Service Water (common usage)

RI = Reportable Indication RPV = Reactor Pressure Vessel R/R = Repair / Replacement RSW = RHR Service Water Rx = Reactor SW = Service Water U&D = Long Seam Upstream & Downstream of Circ Weld U = Long Seam Upstream of Circ Weld US = Upstream UT = Ultrasonic Examination V- = Valve (plus number identifier)

VT = Visual Examination W- = Weld (plus number identifier)

WCR = Weld Control Record WO = Work Order

Monticello Nuclear Generating Plant Cycle 24 Summary Report Inservice Inspection 2009 Refueling Outage II. Form NIS-1 Information Page 1 of 2 Form NIS-1 Owner's Data Report for Inservice Inspections As required by the Provisions of the ASME Code Rules

1. Owner: Xcel Energy, Inc. / Northern States Power Company - Minnesota Address: 414 Nicollet Mall, Mpls, MN 55401

2. Plant: Monticello Nuclear Generating Plant Address: Monticello, MN 55362

3. Plant Unit: 1 4. Owner (Certificate of Authorization): N/A

5. Commercial Service Date: 6/30/71 6. National Board No. for Unit: N/A

7. Components Inspected:

Manufacturer Component or Manufacturer or Installer State or National Appurtenance or Installer Serial No. Province No. Board No.

Reactor Pressure Chicago Bridge B-4697 Vessel & Iron (See appendices for components inspected during the cycle)

8. Examination Dates: 04/28/2007 to 05/10/2009

9. Inspection Interval: 05/01/2003 to 05/31/2012

10. Applicable Edition of Section XI: 1995 Addenda: 1996

11. Abstract of Examinations. Include a list of examinations and a statement concerning status of work required for current interval.

0 See appendices A through E (Attached)

12. Abstract of Conditions Noted.

0 See appendices A through E (Attached)

13. Abstract of Corrective Measures Recommended and Taken.

See appendices A through E (Attached)

Monticello Nuclear Generating Plant Cycle 24 Summary Report Inservice Inspection 2009 Refueling Outage II. Form NIS-1 Information Page 2 of 2 We certify that the statements made in this report are correct and the examinations and corrective measures taken conform to the rules of the ASME Code,Section XI.

Certification of Authorization No. (if applicable) N/A Expiration Date N/A Date 20 09 Signed NSMP1/ X/CiL.. ENeIM' By Owner Section XI ISI Coordinator 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 /i /,iue f,-7 and employed by --Adarrogo 57CP'J -"

OoItfW -EIS ,F Cr" of fm-/gjru ) yCT have inspected the components described in this Owner's Report during the period 1/7 S107 to ,'v l/al , 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 measures described in this Owner'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 /vj? I/jg J A iVt I4Leb1oZS'-co Inspector's Signature National Board, State, Province, Endorsements Date At1q64f-" 6 20__7

Monticello Nuclear Generating Plant Cycle 24 Summary Report Inservice Inspection 2009 Refueling Outage III. Form NIS-2 Information Page I of 4 Cycle 24 NIS-2 Summary R/R ITEM WORK COMPONENT NUMBER DOCUMENT(S) OR SYSTEM WORK DESCRIPTION 2007-24-001 WO-141451 RV-1745 Replace existing like for like with new valve 2007-24-002 WO-331287 P-109B Replace 16 top column flange bolting during pump refurbishment 2007-24-003 WO-331287 P-1 09B Machine ID of Stuffing Box during pump refurbishment EC-1 1704 2007-24-004 WO-324875 TCV-4030A Replace existing valve 2007-24-005 WO-293778 P-1 11A, EDG-ESW Replace P-I I1A with Rebuilt Spare from stock Pump # 11

12 Recirc Pump Replacement of stuffing box cover for Recirc Pump #12 due to 2008-24-006 WO-337964 (P-200B) Stuffing seal replacement Box Cover 2008-24-008 WO-354387 A-Loop FSW pipe Reconfigure piping for future flow meter installation EC-12170 (Div-I) 2008-24-009 WO-354388 B-Loop FSW pipe Reconfigure piping for future flow meter installation EC-12170 (Div-2)

WO-354387 A-Loop FSW pipe Remove temporary blank spool pieces and replace with Krohne EC-12170 (Div-1) 3030 flow meters WO-354388 B-Loop FSW pipe Remove temporary blank spool pieces and replace with Krohne EC- 12170 (Div-2) 3030 flow meters WO-326521 SS-PS2-H2 Snubber Changeouts with rebuilt spares from stock WO-326522 SS-PS l-H3 WO-326527 SS-312-1 WO-326528 SS-312-2 WO-326530 SS-PS l-H2 2008-24-013 WO-326531 SS-6AR WO-326533 SS-306 WO-326577 SS-191 WO-326583 SS-36B WO-326584 SS-36A WO-326592 SS-560 Grind off and restore hinge pin plug seal welds for anti-rotation 2008-24-017 WO-140391 FW pin installation

Monticello Nuclear Generating Plant Cycle 24 Summary Report Inservice Inspection 2009 Refueling Outage III. Form NIS-2 Information Page 2 of 4 Cycle 24 NIS-2 Summary R/R ITEM WORK COMPONENT NUMBER DOCUMENT(S) OR SYSTEM WORK DESCRIPTION WO-356231 Spare Snubbers General R/R Plan to allow replacement of Main Cylinder, (size, s/n) Piston, Piston Rings, Piston Rod, Piston Rod Nut, and Manifold. (see NIS-2 for details of components replaced) 3 Kip, 006A 10 Kip, 403 10 Kip, 013 10 Kip, 028 10 Kip, 033 10 Kip, 035 10 Kip, 037 10 Kip, 040 10 Kip, 047 10 Kip, 054-1 10 Kip, 095 10 Kip, 171 10 Kip, 500 20 Kip, 021A 2008-24-019 20 Kip, 099 20 Kip, 105 20 Kip, 116 20 Kip, 117 20 Kip, 119 20 Kip, 120 20 Kip, 130 20 Kip, 152 20 Kip, 463 30 Kip, 020 30 Kip, 005 30 Kip, 100 30 Kip, 101 30 Kip, 468 30 Kip, 470 30 Kip, 520 130 Kip, 175 2008-24-020 WO-319050 P-111D Replaced existing bowl assembly with new spare; replaced I_ I fasteners during refurbishment.

Monticello Nuclear Generating Plant Cycle 24 Summary Report Inservice Inspection 2009 Refueling Outage III. Form NIS-2 Information Page 3 of 4 Cycle 24 NIS-2 Summary R/R ITEM WORK COMPONENT NUMBER DOCUMENT(S) OR SYSTEM WORK DESCRIPTION 2008-24-021 WO-343959 SW-1 02 Removal and restore disc to nut tackweld to permit disassembly for inspection.

2008-24-022, WO-322606 B Loop FSW Piping Replace piping and fittings upstream of ESW-31 due to MIC Rev. I thinning.

2008-24-023 WO-320292 CRDMs Change out selected drives with refurbished spares 2008-24-024 WO-320292 Cap Screws for Replace 8 cap screws for each drive listed in R/R Plan 2008-CRDMs24-023.

2008-24-025 WO-343738 CV-1728 Replacement of plug due to integral stem replacement for galling.

A-Loop, Recirc Piping REW13A-2008-24-026 WO-346874 28"-DCA, Replacement of flange associated with Decon coupon removal 2" DCA branch connection 2008-24-027 WO-354743 RV-2-71F Replace Main Stage Disc during refurbishment due to disassembly damage 2008-24-028 WO-355 11 MO- 1749 Remove tack weld in support of disassembly for stem and actuator replacement 2008-24-029, WO-374028 RHRSW Replacement of RHRSW piping and associated fittings Rev. 1 2008-24-030 WO-354410 ESW/FSW Replacement of piping and associated fittings 2008-24-031 WO-364432 Spare MS SRV Replace Main Stage Disc during refurbishment due to out of spec tolerances 2008-24-032 WO-3551 11 MO- 749 Replace studs and nuts in support of stem and actuator EC-10869 replacement WO-355111 Replace pipe clamp in support of EC-l10869 replacement of EC-10869 MO-1749 stem and actuator.

2009-24-035 SR-l05 WO-374028 SR-399 Support removal / reinstallation associated with piping SR-469 replacement in R/R Plan 2008-24-029, Rev. I 2009-24-036 WO-362738 TWH-89 Replace existing spring cans in support of EC-1 1125 for EPU EC-1 1125 WO-362738 Modified in support ofEC- 11125 for EPU. Added bumper EC- 11125 plates for additional lateral support.

2009-24-039 WO-362738 TWH-144 Replace existing spring cans in support of EC-1 1125 for EPU EC-1 1125 2009-24-040 WO-380817 RCIC Steam Temporary removal and installation of pipe due to interference with AO-2-86D work activities.

Monticello Nuclear Generating Plant Cycle 24 Summary Report Inservice Inspection 2009 Refueling Outage III. Form NIS-2 Information Page 4 of 4 Cycle 24 NIS-2 Summary R/R ITEM WORK COMPONENT NUMBER DOCUMENT(S) OR SYSTEM WORK DESCRIPTION 2009-24-041 WO-359136 MO-2036 Replaced bonnet fastener due to disassembly damage 2009-24-042 WO-344367 Primary Containment Replace 1 nut, (and 15 washer sets) for the Drywell Head due to normal wear.

2009-24-043 WO-381681 ESW Reroute piping in steam chase and condenser room for HELB.

2009-24-044 WO-380817 AO-2-86D Replace 3 studs and 20 nuts damaged during disassembly in support of valve maintenance activities 2009-24-045 WO-380817 AO-2-86D Replace downstream welded seat ring insert due to damage from flow related disc contact RHRSW-A 2009-24-046 WO-381724 SW9-18"-GF Replace RHRSW-A due to MIC thinning.

WO-383235 RHRSW-B Weld overlay (2) defective RHRSW-B in tunnel to intake and EC-14055 SW1O-18"-GF turbine building per Code Case N-661 due to MIC thinning 2009-24-048 WO-381679 Main Steam Replace defective Strain Gauges EC-91 74 2009-24-049 WO-380817 AO-2-86D Replace disc like-for-like due to flow related damage.

WO-316178 RHRSW-B Weld buildup and machining of basket strainer flange & cover EC-12841 BS-1952 sealing surfaces due to corrosion.

2009-24-051 WO-326530 Snubber Replace misplaced snubber attachment bolting PSI-H2 WO-381679 Removed surface indication identified during strain gauge 2009-24-052 W 3368Main WO-383608 Steam rpaeet replacement.

WO-381707 RHRSW-A Weld overlay defective RHRSW-A above RCIC room per EC-14055 SW9-18"-GF Code Case N-661 due to MIC thinning.

SR-451 SR-452 Shim the supports to restore the pipe-to-support clearances 2009-24-054 WO-381724 SR-453 required by the design following replacement of pipe due to SR-454 MIC thinning.

SR-455 2009-24-055, WO-381724-15/16 SW30A-3"-HF Class 3 boundary change. Previously abandoned in place Rev. 1 EC-14190 piping reclassified as non-safety.

2009-24-056 WO-344364 Rx Vessel Closure Replace potentially damaged spherical washer set like for like Head Washer set

Monticello Nuclear Generating Plant Cycle 24 Summary Report Inservice Inspection 2009 Refueling Outage III. Form NIS-2 Information NIS-2 Forms (119 pages to follow)

MONTICELLO NUCLEAR GENERATING PLANT 3613 ,E TITLE: FORM NIS-2 OWNER'S REPORT FOR Revisof 2 IREPAIR/REPLACEMENT ACTIVITY [ag 1of 2 ]

Repair/Replacement Plan No.:2007-24-001

1. Owner NSP-Minnesota, an Xcel Energy Company Date 7/20/2009 Name 414 Nicollet Mall, Minneapolis, MN 55401 Sheet 1 of 2 Address

2. Plant Monticello Nuclear Generating Plant Unit 1 Name 2807 West County Road 75, Monticello, MN 55362 WO-141451 Address Repair Organization P.O. No., Job No. etc.

3. Work Performed By NSPM/XcelEnergy Type Code Symbol Stamp n/a Company Name Authorization No. n/a 2807 West County Rd. 75, Monticello, MN 55362 Expiration Date n/a Address

4. Identification of System Core Spray (CSP), Class 2

5. (a) Applicable Construction Code B31.1 1977E/W'78AEdition/Addenda (b) Applicable Edition of Section Xl Used for Repair/Replacement Activity 2001 Edition, No Addenda (c) Applicable Section Xl Code Case(s) n/a

6. Identification of Components Corrected, ASME Code Name of Name of Manufacturer National Other Removed, or Staiped Component Manufacturer Serial No. Board No. Identification Year Built Installed YES NO RV-1745 Crosby N89658 n/a UV 2003 Removed LI [

0003 RV-1745 Crosby N89658 0004 n/a UV 2009 Installed LI E] E]

E] E]

7. Description of Work Replaced existingl valve like-for-like with new valve. Year Built is installationdate.

8. Tests Conducted: Hydrostatic EL Pneumatic LI Nominal Operating Pressure ED Exempt EL Other [] Pressure 295 psi Test Temp n/a OF 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 the number of sheets is recorded at the top of this form. (See 4 AWI-09.04.03 [ASME Section Xl Repair/Replacement Program] for further documentation guidance.)

Approval: PCR 01148046 M/asc

MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: FORM NIS-2 OWNER'S REPORT FOR Revision 5 REPAIR/REPLACEMENT ACTIVITY Page 2 of 2 Repair/Replacement Plan No.: 2007-24-001

9. Remarks (Applicable Manufacturer's Data Reports to be Attached)

Accepted valve tests from manufacturer.

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

Signed S4-cCT o,. IrSI .. X- . Date /7/2-/oC)

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 Hartford Steam Boiler Insp & Ins Company of Connecticut of Hartford, Connecticut have inspected the components described in this Owner's Report during the period 4/16 /0 7 to 7 a/ Q7 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 measures 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_ _ _ _4_&_ Commissions /v'fllf'J 4) )f4/,

,I " O i(// -c Inspector's Signature National Board, Province and Endorsements Date 7/ l/o0 M/asc

MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: FORM NIS-2 OWNER'S REPORT FOR Revision 5 I REPAIR/REPLACEMENT ACTIVITY Page 1 of 2 Repair/Replacement Plan No.:2007-24-002

1. Owner NSP-Minnesota, an Xcel Energy Company Date 7/31/2009 Name 414 Nicollet Mall, Minneapolis, MN 55401 Sheet 1 of 2 Address

2. Plant Monticello Nuclear Generating Plant Unit 1 Name 2807 West County Road 75, Monticello, MN 55362 WO-331287 Address Repair Organization P.O. No., Job No. etc.

3. Work Performed By NSPM/XcelEnergy Type Code Symbol Stamp n/a Company Name Authorization No. n/a 2807 West County Rd. 75, Monticello, MN 55362 Expiration Date n/a Address

4. Identification of System RHR Service Water (RSW), Class 3

5. (a) Applicable Construction Code B31.1 , 1977E/W'78A Edition/Addenda (b) Applicable Edition of Section XI Used for Repair/Replacement Activity 2001 Edition, No Addenda (c) Applicable Section XI Code Case(s) n/a

6. Identification of Components Corrected, ASME Code Name of Name of Manufacturer National Other Removed, or Staiped Component Manufacturer Serial No. Board No. Identification Year Built Installed YES NO Top Column Unknown n/a n/a Pump s/n 1967 removed El [

Bolts VTP-24769 Top Colum Cardinal n/a n/a Pump s/n 2007 installed El Z Bolts VTP-24769 E] El El El

7. Description of Work Replaced 16 top column bolts due to normal wear.

8. Tests Conducted: Hydrostatic El Pneumatic E] Nominal Operating Pressure El Exempt El Other El Pressure psi Test Temp OF 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 the number of sheets is recorded at the top of this form. (See 4 AWI-09.04.03 [ASME Section XI Repair/Replacement Program] for further documentation guidance.)

Approval: PCR 01148046 M/asc

MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: FORM NIS-2 OWNER'S REPORT FOR Revision 5 REPAIR/REPLACEMENT ACTIVITY Page 2 of 2 Repair/Replacement Plan No.: 2007-24-002

9. Remarks (Applicable Manufacturer's Data Reports to be Attached)

Original bolting: "Steel". New bolting: ASTM A-449 (bolts built 1988, installed2007).

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

Signed S*,

'E-'-ON I.1 o(-Oo. Date ____/_9 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 Hartford Steam Boiler Insp & Ins Company of Connecticut of Hartford, Connecticut have inspected t e components described in this Owner's Report during the period 6/1-7 /a 2 to r-/L L %

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 measures 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 Alff lq/j 4, "-'4/c,/ 2J.- -CV Inspector's Signature National Board, Province and Endorsements Date t /z Jo 7 M/asc

MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: FORM NIS-2 OWNER'S REPORT FOR Revision 5 I REPAIR/REPLACEMENT ACTIVITY Page 1 of 2 Repair/Replacement Plan No.:2007-24-003

1. Owner NSP-Minnesota, an Xcel Energy Company Date 7/31/2009 Name 414 Nicollet Mall, Minneapolis, MN 55401 Sheet 1 of 2 Address

2. Plant Monticello Nuclear Generating Plant Unit 1 Name 2807 West County Road 75, Monticello, MN 55362 WO-331287, EC-11704 Address Repair Organization P.O. No., Job No. etc.

3. Work Performed By NSPMIXcelEnergy Type Code Symbol Stamp n/a Company Name Authorization No. n/a 2807 West County Rd. 75, Monticello, MN 55362 Expiration Date n/a Address

4. Identification of System RHR Service Water (RSVIO, P-109B, Class 3

5. (a) Applicable Construction Code B31.1 1977E/W'78A Edition /Addenda (b) Applicable Edition of Section Xl Used for Repair/Replacement Activity 2001 Edition, No Addenda (c) Applicable Section Xl Code Case(s) n/a

6. Identification of Components Corrected, ASME Code Name of Name of Manufacturer National Other Removed, or Staiped Component Manufacturer Serial No. Board No. Identification Year Built Installed YES NO P-109B Worthinton Pump n/a n/a 2007 Corrected El Z Stuffina Box (Sulzer) VTP-24769 JE EW E] I]

E] E]

El EW

7. Description of Work Machine stuffing box ID for defect removal (erosion) and install ID sleeve.

8. Tests Conducted: Hydrostatic E] Pneumatic El Nominal Operating Pressure LX]

Exempt R Other L1 Pressure 230 psi Test Temp na OF 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 the number of sheets is recorded at the top of this form. (See 4 AWI-09.04.03 [ASME Section XI Repair/Replacement Program] for further documentation guidance.)

Approval: PCR 01148046 Mlasc

MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: FORM NIS-2 OWNER'S REPORT FOR Revision 5 REPAIR/REPLACEMENT ACTIVITY Page 2 of 2 Repair/Replacement Plan No.: 2007-24-003

9. Remarks (Applicable Manufacturer's Data Reports to be Attached)

Existing Stuffing Box (pressureretaining)was machined on the ID to accept a bushing (non-pressure retaining). (reference EC-1 1074) Stuffing Box re-installed.

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

Signed ,X1 Sr.Cl-nON, IS1 CooR7" Date 8A/0o1 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 Hartford Steam Boiler Insp & Ins Company of Connecticut of Hartford, Connecticut have inspected thp components described in this Owner's Report during the period 6, /2-0 1o7 to 1*r"/?/C. ,

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 measures 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 V,9'"/fW D A iA2 )VI - q o li' ef -c' Inspector's Signature National Board, Province and Endorsements Date ýF / L /of-5 M/asc

MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: FORM NIS-2 OWNER'S REPORT FOR Revision 5 1 REPAIR/REPLACEMENT ACTIVITY Page 1 of 2 Repair/Replacement Plan No.:2007-24-004

1. Owner NSP-Minnesota, an Xcel Energy Company Date 7/29/2009 Name 414 Nicollet Mall, Minneapolis, MN 55401 Sheet I of 2 Address

2. Plant Monticello Nuclear Generating Plant Unit 1 Name 2807 West County Road 75, Monticello, MN 55362 WO-324875 Address Repair Organization P.O. No., Job No. etc.

3. Work Performed By NSPM/XcelEnergy Type Code Symbol Stamp n/a Company Name Authorization No. n/a 2807 West County Rd. 75, Monticello, MN 55362 Expiration Date n/a Address

4. Identification of System Emergency Service Water (FSW), Class 3

5. (a) Applicable Construction Code B31.1 1973E/W'76A Edition /Addenda (b) Applicable Edition of Section Xl Used for Repair/Replacement Activity 2001 Edition, No Addenda (c) Applicable Section Xl Code Case(s) n/a

6. Identification of Components Corrected, ASME Code Name of Name of Manufacturer National Other Removed, or Staiped Component Manufacturer Serial No. Board No. Identification Year Built Installed YES NO TCV-4030A Penn 9405 n/a n/a 2001 Removed 13 ID TCV-4030A Johnson Controls/Penn 60-01704-1-2 n/a n/a 2008 Installed E] Z1 E] E]

_ _ _ E1

_ _ _ _ _ _ 131

7. Description of Work Replace Valve Like-for-Like

8. Tests Conducted: Hydrostatic [] Pneumatic E] Nominal Operating Pressure Exempt 1] Other 13 Pressure 68.5 psi Test Temp N/A OF 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 the number of sheets is recorded at the top of this form. (See 4 AWI-09.04.03 [ASME Section Xi RepairlReplacement Program] for further documentation guidance.)

Approval: PCR 01148046 M/asc

MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: FORM NIS-2 OWNER'S REPORT FOR Revision 5 REPAIR/REPLACEMENT ACTIVITY Page 2 of 2 Repair/Replacement Plan No.: 2007-24-004

9. Remarks (Applicable Manufacturer's Data Reports to be Attached)

Post R/R pressure test per work order PMT.

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

Signed I, Date 7//31/05 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 Hartford Steam Boiler Insp & Ins Company of Connecticut of Hartford, Connecticut have inspected the components described in this Owner's Report during the period I / )hJo1 to 7 /91 )09 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 measures 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 //J.9 3 .4A,,-T A*4lo'0 'y OZ8- (t.

Inspector's Signature National Board, Province and Endorsements Date 7:/b /ae, M/asc

MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: FORM NIS-2 OWNER'S REPORT FOR Revision 5 1 REPAIR/REPLACEMENT ACTIVITY Page 1 of 2 Repair/Replacement Plan No.:2007-24-005

1. Owner NSP-Minnesota, an Xcel Energy Company Date 7/31/2009 Name 414 Nicollet Mall, Minneapolis, MN 55401 Sheet 1 of 2 Address

2. Plant Monticello Nuclear Generating Plant Unit 1 Name 2807 West County Road 75, Monticello, MN 55362 WO-293778 Address Repair Organization P.O. No., Job No. etc.

3. Work Performed By NSPMIXcel Energy Type Code Symbol Stamp n/a Company Name Authorization No. n/a

.2807 West County Rd. 75, Monticello, MN 55362 Expiration Date n/a Address

4. Identification of System EDG Emerg. Service Water (EDG-ESW), Pump #11 (P-I1A) , Class 3

5. (a) Applicable Construction Code B31.1 I 1977E/W'78A Edition /Addenda (b) Applicable Edition of Section XI Used for Repair/Replacement Activity 2001 Edition, No Addenda (c) Applicable Section XI Code Case(s) n/a

6. Identification of Components Corrected, ASME Code Name of Name of Manufacturer National Other Removed, or Staiped Component Manufacturer Serial No. Board No. Identification Year Built Installed YES NO P-111A Johnston QD6701 n/a n/a 2004 Removed LI Z P-111A Johnston QD6702 n/a n/a 2008 Installed LI Z LI Z]

EL EL LI EL

7. Description of Work Replaced EDG-ESW Pump #11 (P-1I1A) with rebuilt spare.

8. Tests Conducted: Hydrostatic LI Pneumatic LI Nominal Operating Pressure Exempt LI Other LI Pressure 48.1 psi Test Temp n/a OF 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 the number of sheets is recorded at the top of this form. (See 4 AWI-09.04.03 [ASME Section XI Repair/Replacement Program] for further documentation guidance.)

Approval: PCR 01148046 M/asc

MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: FORM NIS-2 OWNER'S REPORT FOR Revision 5 REPAIR/REPLACEMENT ACTIVITY Page 2 of 2 Repair/Replacement Plan No.: 2007-24-005

9. Remarks (Applicable Manufacturer's Data Reports to be Attached)

System leakage test with VT-2 of dischargeflange joint and post maintenance IST was performed per the work orderPMT.

This satisfies post-repair/replacementtesting for the spare which was rebuilt under W0152929 (ref.

RIR Plan 2006-23-0022).

Pumps meet requirements of Design Change 92Q300.

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

Signed ,Sec-riLW X( (S C_09 Date L/039 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 Hartford Steam Boiler Insp & Ins Company of Connecticut of I Hartford, Connecticut have inspected the components described in this Owner's Report during the period -7//9 /d 7 to Y 13 /,J ,1 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 measures 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 "Iv HI6J ,I 4 11 L/a 4 ?-<o Inspector's Signature National Board, Province and Endorsements Date - "r(3/J I M/asc

MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: FORM NIS-2 OWNER'S REPORT FOR Revision 5 I REPAIR/REPLACEMENT ACTIVITY Page 1 of 2 Repair/Replacement Plan No.:2008-24-006

1. Owner NSP-Minnesota, an Xcel Energy Company Date 7/30/2009 Name 414 Nicollet Mall, Minneapolis, MN 55401 Sheet 1 of 2 Address

2. Plant Monticello Nuclear Generating Plant Unit 1 Name 2807 West County Road 75, Monticello, MN 55362 WO 337964 Address Repair Organization P.O. No., Job No. etc.

3. Work Performed By NSPMIXcel Energy Type Code Symbol Stamp n/a Company Name Authorization No. n/a 2807 West County Rd. 75, Monticello, MN 55362 Expiration Date n/a Address

4. Identification of System ReactorRecirculation System (REC), P-200B, Class 1

5. (a) Applicable Construction Code ASME Section III, Class C , 1965E/No Add Edition / Addenda (b) Applicable Edition of Section XI Used for Repair/Replacement Activity 2001 Edition, No Addenda (c) Applicable Section XI Code Case(s) n/a

6. Identification of Components Corrected, ASME Code Name of Name of Manufacturer National Other Removed, or Staiped Component Manufacturer Serial No. Board No. Identification Year Built Installed YES NO Stuffing Box Bingham- s/n 11N35-3 n/a Ht. 83852 2007 Removed El [

Cover Williamette Stuffing Box Sulzer p/n 5122530 n/a Ht. 238938 2009 Installed El Z Cover E] E]

El El El E]

Replace stuffing box cover on Recirc Pump 12 (P-200B) as part of seal ass'y.

7. Description of Work Stuffing box cover made in 2007 and installed in 2009.

8. Tests Conducted: Hydrostatic El Pneumatic El Nominal Operating Pressure El Exempt El Other E Pressure n/a psi Test Temp n/a OF 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 the number of sheets is recorded at the top of this form. (See 4 AWI-09.04.03 [ASME Section Xl Repair/Replacement Program] for further documentation guidance.)

Approval: PCR 01148046 M/asc

MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: FORM NIS-2 OWNER'S REPORT FOR Revision 5 REPAIR/REPLACEMENT ACTIVITY Page 2 of 2 Repair/Replacement Plan No.: 2008-24-006

9. Remarks (Applicable Manufacturer's Data Reports to be Attached)

Pressuretesting satisfied per WO 337964, successful completion of 4290-02-OCD.

No PSI or IST required.

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

Signed QC*.-TON X/ IS( Ccoob Date Z1/210)

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 Hartford Steam Boiler Insp & Ins Company of Connecticut of Hartford, Connecticut have inspected ýhe components described in this Owner's Report during the period J /-7 /0'? to /IL (d7 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 measures 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.

);:ý- 4/",1-Inspector's Signature Commissions VP /R6,f1 4jwl. Ai 'tdlJP-Cca National Board, Province and Endorsements Date 6A /02 M/asc

MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: FORM NIS-2 OWNER'S REPORT FOR Revision 5 I REPAIR/REPLACEMENT ACTIVITY Page 1 of 2 Repair/Replacement Plan No.:2008-24-008

1. Owner NSP-Minnesota, an Xcel Energy Company Date 7/30/2009 Name 414 Nicollet Mall, Minneapolis, MN 55401 Sheet I of 3 Address

2. Plant Monticello Nuclear Generating Plant Unit 1 Name 2807 West County Road 75, Monticello, MN 55362 WO 354387/EC12170 Address Repair Organization P.O. No., Job No. etc.

3. Work Performed By NSPMIXcelEnergy Type Code Symbol Stamp n/a Company Name Authorization No. n/a 2807 West County Rd. 75, Monticello, MN 55362 Expiration Date n/a Address

4. Identification of System EFT Emergency Service Water (FSW9, Division 1, Class 3

5. (a) Applicable Construction Code B31.1 , 1977E/W'78A Edition /Addenda (b) Applicable Edition of Section Xl Used for Repair/Replacement Activity 2001 Edition, No Addenda (c) Applicable Section Xl Code Case(s) na

6. Identification of Components Corrected, ASME Code Name of Name of Manufacturer National Other Removed, or Staiped Component Manufacturer Serial No. Board No. Identification Year Built Installed YES NO ESW1-4"-HBD NSP n/a n/a n/a 1983 Removed El Z ESWl-4"-HBD Xcel Energy n/a n/a n/a 2008 Installed E] Z ESW1-3"-HBD NSP n/a n/a n/a 2008 Removed El 0 ESWI-3"-HBD Xcel Energy n/a n/a n/a 2008 Installed E] 0 see subsequent sheets for additional items El El

7. Description of Work Reconfigured piping components and hangers for future flow meter installation

8. Tests Conducted: Hydrostatic E] Pneumatic El Nominal Operating Pressure Z Exempt El Other F1 Pressure 71.7 psi Test Temp n/a OF 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 the number of sheets is recorded at the top of this form. (See 4 AWI-09.04.03 [ASME Section Xl Repair/Replacement Program] for further documentation guidance.)

Approval: PCR 01148046 M/asc

MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: FORM NIS-2 OWNER'S REPORT FOR Revision 5 REPAIR/REPLACEMENT ACTIVITY Page 2 of 2 Sheet 2 of 3 Repair/Replacement Plan No.: 2008-24-008

9. Remarks (Applicable Manufacturer's Data Reports to be Attached)

In support of EC-12170, the piping system was reconfiguredin the Intake Structure and EFT Room to accept future installationof ultrasonicflow meters. This included associatedpipe, fittings,flanges, and one valve, a temporaryspoolpiece assembly, fasteners, and installationof one supportin the intake structure and two supports in the EFT Room. Performed weld visuals and NDE on welds, as applicable. Performedsystem leakage test with VT-2 at nominal system pressure. Performed a check valve open and close test (CTO/CTC) on replaced valve ESW-18.

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

Signed SECTONX iSI O Date 6509 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 Hartford Steam Boiler Insp & Ins Company of Connecticut of Hartford, Connecticut have inspected the components described in this- Owner's Report during the period 3 1/ I,)d/ to 9-/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 measures 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--A t4 -

Inspector's Signature Commissions X/19 f 6il *to,3 t-4 tj o/ut-C-C Lp 4

National Board, Province and Endorsements Date M/asc

NSP-Minnesota, an Xcel Energy Company Sheet 3 of 3 414 Nicollet Mall, Minneapolis, MN 55401 Monticello Nuclear Generating Plant - Unit 1 2807 West County Road 75, Monticello, MN 55362 Work Performed By NSPM/XcE=IEnergy R/R Plan No. 2008-24-008 System EFT-ESW(FSW), Div'.1 WO No. WO 354387 Construction Code B31.1, 1977E, W'78A Section Xl R/R Code 2001 Ed/No Add Section Xl Code Case(s) None Form NIS-2 Continuation Sheet Corrected, ASME Code Name of Name of Manufacturer National Other Removed, or Stam ped Component Manufacturer Serial No. Board No. Identification Year Built Installed Yes No ESW-18 Anchor E1241-3-5 n/a n/a 1983 Removed X Darling ESW-18 Velan 26020-001 n/a n/a 2008 Installed X 00001 Support (EFT H-I1 Room) Xcel Energy n/a n/a n/a 2008 Installed X Support H- Xcel Energy nHa n/a n/a 2008 Installed X (EFT Room) XelErgn/

Supporta Xcel Energy nHa n/a n/a 2008 Installed X (Intake) XelEegn/

28 flange Nova n/a n/a n/a 2008 Installed X studs 56 flange Nova n/a n/a n/a 2008 Installed X nuts 4 4 -I- 4 + +

4 4 + F I +/- t

MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: FORM NIS-2 OWNER'S REPORT FOR Revision 5 I REPAIR/REPLACEMENT ACTIVITY Page 1 of 2 Repair/Replacement Plan No.:2008-24-009

1. Owner NSP-Minnesota, an Xcel Energy Company Date 7/30/2009 Name 414 Nicollet Mall, Minneapolis, MN 55401 Sheet I of 3 Address

2. Plant Monticello Nuclear Generating Plant Unit 1 Name 2807 West County Road 75, Monticello, MN 55362 WO-354388, EC-12170 Address Repair Organization P.O. No., Job No. etc.

3. Work Performed By NSPM/Xcel Energy Type Code Symbol Stamp n/a Company Name Authorization No. n/a 2807 West County Rd. 75, Monticello, MN 55362 Expiration Date n/a Address

4. Identification of System EFT Emergency Service Water (FSW), Division 2, Class 3

5. (a) Applicable Construction Code B31.1 , 1977E/W'78A Edition / Addenda (b) Applicable Edition of Section XI Used for Repair/Replacement Activity 2001 Edition, No Addenda (c) Applicable Section XI Code Case(s) na

6. Identification of Components Corrected, ASME Code Name of Name of Manufacturer National Other Removed, or Staiped Component Manufacturer Serial No. Board No. Identification Year Built Installed YES NO ESW5-4"-HBD NSP na na na 1983 Removed El Z ESW5-4"-HBD Xcel Energy na na na 2008 Installed El [

ESW5-3"-HBD Velan na na na 1983 Removed E] E ESW5-3"-HBD Xcel Energy na na na 2008 Installed El ED see subsequent sheets for additional items ED ]I

7. Description of Work Reconfigured piping components and hangers for future flow meter installation

8. Tests Conducted: Hydrostatic E] Pneumatic El Nominal Operating Pressure Z Exempt El Other El Pressure 71.9 psi Test Temp n/a OF 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 the number of sheets is recorded at the top of this form. (See 4 AWI-09.04.03 [ASME Section Xl Repair/Replacement Program] for further documentation guidance.)

Approval: PCR 01148046 M/asc

MONTICELLO NUCLEAR GENERATING PLANT .3613 TITLE: FORM NIS-2 OWNER'S REPORT FOR Revision 5 I REPAIR/REPLACEMENT ACTIVITY Page 2 of 2 Sheet 2 of 3 Repair/Replacement Plan No.: 2008-24-009

9. Remarks (Applicable Manufacturer's Data Reports to be Attached)

In supportof EC- 12170, the piping system was reconfigured in the Intake Structure and EFT Room to accept future installationof ultrasonicflow meters. This included associatedpipe, fittings,flanges, and one valve, a temporary spoolpiece assembly, fasteners, installationof one support in the intake structure and one support in the EFT Room, and modification of one existing supportin the Intake Structure and one in the EFT Room. Performed weld visuals and NDE on welds, as applicable.

Performed system leakage test with VT-2 at nominal system pressure. Performeda check valve open and close test (CTO/CTC) on replaced valve ESW-17.

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

Signed s*,cmONX4 I,1 c.ooazz Date L/L/

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 Hartford Steam Boiler Insp & Ins Company of Connecticut of Hartford, Connecticut have ,inspected the components described in this Owner's Report during the period C//10-1 P- to *Y/14-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 XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures 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 //6' l6'63 Aj4 JP /V Lvo4/ a -e.

Inspector's Signature National Board, Province and Endorsements Date M/asc

NSP-Minnesota, an Xcel Energy Company Sheet 3 of 3 414 Nicollet Mall, Minneapolis, MN 55401 Monticello Nuclear Generating Plant - Unit 1 2807 West County Road 75, Monticello, MN 55362 Work Performed By NSPMIXcel Energy R/R Plan No. 2008-24-009 System EFT-ESW(FSW), Div.2 WO No. WO 354388 Construction Code B31.1. 1977E. W'78A Section Xl R/R Code 2001 Ed/No Add Section Xl Code Case(s) None Form NIS-2 Continuation Sheet Corrected, ASME Code Name of Name of Manufacturer National Other Removed, or Stamped Component Manufacturer Serial No. Board No. Identification Year Built Installed Yes No ESW-17 Anchor E1241-3-2 n/a n/a 1983 Removed X Darling ESW-17 Velan 26020-001- n/a n/a 2008 Installed X 00002 Support H-3 Xcel Energy n/a n/a n/a 2008 Installed X (EFT Room)

Support H-5 Xcel Energy n/a n/a n/a 2008 Installed X (Intake)

Support SW-1008- Xcel Energy n/a n/a n/a 2008 Corrected X H201 (Intake)

Support sw-I ol- Xcel Energy n/a n/a n/a 2008 Corrected X H208 (EFT Room) 36 flange Nova n/a n/a n/a 2008 Installed X studs 72 flange Nova n/a n/a n/a 2008 Installed X nuts

+ + + t t I I

+ I + I I I I h I I +/- I

MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: FORM NIS-2 OWNER'S REPORT FOR Revision 5 I REPAIR/REPLACEMENT ACTIVITY Page 1 of 2 Repair/Replacement Plan No.:2008-24-011

1. Owner NSP-Minnesota, an Xcel Energy Company Date 7/30/2009 Name 414 Nicollet Mall, Minneapolis, MN 55401 Sheet I of 2 Address

2. Plant Monticello Nuclear Generating Plant Unit 1 Name 2807 West County Road 75, Monticello, MN 55362 WO-354387, EC-12170 Address Repair Organization P.O. No., Job No. etc.

3. Work Performed By NSPM/XcelEnergy Type Code Symbol Stamp n/a Company Name Authorization No. n/a 2807 West County Rd. 75, Monticello, MN 55362 Expiration Date n/a Address

4. Identification of System EFT Emergency Service Water (FSW), Division 1, Class 3

5. (a) Applicable Construction Code B31.1 , 1977E/W'78A Edition /Addenda (b) Applicable Edition of Section XI Used for Repair/Replacement Activity 2001 Edition, No Addenda (c) Applicable Section XI Code Case(s) na

6. Identification of Components Corrected, ASME Code Name of Name of Manufacturer National Other Removed, or Staiped Component Manufacturer Serial No. Board No. Identification Year Built Installed YES NO ESWl-4"-HBD Xcel Energy n/a n/a n/a 2008 Removed El 2 temp soool FE-4230 Krohne A08 71338 n/a n/a 2008 Installed E] ,

ESWl-3"-HBD Xcel Energy n/a n/a n/a 2008 Removed LI [

temp spool FE-4232 Krohne A08 71473 n/a n/a 2008 Installed E] E

7. Description of Work Replace temporary flanged piping spool pieces with ultrasonicflow meters.

8. Tests Conducted: Hydrostatic El Pneumatic E] Nominal Operating Pressure Z Exempt El Other LI Pressure 69.7 psi Test Temp n/a OF 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 the number of sheets is recorded at the top of this form. (See 4 AWI-09.04.03 [ASME Section XI Repair/Replacement Program] for further documentation guidance.)

Approval: PCR 01148046 M/asc

MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: FORM NIS-2 OWNER'S REPORT FOR Revision 5 REPAIR/REPLACEMENT ACTIVITY Page 2 of 2 Repair/Replacement Plan No.: 2008-24-011

9. Remarks (Applicable Manufacturer's Data Reports to be Attached)

Replaced temporary spool pieces at 2 locations of Division I FSW system and installedKrohne UFM 3030 ultrasonicflowmeters. Work was performed in support of EC-12170.

Performeda system leakage test with VT-2 at nominal system pressureper work orderpre-operationaltesting..

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

sE CTIo. XIIS Coowj Date_ ___

Signed i gn 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 Hartford Steam Boiler Insp & Ins Company of Connecticut of Hartford, Connecticut have inspected the components described in this Owner's Report during the period -/- / to _ z_[___/0-1 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 measures 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.

),/ý 14 1444, Inspector's Signature Commissions 4.,,'6 I f , Ao'&I

, l,, fluzo -co National Board, Province and Endorsements Date M/asc

MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: FORM NIS-2 OWNER'S REPORT FOR Revision 5 I REPAIR/REPLACEMENT ACTIVITY Page 1 of 2 Repair/Replacement Plan No.:2008-24-012

1. Owner NSP-Minnesota, an Xcel Energy Company Date 7/30/2009 Name 414 Nicollet Mall, Minneapolis, MN 55401 Sheet 1 of 2 Address

2. Plant Monticello Nuclear Generating Plant Unit 1 Name 2807 West County Road 75, Monticello, MN 55362 WO-354388, EC-12170 Address Repair Organization P.O. No., Job No. etc.

3. Work Performed By NSPMIXcel Energy Type Code Symbol Stamp n/a Company Name Authorization No. n/a 2807 West County Rd. 75, Monticello, MN 55362 Expiration Date n/a Address

4. Identification of System EFT Emergency Service Water (FSW), Division 2, Class 3

5. (a) Applicable Construction Code B31.1 , 1977E/W'78A Edition /Addenda (b) Applicable Edition of Section Xl Used for Repair/Replacement Activity 2001 Edition, No Addenda (c) Applicable Section Xl Code Case(s) na

6. Identification of Components Corrected, ASME Code Name of Name of Manufacturer National Other Removed, or Staiped Component Manufacturer Serial No. Board No. Identification Year Built Installed YES NO ESW5-4"-HBD Xcel Energy n/a n/a n/a 2008 Removed LI 2 temo soool FE-4231 Krohne A08 71339 n/a n/a 2008 Installed 0I 2 ESW5-3"-HBD Xcel Energy n/a n/a n/a 2008 Removed Li Z temp SnOOl FE-4233 Krohne A08 71475 n/a n/a 2008 Installed E] E 0] El

7. Description of Work Replace temporary flanged piping spool pieces with ultrasonic flow meters.

8. Tests Conducted: Hydrostatic L] Pneumatic F1 Nominal Operating Pressure Z Exempt MI Other M] Pressure 68.9 psi TestTemp n/a OF 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 the number of sheets is recorded at the top of this form. (See 4 AWI-09.04.03 [ASME Section XI RepairlReplacement Program] for further documentation guidance.)

Approval: PCR 01148046 M/asc

MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: FORM NIS-2 OWNER'S REPORT FOR Revision 5 I REPAIR/REPLACEMENT ACTIVITY Page 1 of 2 Repair/Replacement Plan No.:2008-24-013

1. Owner NSP-Minnesota, an Xcel Energy Company Date 7/26/2009 Name 414 Nicollet Mall, Minneapolis, MN 55401 Sheet I of 4 Address

2. Plant Monticello Nuclear Generating Plant Unit 1 Name 2807 West County Road 75, Monticello, MN 55362 (see attachedpages for applicable Work Orders)

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

3. Work Performed By NSPM/Xcel Energy Type Code Symbol Stamp n/a Company Name Authorization No. n/a 2807 West County Rd. 75, Monticello, MN 55362 Expiration Date n/a Address

4. Identification of System (see attachedpages for applicable systems and Class)

5. (a) Applicable Construction Code USAS B31.1 1967E/No Add Edition I Addenda (b) Applicable Edition of Section Xl Used for Repair/Replacement Activity 2001 Edition, No Addenda (c) Applicable Section Xl Code Case(s) n/a

6. Identification of Components Corrected, ASME Code Name of Name of Manufacturer National Other Removed, or Staiped Component Manufacturer Serial No. Board No. Identification Year Built Installed YES NO SEE ATTACHED PAGES - E]- 0i El s E

7. Description of Work Removed existing snubbers for seal life program, replaced with rebuilt spares.

8. Tests Conducted: Hydrostatic ED Pneumatic EI Nominal Operating Pressure El Exempt El Other Li Pressure psi Test Temp OF 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 the number of sheets is recorded at the top of this form. (See 4 AWI-09.04.03 [ASME Section Xi Repair/Replacement Program] for further documentation guidance.)

Approval: PCR 01148046 M/asc

MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: FORM NIS-2 OWNER'S REPORT FOR Revision 5 REPAIR/REPLACEMENT ACTIVITY Page 2 of 2 Repair/Replacement Plan No.: 2008-24-012

9. Remarks (Applicable Manufacturer's Data Reports to be Attached)

Replaced temporary spool pieces at 2 locations of Division 2 FSW system and installed Krohne UFM 3030 ultrasonicflowmeters. Work was performed in support of EC-12170.

Performeda system leakage test with VT-2 at nominal system pressureper work orderpre-operationaltesting..

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

Signed SecXTtVN KI . : ki Date e//s o 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 Hartford Steam Boiler Insp & Ins Company of Connecticut of Hartford, Connecticut have inspected the components described in this Owner's Report during the period J--/y / d/ to K /-- JJ) 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 measures 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.

141,ý t4A4-k)

Inspector's Signature Commissions Z.16 I6 /)6] 9C /1/, o itdl X-co 4</,

National Board, Province and Endorsements Date M/asc

MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: FORM NIS-2 OWNER'S REPORT FOR Revision 5 REPAIR/REPLACEMENT ACTIVITY Page 2 of 2 Sheet 2 of 4 Repair/Replacement Plan No.: 2008-24-013

9. Remarks (Applicable Manufacturer's Data Reports to be Attached)

Functionaltesting per procedure 0251. Preservice VT-3 examination of non-exempt snubbers per procedure 4903.

"Year Built" is the installationdate.

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

Signed 5ECT 1 $er-oRX) 1St ISI ::OVM 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 Hartford Steam Boiler Insp & Ins Company of Connecticut of Hartford, Connecticut have inspected the components described in this Owner's Report during the period 7 /l*JJ O- to -7 / Z 7 J YJ ,

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 measures 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 ),44 14 1. tJk1)qo /oafgf-c Ifi(J? A.,i Inspector's Signature National Board, Province and Endorsements Date 7 /?_7 /0~

M/asc

NSP-Minnesota, an Xcel Energy Company Sheet 3 of 4 414 Nicollet Mall, Minneapolis, MN 55401 Monticello Nuclear Generating Plant - Unit 1 2807 West County Road 75, Monticello, MN 55362 Work Performed By NSPMIXcel Energy R/R Plan No. 2008-24-013 System SNB, Snubbers WO No. Various (see below)

Construction Code USAS B31.1, 1967 Section Xl R/R Code 2001 Ed/No Add Section XI Code Case(s) None Form NIS-2 Continuation Sheet Name of Other Corrected, ASME Code Component Name of Manufacturer National Identification Removed, or Stai ed (System, Class) Manufacturer Serial No. Board No. (Work Order) Year Built Installed Yes No PS2-H2 Bergen 516 n/a 30 Kip 2000 removed X (MST, 1) Paterson -(326521)

PS2-H2 Bergen 005 n/a 30 Kip 2009 installed X (MST, 1) Paterson (326521)

PSI-H3 Bergen 192 n/a 30 Kip 2000 removed X (MST, 1). Paterson (326522)

PS1-H3 Bergen 020 n/a 30 Kip 2009 installed X (MST, 1) Paterson (326522)

SS-312-1 Bergen 522 n/a 30 Kip 2000 removed X (RHR, 2) Paterson (326527)

SS-312-1 Bergen 100 n/a 30 Kip 2009 installed X (RHR, 2) Paterson (326527)

SS-312-2 Bergen 518 n/a 30 Kip 2000 removed x (RHR, 2) Paterson (326528)

SS-312-2 Bergen 101 n/a 30 Kip 2009 installed X (RHR, 2) Paterson (326528)

PS1-H2 Bergen 052 n/a 30 Kip 2000 removed X (MST, 1) Paterson (326530)

PSI-H2 Bergen 145 n/a 30 Kip 2009 installed . X (MS T, 1) Paterson (326530)

SS-6AR Bergen 464 n/a 20 Kip 2000 removed X (REC, 1) Paterson (326531)

SS-6AR Bergen 021A n/a 20 Kip 2009 installed X (REC, 1) Paterson (326531)

SS-306 Bergen 517 n/a 30 Kip 2000 removed X (RHR, 2) Paterson (326533)

SS-306 Bergen 468 n/a 30 Kip 2009 installed X (RHR, 2) Paterson (326533)

SS-191 Bergen 112 *n/a 20 Kip 2000 removed X (PCT,2) Paterson (326577)

SS-191 Bergen 099 n/a 20 Kip 2009 installed X (PCT,2) Paterson (326577)

NSP-Minnesota, an Xcel Energy Company Sheet 4 of 4 414 Nicollet Mall, Minneapolis, MN 55401 Monticello Nuclear Generating Plant - Unit 1 2807 West County Road 75, Monticello, MN 55362 Work Performed By NSPM/XcelEnerqy R/R Plan No. 2008-24-013.

System SNB, Snubbers WO No. Various (see below)

Construction Code USAS B31.1, 1967 Section XI R/R Code 2001 Ed/No Add Section Xl Code Case(s) None Form NIS-2 Continuation Sheet Name of Other Corrected, ASME Code Component Name of Manufacturer National Identification Removed, or Stamped (System, Class) Manufacturer Serial No. . Board No. (Work Order) Year Built Installed Yes No SS-36B Bergen 508 n/a 10 Kip 2000 removed x (HPC, 2) Paterson (326583)

SS-36B Bergen 013 n/a 10 Kip 2009 installed X (HPC, 2) Paterson (326583)

SS-36A Bergen 509 n/a 10 Kip 2000 removed X (HPC, 2) Paterson (326584)

SS-36A Bergen 028 n/a 10 Kip 2009 installed X (HPC,2) Paterson (326584)

SS-560 Bergen 486 n/a 10 Kip 2000 removed X (RHR, 2) Paterson (326592)

SS-560 Bergen 047 n/a 10 Kip 2009 installed X (RHR, 2) Paterson (326592)

+ 4 +/- 4 4

MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: FORM NIS-2 OWNER'S REPORT FOR Revision 5 REPAIR/REPLACEMENT ACTIVITY Page 1 of 2 Repair/Replacement Plan No.:2008-24-017

1. Owner NSP-Minnesota, an Xcel Energy Company Date 7/20/2009 Name 414 Nicollet Mall, Minneapolis, MN 55401 Sheet I of 2 Address

2. Plant Monticello Nuclear Generating Plant Unit 1 Name 2807 West County Road 75, Monticello, MN 55362 WO-140391 Address Repair Organization P.O. No., Job No. etc.

3. Work Performed By NSPM/XcelEnergy Type Code Symbol Stamp n/a Company Name Authorization No. n/a 2807 West County Rd. 75, Monticello, MN 55362 Expiration Date n/a Address

4. Identification of System Condensate and Feedwater(CFW), Class I

5. (a) Applicable Construction Code B31.1 1977/'78 Edition / Addenda (b) Applicable Edition of Section Xl Used for Repair/Replacement Activity 2001 Edition, No Addenda (c) Applicable Section Xl Code Case(s) n/a

6. Identification of Components Corrected, ASME Code Name of Name of Manufacturer National Other Removed, or Staiped Component Manufacturer Serial No. Board No. Identification Year Built Installed YES NO FW-97-1 Anchor Darling 14-SPN-218U n/a none unknown Corrected El E

___ El

_ E]

E] El

. Ip f v I I El El

7. Description of Work Removed hinge pin plugs to install anti-rotation pin and reinstalled by welding.

8. Tests Conducted: Hydrostatic El Pneumatic El Nominal Operating Pressure nl Exempt Z Other El Pressure psi Test Temp OF 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 the number of sheets is recorded at the top of this form. (See 4 AWI-09.04.03 [ASME Section XI Repair/Replacement Program] for further documentation guidance.)

Approval: PCR 01148046 M/asc

MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: FORM NIS-2 OWNER'S REPORT FOR Revision 5 REPAIR/REPLACEMENT ACTIVITY Page 2 of 2 Repair/Replacement Plan No.: 2008-24-017

9. Remarks (Applicable Manufacturer's Data Reports to be Attached)

None.

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

Signed t*,c--i*Ei:z e- ScnoXl",J ISE1 0oo0- Date "1/2W/09 Owner or OwIner'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 Hartford Steam Boiler Insp & Ins Company of Connecticut of Hartford, Connecticut have inspected the components described in this Owner's Report during the period __ z__t./_ _ to ,',

"7/12/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 measures 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.

Iset 4-4 oA aur Commissions J/*//t( 3 /9)AL'ýt /It k/ ao0 ta2,--co Inspector's Signature National Board, Province and Endorsements Date ,7/-3 Id M/asc

MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: FORM NIS-2 OWNER'S REPORT FOR Revision 5 I REPAIR/REPLACEMENT ACTIVITY Page 1 of 2 Repair/Replacement Plan No. :2008-24-019

1. Owner NSP-Minnesota, an Xcel Energy Company Date 7/23/2009 Name 414 Nicollet Mall, Minneapolis, MN 55401 Sheet I of 9 Address

2. Plant Monticello Nuclear Generating Plant Unit 1 Name 2807 West County Road 75, Monticello, MN 55362 WO-356231 Address Repair Organization P.O. No., Job No. etc.

3. Work Performed By NSPMIXcelEnergy Type Code Symbol Stamp n/a Company Name Authorization No. n/a 2807 West County Rd. 75, Monticello, MN 55362 Expiration Date n/a Address

4. Identification of System SNB, Spare Snubbers, Class unassigned

5. (a) Applicable Construction Code USAS B31.1 1967E/No Add Edition / Addenda (b) Applicable Edition of Section Xl Used for Repair/Replacement Activity 2001 Edition, No Addenda (c) Applicable Section Xl Code Case(s) n/a

6. Identification of Components Corrected, ASME Code Name of Name of Manufacturer National Other Removed, or Staiped Component Manufacturer Serial No. Board No. Identification Year Built Installed YES NO Main Cylinder Bergen Paterson 005A n/a 3 Kip unknown Removed El 0 Main Cylinder Anchor/Darling 005A n/a 3 Kip 2008 Installed [] Z Valve Bergen 005A n/a 3 Kip unknown Removed E] M Assembly Paterson Valve Anchor/Darling 005A n/a 3 Kip Assembly'I 2008 Installed E] Z SEE SUBSEQUENT SHEETS FOR ADDITIONAL ITEMS El El Individual components replaced during rebuild of spare Bergen-Paterson

7. Description of Work snubbers for 2009 RFO.

8. Tests Conducted: Hydrostatic El Pneumatic E] Nominal Operating Pressure E]

Exempt El Other El Pressure psi Test Temp OF 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 the number of sheets is recorded at the top of this form. (See 4 AWI-09.04.03 [ASME Section Xl RepairlReplacement Program] for further documentation guidance.)

Approval: PCR 01148046 M/asc

MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: FORM NIS-2 OWNER'S REPORT FOR Revision 5 REPAIR/REPLACEMENT ACTIVITY Page 2 of 2 Sheet 2 of 9 I Repair/Replacement Plan No.: 2008-24-019

9. Remarks (Applicable Manufacturer's Data Reports to be Attached)

Functionaltest per procedure 0251.

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

Signed S X(I sCoo1, Date 71a3/2*

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 Hartford Steam Boiler Insp & Ins Company of Connecticut of Hartford, Connecticut have inspected the components described in this Owner's Report during the period ff" I . / 0&

. to 71 L/ /01 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 measures 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.

___ /"_k,

__A Commissions V/,K' ,IT Aj," 4' , o L C0 Inspector's Signature National Board, Pr6vince and Endorsements Date 7/U l ( J oI M/asc

NSP-Minnesota, an Xcel Energy Company Sheet 3 of 9 414 Nicollet Mall, Minneapolis, MN 55401 Monticello Nuclear Generating Plant - Unit 1 2807 West County Road 75, Monticello, MN 55362 Work Performed By NSPM/XcelEnerqy R/R Plan No. 2008-24-019 System SNB, Spare Snubbers WO No. 356231 Construction Code USAS B31.1, 1967 Section Xl R/R Code 2001 Ed/No Add Section Xl Code Case(s) None Form NIS-2 Contin uation Sheet Corrected, ASME Code Name of Name of Manufacturer National Other Removed, or Stai ped Component Manufacturer Serial No. Board No. Identification Year Built Installed Yes No Valve Bergen 006A n/a 3 Kip unknown removed X Assembly Paterson Valve Anchor 006A n/a 3 Kip 2008 installed X Assembly Darling Valve Bergen 403 n/a 10 Kip unknown removed X Assembly Paterson Valve Anchor 403 n/a 10 Kip 2008 installed X Assembly Darling Main Bergen 013 n/a 10 Kip unknown removed X Cylinder Paterson Main Anchor 013 n/a 10 Kip 2008 installed X Cylinder Darling Valve Bergen 013 n/a 10 Kip unknown removed X Assembly Paterson Valve Anchor 013 n/a 10 Kip 2008 installed X Assembly Darling Valve Bergen 028 n/a 10 Kip unknown removed X Assembly Paterson Valve Anchor 028 n/a 10 Kip 2008 installed X Assembly Darling Piston Rod Bergen 028 n/a 10 Kip unknown removed X Nut Paterson Piston Rod Bergen 028 n/a 10 Kip 2008 installed X Nut Paterson Piston Bergen 028 n/a 10 Kip unknown removed X Paterson Piston Anchor 028 n/a 10 Kip 2008 installed X Darling Piston Bergen 028 n/a 10 Kip unknown removed X Rings Paterson Piston Anchor 028 n/a 10 Kip 2008 installed X Rings Darling

NSP-Minnesota, an Xcel Energy Company Sheet 4 of 9 414 Nicollet Mall, Minneapolis, MN 55401 Monticello Nuclear Generating Plant - Unit 1 2807 West County Road 75, Monticello, MN 55362 Work Performed By NSPMIXcelEnergy R/R Plan No. 2008-24-019 System SNB, Spare Snubbers WO No. 356231 Construction Code USAS B31.1, 1967 Section XI R/R Code 2001 Ed/No Add Section Xl Code Case(s) None Form NIS-2 Contin uation Sheet Corrected, ASME Code Name of Name of Manufacturer National Other Removed, or Stam ped Component Manufacturer Serial No. Board No. Identification Year Built Installed Yes No Main Bergen 028 n/a 10 Kip unknown removed X Cylinder Paterson Main Anchor 028 n/a 10 Kip 2008 installed X Cylinder Darling Valve Bergen 033 n/a 10 Kip unknown removed X Assembly Paterson Valve Anchor 033 n/a 10 Kip 2008 installed X Assembly Darling Valve Bergen 035 n/a 10 Kip unknown removed X Assembly Paterson Valve Anchor 035 n/a 10 Kip 2008 installed X Assembly Darling Valve Bergen 037 n/a 10 Kip unknown removed X Assembly Paterson Valve Anchor 037 n/a 10 Kip 2008 installed Assembly Darling Main Bergen 037 n/a 10 Kip unknown removed X Cylinder Paterson Main Anchor 037 n/a 10 Kip 2008 installed X Cylinder Darling Piston Bergen 037 n/a 10 Kip unknown removed X Rings Paterson Piston Anchor 037 n/a 10 Kip 2008 installed X Rings Darling Piston Bergen 037 n/a 10 Kip unknown removed X Paterson Piston Anchor 037 n/a 10 Kip 2008 installed X Darling Piston Bergen 040 n/a 10 Kip unknown removed X Rings Paterson Piston Anchor 040 n/a 10 Kip 2008 installed X Rings Darling

NSP-Minnesota, an Xcel Energy Company Sheet 5 of 9 414 Nicollet Mall, Minneapolis, MN 55401 Monticello Nuclear Generating Plant - Unit 1 2807 West County Road 75, Monticello, MN 55362 Work Performed By NSPM/Xcel Enerqy R/R Plan No. 2008-24-019 System SNB, Spare Snubbers WO No. 356231 Construction Code USAS B31.1, 1967 Section Xl R/R Code 2001 Ed/No Add Section Xl Code Case(s) None Form NIS-2 Contin uation Sheet Corrected, ASME Code Name of Name of Manufacturer National Other Removed, or Stam ped Component Manufacturer Serial No. Board No. Identification Year Built Installed Yes No Valve Bergen 040 n/a 10 Kip unknown removed X Assembly Paterson Valve Anchor 040 n/a 10 Kip 2008 installed X Assembly Darling Valve Bergen 047 n/a 10 Kip unknown removed X Assembly Paterson Valve Anchor 047 n/a 10 Kip 2008 installed X Assembly Darling Valve Bergen 054-1 n/a 10 Kip unknown removed X Assembly Paterson Valve Anchor 054-1 n/a 10 Kip 2008 installed X Assembly Darling Main Bergen 095 n/a 10 Kip unknown removed X Cylinder Paterson Main Anchor 095 n/a 10 Kip 2008 installed X Cylinder Darling Valve Bergen 095 n/a 10 Kip unknown removed X Assembly Paterson Valve Anchor 095 n/a 10 Kip 2008 installed X Assembly Darling Main Bergen 171 n/a 10 Kip unknown removed X Cylinder Paterson Main Anchor 171 n/a 10 Kip 2008 installed X Cylinder Darling Piston Bergen 171 n/a 10 Kip unknown removed X Rings Paterson Piston Anchor 171 n/a 10 Kip 2008 installed X Rings Darling Main Bergen 500 n/a 10 Kip unknown removed X Cylinder Paterson Main Anchor 500 n/a 10 Kip 2008 installed X Cylinder Darling

NSP-Minnesota, an Xcel Energy Company Sheet 6 of 9 414 Nicollet Mall, Minneapolis, MN 55401 Monticello Nuclear Generating Plant - Unit 1 2807 West County Road 75, Monticello, MN 55362 Work Performed By NSPMIXcel Energy R/R Plan No. 2008-24-019 System SNB, Spare Snubbers WO No. 356231 Construction Code USAS B31.1, 1967 Section XI R/R Code 2001 Ed/NoAdd Section Xl Code Case(s) None Form NIS-2 Contin uation Sheet Corrected, ASME Code Name of Name of Manufacturer National Other Removed, or Stam ped Component Manufacturer Serial No. Board No. Identification Year Built Installed Yes No Piston Bergen 500 n/a 10 Kip unknown removed X Paterson Piston Anchor 500 n/a 10 Kip 2008 installed X Darling Piston Rod Bergen 500 n/a 10 Kip unknown removed X Paterson Piston Rod Bergen 500 n/a 10 Kip 2008 installed X Power Piston Bergen 500 n/a 10 Kip unknown removed X Rings Paterson Piston Anchor 500 n/a 10 Kip 2008 installed X Rings Darling Valve Bergen 500 n/a 10 Kip unknown removed X Assembly Paterson Valve Anchor 500 n/a 10 Kip 2008 installed X Assembly Darling Valve Bergen 021A n/a 20 Kip unknown removed X Assembly Paterson Valve Anchor 021A n/a 20 Kip 2008 installed X Assembly Darling Valve Bergen 099 n/a 20 Kip unknown removed X Assembly Paterson Valve Anchor 099 n/a 20 Kip 2008 installed X Assembly Darling Valve Bergen 105 n/a 20 Kip unknown removed X Assembly Paterson Valve Anchor 105 n/a 20 Kip 2008 installed X Assembly Darling Valve Bergen 116 n/a 20 Kip unknown removed X Assembly Paterson Valve Anchor 116 n/a 20 Kip 2008 installed X Assembly Darling

NSP-Minnesota, an Xcel Energy Company Sheet 7 of 9 414 Nicollet Mall, Minneapolis, MN 55401 Monticello Nuclear Generating Plant - Unit 1 2807 West County Road 75, Monticello, MN 55362 Work Performed By NSPMIXcel Energy R/R Plan No. 2008-24-019 System SNB, Spare Snubbers WO No. 356231 Construction Code USAS B31.1, 1967 Section Xl R/R Code 2001 Ed/No Add Section Xl Code Case(s) None Form NIS-2 Contin uation Sheet Corrected, ASME Code Name of Name of Manufacturer National Other Removed, or Stai ped Component Manufacturer Serial No. Board No. Identification Year Built Installed Yes No Valve Bergen 117 n/a 20 Kip unknown removed X Assembly Paterson Valve Anchor 117 n/a 20 Kip 2008 installed X Assembly Darling Valve Bergen 119 n/a 20 Kip unknown removed X Assembly Paterson Valve Anchor 119 n/a 20 Kip 2008 installed X Assembly Darling Valve Bergen 120 n/a 20 Kip unknown removed x Assembly Paterson Valve Anchor 120 n/a 20 Kip 2008 installed X Assembly Darling Piston Bergen 130 n/a 20 Kip unknown removed X Rings Paterson Piston Bergen 130 n/a 20 Kip 2008 installed X Rings Paterson Valve Bergen 130 n/a 20 Kip unknown removed X Assembly Paterson Valve Anchor 130 n/a 20 Kip 2008 installed X Assembly Darling Main Bergen 152 n/a 20 Kip unknown removed X Cylinder Paterson Main Anchor 152 n/a 20 Kip 2008 installed X Cylinder Darling Valve Bergen 463 n/a 20 Kip unknown removed X Assembly Paterson Valve Anchor 463 n/a 20 Kip 2008 installed X Assembly Darling Piston Bergen 020 n/a 30 Kip unknown removed X Rings Paterson Piston Bergen 020 n/a 30 Kip 2008 installed X Rings Paterson

NSP-Minnesota, an Xcel Energy Company Sheet 8 of 9 414 Nicollet Mall, Minneapolis, MN 55401 Monticello Nuclear Generating Plant - Unit 1 2807 West County Road 75, Monticello, MN 55362 Work Performed By NSPM/XcelEnerqy R/R Plan No. 2008-24-019 System SNB, Spare Snubbers WO No. 356231 Construction Code USAS B31.1, 1967 Section Xl R/R Code 2001 Ed/No Add Section Xl Code Case(s) None Form NIS-2 Contin uation Sheet Corrected, ASME Code Name of Name of Manufacturer National ' Other Removed, or Stamped Component Manufacturer Serial No. Board No. Identification Year Built Installed Yes No Main Bergen 020 n/a 30 Kip unknown removed X Cylinder Paterson Main Anchor 020 n/a 30 Kip 2008 installed X Cylinder Darling Valve Bergen 020 n/a 30 Kip unknown removed X Assembly Paterson Valve Anchor 020 n/a 30 Kip 2008 installed X Assembly Darling Valve Bergen 005 n/a . 30 Kip unknown removed X Assembly Paterson.

Valve Anchor 005 n/a 30 Kip 2008 installed X Assembly Darling Valve Bergen 100 n/a 30 Kip unknown removed X Assembly Paterson Valve Anchor 100 n/a 30 Kip 2008 installed X Assembly Darling Main Bergen 100 n/a 30 Kip unknown removed X Cylinder Paterson Main Anchor 100 n/a 30 Kip 2008 installed X Cylinder Darling Valve Bergen 101 n/a 30 Kip unknown removed X Assembly Paterson Valve Anchor 101 n/a 30 Kip 2008 installed X Assembly Darling

- Valve Bergen 468 n/a 30 Kip unknown removed X Assembly Paterson Valve Anchor 468 n/a 30 Kip 2008 installed X Assembly Darling Main Bergen 470 n/a 30 Kip unknown removed X Cylinder Paterson Main Anchor 470 n/a 30 Kip 2008 installed X Cylinder Darling

NSP-Minnesota, an Xcel Energy Company Sheet 9 of 9 414 Nicollet Mall, Minneapolis, MN 55401 Monticello Nuclear Generating Plant - Unit 1 2807 West County Road 75, Monticello, MN 55362 Work Performed By NSPM/Xcel Enerqy R/R Plan No. 2008-24-019 System SNB, Spare Snubbers WO No. 356231 Construction Code USAS B31.1, 1967 Section XI R/R Code 2001 Ed/No Add Section Xl Code Case(s) None Form NIS-2 Continuation Sheet Corrected, ASME Code Name of Name of Manufacturer National Other Removed, or Staiped Component Manufacturer Serial No. Board No. Identification Year Built Installed Yes No Valve Bergen 470 n/a 30 Kip unknown removed X Assembly Paterson Valve Anchor 470 n/a 30 Kip 2008 installed X Assembly Darling Valve Bergen 520 n/a 30 Kip unknown removed X Assembly Paterson Valve Anchor 520 n/a 30 Kip 2008 installed X Assembly Darling Piston Bergen 175 n/a 130 Kip unknown removed X Rings Paterson Piston Anchor 175 n/a 130 Kip 2008 installed X Rings Darling Main Bergen 175 n/a 130 Kip unknown removed X Cylinder Paterson Main Anchor 175 n/a 130 Kip 2008 installed X Cylinder Darling

MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: FORM NIS-2 OWNER'S REPORT FOR Revision 5 REPAIR/REPLACEMENT ACTIVITY Page 1 of 2 Repair/Replacement Plan No.:2008-24-020

1. Owner NSP-Minnesota, an Xcel Energy Company Date 8/3/2009 Name 414 Nicollet Mall, Minneapolis, MN 55401 Sheet I of 2 Address

2. Plant Monticello Nuclear Generating Plant Unit 1 Name 2807 West County Road 75, Monticello, MN 55362 WO-319050 Address Repair Organization P.O. No., Job No. etc.

3. Work Performed By NSPMIXcel Energy Type Code Symbol Stamp N/A Company Name Authorization No. N/A 2807 West County Rd. 75, Monticello, MN 55362 Expiration Date N/A Address

4. Identification of System RHRSW, P-111D, Class 3

5. (a) Applicable Construction Code B31.1 , 1977E/ W'78AEdition / Addenda (b) Applicable Edition of Section Xl Used for Repair/Replacement Activity 2001 Edition, No Addenda (c) Applicable Section XI Code Case(s) N/A

6. Identification of Components Corrected, ASME Code Name of Name of Manufacturer National Other Removed, or Stamp d Component Manufacturer Serial No. Board No. Identification Year Built Installed YES NO Pump Bowl Johnson Pump 99JC1702S N/A None 1999 Removed LI Z Pump Bowl Johnson Pump 99JC1407S N/A None 1999 Installed El Z Fasteners Sulzer N/A N/A None 2009 Removed El E Fasteners Sulzer N/A N/A None 2009 Installed El [

El El

7. Description of Work Replacement of pump bowl assembly, like for like

8. Tests Conducted: Hydrostatic El Pneumatic E] Nominal Operating Pressure El Exempt El Other Z Pressure N/A psi Test Temp N/A OF 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 the number of sheets is recorded at the top of this form. (See 4 AWI-09.04.03 [ASME Section XI RepairlReplacement Program] for further documentation guidance.)

Approval: PCR 01148046 M/asc

MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: FORM NIS-2 OWNER'S REPORT FOR Revision 5 REPAIR/REPLACEMENT ACTIVITY Page 2 of 2 Repair/Replacement Plan No.: 2008-24-020

9. Remarks (Applicable Manufacturer's Data Reports to be Attached)

The bowl assembly is inaccessible to perform a VT-2 examination. A preservice functional test was performed to verify flow is not impairedand meets system requirements.

"Year Built" is the removal and the installationdate for fasteners.

Mod 99Q050 is applicable.

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

Signed K( ISI coopVD Date OL3/09 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 Hartford Steam Boiler Insp & Ins Company of Connecticut of Hartford, Connecticut have inspected the components described in this Owner's Report during the period 7 //(- Wi-j to S_-/._Jluel 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 measures 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 4,;/I/( 3 A,,IA1, ,/4-,o Ldfe-co I Inspector's Signature National Board, Province and Endorsements Date M/asc

MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: FORM NIS-2 OWNER'S REPORT FOR Revision 5 REPAIR/REPLACEMENT ACTIVITY Page 1 of 2 Repair/Replacement Plan No.:2008-24-021

1. Owner NSP-Minnesota, an Xcel Energy Company Date 7/29/2009 Name 414 Nicollet Mall, Minneapolis, MN 55401 Sheet 1 of 2 Address

2. Plant Monticello Nuclear Generating Plant Unit 1 Name 2807 West County Road 75, Monticello, MN 55362 WO 343959 Address Repair Organization P.O. No., Job No. etc.

3. Work Performed By NSPM/Xcel Energy Type Code Symbol Stamp n/a Company Name Authorization No. n/a 2807 West County Rd. 75, Monticello, MN 55362 Expiration Date n/a Address

4. Identification of System EDG Emergency Service Water (EDG-ESW), Valve SW-102, Class 3

5. (a) Applicable Construction Code USAS B31.1 1967E/No Add Edition / Addenda (b) Applicable Edition of Section Xl Used for Repair/Replacement Activity 2001 Edition, No Addenda (c) Applicable Section Xl Code Case(s) n/a

6. Identification of Components Corrected, ASME Code Name of Name of Manufacturer National Other Removed, or Staiped Component Manufacturer Serial No. Board No. Identification Year Built Installed YES NO SW-102 OIC Corp 1573C-61-004 n/a n/a 1969 Repaired El 0 El []

7. Description of Work Removed/restored disc stem-to-nut tack weld to permit full inspection.

8. Tests Conducted: Hydrostatic E] Pneumatic F1 Nominal Operating Pressure E]

Exempt EL Other L] Pressure N/A psi Test Temp N/A OF 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 the number of sheets is recorded at the top of this form. (See 4 AWI-09.04.03 [ASME Section Xl Repair/Replacement Program] for further documentation guidance.)

Approval: PCR 01148046 M/asc

MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: FORM NIS-2 OWNER'S REPORT FOR Revision 5 REPAIR/REPLACEMENT ACTIVITY Page 2 of 2 Repair/Replacement Plan No.: 2008-24-021

9. Remarks (Applicable Manufacturer's Data Reports to be Attached)

No PSI or pressure testing requiredfor valve internal components.

Check Valve Open/Close Test per 0255-11-1A-7.

Existing disc installedin 2005 per WO 307107.

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

Signed Date 713/,07 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 Hartford Steam Boiler Insp & Ins Company of Connecticut of Hartford, Connecticut have inspected the components described in this Owner's Report during the period '/ h f to ? 3H P, 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 measures 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 t-ý Commissions IJ*V. (l*.J. A,$* n w'Oooy 1*/eo Inspector's Signature National Board, Province and Endorsements Date 7 t31/o4 M/asc

MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: FORM NIS-2 OWNER'S REPORT FOR Revision 5 I REPAIR/REPLACEMENT ACTIVITY Page 1 of 2 Repair/Replacement Plan No.:2008-24-022, Rev. 1

1. Owner NSP-Minnesota, an Xcel Energy Company Date 7/30/2009 Name 414 Nicollet Mall, Minneapolis, MN 55401 Sheet 1 of 2 Address

2. Plant Monticello Nuclear Generating Plant Unit 1 Name 2807 West County Road 75, Monticello, MN 55362 WO 322606 Address Repair Organization P.O. No., Job No. etc.

3. Work Performed By NSPMIXcel Energy Type Code Symbol Stamp n/a Company Name Authorization No. n/a 2807 West County Rd. 75, Monticello, MN 55362 Expiration Date n/a Address

4. Identification of System EFT Service Water (FSW), Class 3

5. (a) Applicable Construction Code B31.1 1977E/W78A Edition /Addenda (b) Applicable Edition of Section Xl Used for Repair/Replacement Activity 2001 Edition, No Addenda (c) Applicable Section Xl Code Case(s) na

6. Identification of Components Corrected, ASME Code Name of Name of Manufacturer National Other Removed, or Staiped Component Manufacturer Serial No. Board No. Identification Year Built Installed YES NO ESW5-3"-HBD NSP n/a n/a n/a 1981 Removed E] 0 ESW5-3"-HBD Xcel Energy n/a n/a n/a 2009 Installed [] [

7] D]

7. Description of Work Like for like replacementof piping components due to thinning.

8. Tests Conducted: Hydrostatic El Pneumatic El Nominal Operating Pressure Exempt El Other LI Pressure 78.5 psi Test Temp n/a OF 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 the number of sheets is recorded at the top of this form. (See 4 AWI-09.04.03 [ASME Section XI Repair/Replacement Program] for further documentation guidance.)

Approval: PeR 01148046 M/asc

MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: FORM NIS-2 OWNER'S REPORT FOR Revision 5 REPAIR/REPLACEMENT ACTIVITY Page 2 of 2 Repair/Replacement Plan No.: 2008-24-022, Rev. 1

9. Remarks (Applicable Manufacturer's Data Reports to be Attached)

Welds were examined by MT or PT for construction code.

System leakage test with VT-2 at nominal operatingpressure.

Existing bolting materials were reused.

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

the ASME Code,Section XI.

Signed -- SEC**-ONXf ISI*oOO::. Date 071/o9 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 Hartford Steam Boiler Insp & Ins Company of Connecticut of Hartford, Connecticut have inspected the components described in this Owner's Report during the period 't I t./ of to 7/1)1 0e -,

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 measures 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'0//'(r AJV,l /IlA/,09.d4,'-Cof Inspector's Signature National Board, Province and Endorsements Date M/asc

MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: FORM NIS-2 OWNER'S REPORT FOR Revision 5 REPAIR/REPLACEMENT ACTIVITY Page 1 of 2 Repair/Replacement Plan No.:2008-24-023

1. Owner NSP-Minnesota, an Xcel Energy Company Date 7/27/2009 Name 414 Nicollet Mall, Minneapolis, MN 55401 Sheet I of 5 Address

2. Plant Monticello Nuclear Generating Plant Unit 1 Name 2807 West County Road 75, Monticello, MN 55362 WO-320292 Address Repair Organization P.O. No., Job No. etc.

3. Work Performed By NSPM/Xcel Energy Type Code Symbol Stamp n/a Company Name Authorization No. n/a 2807 West County Rd. 75, Monticello, MN 55362 Expiration Date n/a Address

4. Identification of System Control Rod Drive (CRD), Class I

5. (a) Applicable Construction Code ASME Section III , 1965/No Edition/Addenda (b) Applicable Edition of Section Xl Used for Repair/Replacement Activity 2001 Edition, No Addenda (c) Applicable Section XI Code Case(s) n/a

6. Identification of Components Corrected, ASME Code Name of Name of Manufacturer National Other Removed, or Staiped Component Manufacturer Serial No. Board No. Identification Year Built Installed YES NO SEE SUBSEQUENT PAGES -- El E]

E] E]

El E]

El F7 Removed selected CRDM's and replaced with previously in-service refurbished

7. Description of Work spares.

8. Tests Conducted: Hydrostatic El Pneumatic F1 Nominal Operating Pressure El Exempt Rl Other 2 Pressure *1003 psi Test Temp *189 OF 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 the number of sheets is recorded at the top of this form. (See 4 AWI-09.04.03 [ASME Section XI Repair/Replacement Program] for further documentation guidance.)

Approval: PCR 01148046 M/asc

MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: FORM NIS-2 OWNER'S REPORT FOR Revision 5 REPAIR/REPLACEMENT ACTIVITY Page 2 of 2 Sheet 2 of 5 Repair/Replacement Plan No.: 2008-24-023

9. Remarks (Applicable Manufacturer's Data Reports to be Attached)

Drives exchanged per procedure 9309 and tested per procedure 9019.

Pressuretest not requiredper 4 th Interval ISI Relief Req. #7, however, verified SAT wi VT-2 per System Leakage Test 0255-20-IIC-2.

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

Signed S-.ECONXI 3 JS1*:i..t, Date "//277/09 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 Hartford Steam Boiler Insp & Ins Company of Connecticut of Hartford, Connecticut have inspected the components described in this Owner's Report during the period i6 /9 /Qd" to We/e' 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 Xl.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures 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 &,6/*J A,,,. ,',4*3-XO., --e'e, Inspector's Signature National Board, Province and Endorsements Date `7 / 2-r/C/9 M/asc

NSP-Minnesota, an Xcel Energy Company Sheet 3 of 5 414 Nicollet Mall, Minneapolis, MN 55401 Monticello Nuclear Generating Plant - Unit 1 2807 West County Road 75, Monticello, MN 55362 Work Performed By NSPMIXcel Energy R/R Plan No. 2008-24-023 System Control Rod Drive (CRD) Class I WO No. 320292 Construction Code ASME III, 1965 Section Xl R/R Code 2001 Ed/No Add Section Xl Code Case(s) None Form NIS-2 Contin uation Sheet Corrected, ASME Code Name of Name of Manufacturer National Other Removed, or Staiped Component Manufacturer Serial No. Board No. Identification Year Built Installed Yes No CRD 06-19 General 411 n/a n/a unknown removed X Electric CRD 06-19 General 1484 n/a n/a 2009 installed X Electric CRD 06-27 General 537A n/a n/a unknown removed X Electric CRD 06-27 General 351 n/a n/a 2009 installed X Electric CRD 06-35 General 325 n/a n/a unknown removed X Electric CRD 06-35 General 582 n/a n/a 2009 installed X Electric CRD 10-11 General 73 n/a n/a unknown removed X Electric CRD 10-11 General 795 n/a n/a 2009 installed X Electric CRD 10-43 General 926 n/a n/a unknown removed X Electric CRD 10-43 General 568A n/a n/a 2009 installed X Electric CRD 14-11 General 459 n/a n/a unknown removed X Electric CRD 14-11 General 722 n/a n/a 2009 installed X Electric CRD 14-19 General 536 n/a n/a unknown removed X Electric CRD 14-19 General 353 n/a n/a 2009 installed X Electric CRD 14-35 General 793 n/a n/a unknown removed X Electric CRD 14-35 General 954 n/a n/a 2009 installed X Electric

NSP-Minnesota, an Xcel Energy Company Sheet 4 of 5 414 Nicollet Mall, Minneapolis, MN 55401 Monticello Nuclear Generating Plant - Unit 1 2807 West County Road 75, Monticello, MN 55362 Work Performed By NSPMIXcelEnerqy R/R Plan No. 2008-24-023 System Control Rod Drive (CRD) Class 1 WO No. 320292 Construction Code ASME III, 1965 Section Xl R/R Code 2001 Ed/No Add Section XI Code Case(s) None Form NIS-2 Contin uation Sheet Corrected, ASME Code Name of Name of Manufacturer National Other Removed, or Stai ped Component Manufacturer Serial No. Board No. Identification Year Built Installed Yes No CRD 18-43 General 695 n/a n/a unknown removed X Electric CRD 18-43 General A6718 n/a n/a 2009 installed X Electric CRD 18-31 General 152 n/a n/a unknown removed X Electric CRD 18-31 General 613 n/a n/a 2009 installed X Electric CRD 22-03 General 816 n/a n/a unknown removed X Electric CRD 22-03 General 625 n/a n/a 2009 installed X Electric CRD 22-07 General 553 n/a n/a unknown removed X Electric CRD 22-07 General 1547 n/a n/a 2009 installed X Electric CRD 22-11 General 388 n/a n/a unknown removed X Electric CRD 22-11 General 603 n/a n/a 2009 installed X Electric CRD 22-43 General 12 n/a n/a unknown removed X Electric CRD 22-43 General 694 n/a n/a 2009 installed X Electric CRD 26-03 General 531 n/a n/a unknown removed X Electric CRD 26-03 General 831 n/a n/a 2009 installed X Electric CRD 26-47 General 871 n/a n/a unknown removed X Electric CRD 26-47 General 642 n/a n/a 2009 installed X Electric

NSP-Minnesota, an Xcel Energy Company Sheet 5 of 5 414 Nicollet Mall, Minneapolis, MN 55401 Monticello Nuclear Generating Plant - Unit 1 2807 West County Road 75, Monticello, MN 55362 Work Performed By NSPMIXcel Energy R/R Plan No. 2008-24-023 System Control Rod Drive (CRD) Class 1 WO No. 320292 Construction Code ASME III, 1965 Section Xl R/R Code 2001 Ed/No Add Section Xl Code Case(s) None Form NIS-2 Continuation Sheet Corrected, ASME Code Name of Name of Manufacturer National Other Removed, or Stam ped Component Manufacturer Serial No. Board No. Identification Year Built Installed Yes No CRD 34-39 General 825 n/a n/a unknown removed X Electric CRD 34-39 General 756 n/a n/a 2009 installed X Electric CRD 34-47 General 512 n/a n/a unknown removed X Electric CRD 34-47 General 803 n/a n/a 2009 installed X Electric CRD 38-11 General 521 n/a n/a unknown removed X Electric CRD 38-11 General 852 n/a n/a 2009 installed X Electric

+ t I + I +/-

I I 4 4 I F I -I- F I F I

MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: FORM NIS-2 OWNER'S REPORT FOR Revision 5 I REPAIR/REPLACEMENT ACTIVITY Page 1 of 2 Repair/Replacement Plan No.:2008-24-024

1. Owner NSP-Minnesota, an Xcel Energy Company Date 7/28/2009 Name 414 Nicollet Mall, Minneapolis, MN 55401 Sheet I of 5 Address

2. Plant Monticello Nuclear Generating Plant Unit 1 Name 2807 West County Road 75, Monticello, MN 55362 WO-320292 Address Repair Organization P.O. No., Job No. etc.

3. Work Performed By NSPM/Xcel Energy Type Code Symbol Stamp n/a Company Name Authorization No. n/a 2807 West County Rd. 75, Monticello, MN 55362 Expiration Date n/a Address

4. Identification of System Control Rod Drive (CRD), Class 1

5. (a) Applicable Construction Code ASME Section III 1965/No Edition /Addenda (b) Applicable Edition of Section Xl Used for Repair/Replacement Activity 2001 Edition, No Addenda (c) Applicable Section Xl Code Case(s) n/a

6. Identification of Components Corrected, ASME Code Name of Name of Manufacturer National Other Removed, or Staiped Component Manufacturer Serial No. Board No. Identification Year Built Installed YES NO SEE SUBSEQUENT PAGES E] El E] El DL DLE] [

Replacement of flange fasteners (8 each) for 19 CRDM's exchanged with

7. Description of Work refurbished spares during outage.

8. Tests Conducted: Hydrostatic E] Pneumatic D1 Nominal Operating Pressure EF Exempt ED Other D] Pressure psi Test Temp OF 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 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form. (See 4 AWI-09.04.03 [ASME Section Xi Repair/Replacement Program] for further documentation guidance.)

Approval: PCR 01148046 M/asc

MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: FORM NIS-2 OWNER'S REPORT FOR Revision 5 REPAIR/REPLACEMENT ACTIVITY Page 2 of 2 Sheet 2 of 5 Repair/Replacement Plan No.: 2008-24-024

9. Remarks (Applicable Manufacturer's Data Reports to be Attached)

Reference Alt. 's 0OA026 and 02A040.

Drives exchanged per procedure 9309 and tested perprocedure 9019.

VT-1 PSI performed on replacement capscrews. No pressure testing required.

Capscrewsfrom PO P007534 were built in 2002. Capscrews from PO 24579 were built in 2008.

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

Signed , *CI-ON X)I Vst C0 r-t--. Date 1/28/09 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 Hartford Steam Boiler Insp & Ins Company of Connecticut of Hartford, Connecticut have inspecte~l the components described in this Owner's Report during the period 1.o IV '4t to -?..h 0?

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 measures 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 /1/19 Qff6 /A ,&'t k 1Vt,/ X -Ooz2f ,-..o Inspector's Signature National Board, Province and Endorsements Date - 7 /?I~

M/asc

NSP-Minnesota, an Xcel Energy Company Sheet 3 of 5 414 Nicollet Mall, Minneapolis, MN 55401 Monticello Nuclear Generating Plant - Unit 1 2807 West County Road 75, Monticello, MN 55362 Work Performed By NSPMIXcelEnergy R/R Plan No. 2008-24-024 System Control Rod Drive (CRD) Class I WO No. 320292 Construction Code ASME III, 1965 Section Xl R/R Code 2001 Ed/No Add Section XI Code Case(s) None Form NIS-2 Contin uation Sheet Corrected, ASME Code Name of Name of Manufacturer National Other Removed, or Stam Ped Component Manufacturer Serial No. Board No. Identification Year Built Installed Yes No CRD 06-19 Nova n/a n/a n/a unknown removed X (8) Capscrews CRD 06-19 Nova n/a n/a n/a 2009 installed X (8) Capscrews CRD 06-27 Nova n/a n/a n/a unknown removed X (8) Capscrews CRD 06-27 Nova n/a n/a n/a 2009 installed X (8) Capscrews CRD 06-35 Nova n/a n/a n/a unknown removed X (8) Capscrews CRD 06-35 Nova n/a n/a n/a 2009 installed X (8) Capscrews CRD 10-11 Nova n/a n/a n/a unknown removed X (8) Capscrews CRD 10-11 Nova n/a n/a n/a 2009 installed X (8) Capscrews CRD 10-43 Nova n/a n/a n/a unknown removed X (8) Capscrews CRD 10-43 Nova n/a n/a n/a 2009 installed X (8) Capscrews CRD 14-11 Nova n/a n/a n/a unknown removed X (8) Capscrews CRD 14-11 Nova n/a n/a n/a 2009 installed X (8) Capscrews CRD 14-19 Nova n/a n/a n/a unknown removed X (8) Capscrews CRD 14-19 Nova n/a n/a n/a 2009 installed X (8) Capscrews CRD 14-35 Nova n/a n/a n/a unknown removed X (8) Capscrews CRD 14-35 Nova n/a n/a n/a 2009 installed X (8) Capscrews

NSP-Minnesota, an Xcel Energy Company Sheet 4 of 5 414 Nicollet Mall, Minneapolis, MN 55401 Monticello Nuclear Generating Plant - Unit 1 2807 West County Road 75, Monticello, MN 55362 Work Performed By NSPM/XcelEnerqy R/R Plan No. 2008-24-024 System Control Rod Drive (CRD) Class 1 WO No. 320292 Construction Code ASME III, 1965 Section Xl R/R Code 2001 Ed/No Add Section Xl Code Case(s) None Form NIS-2 Contin uation Sheet Corrected, ASME Code Name of Name of Manufacturer National Other Removed, or Stam ped Component Manufacturer Serial No. Board No. Identification Year Built Installed Yes No CRD 18-43 Nova n/a n/a n/a unknown removed X (8) Capscrews CRD 18-43 Nova n/a n/a n/a 2009 installed X (8) Capscrews CRD 18-31 Nova n/a n/a n/a unknown removed X (8) Capscrews CRD 18-31 Nova n/a n/a n/a 2009 installed X (8) Capscrews CRD 22-03 Nova n/a n/a n/a unknown removed X (8) Capscrews CRD 22-03 Nova n/a n/a n/a 2009 installed X (8) Capscrews CRD 22-07 Nova n/a n/a n/a unknown removed X (8) Capscrews CRD 22-07 Nova n/a n/a n/a 2009 installed X (8) Capscrews CRD 22-11 Nova n/a n/a n/a unknown removed X (8) Capscrews CRD 22-11 Nova n/a n/a n/a 2009 installed X (8) Capscrews CRD 22-43 Nova n/a n/a n/a unknown removed X (8) Capscrews CRD 22-43 Nova n/a n/a n/a 2009 installed X (8) Capscrews CRD 26-03 Nova n/a n/a n/a unknown removed X (8) Capscrews CRD 26-03 Nova n/a n/a n/a 2009 installed X (8) Capscrews CRD 26-47 Nova n/a n/a n/a unknown removed X (8) Capscrews CRD 26-47 Nova n/a n/a n/a 2009 installed X (8) Capscrews

NSP-Minnesota, an Xcel Energy Company Sheet 5 of 5 414 Nicollet Mall, Minneapolis, MN 55401 Monticello Nuclear Generating Plant - Unit 1 2807 West County Road 75, Monticello, MN 55362 Work Performed By NSPMIXcel Energy R/R Plan No. 2008-24-024 System Control Rod Drive (CRD) Class I WO No. 320292 Construction Code ASME III, 1965 Section Xl R/R Code 2001 Ed/No Add Section Xl Code Case(s) None Form NIS-2 Continuation Sheet Corrected, ASME Code Name of Name of Manufacturer National Other Removed, or Staiped Component Manufacturer Serial No. Board No. Identification Year Built Installed Yes No CRD 34-39 Nova n/a n/a n/a unknown removed X (8) Capscrews CRD 34-39 Nova n/a n/a n/a 2009 installed X (8) Capscrews CRD 34-47 Nova n/a n/a n/a unknown removed X (8) Capscrews CRD 34-47 Nova n/a n/a n/a 2009 installed X (8) Capscrews CRD 38-11 Nova n/a n/a n/a unknown removed X (8) Capscrews CRD 38-11 Nova n/a n/a n/a 2009 installed X (8) Capscrews I 4 4 4 + 4 +

4 + 4 + 4 + +

4 4 4 4- 4 1 4 4

_____ I ______ I _____ I ____ [ _____ I I

___ ______ II__ __

MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: FORM NIS-2 OWNER'S REPORT FOR Revision 5 I REPAIR/REPLACEMENT ACTIVITY Page 1 of 2 Repair/Replacement Plan No.:2008-24-025

1. Owner NSP-Minnesota, an Xcel Energy Company Date 8/3/2009 Name 414 Nicollet Mall, Minneapolis, MN 55401 Sheet 1 of 2 Address

2. Plant Monticello Nuclear Generating Plant Unit 1 Name 2807 West County Road 75, Monticello, MN 55362 WO-343738 Address Repair Organization P.O. No., Job No. etc.

3. Work Performed By NSPM/Xcel Energy Type Code Symbol Stamp n/a Company Name Authorization No. n/a 2807 West County Rd. 75, Monticello, MN 55362 Expiration Date n/a Address

4. Identification of System RHR Service Water (RHRSW), CV-1728, Class 3

5. (a) Applicable Construction Code B31.1 , 77E/W'78A Edition / Addenda (b) Applicable Edition of Section XI Used for Repair/Replacement Activity 2001 Edition, No Addenda (c) Applicable Section XI Code Case(s) n/a

6. Identification of Components Corrected, ASME Code Name of Name of Manufacturer National Other Removed, or Staiped Component Manufacturer Serial No. Board No. Identification Year Built Installed YES NO Plug Flowserve 47907-001 n/a n/a 2005 Removed El Z Plug Flowserve n/a Ht. Code 2009. Installed El N 91772 ED []

ED El E_ DD

7. Description of Work Like-for-like replacement of plug and the integralstem due to stem galling.

8. Tests Conducted: Hydrostatic ED Pneumatic D] Nominal Operating Pressure E]

Exempt El Other F] Pressure n/a psi Test Temp n/a OF 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 the number of sheets is recorded at the top of this form. (See 4 AWI-09.04.03 [ASME Section XI Repair/Replacement Program] for further documentation guidance.)

Approval: PCR 01148046 M/asc

MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: FORM NIS-2 OWNER'S REPORT FOR Revision 5 REPAIR/REPLACEMENT ACTIVITY Page 2 of 2 Repair/Replacement Plan No.: 2008-24-025

9. Remarks (Applicable Manufacturer's Data Reports to be Attached)

Design Change 87Z015 is applicable to valve.

Alteration 95A01I is applicable to plug.

/ST performed per WO PMT

Attachment:

Stroke time open (STO) and position indication (PIT).

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

Signed Ownezr SECMON ei/3e Titl Y1 ISo 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 Hartford Steam Boiler Insp & Ins Company of Connecticut of Hartford, Connecticut have inspected tte components described in this Owner's Report during the period e/,z 11 hd to e&/13/ya1 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 measures 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 V17 i1fr 7 4 &,./4,-o 1rz.-co Inspector's Signature National Board, Province and Endorsements Date M/asc

MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: FORM NIS-2 OWNER'S REPORT FOR Revision 5 I REPAIR/REPLACEMENT ACTIVITY Page 1 of 2 Repair/Replacement Plan No.:2008-24-026

1. Owner NSP-Minnesota, an Xcel Energy Company Date 7/31/2009 Name 414 Nicollet Mall, Minneapolis, MN 55401 Sheet 1 of 2 Address

2. Plant Monticello Nuclear Generating Plant Unit 1 Name 2807 West County Road 75, Monticello, MN 55362 WO-346874 Address Repair Organization P.O. No., Job No. etc.

3. Work Performed By NSPM/Xcel Energy Type Code Symbol Stamp n/a Company Name Authorization No. n/a 2807 West County Rd. 75, Monticello, MN 55362 Expiration Date n/a Address

4. Identification of System ReactorRecirculation (REC), Class I

5. (a) Applicable Construction Code B31.1 , 77E/W'78A Edition / Addenda (b) Applicable Edition of Section Xl Used for Repair/Replacement Activity 2001 Edition, No Addenda (c) Applicable Section Xl Code Case(s) n/a

6. Identification of Components Corrected, ASME Code Name of Name of Manufacturer National Other Removed, or Staiped Component Manufacturer Serial No. Board No. Identification Year Built Installed YES NO Decon test Guyon Alloys 1N0177-3 n/a na 1993 Removed El Z assy Decon flange Dubose N090126-1-2 n/a na 2009 Installed 11 Z

_ 17]

El El

_El

7. Description of Work Remove decontaminationtest assembly and install blind flange.

8. Tests Conducted: Hydrostatic LI Pneumatic [] Nominal Operating Pressure Z Exempt DI Other [] Pressure 1003 psi Test Temp 189 OF 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 the number of sheets is recorded at the top of this form. (See 4 AWI-09.04.03 [ASME Section XI Repair/Replacement Program] for further documentation guidance.)

Approval: PCR 01148046 M/asc

MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: FORM NIS-2 OWNER'S REPORT FOR Revision 5 REPAIR/REPLACEMENT ACTIVITY Page 2 of 2 Repair/Replacement Plan No.: 2008-24-026

9. Remarks (Applicable Manufacturer's Data Reports to be Attached)

The decontaminationtest assembly installedcirca 1993 on P-200A was removed and replacedwith a blind flange using the existing bolting materials.

VT-2 exam during Class 1 pressure test 0255-20-41C-2 per work order PMT (reference WO-344337).

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

Signed , SIs%-o* XI : Date 1/3,109 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 Hartford Steam Boiler Insp & Ins Company of Connecticut of Hartford, Connecticut have inspected the components described in this Owner's Report during the period /--c. J/*6'f to 1T/)-1 / ,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 XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures 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.

1ý A A.A-,/,

Inspector's Signature Commissions kb' // *-( 1 4/, A,', Ai A'""00 'I/(ik -Co National Board, Province and Endorsements Date - --I /)I / C)ý M/asc

MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: FORM NIS-2 OWNER'S REPORT FOR Revision 5 1 REPAIR/REPLACEMENT ACTIVITY Page 1 of 2 Repair/Replacement Plan No.:2008-24-027

1. Owner NSP-Minnesota, an Xcel Energy Company Date 7/31/2009 Name 414 Nicollet Mall, Minneapolis, MN 55401 Sheet 1 of 2 Address

2. Plant Monticello Nuclear Generating Plant Unit 1 Name 2807 West County Road 75, Monticello, MN 55362 WO-354743 Address Repair Organization P.O. No., Job No. etc.

3. Work Performed By NSPMIXcel Energy Type Code Symbol Stamp n/a Company Name Authorization No. n/a 2807 West County Rd. 75, Monticello, MN 55362 Expiration Date n/a Address

4. Identification of System Auto PressureRelief (APR) RV-2-71F, Class I

5. (a) Applicable Construction Code ASME Section III 1968E/ W'68A Edition / Addenda (b) Applicable Edition of Section XI Used for Repair/Replacement Activity 2001 Edition, No Addenda (c) Applicable Section XI Code Case(s) n/a

6. Identification of Components Corrected, ASME Code Name of Name of Manufacturer National Other Removed, or Staiped Component Manufacturer Serial No. Board No. Identification Year Built Installed YES NO Main Disc Target Rock 593 n/a Body s/n 25 2008 Removed 0l 0 Main Disc Target Rock 605 n/a Body s/n 25 2008 Installed El Z El Dsa 1:1 E]

7. Description of Work The main disc replaced like for like with a refurbished spare from stock.

8. Tests Conducted: Hydrostatic E] Pneumatic El Noominal Operating Pressure El Exempt El Other nI Pressure n/a psi Test Temp n/a OF 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 the number of sheets is recorded at the top of this form. (See 4 AWI-09.04.03 [ASME Section Xl RepairlReplacement Program] for further documentation guidance.)

Approval: PCR 01148046 M/asc

MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: FORM NIS-2 OWNER'S REPORT FOR Revision 5 REPAIR/REPLACEMENT ACTIVITY Page 2 of 2 Repair/Replacement Plan No.: 2008-24-027

9. Remarks (Applicable Manufacturer's Data Reports to be Attached)

GE Spec 21A9206 applies.

The valve test requirements were met by set point testing with steam per 4280-03-PM.

Post installationtesting performed per procedure 0112.

The replacement disc was originallyin valve assembly s/n 122.

"Year Built" is the removal and the installationdate.

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

,- .CCt,*XI IS-- Cj:ciz::D Date 7/3rO' Signed D 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 Hartford Steam Boiler Insp & Ins Company of Connecticut of Hartford, Connecticut have inspect d tl'e components described in this Owner's Report during the period to7J/

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 measures 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 /14 ( ) A ItUS( -- A,"00Ld2I4'-Cte Inspector's Signature National Board, Province and Endorsements Date "17 6 /'Idi M/asc

MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: FORM NIS-2 OWNER'S REPORT FOR Revision 5 I REPAIR/REPLACEMENT ACTIVITY Page 1 of 2 Repair/Replacement Plan No.:2008-24-028

1. Owner NSP-Minnesota, an Xcel Energy Company Date 7/31/2009 Name 414 Nicollet Mall, Minneapolis, MN 55401 Sheet I of 2 Address

2. Plant Monticello Nuclear Generating Plant Unit 1 Name 2807 West County Road 75, Monticello, MN 55362 WO-3551 11 Address Repair Organization P.O. No., Job No. etc.

3. Work Performed By NSPMIXcel Energy Type Code Symbol Stamp n/a Company Name Authorization No. n/a 2807 West County Rd. 75, Monticello, MN 55362 Expiration Date n/a Address

4. Identification of System Core Spray (CSP), MO-I 749, Class 2

5. (a) Applicable Construction Code B31.1 1977E / W'78A Edition /Addenda (b) Applicable Edition of Section Xl Used for Repair/Replacement Activity 2001 Edition, No Addenda (c) Applicable Section XI Code Case(s) n/a

6. Identification of Components Corrected, ASME Code Name of Name of Manufacturer National Other Removed, or Staiped Component Manufacturer Serial No. Board No. Identification Year Built Installed YES NO MO-1749 Anchor Darling 4543-68* n/a n/a 1969 Corrected E] E DE]

El 1

. D I of Wi ]

7. Description of Work Weldingl on MO-1749 disc nut to disc for disassembly/reassembly.

8. Tests Conducted: Hydrostatic D] Pneumatic F1 Nominal Operating Pressure ED Exempt El Other El Pressure psi Test Temp NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8-1/2 in x 1I in, (2) information in items I through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form. (See 4 AWI-09.04.03 [ASME Section XI Repair/Replacement Program] for further documentation guidance.)

Approval: PCR 01148046 M/asc

MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: FORM NIS-2 OWNER'S REPORT FOR Revision 5 REPAIR/REPLACEMENT ACTIVITY Page 2 of 2 Repair/Replacement Plan No.: 2008-24-028

9. Remarks (Applicable Manufacturer's Data Reports to be Attached)

The disc nut to disc tack weld was required to be removed and rewelded to permit disassembly and reassembly of the valve to accommodate maintenance activities for EC-10869.

Valve serial number retrieved from work plan field observation. Disc markings recorded as HT 5208D.

No pressure testing or PSI required.

Position indication testing (PIT)was performed per work orderpreoperationaltesting instructions.

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

Signed *' -ET-T, ON X1I SI Coogýi 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 Hartford Steam Boiler Insp & Ins Company of Connecticut of Hartford, Connecticut have inspected the components described in this Owner's Report during the period 3 //7 J 0 $ to 01/d-9 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 measures 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 /R,/2J2// ,,q Jj/Lce1,WocJYJZ-2-Ct)

Inspector's Signature National Board, Province and Endorsements Date tl M/asc

MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: FORM NIS-2 OWNER'S REPORT FOR Revision 5 1 REPAIR/REPLACEMENT ACTIVITY Page 1 of 2 Repair/Replacement Plan No.:2008-24-029, Rev. 1

1. Owner NSP-Minnesota, an Xcel Energy Company Date 8/4/2009 Name 414 Nicollet Mall, Minneapolis, MN 55401 Sheet I of 2 Address

2. Plant Monticello Nuclear Generating Plant Unit 1 Name 2807 West County Road 75, Monticello, MN 55362 WO-374028 Address Repair Organization P.O. No., Job No. etc.

3. Work Performed By NSPM/Xcel Energy Type Code Symbol Stamp N/A Company Name Authorization No. N/A 2807 West County Rd. 75, Monticello, MN 55362 Expiration Date N/A Address

4. Identification of System RHR Service Water (RSW/ESW), Loop A, Class 3

5. (a) Applicable Construction Code B31. I , 1977E/W'78A Edition /Addenda (b) Applicable Edition of Section XI Used for Repair/Replacement Activity 2001 Edition, No Addenda (c) Applicable Section Xl Code Case(s) N/A

6. Identification of Components Corrected, ASME Code Name of Name of Manufacturer National Other Removed, or Staiped Component Manufacturer Serial No. Board No. Identification Year Built Installed YES NO SW9-18"-GF Navco N/A N/A N/A 1969 Removed El [

SW9-18"-GF Dubose N/A N/A N/A 2009 Installed El [

SW58-16"-GF Navco N/A N/A N/A 1969 Removed [Ell SW58-16"-GF Dubose N/A N/A N/A 2009 Installed El [

E] E]

7. Description of Work Replace A-Loop RHRSW piping components due to MIC thinning.

8. Tests Conducted: Hydrostatic E] Pneumatic Ml Nominal Operating Pressure Z Exempt El Other El Pressure 238 psi Test Temp N/A OF 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 the number of sheets is recorded at the top of this form. (See 4 AWI-09.04.03 [ASME Section Xl Repair/Replacement Program] for further documentation guidance.)

Approval: PCR 01148046 M/asc

MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: FORM NIS-2 OWNER'S REPORT FOR Revision 5 REPAIR/REPLACEMENT ACTIVITY Page 2 of 2 Sheet 2 of 2 Repair/Replacement Plan No.: 2008-24-029, Rev. 1

9. Remarks (Applicable Manufacturer's Data Reports to be Attached)

Approx. 80 feet of pipe and associatedfittings and flanges were replacedin the intake structure due to MIC thinning. Associated valves were reused. Post-weld heat treat and construction surface exams were performed, as applicable. System leakage test with VT-2 performed per WO PMT.

Check test open and close tests (CTO/CTC) were performed on affected valves RHRSW-48-1 and RHRSW-50-1. Stroke time open and closed tests (STO/STC) were performed on affected valve RHRSW-3-1. Valve testing per WO PMT.

Repair/Replacementto associatedsupports was performed under a separate R/R Plan.

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

Signed ), - I/ 'o(" Date

t///G 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 Hartford Steam Boiler Insp & Ins Company of Connecticut of Hartford, Connecticut have inspected the components described in this Owner's Report during the period 1/? 2"b[( to s-/s-"/c/

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 measures 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.

41ýý 1-f- "o 4j-,1,7 Commissions A-/3tuj Aj /-J ,'/a~q

/ -<c.

Inspector's Signature National Board, Province and Endorsements Date &-(J- lo 7 M/asc

MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: FORM NIS-2 OWNER'S REPORT FOR Revision 5 I REPAIR/REPLACEMENT ACTIVITY Page 1 of 2 Repair/Replacement Plan No.:2008-24-030

1. Owner NSP-Minnesota, an Xcel Energy Company Date 7/29/2009 Name 414 Nicollet Mall, Minneapolis, MN 55401 Sheet 1 of 2 Address

2. Plant Monticello Nuclear Generating Plant Unit 1 Name 2807 West County Road 75, Monticello, MN 55362 WO-354410 Address Repair Organization P.O. No., Job No. etc.

3. Work Performed By NSPMIXcel Energy Type Code Symbol Stamp n/a Company Name Authorization No. n/a 2807 West County Rd. 75, Monticello, MN 55362 Expiration Date n/a Address

4. Identification of System Emergency Service Water Loop A

5. (a) Applicable Construction Code B31.1 77W78 Edition / Addenda (b) Applicable Edition of Section Xl Used for Repair/Replacement Activity 2001 Edition, No Addenda (c) Applicable Section Xl Code Case(s) n/a

6. Identification of Components Corrected, ASME Code Name of Name of Manufacturer National Other Removed, or Staiped Component Manufacturer Serial No. Board No. Identification Year Built Installed YES NO ESWI-4"-HBD na na n/a na 1981 Removed El 0 ESWI-4"-HBD Dubose Tioqa na n/a na 2008 Installed LI Z H-215 na na n/a na 1981 Removed 0l 0 H-215 Dubose na n/a na 2008 Installed El [

El El Like for like piping replacementand like for like partialreplacement of one

7. Description of Work support.

8. Tests Conducted: Hydrostatic El Pneumatic El Noominal Operating Pressure Z Exempt El Other El Pressure 81 psi Test Temp n/a OF 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 the number of sheets is recorded at the top of this form. (See 4 AWI-09.04.03 [ASME Section XI Repair/Replacement Program] for further documentation guidance.)

Approval: PCR 01148046 M/asc

MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: FORM NIS-2 OWNER'S REPORT FOR Revision 5 REPAIR/REPLACEMENT ACTIVITY Page 2 of 2 Repair/Replacement Plan No.: 2008-24-030

9. Remarks (Applicable Manufacturer's Data Reports to be Attached)

Piping components andportion of one hanger (H-215) replacedin the intake structure.

VT-2 per work order PMT at normal operatingpressure (81 psig).

STO and STC on ESW-20 per the WO PMT.

92Q610 is applicable.

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

Signed , SecrioN XI 151 Coog.* . Date 7/30 /0 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 Hartford Steam Boiler Insp & Ins Company of Connecticut of Hartford, Connecticut have inspected the components described in this Owner's Report during the period ,I fl 4/ /!j to 7 /JZ J62 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 measures 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.

Y, " a-, ýJ, -" -

Inspe'or's Signature Commissions qV,/',.

,A 1 /aoz-qlO National Board, Province and Endorsements Date M/asc

MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: FORM NIS-2 OWNER'S REPORT FOR Revision 5 REPAIR/REPLACEMENT ACTIVITY Page 1 of 2 Repair/Replacement Plan No.:2008-24-031

1. Owner NSP-Minnesota, an Xcel Energy Company Date 7/31/2009 Name 414 Nicollet Mall, Minneapolis, MN 55401 Sheet 1 of 2 Address

2. Plant Monticello Nuclear Generating Plant Unit 1 Name 2807 West County Road 75, Monticello, MN 55362 WO-364432 Address Repair Organization P.O. No., Job No. etc.

3. Work Performed By NSPM/XcelEnergy Type Code Symbol Stamp n/a Company Name Authorization No. n/a 2807 West County Rd. 75, Monticello, MN 55362 Expiration Date n/a Address

4. Identification of System Auto PressureRelief (APR), SRV-MSB-195 / Slave-Spare, Class 1

5. (a) Applicable Construction Code ASME Section III 1968E/ W'68A Edition /Addenda

,(b) Applicable Edition of Section XI Used for Repair/Replacement Activity 2001 Edition, No Addenda (c) Applicable Section XI Code Case(s) n/a

6. Identification of Components Corrected, ASME Code Name of Name of Manufacturer National Other Removed, or Staiped Component Manufacturer Serial No. Board No. Identification Year Built Installed YES NO Main Disc Target Rock 628 n/a SRV-MSB-195 2008 Removed II Z Main Disc Target Rock 4732 n/a SRV-MSB-195 2008 Installed [i Z El ED EDE

_T El El Replaced main disc during refurbishment of SRV-MSB-195 Main Body Test

7. Description of Work Slave per applicable steps of 4280-03-PM

8. Tests Conducted: Hydrostatic L] Pneumatic [] Nominal Operating Pressure []

Exempt El Other El Pressure n/a psi Test Temp n/a OF

.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 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form. (See 4 AWI-09.04.03 [ASME Section XI Repair/Replacement Program] for further documentation guidance.)

Approval: PCR 01148046 M/asc

MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: FORM NIS-2 OWNER'S REPORT FOR Revision 5 REPAIR/REPLACEMENT ACTIVITY Page 2 of 2 Repair/Replacement Plan No.: 2008-24-031

9. Remarks (Applicable Manufacturer's Data Reports to be Attached)

This valve main body #SRV-MSB-195 is for steam testing topworks only, is not being refurbished for plant use at this time, and per the system engineer, does not requirepost-repairfunctional testing.

GE Spec 21A9206 applies.

"Year Built" is the removal and the installation date. The replacement disc was built in 2003.

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

Signed SE ECTION,( 1', CObtZ-t Date IL3169 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 Hartford Steam Boiler Insp & Ins Company of Connecticut of Hartford, Connecticut have inspected the components described in this Owner's Report during the period I I/("c/' - to ý-1/3l 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 measures 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 Ig 11j-t A,,,.,, / /,.-

," <aL/vz,?-cc Inspector's Signature National Board, Province and Endorsements Date f / 3 0,g M/asc

MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: FORM NIS-2 OWNER'S REPORT FOR Revision 5 I REPAIR/REPLACEMENT ACTIVITY Page 1 of 2 1 Repair/Replacement Plan No.:2008-24-032

1. Owner NSP-Minnesota, an Xcel Energy Company Date 7/31/2009 Name 414 Nicollet Mall, Minneapolis, MN 55401 Sheet I of 2 Address

2. Plant Monticello Nuclear Generating Plant Unit 1 Name 2807 West County Road 75, Monticello, MN 55362 WO-3551 11, EC-10869 Address Repair Organization P.O. No., Job No. etc.

3. Work Performed By NSPM/Xcel Energy Type Code Symbol Stamp n/a Company Name Authorization No. n/a 2807 West County Rd. 75, Monticello, MN 55362 Expiration Date n/a Address

4. Identification of System Core Spray (CSP), MO-I 749, Class 2

5. (a) Applicable Construction Code B31.1 1977E/W'78A Edition / Addenda (b) Applicable Edition of Section Xl Used for Repair/Replacement Activity 2001 Edition, No Addenda (c) Applicable Section XI Code Case(s) n/a

6. Identification of Components Corrected, ASME Code Name of Name of Manufacturer National Other Removed, or Staiped Component Manufacturer Serial No. Board No. Identification Year Built Installed YES NO MO- 1749 Anchor Darling n/a n/a n/a 1969 removed El Z Bonnet Studs MO- 1749 Nova n/a n/a n/a Bonnet Studs 2009 installed E] 0 MO- 1749 Anchor Darling n/a n/a n/a 1969 removed El E Bonnet Nuts MO- 1749 Nova n/a n/a n/a 2009 installed El [

Bonnet Nuts El E Like for like replacementof (10) bonnet studs and (20) nuts (replacement

7. Description of Work studs/nuts built in 2008, installed in 2009).

8. Tests Conducted: Hydrostatic El Pneumatic El Nominal Operating Pressure El Exempt El Other El Pressure psi Test Temp oF 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 the number of sheets is recorded at the top of this form. (See 4 AWI-09.04.03 [ASME Section Xi RepairlReplacement Program] for further documentation guidance.)

Approval: PCR 01148046 M/asc

MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: FORM NIS-2 OWNER'S REPORT FOR Revision 5 REPAIR/REPLACEMENT ACTIVITY Page 2 of 2 Repair/Replacement Plan No.: 2008-24-032

9. Remarks (Applicable Manufacturer's Data Reports to be Attached)

Like for like replacement of bonnet nuts and studs during disassembly/reassemblyfor other scheduled valve work (reference EC-10869 for valve actuatorreplacement). Studs and nuts were preemptively replaceddue to possibility of damage.

No PMT or PSI required for bolting replacement.

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

Signed I 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 Hartford Steam Boiler Insp & Ins Company of Connecticut of Hartford, Connecticut have inspected the components described in this Owner's Report during the period _)/i 2-f to i-/ y/dl 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 measures 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-o-t-A /" - Commissions 4/2) /Iff-3 A ))A-' I hio, 0aI-e -(Co Inspector's Signature National Board, Province and Endorsements Date s-AK0 1 M/asc

MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: FORM NIS-2 OWNER'S REPORT FOR Revision 5 I REPAIR/REPLACEMENT ACTIVITY Page 1 of 2 Repair/Replacement Plan No.:2008-24-033

1. Owner NSP-Minnesota, an Xcel Energy Company Date 7/31/2009 Name 414 Nicollet Mall, Minneapolis, MN 55401 Sheet 1 of 2 Address

2. Plant Monticello Nuclear Generating Plant Unit 1 Name 2807 West County Road 75, Monticello, MN 55362 WO-3551 11, EC-10869 Address Repair Organization P.O. No., Job No. etc.

3. Work Performed By NSPM IXcel Energy Type Code Symbol Stamp n/a Company Name Authorization No. n/a 2807 West County Rd. 75, Monticello, MN 55362 Expiration Date n/a Address

4. Identification of System Core Spray (CSP), Class 2

5. (a) Applicable Construction Code B31.1 1977E/W'78A Edition / Addenda (b) Applicable Edition of Section Xl Used for Repair/Replacement Activity 2001 Edition, No Addenda (c) Applicable Section XI Code Case(s) n/a

6. Identification of Components Corrected, ASME Code Name of Name of Manufacturer National Other Removed, or Staiped Component Manufacturer Serial No. Board No. Identification Year Built Installed YES NO TWH-114 Bergen n/a n/a n/a 1969 removed E] 2 Paterson TWH- 114 Bergen n/a n/a n/a 2009 installed [] [

Paterson E] ED E] E]

El LI Modify hanger TWH-1 14 by replacing existing clamp with a heavierclamp (new

7. Description of Work clamp built in 2008, installedin 2009).

8. Tests Conducted: Hydrostatic E] Pneumatic E] Nominal Operating Pressure LI Exempt E] Other LI Pressure psi Test Temp 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 the number of sheets is recorded at the top of this form. (See 4 AWI-09.04.03 [ASME Section Xl Repair/Replacement Program] for further documentation guidance.)

Approval: PCR 01148046 M/asc

MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: FORM NIS-2 OWNER'S REPORT FOR Revision 5 REPAIR/REPLACEMENT ACTIVITY Page 2 of 2 Repair/Replacement Plan No.: 2008-24-033

9. Remarks (Applicable Manufacturer's Data Reports to be Attached)

Hanger TWH- 114 was modified due to revised piping loads (Reference EC-10869)

PSI VT-3 exam was performed.

Existing mod 83M026 also applies.

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

Signed lo oo'-D 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 Hartford Steam Boiler Insp & Ins Company of Connecticut of Hartford, Connecticut have inspected the components described in this Owner's Report during the period / a J-7 J- to If/ i )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 measures 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, Commissions 41g ,/ ,3 A ) ,t A'A/cVqol?, --t Inspector's Signature National Board, Province and Endorsements Date , /,ol M/asc

MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: FORM NIS-2 OWNER'S REPORT FOR Revision 5 1 REPAIR/REPLACEMENT ACTIVITY Page 1 of 2 Repair/Replacement Plan No.:2009-24-035

1. Owner NSP-Minnesota, an Xcel Energy Company Date 8/4/2009 Name 414 Nicollet Mall, Minneapolis, MN 55401 Sheet 1 of 3 Address

2. Plant Monticello Nuclear Generating Plant Unit 1 Name 2807 West County Road 75, Monticello, MN 55362 WO-374028 Address Repair Organization P.O. No., Job No. etc.

3. Work Performed By NSPMIXcelEnergy Type Code Symbol Stamp N/A Company Name Authorization No. N/A 2807 West County Rd. 75, Monticello, MN 55362 Expiration Date N/A Address

4. Identification of System RHR Service Water (RSW/ESW), Loop A, Class 3 1ý

5. (a) Applicable Construction Code B31.1 , 1977E/W'78A Edition /Addenda (b) Applicable Edition of Section Xl Used for Repair/Replacement Activity 2001 Edition, No Addenda (c) Applicable Section XI Code Case(s) N/A

6. Identification of Components Corrected, ASME Code Name of Name of Manufacturer National Other Removed, or Staiped Component Manufacturer Serial No. Board No. Identification Year Built Installed YES NO SR-399 Navco n/a n/a n/a 1969 removed E] 0 SR-399 Xcel Energy n/a n/a n/a 2009 installed El Z SR-469 Navco n/a n/a n/a 1969 removed LI ,

SR-469 Xcel Energy n/a n/a n/a 2009 installed El [

See subsequent sheets for additional items El El Removal and partialreplacement of supports by welding to facilitate piping

7. Description of Work replacement.

8. Tests Conducted: Hydrostatic El Pneumatic E] Nominal Operating Pressure E]

Exempt El Other El Pressure n/a psi Test Temp n/a OF 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 the number of sheets is recorded at the top of this form. (See 4 AWI-09.04.03 [ASME Section Xl RepairlReplacement Program] for further documentation guidance.)

Approval: PCR 01148046 M/asc

MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: FORM NIS-2 OWNER'S REPORT FOR Revision 5 REPAIR/REPLACEMENT ACTIVITY Page 2 of 2 Sheet 2 of 3 Repair/Replacement Plan No.: 2009-24-035

9. Remarks (Applicable Manufacturer's Data Reports to be Attached)

Supports were removed and partiallyreplaced by welding (SR-399, SR-469, and SR-105) to facilitate replacementof piping thinned due to MIC. Pipingreplacement was performed under a separate R/R Plan.

Additional supports (SR-397, SR-456, IS SWH-75, and IS SWH-76) were disassembled and reassembled to facilitate the piping replacement.

Weld Visual performed on welded supports. PSI VT-3 performed on all supports. Additionally, PSI VT-1 was performed on the integrally welded attachment of SR-105.

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

Signed .I )' Date f 4 o0 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 Hartford Steam Boiler Insp & Ins Company of Connecticut of Hartford, Connecticut have inspected the components described in this Owner's Report during the period 3/ /(, Pk4 to g-f./Pjo 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 measures 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.

KrAIA~r Commissions &g //,f'41 A, ,V'i.P N4/- 0 l\JLt-CO Inspector's Signature National Board, Province and Endorsements Date 8- /J-/(/1 M/asc

NSP-Minnesota, an Xcel Energy Company Sheet 3 of 3 414 Nicollet Mall, Minneapolis, MN 55401 Monticello Nuclear Generating Plant - Unit 1 2807 West County Road 75, Monticello, MN 55362 Work Performed By NSPM/Xcel Enerqy R/R Plan No. 2009-24-035 System RSW/ESW WO No. WO 374028 Construction Code B31.1, 1977E, W'78A Section Xl R/R Code 2001 Ed/No Add Section Xl Code Case(s) None Form NIS-2 Continuation Sheet Corrected, ASME Code Name of Name of Manufacturer National Other Removed, or Stamped Component Manufacturer Serial No. Board No. Identification Year Built Installed Yes No SR-105 Navco N/A N/A N/A 1969 Removed X SR-105 Xcel Energy N/A N/A N/A 2009 Installed X

+/- + + + + 4 4 +/- +/- + + F 4 4 f 4 +/- +/- F 4

+ -I- 4 4 ___

+ + + + + F 4 F 4 -I- + + + * + F 4 4 +/- 4- t + F 1 4 4- -I- t + F F 4 F F 4 4- F 4 F 4 F F 4 4- 4

MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: FORM NIS-2 OWNER'S REPORT FOR Revision 5 I REPAIR/REPLACEMENT ACTIVITY Page 1 of 2 Repair/Replacement Plan No.:2009-24-036

1. Owner NSP-Minnesota, an Xcel Energy Company Date 7/31/2009 Name 414 Nicollet Mall, Minneapolis, MN 55401 Sheet 1 of 2 Address

2. Plant Monticello Nuclear Generating Plant Unit 1 Name 2807 West County Road 75, Monticello, MN 55362 WO-362738, EC-11125 Address Repair Organization P.O. No., Job No. etc.

3. Work Performed By NSPMIXcel Energy Type Code Symbol Stamp n/a Company Name Authorization No. n/a 2807 West County Rd. 75, Monticello, MN 55362 Expiration Date n/a Address

4. Identification of System Residual Heat Removal (RHR), Class 2

5. (a) Applicable Construction Code B31.1 1977E / W'78A Edition /Addenda (b) Applicable Edition of Section XI Used for Repair/Replacement Activity 2001 Edition, No Addenda (c) Applicable Section Xl Code Case(s) n/a

6. Identification of Components Corrected, ASME Code Name of Name of Manufacturer National Other Removed, or Staiped Component Manufacturer Serial No. Board No. Identification Year Built Installed YES NO TWH-89 Bergen-Paterson n/a n/a n/a 1969 Removed U [

TWH-89 Anvil n/a n/a n/a 2009 Installed LI [

7. Description of Work Replace spring cans.

8. Tests Conducted: Hydrostatic U Pneumatic U1 Nominal Operating Pressure EF Exempt Ul Other U] Pressure psi Test Temp OF 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 the number of sheets is recorded at the top of this form. (See 4 AWI-09.04.03 [ASME Section Xi RepairlReplacement Program] for further documentation guidance.)

Approval: PCR 01148046 M/asc

MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: FORM NIS-2 OWNER'S REPORT FOR Revision 5 REPAIR/REPLACEMENT ACTIVITY Page 2 of 2 Repair/Replacement Plan No.: 2009-24-036

9. Remarks (Applicable Manufacturer's Data Reports to be Attached)

Spring cans were replaced due to change in piping load (ref. EC11125).

PSI VT-3 exam was performed.

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

Signed 9 SX**.c'1 Is. COom:z:: 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 Hartford Steam Boiler Insp & Ins Company of Connecticut of Hartford, Connecticut have inspected the components described in this Owner's Report during the period vh/7 I0 to s-/Iq1,Jq 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 measures 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.

&TAKL444( Commissions /v,61 it, 3 0,&A,'" /I&,, vo -*_f-C Inspector's Signature National Board, Province and Endorsements Date M/asc

MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: FORM NIS-2 OWNER'S REPORT FOR Revision 5 REPAIR/REPLACEMENT ACTIVITY Page 1 of 2 Repair/Replacement Plan No.:2009-24-037

1. Owner NSP-Minnesota, an Xcel Energy Company Date 7/31/2009 Name 414 Nicollet Mall, Minneapolis, MN 55401 Sheet 1 of 2 Address

2. Plant Monticello Nuclear Generating Plant Unit 1 Name 2807 West County Road 75, Monticello, MN 55362 WO-362738, EC-11125 Address Repair Organization P.O. No., Job No. etc.

3. Work Performed By NSPM/Xcel Energy Type Code Symbol Stamp n/a Company Name Authorization No. n/a 2807 West County Rd. 75, Monticello, MN 55362 Expiration Date n/a Address

4. Identification of System Core Spray (CSP), Class 2

5. (a) Applicable Construction Code B31.1 I 1977E/W'78A Edition /Addenda (b) Applicable Edition of Section XI Used for Repair/Replacement Activity 2001 Edition, No Addenda (c) Applicable Section XI Code Case(s) n/a

6. Identification of Components Corrected, ASME Code Name of Name of Manufacturer National Other Removed, or Staiped Component Manufacturer Serial No. Board No. Identification Year Built Installed YES NO SR- 113 NSP n/a n/a n/a 1969 Corrected E] 0 E] E]

7E 0

7. Description of Work Modified support.

8. Tests Conducted: Hydrostatic LI Pneumatic EL Nominal Operating Pressure EL Exempt EL Other LI Pressure psi Test Temp 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 the number of sheets is recorded at the top of this form. (See 4 AWI-09.04.03 [ASME Section XI RepairlReplacement Program] for further documentation guidance.)

Approval: PCR 01148046 M/asc

MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: FORM NIS-2 OWNER'S REPORT FOR Revision 5 REPAIR/REPLACEMENT ACTIVITY Page 2 of 2 Repair/Replacement Plan No.: 2009-24-037

9. Remarks (Applicable Manufacturer's Data Reports to be Attached)

Bumper plates were added to existing support for additionalrestraintbased on EC-11125).

Weld visual performed.

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

Signed *1 l SeT-m X 151 C*

CoP--O. Date Q/q/07 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 Hartford Steam Boiler Insp & Ins Company of Connecticut of Hartford, Connecticut have inspected the components described in this Owner's Report during the period 3 /Z-3 /,j to R-[/V /hI 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 measures 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.

ýý, AlJd, Q tý Inspector's Signature Commissions /1V*/J*3 A*, "

National Board, Province oa ".i2J*-Cc2 and Endorsements Date i - T I M/asc

MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: FORM NIS-2 OWNER'S REPORT FOR Revision 5 I REPAIR/REPLACEMENT ACTIVITY Page 1 of 2 1 Repair/Replacement Plan No.:2009-24-039

1. Owner NSP-Minnesota, an Xcel Energy Company Date 7/31/2009 Name 414 Nicollet Mall, Minneapolis, MN 55401 Sheet I of 2 Address

2. Plant Monticello Nuclear Generating Plant Unit 1 Name 2807 West County Road 75, Monticello, MN 55362 WO-362738, EC-11125 Address Repair Organization P.O. No., Job No. etc.

3. Work Performed By NSPM/XcelEnergy Type Code Symbol Stamp n/a Company Name Authorization No. n/a 2807 West County Rd. 75, Monticello, MN 55362 Expiration Date n/a Address

4. Identification of System Residual Heat Removal (RHR), Class 2

5. (a) Applicable Construction Code B31.1 1977E / W'78A Edition / Addenda (b) Applicable Edition of Section XI Used for Repair/Replacement Activity 2001 Edition, No Addenda (c) Applicable Section XI Code Case(s) n/a

6. Identification of Components Corrected, ASME Code Name of Name of Manufacturer National Other Removed, or Staiped Component Manufacturer Serial No. Board No. Identification Year Built Installed YES NO TWH-144 Bergen-Paterson n/a n/a n/a 1969 Removed El Z TWH-144 Anvil n/a n/a n/a 2009 Installed E. 0 E] EL E7 EL

7. Description of Work Replaced spring can.

8. Tests Conducted: Hydrostatic El Pneumatic El Nominal Operating Pressure El Exempt El Other FE Pressure psi Test Temp OF 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 the number of sheets is recorded at the top of this form. (See 4 AWI-09.04.03 [ASME Section XI Repair/Replacement Program] for further documentation guidance.)

Approval: PCR 01148046 M/asc

MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: FORM NIS-2 OWNER'S REPORT FOR Revision 5 REPAIR/REPLACEMENT ACTIVITY Page 2 of 2 Repair/Replacement Plan No.: 2009-24-039

9. Remarks (Applicable Manufacturer's Data Reports to be Attached)

Spring can was replaceddue to change in piping load (ref. EC 11125).

PSI VT-3 exam was performed.

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

Signed ' -'I Se-nob(-(,Kt /51 C:z- Date _/____3 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 Hartford Steam Boiler Insp & Ins Company of Connecticut of Hartford, Connecticut have inspected the components described in this Owner's Report during the period q )/7 /h i to b-/tj//q 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 measures 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 447f I/oY- *A ,AJ h-cqatZ-co Inspector's Signature National Board, Province and Endorsements Date M/asc

MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: FORM NIS-2 OWNER'S REPORT FOR Revision 5 I REPAIR/REPLACEMENT ACTIVITY Page 1 of 2 Repair/Replacement Plan No.:2009-24-040

1. Owner NSP-Minnesota, an Xcel Enerqy Company Date 7/31/2009 Name 414 Nicollet Mall, Minneapolis, MN 55401 Sheet I of 2 Address

2. Plant Monticello Nuclear Generating Plant Unit 1 Name 2807 West County Road 75, Monticello, MN 55362 WO-380817 Address Repair Organization P.O. No., Job No. etc.

3. Work Performed By NSPM/XcelEnergy Type Code Symbol Stamp n/a Company Name Authorization No. n/a 2807 West County Rd. 75, Monticello, MN 55362 Expiration Date n/a Address

4. Identification of System Reactor Core Isolation Cooling (RCIC), Steam Supply, Class 2

5. (a) Applicable Construction Code B31.1 , 1977E/W'78A Edition/Addenda (b) Applicable Edition of Section XI Used for Repair/Replacement Activity 2001 Edition, No Addenda (c) Applicable Section XI Code Case(s) n/a

6. Identification of Components Corrected, ASME Code Name of Name of Manufacturer National Other Removed, or Staiped Component Manufacturer Serial No. Board No. Identification Year Built Installed YES NO PS-17-3"ED unknown n/a n/a n/a 2007 Removed RZ Z PS-17-3"ED unknown n/a n/a n/a 2009 Installed ED Z ED ED ED ED ED ED

7. Description of Work Removed/reinstalled section of due to interference with adjacent work.

8. Tests Conducted: Hydrostatic E] Pneumatic 0 Nominal Operating Pressure Z Exempt El Other FD Pressure 955 psi Test Temp n/a OF 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 the number of sheets is recorded at the top of this form. (See 4 AWI-09.04.03 [ASME Section XI Repair/Replacement Program] for further documentation guidance.)

Approval: PCR 01148046 M/asc

MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: FORM NIS-2 OWNER'S REPORT FOR Revision 5 REPAIR/REPLACEMENT ACTIVITY Page 2 of 2 Repair/Replacement Plan No.: 2009-24-040

9. Remarks (Applicable Manufacturer's Data Reports to be Attached)

A small section of piping in the steam chase was removed and reinstalleddue to interference with adjacent MSIVA O-2-86D actuatormaintenance activities. Pinned support PSH-114 and restored.

Disassembled and reassembled associatedsupport PSH-1 15.

R T performed following reinstallationof piping.

No PSI required.

System leakage test with VT-2 performed during RCIC System Leakage Test 0255-08-11C-1.

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

Signed S"!ErnO Y k( COO5- 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 Hartford Steam Boiler Insp & Ins Company of Connecticut of Hartford, Connecticut have inspected the components described in this Owner's Report during the period 1/2 7/0I to r/J lIgI 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 measures 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.

v4/jAlb 41 Commissions 4," /I ) A/, i4 Q01/

I bAV o -CV

,,p"F Inspector's Signature National Board, Province and Endorsements Date Dat g (-3/ ,

M/asc

MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: FORM NIS-2 OWNER'S REPORT FOR Revision 5 I REPAIR/REPLACEMENT ACTIVITY Page 1 of 2 Repair/Replacement Plan No.:2009-24-041

1. Owner NSP-Minnesota, an Xcel Energy Company Date 7/30/2009 Name 414 Nicollet Mall, Minneapolis, MN 55401 Sheet I of 2 Address

2. Plant Monticello Nuclear Generating Plant Unit 1 Name 2807 West County Road 75, Monticello, MN 55362 WO-359136 Address Repair Organization P.O. No., Job No. etc.

3. Work Performed By NSPMIXcelEnergy Type Code Symbol Stamp n/a Company Name Authorization No. n/a 2807 West County Rd. 75, Monticello, MN 55362 Expiration Date n/a Address

4. Identification of System High Press Coolant Injection (HPC), MO-2035, Class 2

5. (a) Applicable Construction Code B31.1 1977E / W'78A Edition /Addenda (b) Applicable Edition of Section XI Used for Repair/Replacement Activity 2001 Edition, No Addenda (c) Applicable Section XI Code Case(s) n/a

6. Identification of Components Corrected, ASME Code Name of Name of Manufacturer National Other Removed, or Staiped Component Manufacturer Serial No. Board No. Identification Year Built Installed YES NO MO-2036 unknown n/a n/a n/a 1978 Removed [] Z Bonnet Bolt MO-2036 Cardinal n/a n/a Ht# 80768 1991 Installed Bonnet Bolt El 0 El E]

E] E]

Like for like replacementof one bonnet flange bolt on MO-2036. Bolt installed in

7. Description of Work 2009

8. Tests Conducted: Hydrostatic El Pneumatic El Nominal Operating Pressure El Exempt EL Other Ml Pressure _psi Test Temp 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 the number of sheets is recorded at the top of this form. (See 4 AWI-09.04.03 [ASME Section XI RepairlReplacement Program] for further documentation guidance.)

Approval: PCR 01148046 M/asc

MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: FORM NIS-2 OWNER'S REPORT FOR Revision 5 REPAIR/REPLACEMENT ACTIVITY Page 2 of 2 Repair/Replacement Plan No.: 2009-24-041

9. Remarks (Applicable Manufacturer's Data Reports to be Attached)

Like-for-like replacement of one bonnet bolt (A 193 Gr. B7) for MO-2036 due to damage during valve disassembly.

No PMT required for bolting replacement.

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

Signed _ ,-,t-ro*)-4X( ISI Coo .zO Date

2-.07 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 Hartford Steam Boiler Insp & Ins Company of Connecticut of Hartford, Connecticut have inspected hhe components described in this Owner's Report during the period 3 /.1 /-"- to -/ LI/0 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 measures 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.

'K 449 Commissions iv/g It/,(, i , 1 1" Aflv Oc*0r,1z-e(

/jV Inspector's Signature National Board, Province and Endorsements Date _ _ _ _ _ _ _ _ _

M/asc

MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: FORM NIS-2 OWNER'S REPORT FOR Revision 5 1 REPAIR/REPLACEMENT ACTIVITY Page 1 of 2 Repair/Replacement Plan No.:2009-24-042

1. Owner NSP-Minnesota, an Xcel Enerqv Company Date 7/29/2009 Name 414 Nicollet Mall, Minneapolis, MN 55401 Sheet 1 of 2 Address

2. Plant Monticello Nuclear Generating Plant Unit 1 Name 2807 West County Road 75, Monticello, MN 55362 WO-344367 Address Repair Organization P.O. No., Job No. etc.

3. Work Performed By NSPM/XcelEnergy Type Code Symbol Stamp n/a Company Name Authorization No. n/a 2807 West County Rd. 75, Monticello, MN 55362 Expiration Date n/a Address

4. Identification of System Primary Containment (PCT), Drywell Head, Class MC

5. (a) Applicable Construction Code ASME Section III 1965E/1967A Edition / Addenda (b) Applicable Edition of Section Xl Used for Repair/Replacement Activity 2001 Edition, No Addenda (c) Applicable Section Xl Code Case(s) n/a

6. Identification of Components Corrected, ASME Code Name of Name of Manufacturer National Other Removed, or Staiped Component Manufacturer Serial No. Board No. Identification Year Built Installed YES NO Drywell Head Chicago Bridge n/a n/a 1969 Removed El Z FlanaeNut & Iron Drywell Head Chicago Bridge n/a Ht# 6390344 1975 Installed El Z Flange Nut & Iron _ _ _ _ 6390344

_ _ 197 _Istlld_]_

El1 E]

El1 El

7. Description of Work Replaced 1 nut at location 55 on drywell head. Installed in 2009.

8. Tests Conducted: Hydrostatic El Pneumatic El Nominal Operating Pressure El Exempt El Other El Pressure psi Test Temp OF 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 the number of sheets is recorded at the top of this form. (See 4 AWI-09.04.03 [ASME Section XI Repair/Replacement Program] for further documentation guidance.)

Approval: PCR 01148046 M/asc

MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: FORM NIS-2 OWNER'S REPORT FOR Revision 5 REPAIR/REPLACEMENT ACTIVITY Page 2 of 2 Repair/Replacement Plan No.: 2009-24-042

9. Remarks (Applicable Manufacturer's Data Reports to be Attached)

Nut replaced due to a slight protrusionon the nut face that contacts the washer.

Preservice VT-1 performed per WO-344367 task 02 (reference ISI report 2009VT103).

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

Signed : SEC.oNX I., IS' ý Cf N 5 Date 712-9102 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 Hartford Steam Boiler Insp & Ins Company of Connecticut of Hartford, Connecticut have inspected the components described in this Owner's Report during the period -/1Zo /,a to 7 /3J AiV 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 measures 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 0-//qjr /t &Z /*/,Lox-co Inspector's Signature National Board, Province and Endorsements Date 7 / ~o M/asc

MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: FORM NIS-2 OWNER'S REPORT FOR Revision 5 1 REPAIR/REPLACEMENT ACTIVITY Page 1 of 2 Repair/Replacement Plan No.:2009-24-043

1. Owner NSP-Minnesota, an Xcel Energy Company Date 8/3/2009 Name 414 Nicollet Mall, Minneapolis, MN 55401 Sheet 1 of 3 Address

2. Plant Monticello Nuclear Generating Plant Unit 1 Name 2807 West County Road 75, Monticello, MN 55362 WO-381681 Address Repair Organization P.O. No., Job No. etc.

3. Work Performed By NSPM/Xcel Energy Type Code Symbol Stamp N/A Company Name Authorization No. N/A 2807 West County Rd. 75, Monticello, MN 55362 Expiration Date N/A Address

4. Identification of System Emergency Service Water (FSW), SW3OB-3"-HF, Class 3

5. (a) Applicable Construction Code B31.1 , 1977E/W'78A Edition/Addenda (b) Applicable Edition of Section XI Used for Repair/Replacement Activity 2001 Edition, No Addenda (c) Applicable Section XI Code Case(s) N/A

6. Identification of Components Corrected, ASME Code Name of Name of Manufacturer National Other Removed, or Staiped Component Manufacturer Serial No. Board No. Identification Year Built Installed YES NO 3" Pipe and Dubose N/A N/A N/A 2009 Installed El 0 Fittinqs 4" x 4" x 1/2" Not specified N/A N/A N/A 2009 Installed El E Tube Steel 3" x 3"x 1/4" Dubose N/A N/A N/A 2009 Installed Eli Z Tube Steel 1/2" Plate Dubose N/A N/A N/A 2009 Installed LI Z 1/2" Lug Dubose N/A N/A N/A 2009 Installed EII Z

7. Description of Work Reroute portion of SW3OB-3"-HF line due to HELB effect of FW5-4"-ED

8. Tests Conducted: Hydrostatic E] Pneumatic E] Nlominal Operating Pressure Z Exempt El Other L] Pressure 77 psi Test Temp N/A OF 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 the number of sheets is recorded at the top of this form. (See 4 AWI-09.04.03 [ASME Section Xl Repair/Replacement Program] for further documentation guidance.)

Approval: PCR 01148046 M/asc

MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: FORM NIS-2 OWNER'S REPORT FOR Revision 5 REPAIR/REPLACEMENT ACTIVITY Page 2 of 2 Sheet 2 of 3 Repair/Replacement Plan No.: 2009-24-043

9. Remarks (Applicable Manufacturer's Data Reports to be Attached)

Some of the existing supports, i.e., SR-37, SWH-303, SWH-302, SR-37C, SR-38, SR-13, SR-13A, SWH-218, SR-14, SWH-219, SR-15 and SR-237 were abandonedin place.

Additional supports, i.e., SW30B-HI, SW30B-H2, SW3OB-H3, and SW30B-H4, were required to be added for the reroutedpipe.

Tube and plate stock listed was used in fabrication of new supports. EC-14036 applies.

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

Signed Sc-'r Or X SI c 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 Hartford Steam Boiler Insp & Ins Company of Connecticut of Hartford, Connecticut have inspected the components described in this Owner's Report during the period 1/ C/ t9 to r /? /d9 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 measures 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.

K.-V 44--ý Inspector's Signature Commissions XI? //,uz' AcJ ,o -

National Board, Province and Endorsements Date 8-/1, lae M/asc

NSP-Minnesota, an Xcel Energy Company Sheet 3 of 3 414 Nicollet Mall, Minneapolis, MN 55401 Monticello Nuclear Generating Plant - Unit 1 2807 West County Road 75, Monticello, MN 55362 Work Performed By NSPMIXcel Energy R/R Plan No. 2009-24-043 System FSW WO No. WO 381681 Construction Code B31.1. 1977E. W'78A Section Xl R/R Code 2001 Ed/No Add Section Xl Code Case(s) None Form NIS-2 Continuation Sheet Corrected, ASME Code Name of Name of Manufacturer National Other Removed, or Stam ped Component Manufacturer Serial No. Board No. Identification Year Built Installed Yes No W4 W4 x 13 Dubose N/A N/A N/A 2009 Installed X Beam 5/8" Stud Nova N/A N/A N/A 2009 Installed X SR-37 NSP N/A N/A N/A 1969 AbandonedX in place Abandoned SWH-303 NSP N/A N/A N/A 1969 XA in place SWH-302 NSP N/A N/A N/A 1969 AbandonedX in place SR-37C NSP N/A N/A N/A 1969 AbandonedX in place SR-38 NSP N/A N/A N/A 1969 AbandonedX in place SR-13 NSP N/A N/A N/A 1969 Abandoned

________in place SR-13A NSP N/A N/A N/A 1969 Abandonedx in place SWH-218 NSP N/A NIA N/A 1969 Abandoned in placeX SR-14 NSP N/A N/A N/A 1969 AbandonedX in place SWH-219 NSP N/A N/A N/A 1969 AbandonedX in place SR-15 NSP N/A N/A N/A 1969 AbandonedX in place SR-237 NSP N/A N/A N/A 1969 AbandonedX in place SW3OB-HI Xcel Energy N/A N/A N/A 2009 Installed X SW3OB-H2 Xcel Energy N/A N/A NIA 2009 Installed X SW30B-H3 Xcel Energy N/A N/A N/A 2009 Installed X SW3OB-H4 Xcel Energy N/A N/A N/A 2009 Installed X

MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: FORM NIS-2 OWNER'S REPORT FOR Revision 5 I REPAIR/REPLACEMENT ACTIVITY Page 1 of 2 Repair/Replacement Plan No.:2009-24-044

1. Owner NSP-Minnesota, an Xcel Energy Company Date 7/31/2009 Name 414 Nicollet Mall, Minneapolis, MN 55401 Sheet I of 2 Address

2. Plant Monticello Nuclear Generating Plant Unit 1 Name 2807 West County Road 75, Monticello, MN 55362 WO-380817 Address Repair Organization P.O. No., Job No. etc.

3. Work Performed By NSPMIXcel Energy Type Code Symbol Stamp n/a Company Name Authorization No. n/a 2807 West County Rd. 75, Monticello, MN 55362 Expiration Date n/a Address

4. Identification of System Main Steam "D" (MST), AO-2-86D, Class 1

5. (a) Applicable Construction Code B31.1 , 1977E/ W78A Edition / Addenda (b) Applicable Edition of Section XI Used for Repair/Replacement Activity 2001 Edition, No Addenda (c) Applicable Section XI Code Case(s) n/a

6. Identification of Components Corrected, ASME Code Name of Name of Manufacturer National Other Removed, or Staiped Component Manufacturer Serial No. Board No. Identification Year Built Installed YES NO Studs (3) Anchor/Darling n/a n/a n/a various removed El 0 Studs (3) Anchor/Darling n/a n/a Ht# 25748 2009 installed [] Z Nuts (20) Anchor/Darling n/a n/a n/a 1994 removed E] ED Nuts (20) Nova n/a n/a Ht# 8898297 2009 installed [] [

E] El Replaced fasteners damaged during disassembly for maintenance. Studs: A 193

7. Description of Work Gr. B7 built 1994, installed 2009; Nuts: A194 Gr.2H, built 2003, installed2009.

8. Tests Conducted: Hydrostatic L] Pneumatic EL Nominal Operating Pressure I--I Exempt El Other Rl Pressure n/a psi Test Temp n/a OF 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 the number of sheets is recorded at the top of this form. (See 4 AWI-09.04.03 [ASME Section XI RepairlReplacement Program] for further documentation guidance.)

Approval: PCR 01148046 M/asc

MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: FORM NIS-2 OWNER'S REPORT FOR Revision 5 REPAIR/REPLACEMENT ACTIVITY Page 2 of 2 Repair/Replacement Plan No.: 2009-24-044

9. Remarks (Applicable Manufacturer's Data Reports to be Attached)

Preservice VT-I performed on replacementfasteners.

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

Signed -Q t1 Date oIS 6/3f 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 Hartford Steam Boiler Insp & Ins Company of Connecticut of Hartford, Connecticut have inspected the components described in this Owner's Report during the period -f / ? to 61.7 l'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 Xl.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures 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 X/V')/oJr_3 ,q,4/jj- ,/1AoL,QP1-d Inspector's Signature National Board, Province and Endorsements Date F__'_

_ _ __q M/asc

-MONTICELLONUCLEAR GENERATING PLANT 3613 TITLE: FORM NIS-2 OWNER'S REPORT FOR Revision 5 I REPAIR/REPLACEMENT ACTIVITY Page 1 of 2 Repair/Replacement Plan No.:2009-24-045

1. Owner NSP-Minnesota, an Xcel Energy Company Date 7/31/2009 Name 414 Nicollet Mall, Minneapolis, MN 55401 Sheet 1 of 2 Address

2. Plant Monticello Nuclear Generating Plant Unit 1 Name 2807 West County Road 75, Monticello, MN 55362 WO-380817 Address Repair Organization P.O. No., Job No. etc.

3. Work Performed By NSPM/XcelEnergy Type Code Symbol Stamp n/a Company Name Authorization No. n/a 2807 West County Rd. 75, Monticello, MN 55362 Expiration Date n/a Address

4. Identification of System Main Steam "D"(MST), AO-2-86D, Class I

5. (a) Applicable Construction Code B31.1 1977E / W'78A Edition / Addenda (b) Applicable Edition of Section Xl Used for Repair/Replacement Activity 2001 Edition, No Addenda (c) Applicable Section XI Code Case(s) n/a

6. Identification of Components Corrected, ASME Code Name of Name of Manufacturer National Other Removed, or Staiped Component Manufacturer Serial -No. Board No. Identification Year Built Installed YES NO DS Seat Ring Anchor Darling n/a n/a n/a 1994 removed [] 0 DS Seat Ring Anchor Darling PC #1 n/a Ht #C8789 2009 installed ED N ED D]

El ED ED ED

7. Description of Work Damaged downstream seat ring replaced with like for like seat ring.

8. Tests Conducted: Hydrostatic D Pneumatic LI Nominal Operating Pressure El Exempt R] Other LI Pressure n/a psi Test Temp n/a OF 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 the number of sheets is recorded at the top of this form. (See 4 AWI-09.04.03 [ASME Section XI Repair/Replacement Program] for further documentation guidance.)

Approval: PCR 01148046 M/asc

MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: FORM NIS-2 OWNER'S REPORT FOR Revision 5 REPAIR/REPLACEMENT ACTIVITY Page 2 of 2 Repair/Replacement Plan No.: 2009-24-045

9. Remarks (Applicable Manufacturer's Data Reports to be Attached)

Weld Visual of new seat ring to body weld.

Valve functional testing completed: Stroke time open /close (STO/STC), position indication (PIT),

Appx J/LLRT (LT), Fail Close (FC). PartialStoke (PS) is satisfied by STO/STC.

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

Signed ' 0 NX,) I S)I Co Date 8L3109 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 Hartford Steam Boiler Insp & Ins Company of Connecticut of Hartford, Connecticut have inspected the components described in this Owner's Report during the period vi/t, J9q to 513 )XI 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 measures 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 14 /1443 A,/'iJ? OOt/Ja,'CV Inspector's Signature National Board, Province and Endorsements Date /al Datte'(

M/asc

MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: FORM NIS-2 OWNER'S REPORT FOR Revision 5 REPAIR/REPLACEMENT ACTIVITY Page 1 of 2 Repair/Replacement Plan No.:2009-24-046

1. Owner NSP-Minnesota, an Xcel Energy Company Date 8/4/2009 Name 414 Nicollet Mall, Minneapolis, MN 55401 Sheet I of 2 Address

2. Plant Monticello Nuclear Generating Plant Unit 1 Name 2807 West County Road 75, Monticello, MN 55362 WO-381724 Address Repair Organization P.O. No., Job No. etc.

3. Work Performed By NSPM/Xcel Energy Type Code Symbol Stamp n/a Company Name Authorization No. n/a 2807 West County Rd. 75, Monticello, MN 55362 Expiration Date n/a Address

4. Identification of System RHR Service Water (RHRSW/ESW), Loop A, Class 3

5. (a) Applicable Construction Code B31.1 1977E/ W'78AEdition / Addenda (b) Applicable Edition of Section XI Used for Repair/Replacement Activity 2001 Edition, No Addenda (c) Applicable Section XI Code Case(s) n/a

6. Identification of Components Corrected, ASME Code Name of Name of Manufacturer National Other Removed, or Staiped Component Manufacturer Serial No. Board No. Identification Year Built Installed YES NO SW9-18"-GF Navco n/a n/a n/a 1969 Removed El Z SW9-18"-GF Dubose n/a n/a n/a 2009 Installed [] Z SR-457 NSP n/a n/a n/a 1969 Corrected LI Z LIE]

LID[

Like-for-like replacement of piping and elbow due to MIC thinning. Also

7. Description of Work temporary lifting padeyes installed on, and removed from, SR-457.

8. Tests Conducted: Hydrostatic El Pneumatic El Nominal Operating Pressure 0 Exempt 0] Other n] Pressure 245 psi Test Temp n/a OF NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8-1/2 in x 1I in, (2) information in items I through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form. (See 4 AWI-09.04.03 [ASME Section XI Repair/Replacement Program] for further documentation guidance.)

Approval: PCR 01148046 M/asc

MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: FORM NIS-2 OWNER'S REPORT FOR Revision 5 REPAIR/REPLACEMENT ACTIVITY Page 2 of 2 Repair/Replacement Plan No.: 2009-24-046

9. Remarks (Applicable Manufacturer's Data Reports to be Attached)

Approx 100 ft of pipe and the downstream elbow replaced in the tunnel to the intake structure.

System leakage test with VT-2 per work orderPMT at normal operatingpressure.

PSI VT-3 performed on affected supports: SR-450, SR-451, SR-452, SR-453, SR-454, SR-455, SR-457, and SWH-8. MT performed on SR-457 temporary padeye installationlocations.

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

Signed 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 Hartford Steam Boiler Insp & Ins Company of Connecticut of Hartford, Connecticut have inspected the components described in this Owner's Report during the period 'i/i//Ide to if /,/ 6,*h*

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 measures 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 k/-'/g 3 4, A/, Z7 /-k/A/ 00 VizZS'-(o Inspector's Signature National Board, Province and Endorsements Date M/asc

MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: FORM NIS-2 OWNER'S REPORT FOR Revision 5 I REPAIR/REPLACEMENT ACTIVITY Page 1 of 2 Repair/Replacement Plan No.:2009-24-047

1. Owner NSP-Minnesota, an Xcel Energy Company Date 7/30/2009 Name 414 Nicollet Mall, Minneapolis, MN 55401 Sheet 1 of 2 Address

2. Plant Monticello Nuclear Generating Plant Unit 1 Name 2807 West County Road 75, Monticello, MN 55362 WO-383235, EC-14055 Address Repair Organization P.O. No., Job No. etc.

3. Work Performed By NSPMIXcel Energy Type Code Symbol Stamp n/a Company Name Authorization No. n/a 2807 West County Rd. 75, Monticello, MN 55362 Expiration Date n/a Address

4. Identification of System RHR-SWB Loop (RSVL'9, Class 3

5. (a) Applicable Construction Code B31.1 1977E/W'78A Edition / Addenda (b) Applicable Edition of Section XI Used for Repair/Replacement Activity 2001 Edition, No Addenda (c) Applicable Section Xl Code Case(s) N-661

6. Identification of Components Corrected, ASME Code Name of Name of Manufacturer National Other Removed, or Staiped Component Manufacturer Serial No. Board No. Identification Year Built Installed YES NO SW10-18"-GF Navco n/a n/a n/a 1969 Corrected 1:1 E E] E]

7. Description of Work Weld overlay repairfor two MIC thinned areasper Code Case N-661.

8. Tests Conducted: Hydrostatic EL Pneumatic W] Noominal Operating Pressure EW Exempt Z Other W] Pressure n/a psi Test Temp n/a OF 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 the number of sheets is recorded at the top of this form. (See 4 AWI-09.04.03 [ASME Section Xi Repair/Replacement Program] for further documentation guidance.)

Approval: PCR 01148046 M/asc

MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: FORM NIS-2 OWNER'S REPORT FOR Revision 5 REPAIR/REPLACEMENT ACTIVITY Page 2 of 2 Repair/Replacement Plan No.: 2009-24-047

9. Remarks (Applicable Manufacturer's Data Reports to be Attached)

Weld repairof two MIC thinned areasper Code Case N-661.

Pre and post overlay MT performed.

Post overlay UT thickness testing performed.

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

Signed I g 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 Hartford Steam Boiler Insp & Ins Company of Connecticut of Hartford, Connecticut have inspected the components described in this Owner's Report during the period I /I- l? to S/3 /J-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 measures 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.

~t&~

Commissions -A/* J'r63 4, *,j /f,voo a#,a~y-co Inspector's Signature National Board, Province and Endorsements Date 7ý /,) Id -

M/asc

MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: FORM NIS-2 OWNER'S REPORT FOR Revision 5 1 REPAIR/REPLACEMENT ACTIVITY Page 1 of 2 Repair/Replacement Plan No. :2009-24-048

1. Owner NSP-Minnesota, an Xcel Energy Company Date 7/30/2009 Name 414 Nicollet Mall, Minneapolis, MN 55401 Sheet I of 3 Address

2. Plant Monticello Nuclear Generating Plant Unit 1 Name 2807 West County Road 75, Monticello, MN 55362 WO 381679, EC 9174 Address Repair Organization P.O. No., Job No. etc.

3. Work Performed By NSPM/XcelEnergy Type Code Symbol Stamp n/a Company Name Authorization No. n/a 2807 West County Rd. 75, Monticello, MN 55362 Expiration Date n/a Address

4. Identification of System Main Steam (MST)); Loops A, B, C, D; Class I

5. (a) Applicable Construction Code B31.1 77W78 Edition / Addenda (b) Applicable Edition of Section Xl Used for Repair/Replacement Activity 2001 Edition, No Addenda (c) Applicable Section XI Code Case(s) n/a

6. Identification of Components Corrected, ASME Code Name of Name of Manufacturer National Other Removed, or Staiped Component Manufacturer Serial No. Board No. Identification Year Built Installed YES NO Strain Gage HITEC Product na na na 2007 Removed [] [

PSI-18"-ED Strain Gage HITEC Product na na na 2007 Removed E] 1K PS2-18"-ED I Strain Gage HITEC Product na na na 2007 Removed LI [

PS3-18"-ED_

Strain Gage HITEC Product na na na 2007 Removed El E PS4-1 8"-ED I

7. Description of Work Install replacements for failed main steam line straingages. See Remarks

8. Tests Conducted: Hydrostatic F] Pneumatic F1 Nominal Operating Pressure F1 Exempt El Other El Pressure psi Test Temp na OF 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 the number of sheets is recorded at the top of this form. (See 4 AWI-09.04.03 [ASME Section Xl Repair/Replacement Program] for further documentation guidance.)

Approval: PCR 01148046 M/asc

MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: FORM NIS-2 OWNER'S REPORT FOR Revision 5 REPAIR/REPLACEMENT ACTIVITY Page 2 of 2 Sheet 2 of 3 Repair/Replacement Plan No.: 2009-24-048

9. Remarks (Applicable Manufacturer's Data Reports to be Attached)

A number of strain gages installed in 2007 failed and required replacement.

MT performed at strain gage removal areas.

21 gages removed (locations MSA-1, 7, 14; MSB-4, 8, 9, 11, 12, 13, 16; MSC-1, 2, 6, 12, 14, 16; MSC-2, 4, 8, 11, 13). Reference CAP AIR-0 1178704.

19 gages replaced(MSA-1, 7, 14; MSB-4, 8, 9, 11, 13; MSC-1, 2, 6, 12, 14, 16; MSD-2, 4, 8, 11, 13)

MSB-12 and 16 not replaced.

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

Signed . 1 , '. Date ý13/09 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 Hartford Steam Boiler Insp & Ins Company of Connecticut of Hartford, Connecticut have inspected the components described in this Owner's Report during the period v//J /,jet Ito ,.f/31 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 measures 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.

634- L Commissions k 1fK7 j44A,*t44..OO (L-tc' Inspector's Signature National Board, Province and Endorsements Date _ _ __io_

M/asc

NSP-Minnesota, an Xcel Energy Company Sheet 3 of 3 414 Nicollet Mali, Minneapolis, MN 55401 Monticello Nuclear Generating Plant - Unit 1 2807 West County Road 75, Monticello, MN 55362 Work Performed By NSPMIXcel Energy R/R Plan No. 2009-24-048 System Main Steam, MST WO No. WO 381679 Construction Code B31.1, 1977E, W'78A Section Xl R/R Code 2001 Ed/No Add Section Xl Code Case(s) None Form NIS-2 Continuation Sheet Corrected, ASME Code Name of Name of Manufacturer National Other Removed, or Stamped Component Manufacturer Serial No. Board No. Identification Year Built Installed Yes No Strain Gage HITEC na na na 2009 Installed x PSI -18"-ED Product Strain Gage HITEC na na na 2009 Installed x PS2-I8"ED Product Strain Gage HITEC na na na 2009 Installed x PS3-I8"ED Product Strain Gage HITEC na na na 2009 Installed x PS4-18"-ED Product I F I + F + + 4

___ ___ ___I __ ___ __ ___ _ _

MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: FORM NIS-2 OWNER'S REPORT FOR Revision 5 REPAIR/REPLACEMENT ACTIVITY Page 1 of 2 Repair/Replacement Plan No.:2009-24-049

1. Owner NSP-Minnesota, an Xcel Energy Company Date 7/31/2009 Name 414 Nicollet Mall, Minneapolis, MN 55401 Sheet I of 2 Address

2. Plant Monticello Nuclear Generating Plant Unit 1 Name 2807 West County Road 75, Monticello, MN 55362 WO-380817 Address Repair Organization P.O. No., Job No. etc.

3. Work Performed By NSPM/XcelEnergy Type Code Symbol Stamp n/a Company Name Authorization No. n/a 2807 West County Rd. 75, Monticello; MN 55362 Expiration Date n/a Address 4.- Identification of System Main Steam "D", AO-2-86D, Class I

5. (a) Applicable Construction Code B31.1 1977E/W'78A Edition /Addenda (b) Applicable Edition of Section XI Used for Repair/Replacement Activity 2001 Edition, No Addenda (c) Applicable Section XI Code Case(s) n/a

6. Identification of Components Corrected, ASME Code Name of Name of Manufacturer National Other Removed, or Staiped Component Manufacturer Serial No. Board No. Identification Year Built Installed YES NO DS Disc Anchor Darling n/a n/a n/a 2001 Removed ED N DS Disc Anchor Darling n/a n/a n/a 2009 Installed El N D] El D] ED

__ ED

7. Description of Work Damaged downstream disc replaced with like for like disc.

8. Tests Conducted: Hydrostatic D Pneumatic D Noominal Operating Pressure E]

Exempt El Other F-1 Pressure n/a psi Test Temp n/a OF 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 the number of sheets is recorded at the top of this form. (See 4 AWI-09.04.03 [ASME Section XI Repair/Replacement Program] for further documentation guidance.)

Approval: PCR 01148046 M/asc

MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: FORM NIS-2 OWNER'S REPORT FOR Revision 5 REPAIR/REPLACEMENT ACTIVITY Page 2 of 2 Repair/Replacement Plan No.: 2009-24-049

9. Remarks (Applicable Manufacturer's Data Reports to be Attached)

The damaged downstream disc was replacedlike for like. The upstream disc was also replaced, but is not pressure retaining. The new disc Heat numbers are 83828-1 and 83539-1. It is not known which disc is upstream or which is downstream.

Valve functional testing completed: Stroke time open /close (STO/STC), position indication (PIT),

Appx J/LLRT (LT), Fail Close (FC). PartialStoke (PS) is satisfied by STO/STC.

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

Signed Si c--TFot.)(I S X SI Date 0ý3/0cl 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 Hartford Steam Boiler Insp & Ins Company of Connecticut of Hartford, Connecticut have inspected the components described in this Owner's Report during the period v / F/01 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 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 measures 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 I91 /(f'K A, Aý t'AM*A-u"zJ--C' Inspector's Signature National Board, Province and Endorsements Date - 5r-( ,3J M/asc

MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: FORM NIS-2 OWNER'S REPORT FOR Revision 5 I REPAIR/REPLACEMENT ACTIVITY Page 1 of 2 Repair/Replacement Plan No.:2009-24-050

1. Owner NSP-Minnesota, an Xcel Energy Company Date 7/30/2009 Name 414 Nicollet Mall, Minneapolis, MN 55401 Sheet 1 of 2 Address

2. Plant Monticello Nuclear Generating Plant Unit 1 Name 2807 West County Road 75, Monticello, MN 55362 WO-316178, EC12841 Address Repair Organization P.O. No., Job No. etc.

3. Work Performed By NSPMIXcelEnergy Type Code Symbol Stamp n/a Company Name Authorization No. n/a 2807 West County Rd. 75, Monticello, MN 55362 Expiration Date n/a Address

4. Identification of System RHR Service Water (FSW, Class 3

5. (a) Applicable Construction Code B31.1 , 77W78 Edition / Addenda (b) Applicable Edition of Section XlI Used for Repair/Replacement Activity 2001 Edition, No Addenda (c) Applicable Section Xl Code Case(s) n/a

6. Identification of Components Corrected, ASME Code Name of Name of Manufacturer National Other Removed, or Staiped Component Manufacturer Serial No. Board No. Identification Year Built Installed YES NO BS-1952 Zum n/a n/a n/a 1969 Corrected E] E E] E]

WEl E E]

Weld buildup and machining of eroded/corrodedflange faces to restore sealing

7. Description of Work surfaces.

8. Tests Conducted: Hydrostatic EL Pneumatic El Nominal Operating Pressure Exempt El Other Ri Pressure 230 psi Test Temp na OF 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 the number of sheets is recorded at the top of this form. (See 4 AWI-09.04.03 [ASME Section XI Repair/Replacement Program] for further documentation guidance.)

Approval: PCR 01148046 M/asc

MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: FORM NIS-2 OWNER'S REPORT FOR Revision 5 REPAIR/REPLACEMENT ACTIVITY Page 2 of 2 Repair/Replacement Plan No.: 2009-24-050

9. Remarks (Applicable Manufacturer's Data Reports to be Attached)

Weld build up area was magnetic particle examined.

A pressure test at normal operatingpressure was performed.

EC12841 is applicable.

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

Signed Date 71-90109 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 Hartford Steam Boiler Insp &, Ins Company of Connecticut of Hartford, Connecticut have inspected the components described in this Owner's Report during the period 'I/?Iqi to 7/010 -1 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 measures 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 140114'Q Aw(T M, 4~iVJ' Inspector's Signature National Board, Province and Endorsements Date _ _ 7 ,_,__ _ _ _ _

M/asc

MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: FORM NIS-2 OWNER'S REPORT FOR Revision 5 REPAIR/REPLACEMENT ACTIVITY Page 1 of 2 Repair/Replacement Plan No.:2009-24-051

1. Owner NSP-Minnesota, an Xcel Energy Company Date 7/26/2009 Name 414 Nicollet Mall, Minneapolis, MN 55401 Sheet I of 2 Address

2. Plant Monticello Nuclear Generating Plant Unit 1 Name 2807 West County Road 75, Monticello, MN 55362 WO-326530 Address Repair Organization P.O. No., Job No. etc.

3. Work Performed By NSPMIXcel Energy Type Code Symbol Stamp n/a Company Name Authorization No. n/a 2807 West County Rd. 75, Monticello, MN 55362 Expiration Date n/a Address

4. Identification of System Snubber (SNB) / Main Steam (MST), Class I

5. (a) Applicable Construction Code USAS B31.1 , 1967 Edition / Addenda (b) Applicable Edition of Section XI Used for Repair/Replacement Activity 2001 Edition, No Addenda (c) Applicable Section XI Code Case(s) n/a

6. Identification of Components Corrected, ASME Code Name of Name of Manufacturer National Other Removed, or Staiped Component Manufacturer Serial No. Board No. Identification Year Built Installed YES NO PS1-H2 Bergen Paterson n/a n/a Part#942721 unknown removed ED M PSI-H2 Bergen n/a n/a Part #942721 1986 installed ED M Paterson ED ED Ew El ED ED

7. Description of Work Replaced flange mounting bolt - lost during snubber removal/reinstallation.

8. Tests Conducted: Hydrostatic E] Pneumatic 0 Nominal Operating Pressure D Exempt El Other FZ Pressure psi Test Temp OF 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 the number of sheets is recorded at the top of this form. (See 4 AWI-09.04.03 [ASME Section Xl Repair/Replacement Program] for further documentation guidance.)

-Approval: PCR 01148046 M/asc

MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: FORM NIS-2 OWNER'S REPORT FOR Revision 5 REPAIR/REPLACEMENT ACTIVITY Page 2 of 2 Repair/Replacement Plan No.: 2009-24-051

9. Remarks (Applicable Manufacturer's Data Reports to .be Attached)

Preservice VT-3 examination of snubber following re-installation,as required by procedure 4903.

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

Signed ;KN'- ,.SEz:-C- X( ISI 'CoORai Date 7/Z2(/ci)

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 Hartford Steam Boiler Insp & Ins Company of Connecticut of Hartford, Connecticut have inspected the components described in this Owner's Report during the period V1Iho to 7 /d 7 IJ1 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 measures 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 arisingfrom or connected with this inspection.

Commissions k4'/fi"tfs. / - -- cd Inspector's Signature

National Board, Province and Endorsements Date 7 /L7h/9 M/asc

MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: FORM NIS-2 OWNER'S REPORT FOR Revision 5 1 REPAIR/REPLACEMENT ACTIVITY Page 1 of 2 Repair/Replacement Plan No. :2009-24-052

1. Owner NSP-Minnesota, an Xcel Energy Company Date 7/30/2009 Name 414 Nicollet Mall, Minneapolis, MN 55401 Sheet I of 2 Address

2. Plant Monticello Nuclear Generating Plant Unit 1 Name 2807 West County Road 75, Monticello, MN 55362 WO-381679 and 383608 Address Repair Organization P.O. No., Job No. etc.

3. Work Performed By NSPM/Xcel Energy Type Code Symbol Stamp n/a Company Name Authorization No. n/a 2807 West County Rd. 75, Monticello, MN 55362 Expiration Date n/a Address

4. Identification of System Main Steam (MST), ASME Code Class I

5. (a) Applicable Construction Code USAS B31.1 , 1967 Edition / Addenda (b) Applicable Edition of Section Xl Used for Repair/Replacement Activity 2001 Edition, No Addenda (c) Applicable Section XI Code Case(s) n/a

6. Identification of Components Corrected, ASME Code Name of Name of Manufacturer National Other Removed, or Staiped Component Manufacturer Serial No. Board No. Identification Year Built Installed YES NO Main Steam C Bechtel n/a n/a n/a 1967 Corrected El 2 PS3-18"ED El1El E] E]

El El Removed surface indicationon Main Steam C adjacentto strain gage removal

7. Description of Work area (location MSC-12). Indication removed in 2009.

8. Tests Conducted: Hydrostatic El Pneumatic El Nominal Operating Pressure El Exempt El Other El Pressure psi Test Temp OF 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 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form. (See 4 AWI-09.04.03 [ASME Section XI RepairlReplacement Program] for further documentation guidance.)

Approval: PCR 01148046 M/asc

MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: FORM NIS-2 OWNER'S REPORT FOR Revision 5 REPAIRIREPLACEMENT ACTIVITY Page 2 of 2 Repair/Replacement Plan No.: 2009-24-052

9. Remarks (Applicable Manufacturer's Data Reports to be Attached)

The surface indicationwas removed by light grinding.

Pre and post UT thickness measurements were taken (reference report BOP-VE-09-036).

Post removal MT was performed (reference report BOP-MT-09-066).

EC-9174 applies to WO-381679 activities.

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

Signed , SECoCWX( )St Coo.-o, Date B/ýOL9 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 Hartford Steam Boiler Insp & Ins Company of Connecticut of Hartford, Connecticut have inspected the components described in this Owner's Report during the period -i/ " /Id to J-/- 4le 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 measures 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 /,.1f //,6"7 A, &*.. 'Ict

/ 4'olz P -co Inspector's Signature National Board, Province and Endorsements Date - ff/-,/Og M/asc

MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: FORM NIS-2 OWNER'S REPORT FOR Revision 5 I REPAIRIREPLACEMENT ACTIVITY Page 1 of 2 Repair/Replacement Plan No.:2009-24-053

1. Owner NSP-Minnesota, an Xcel Energy Company Date 7/31/2009 Name 414 Nicollet Mall, Minneapolis, MN 55401 Sheet I of 2 Address

2. Plant Monticello Nuclear Generating Plant Unit 1 Name 2807 West County Road 75, Monticello, MN 55362 WO-381707, EC-14055 Address Repair Organization P.O. No., Job No. etc.

3. Work Performed By NSPM/Xcel Energy Type Code Symbol Stamp n/a Company Name Authorization No. n/a 2807 West County Rd. 75, Monticello, MN 55362 Expiration Date n/a Address

4. Identification of System RHR-SWA Loop (RSI~i9, Class 3

5. (a) Applicable Construction Code B31.1 1977E/W'78A Edition / Addenda (b) Applicable Edition of Section XI Used for Repair/Replacement Activity 2001 Edition, No Addenda (c) Applicable Section XI Code Case(s) N-661

6. Identification of Components Corrected, ASME Code Name of Name of Manufacturer National Other Removed, or Stamped Component Manufacturer Serial No. Board No. Identification Year Built Installed YES NO SW9-18"-GF Navco n/a n/a n/a 1969 Corrected EL M 7d Ei

7. Description of Work Weld overlay repairfor MIC thinned area per Code Case N-661.

8. Tests Conducted: Hydrostatic L] Pneumatic E] Nominal Operating Pressure LI Exempt Z Other LI Pressure n/a psi Test Temp n/a OF 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 the number of sheets is recorded at the top of this form. (See 4 AWI-09.04.03 [ASME Section XI Repair/Replacement Program] for further documentation guidance.)

Approval: PCR 01148046 M/asc

MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: FORM NIS-2 OWNER'S REPORT FOR Revision 5 REPAIR/REPLACEMENT ACTIVITY Page 2 of 2 Repair/Replacement Plan No.: 2009-24-053

9. Remarks (Applicable Manufacturer's Data Reports to be Attached)

Weld overlay repairof MIC thinned area per Code Case N-661.

Pre and post overlay MT performed.

Post overlay UT thickness performed.

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

Sig nd Ow EC's'Desi ISnt C0t Date 3 09 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 Hartford Steam Boiler Insp & Ins Company of Connecticut of Hartford, Connecticut have inspected the components described in this Owner's Report during the period ij / - to f/3 4de, 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 measures 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 -KJ A 1),/ s )*14,--jo tfdc:1z(o Inspector's Signature National Board, Province and Endorsements Date S7/ )ý M/asc

MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: FORM NIS-2 OWNER'S REPORT FOR Revision 5 I REPAIR/REPLACEMENT ACTIVITY Page 1 of 2 r/Replacement Plan No.:2009-24-054

1. Owner NSP-Minnesota, an Xcel Energy Company Date 8/3/2009

. Name 414 Nicollet Mall, Minneapolis, MN 55401 Sheet 1 of 2 Address

2. Plant Monticello Nuclear Generating Plant Unit 1 Name 2807 West County Road 75, Monticello, MN 55362 WO-381724 Address Repair Organization P.O. No., Job No. etc.

3. Work Performed By NSPMIXcelEnergy Type Code Symbol Stamp N/A Company Name Authorization No. N/A 2807 West County Rd. 75, Monticello, MN 55362 Expiration Date N/A Address

4. Identification of System RHR Service Water (RHRSW/ESW), Class 3

5. (a) Applicable Construction Code B31.1 , 1977E/W'78AEdition /Addenda (b) Applicable Edition of Section XI Used for Repair/Replacement Activity 2001 Edition, No Addenda (c) Applicable Section Xl Code Case(s) N/A

6. Identification of Components Corrected, ASME Code Name of Name of Manufacturer National Other Removed, or Staiped Component Manufacturer Serial No. Board No. Identification Year Built Installed YES NO SR-451 shim Dubose N/A N/A N/A 2009 Installed 0I Z SR-452 shim Dubose N/A N/A N/A 2009 Installed E] Z SR-453 shim Dubose N/A N/A N/A 2009 Installed E] E SR-454 shim Dubose N/A N/A N/A 2009 Installed EI Z SR-455 shim Dubose N/A N/A N/A 2009 Installed El E Added shims to pipe supports to meet requiredclearancesfollowing pipe

7. Description of Work replacement

8. Tests Conducted: Hydrostatic LI Pneumatic El Nominal Operating Pressure LI Exempt El Other RI Pressure psi Test Temp OF 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 the number of sheets is recorded at the top of this form. (See 4 AWI-09.04.03 [ASME Section XI Repair/Replacement Program] for further documentation guidance.)

Approval: PCR 01148046 M/asc

MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: FORM NIS-2 OWNER'S REPORT FOR Revision 5 REPAIR/REPLACEMENT ACTIVITY Page 2 of 2 Repair/Replacement Plan No.: 2009-24-054

9. Remarks (Applicable Manufacturer's Data Reports to be Attached)

Weld Visuals and PSI VT-3 performed.

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

Signed o 20?Q IS C1Q5Z' Date 8/4/9o 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 Hartford Steam Boiler Insp & Ins Company of Connecticut of Hartford, Connecticut have inspected the components described in this Owner's Report during the period //1 5I)0J

-- to F /iE //'

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 measures 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.

Y-r A I Commissions )f/(l -J A,) All"f lJv*o OY-C6d 1

Inspector's Signature National Board, Province and Endorsements Date M/asc

MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: FORM NIS-2 OWNER'S REPORT FOR Revision 5 1 REPAIR/REPLACEMENT ACTIVITY Page 1 of 2 Repair/Replacement Plan No.:2009-24-055, Rev. I

1. Owner NSP-Minnesota, an Xcel Energy Company Date 7/30/2009 Name 414 Nicollet Mall, Minneapolis, MN 55401 Sheet 1 of 5 Address

2. Plant Monticello Nuclear Generating Plant Unit 1 Name 2807 West County Road 75, Monticello, MN 55362 WO-381724 Tasks 15 & 16, EC-14190 Address Repair Organization P.O. No., Job No. etc.

3. Work Performed By NSPMIXcel Energy Type Code Symbol Stamp n/a Company Name Authorization No. n/a 2807 West County Rd. 75, Monticello, MN 55362 Expiration Date n/a Address

4. Identification of System Emergency Service Water (ESW), Class 3

5. (a) Applicable Construction Code B31.1 , 1977/W'78 Edition /Addenda (b) Applicable Edition of Section Xl Used for Repair/Replacement Activity 2001 Edition, No Addenda (c) Applicable Section Xl Code Case(s) n/a

6. Identification of Components Corrected, ASME Code Name of Name of Manufacturer National Other Removed, or Staiped Component Manufacturer Serial No. Board No. Identification Year Built Installed YES NO SW3OA-3"-HF NAVCO n/a n/a n/a 1969 removed El Z see subsequent sheets for additional items downgraded I] E]

7. Description of Work ASME Class 3 boundary moved, components downgraded to non-safety.

8. Tests Conducted: Hydrostatic El Pneumatic El Nominal Operating Pressure El Exempt El Other Fl Pressure n/a psi Test Temp n/a OF 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 the number of sheets is recorded at the top of this form. (See 4 AWI-09.04.03 [ASME Section X1 Repair/Replacement Program] for further documentation guidance.)

Approval: PCR 01148046 M/asc

MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: FORM NIS-2 OWNER'S REPORT FOR Revision 5 REPAIR/REPLACEMENT ACTIVITY Page 2 of 2 Sheet 2 of 5 Repair/Replacement Plan No.: 2009-24-055, Rev. 1

9. Remarks (Applicable Manufacturer's Data Reports to be Attached)

All pipe, fittings, and supports located downstream of valve ESW-61-1, which were previously abandonedin-place under mod 87Z028, were downgraded from Class 3 to non-safety. The new Class 3 boundary was moved to ESW-61-1, which is a manual valve that is kept in a "normally closed" position.

No post-maintenance testing was requiredfor this code boundary change.

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

Signed SG-CTIcNX( (51 COOZ. Date 7/3ý/09 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 Hartford Steam Boiler Insp & Ins Company of Connecticut of Hartford, Connecticut have inspected the components described in this Owner's Report during the period 'iyZ# r /0' to -I/.I J01 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 measures 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'1_4 Inspector's Signature Commissions ,IZI4fg( 3 A. A,/ I' /L, i 0oo'aP-c,,

'National Board, Province and Endorsements Date 7 /3o Iq M/asc

NSP-Minnesota, an Xcel Energy Company Sheet 3 of 5 414 Nicollet Mall, Minneapolis, MN 55401 Monticello Nuclear Generating Plant - Unit 1 2807 West County Road 75, Monticello, MN 55362 Work Performed By NSPM/XcelEnergy R/R Plan No. 2009-24-055, Rev. I System Emergency Service Water (ESW) WO No. 381724 Tasks 15 & 16 Construction Code B31.1, 1977/ W'78 Section Xl R/R Code 2001 Ed/ No Add Section Xl Code Case(s) None Form NIS-2 Continuation Sheet Corrected, ASME Code Name of Name of Manufacturer National Other Removed, or Stai ped Component Manufacturer Serial No. Board No. Identification Year Built Installed Yes No SWH-83 NSP and n/a n/a n/a 1969 removed X Bechtel SR-26 NSP and n/a n/a n/a 1969 removed X Bechtel SWH-85 NSP and n/a n/a n/a 1969 removed X Bechtel SWH-86 NSP and n/a n/a n/a 1969 removed X Bechtel SR-27 NSP and n/a n/a n/a 1969 removed X Bechtel SWH-2B NSP and n/a n/a n/a 1969 removed X Bechtel SWH-2A NSP and n/a n/a n/a 1969 removed X Bechtel SWH-4 NSP and n/a n/a n/a 1969 removed X Bechtel SWH-3 NSP and n/a n/a n/a 1969 removed X Bechtel SR-293 NSP and n/a n/a n/a 1969 removed X Bechtel SR-309 NSP and n/a n/a n/a 1969 removed X Bechtel SWH-96 NSP and n/a n/a n/a 1969 removed X Bechtel SR-308 NSP and n/a n/a n/a 1969 removed X Bechtel SWH-200 NSP and n/a n/a n/a 1969 removed X Bechtel SR-1 NSP and n/a n/a n/a 1969 removed X Bechtel SR-6 NSP and n/a n/a n/a 1969 removed X Bechtel

NSP-Minnesota, an Xcel Energy Company Sheet 4 of 5 414 Nicollet Mall, Minneapolis, MN 55401 Monticello Nuclear Generating Plant - Unit 1 2807 West County Road 75, Monticello, MN 55362 Work Performed By NSPM/XcelEnervqy R/R Plan No. 2009-24-055, Rev. 1 System Emerqency Service Water (ESW) WO No. 381724 Tasks 15 & 16 Construction Code B31.1, 1977/ W'78 Section Xl R/R Code 2001 Ed/No Add Section Xl Code Case(s) None Form NIS-2 Continuation Sheet Corrected, ASME Code Name of Name of Manufacturer National Other Removed, or Stai ped Component Manufacturer Serial No. Board No. Identification Year Built Installed Yes No SR-269 NSP and n/a n/a n/a 1969 removed X Bechtel SWH-199A NSP and n/a n/a n/a 1969 removed X Bechtel SR-3 NSP and n/a n/a n/a 1969 removed X Bechtel SWH-201 NSP and n/a n/a n/a 1969 removed X Bechtel SR-4 NSP and n/a n/a n/a 1969 removed X Bechtel SWH-202 NSP and n/a n/a n/a 1969 removed X Bechtel SWH-203 NSP and n/a n/a n/a 1969 removed X Bechtel SR-5 NSP and n/a n/a n/a 1969 removed X Bechtel SWH-204 NSP and n/a n/a n/a 1969 removed X Bechtel SR-280 NSP and n/a n/a n/a 1969 removed X Bechtel SWH-205 NSP and n/a n/a n/a 1969 removed X Bechtel SWH-205A NSP and n/a n/a n/a 1969 removed X Bechtel SR-8 NSP and n/a n/a n/a 1969 removed X Bechtel SWH-206 NSP and n/a n/a n/a 1969 removed X Bechtel SWH-207 NSP and n/a n/a n/a 1969 removed X Bechtel SR-9 NSP and n/a n/a n/a 1969 removed X Bechtel

NSP-Minnesota, an Xcel Energy Company Sheet 5 of 5 414 Nicollet Mall, Minneapolis, MN 55401 Monticello Nuclear Generating Plant - Unit 1 2807 West County Road 75, Monticello, MN 55362 Work Performed By NSPM/Xcel Enerqy R/R Plan No. 2009-24-055, Rev. 1 System Emergency Service Water (ESW) WO No. 381724 Tasks 15 & 16 Construction Code B31.1, 1977/ W'78 Section Xl R/R Code 2001 Ed/No Add Section Xl Code Case(s) None Form NIS-2 Continuation Sheet Corrected, ASME Code Name of Name of Manufacturer National Other Removed, or Stai ped Component Manufacturer Serial No. Board No. Identification Year Built Installed Yes No SWH-209 NSP and n/a n/a n/a 1969 removed X Bechtel SWH-210 NSP and n/a n/a n/a 1969 removed X Bechtel SR-10 NSP and n/a n/a n/a 1969 removed X Bechtel SWH-211 NSP and n/a n/a n/a 1969 removed X Bechtel SWH-212 NSP and n/a n/a n/a 1969 removed X Bechtel SWH-213 NSP and n/a n/a n/a 1969 removed X Bechtel SR-11 NSP and n/a n/a n/a 1969 removed X Bechtel SR-281 NSP and n/a n/a n/a 1969 removed X Bechtel

-I- + -I- +

4 4 4 4 +

MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: FORM NIS-2 OWNER'S REPORT FOR Revision 5 1 REPAIR/REPLACEMENT ACTIVITY Page 1 of 2 Repair/Replacement Plan No.:2009-24-056

1. Owner NSP-Minnesota, an Xcel Energy Company Date 7/30/2009 Name 414 Nicollet Mall, Minneapolis, MN 55401 Sheet I of 2 Address

2. Plant Monticello Nuclear Generating Plant Unit 1 Name 2807 West County Road 75, Monticello, MN 55362 WO-344364 Address Repair Organization P.O. No., Job No. etc.

3. Work Performed By NSPM/Xcel Energy Type Code Symbol Stamp n/a Company Name Authorization No. n/a 2807 West County Rd. 75, Monticello, MN 55362 Expiration Date n/a Address

4. Identification of System Reactor Pressure Vessel (RPV), ASME Class I

5. (a) Applicable Construction Code ASME Section III 1965E/S'66A Edition/Addenda (b) Applicable Edition of Section Xl Used for Repair/Replacement Activity 2001 Edition, No Addenda (c) Applicable Section XI Code Case(s) n/a

6. Identification of Components Corrected, ASME Code Name of Name of Manufacturer National Other Removed, or Staiped Component Manufacturer Serial No. Board No. Identification Year Built Installed YES NO Spherical Washer n/a n/a na 1965 Removed El 0 Washer Set Unknown Spherical Pipe Machinery 2-S n/a Ht# 17501 1974 Installed LI [

Washer Set Compan _

7] D]

7. Description of Work Like-for-like replacement of 1 sphericalwasher set at stud #28. Installed in 2009.

8. Tests Conducted: Hydrostatic LI Pneumatic LI Nominal Operating Pressure LI Exempt 0I Other LI Pressure psi Test Temp OF 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 the number of sheets is recorded at the top of this form. (See 4 AWI-09.04.03 [ASME Section Xl Repair/Replacement Program] for further documentation guidance.)

Approval: PCR 01148046 M/asc

MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: FORM NIS-2 OWNER'S REPORT FOR Revision 5 REPAIR/REPLACEMENT ACTIVITY Page 2 of 2 Repair/Replacement Plan No.: 2009-24-056

9. Remarks (Applicable Manufacturer's Data Reports to be Attached)

One spherical washer set replacedlike-for-like at stud #28, due to potential damage of the existing set during reassembly.

Stud was retensionedper procedure 9267 on WO 344364.

Preservice VT-I performed per WO-344364 task 05 (reference ISI report 2009VT134).

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

Signed S( CGQQzý Date / 9 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 Hartford Steam Boiler Insp & Ins Company of Connecticut of Hartford, Connecticut have inspected the components described in this Owner's Report during the period *L1 it 'd*F' to _1___10J__

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 measures 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 /,/5I//"1 ,1,i j- Myvoolrar-co Inspector's Signature National Board, Province and Endorsements Date M/asc

Monticello Nuclear Generating Plant Cycle 24 Summary Report Inservice Inspection 2009 Refueling Outage IV. Form NIS-1 Information Page 1 of 2 Form NIS-1 Owner's Data Report for Inservice Inspections

(**Supplement to Submittal for Cycle 23, 2007 RFO**)

As required by the Provisions of the ASME Code Rules

1. Owner: Xcel Energy, LLC / Nuclear Management Company, LLC Address: 800 Nicollet Mall, Mpls, MN 55402 / 700 1st St.. Hudson WI 54016

2. Plant: Monticello Nuclear Generating Plant Address: Monticello, MN 55362

3. Plant Unit: 1 4. Owner (Certificate of Authorization): N/A

5. Commercial Service Date: 6/30/71 6. National Board No. for Unit: N/A

7. Components Inspected:

Manufacturer Component or Manufacturer or Installer State or National Appurtenance or Installer Serial No. Province No. Board No.

Reactor Pressure Chicago Bridge B-4697 Vessel & Iron (See appendices for components inspected during the cycle)

8. Examination Dates: 04/13/05 to 04/28/07.

9. Inspection Interval: 05/01/03 to 05/31/12

10. Applicable Edition of Section XI: 1995 Addenda: 1996

11. Abstract of Examinations. Include a list of examinations and a statement concerning status of work required for current interval.

See Sections IV and V for supplemental Cycle 23 Form NIS-2 and NIS-1 Attachment (Appendix A)

12. Abstract of Conditions Noted.

See Sections IV and V for supplemental Cycle 23 Form NIS-2 and NIS-1 Attachment (Appendix A)

14. Abstract of Corrective Measures Recommended and Taken.

See Sections IV and V for supplemental Cycle 23 Form NIS-2 and NIS-1 Attachment (Appendix A)

Monticello Nuclear Generating Plant Cycle 24 Summary Report Inservice Inspection 2009 Refueling Outage IV. Form NIS-1 Information Page 2 of 2

(**Supplement to Submittal for Cycle 23, 2007 RFO**)

We certify that the statements made in this report are correct and the examinations and corrective measures taken conform to the rules of the ASME Code,Section XI.

Certification of Authorization No. (if applicable) N/A Expiration Date N/A Date 4 20 oq Signed NPMq C-61.-E NE By 0 Owner Section XI ISI Coordinator 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 /-I /4/ei o74A and employed by 1.ikIrxh JTt/J/ /3r01Lcx J-tZ o t- CT of !aA IJ'F j4eO , cT have inspected the components described in this Owner's Report during the period 11/131)S- to 8- /a 1, , 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 measures described in this Owner'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 , ,t,Z/?//d"6

, )o od2Y -co Inspector's Signature National Board, State, Province, Endorsements Date ,1c4C-GtJ7 g 20,4

Monticello Nuclear Generating Plant Cycle 24 Summary Report Inservice Inspection 2009 Refueling Outage V. Form NIS-1 Information

(**Supplement to Submittal for Cycle 23, 2007 RFO**)

Supplemental NIS-2 Form for Cycle 23 2007 RFO Summary Report Revised Form NIS-2 WORK DESCRIPTION Replaced approximately 6" section of pipe and adjacent 90 degree elbow (2 pages to follow)

MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 I REPLACEMENTS - FORM NIS-2 Page 1 of 2 ITEM 2007-23-0070 I NOTE 1: This form may not address all items needed for documentation of a repair/replacementprogram, see 4 AWI-09.04.03 (ASME SECTION XI REPAIRIREPLACEMENT PROGRAM) for further guidance.

NOTE 2: 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 the number of sheets is recorded at the top of this form.

1. Owner Xcel Energy Company Date 7/14/2007 Name

2. Plant Monticello Nuclear Generating Plant Sheet 1 of 2 Name 2807 W. Cnty. Rd. 75, Monticello, Minnesota 55362 WO 325774 Address Repair Organization P.O. No., Job No. etc.

3. Work Performed By NMC/Xcel Energy - Type Code Symbol Stamp n/a Company Name Authorization No. n/a 2807 W Cty Rd 75, Monticello, MN 55362 Expiration Date n/a Address

4. Identification of System Emergency Service Water (ESMV, Div I, Class 3

5. (a) Applicable Construction Code ANSI B31.1 1977 Edition Year Addenda Winter 1978 Addenda Code Case n/a (b) Applicable Edition of Section Xl Utilized for Repairs or Replacement 2001 Edition, No Addenda

6. Identification of Components Repaired or Replaced and Replacement Components ASME Repaired, Code Name of Name of Manufacturer National Other Year Replaced or Staiped Component Manufacturer Serial No. Board No. Identification Built Replacement YES NO ESWI-4"- unknown n/a n/a n/a 1981 Replaced E] E HBD Pioe ESWI-4" HBD Pine ESWH-4"Eb Tioga Pipe unknown n/a n/a n/a n/a Ht#.A88__

o.%.___,

n/a A,

2007 1981 Replacement Replaced E]

E]

Z Z

I HBD Elbow ESWI-4"- Consolidated n/a n/a Ht# 7662 2007 Replacement Ej E HBD Elbow Power

__El l

7. Description of Work Replaced approx 6 inches of A-106 Gr. B pipe and adjacent A-234 WPB elbow (line designation ESW1-4'"-HBD) like-for-like by welding due to localized ID corrosion (replacementpipe built 2000, replacement elbow built 1991, both installed 2007).

8. Tests Conducted: Hydrostatic El Pneumatic El Nominal Operating Pressure M Other ni Pressure 77 psi Test Temp n/a OF

~ '~~A~4o9 APPROVED (Signatures available in Master File)

MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS - FORM NIS-2 Pagejof&,,1 ,,[o.*

ITEM 2007-23-0070

9. Remarks (Applicable Manufacturer's Data Reports to be Attached)

System leakage tests in lieu of a hydro per IWA-4540(a)(2) per WO PMT attachments.

CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this 1c'?ALe./ 9FPL-1CMENT /ACT-ItTj conforms to the rules on the ASME Code,Section XI. repair/replacement Signed '

SE- X1 Isl C000 Date , 2-I 2007 Owner or Owner's Designee, Title SCe-T )I Is I coo-p =10 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 /-It,..*..-soTA and employed by PAO-thPForO tAi),1 Ol t' o1_COý.0,wit-lcyIT of f-n/ek xfl, CF have inspected the components described in this Owners Report during the period u//lw/o ' to

-7/7,) 10 7 , 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.

2c j Commissions 1/4R 11,r63 41)iv 1410'J~' Ct")

Inspector's Signature National Board, Province and Endorsements Date 7LtL/_ - o, APPROVED (Signatures available in Master File)

Monticello Nuclear Generating Plant Cycle 24 Summary Report Inservice Inspection 2009 Refueling Outage V. Form NIS-1 Information (continued)

(**Supplement to Submittal for Cycle 23, 2007 RFO**)

NIS- l Attachment (Appendix A) for Cycle 23 2007 RFO Summary Report Revised Attachment (1 page to follow)

NOTE: The header for all pages (1-19) of the NIS-1 Attachment (Appendix A) contained an editorial error. Cycle 22 should be corrected to indicate Cycle 23.

NIS-1 Attachment (Appendix A)

Cycle 23 Inservice Inspection Report (2007 RFO)

1,NIS-1 Attacthment (Appendix A)

Cce 22 Inservice, Inspection Report (2007 RFO Owner XcWEnegy. LLC, S00 Nicllet Matl Mlinensols. MN 56402 Orier Ceilifta1 ofAu*whtrsJoa (IRvq.): NIA Operator Nuclear Maiagem-nt Com*vny, LLC, 700 First street, Hudson, VI 54016 Conercial m ervie Doe W/301971 PRant Montleeo Nclear Generating Plant Um 1. 2807 West County Rd #75. Mhontioeho. UN 55362 National Board Number for Unt NIA Summar No. Comp ID Comp Desr. Category Item Procedure Method/SheetiResults System ISO Num Exam Date Class 1 Category B.A, EXAMS PERFORMED FOR ISI(4th Interval, Period 2 Credited Exams) and PSI 1063 VtAA-2 Long Seam 81.12

'IS PEI-02.03.15 UT 2007*/7059 URI Rtector Vessel ISIFig 4 3/222007 Comments: Limlled exam. Supplemental for furture 10exao, no relief request required at t1is time.

Class I Category B-D, EXAMS PERFORMED FOR ISl (4th Intorval. Period 2 Credited Exams) and PSI i=274 N.-GA IR N- GAterrer Radius 83.*100 Is7 FP-PE-NDE-jT-03 UT 2007UTI05 NRI Reactor Vessel 181Fig 1 3125,2007 NzhMdWl 3190 .

1035N8V 102375 N-GA NV NOZlI5I1 weld I$1 PE1-02.03.15 UT 2007UT104 NRI ReactorVossol 1SIFig I 3U2512007 Comments: Umited exm less It*an 90% coverage -Relief Request required 1028M57 N.28 IR H-28 lItes Radius 83,100 FP.PE.NOE.UT-03 UT 2007UT057 NRI ReascorVessel Il FIg5 3/21=2007 10558 N.29 W N- 29 NoI Val Weld PEI-02M08.l5 UT 2007UT068 NPJ Reartor Vessel 15 Fig 5 3/21=2007 Comments: Limitd exam Is tha 90%ooverse - Relie Request reqoured 102667 N- 2G IR N- 2G Inner Radius 63,' 00 ISI FP-FE-DE-UT-03 UT 20071106 NRI ReacorVessel 11 Fig 5 3122.2007 102668 N- 20 NV N- 2G NozNsl Weld 83.90 P-02.03.1 UT 2007UT061 NRI ReacerVessel ISI Fig 5 Win2" lCrrin*ets: Umf.d etam less, than 90% coverage - Rallef Request required Page 1 of 19

Monticello Nuclear Generating Plant Cycle 24 Summary Report Inservice Inspection 2009 Refueling Outage VI. Form NIS-1 Information Page 1 of 2 Form NIS-1 Owner's Data Report for Inservice Inspections

(**Supplement to Submittal for Cycle 22, 2005 RFO**)

As required by the Provisions of the ASME Code Rules

1. Owner: Xcel Energy, LLC / Nuclear Management Company, LLC Address: 800 Nicollet Mall, Mpls, MN 55402 / 700 1st St., Hudson WI 54016

2. Plant: Monticello Nuclear Generating Plant Address: Monticello, MN 55362

3. Plant Unit: 1 4. Owner (Certificate of Authorization): N/A

5. Commercial Service Date: 6/30/71 6. National Board No. for Unit: N/A

7. Components Inspected:

Manufacturer Component or Manufacturer or Installer State or National Appurtenance or Installer Serial No. Province No. Board No.

Reactor Pressure Chicago Bridge B-4697 Vessel & Iron (See appendices for components inspected during the cycle)

8. Examination Dates: 05/26/03 to 04/13/05.

9. Inspection Interval: 05/01/03 to 05/31/12

10. Applicable Edition of Section XI: 1995 Addenda: 1996

11. Abstract of Examinations. Include a list of examinations and a statement concerning status of work required for current interval.

0 See Sections VI and VII for supplemental Form NIS-2 Cycle 22 information

12. Abstract of Conditions Noted.

0 See Sections VI and VII for supplemental Form NIS-2 Cycle 22 information

15. Abstract of Corrective Measures Recommended and Taken.

0 See Sections VI and VII for supplemental Form NIS-2 Cycle 22 information

Monticello Nuclear Generating Plant Cycle 24 Summary Report Inservice Inspection 2009 Refueling Outage VI. Form NIS-1 Information Page 2 of 2

(**Supplement to Submittal for Cycle 22, 2005 RFO**)

We certify that the statements made in this report are correct and the examinations and corrective measures taken conform to the rules of the ASME Code,Section XI.

Certification of Authorization No. (if applicable) N/A Expiration Date N/A Date~4j~tIk 20 09 Signed NSPMZ Kd6E1ZCfY By

'Owner Section XI ISI Coordinator 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 /l juke J ,a--,yi and employed by fvit m'ytv s5i'iI1 6otw , 0 -ofcr of HI4i Z-Fixt,) CT have inspected the components described in this Owner's Report during the period r-h6I i ) to y-I ( Io' , 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 measures described in this Owner'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.

2*>r' Aý Inspector's Signature Commissions "&*,j A'I

,A-:J- /,/ (ootIla e-(6--

National Board, State, Province, Endorsements Date Au(,wt C 20011

Monticello Nuclear Generating Plant Cycle 24 Summary Report Inservice Inspection 2009 Refueling Outage VII. Form NIS-2 Information Supplemental NIS-2 Form for Cycle 22 2005 RFO Summary Report Additional comments added for CAP A/R 01107745 WORK DESCRIPTION Replace SRV Pilot Stage assembly (top works) with refurbished spare (2 pages to follow)

MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS - FORM NIS-2 Page 1 of 2 ITEM 2004-22-0037 NOTE 1: This form may not address all items needed for documentation of a repair/replacement program, see 4 AWI-09.04.03 (ASME SECTION XI REPAIR/REPLACEMENT PROGRAM) for further guidance.

NOTE 2: 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 the number of sheets is recorded at the top of this form.

1. Owner Xcel Energy Company Date 7/2/2005 Name

2. Plant Monticello Nuclear Generating Plant Sheet 1 0f 2 Name 2807 W. Cnty. Rd. 75, Monticello, Minnesota 55362 WO-0311656 (see remarks)

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

3. Work Performed By NMC/Xcel Energy Co Type Code Symbol Stamp n/a Company Name Authorization No. n/a 2807 W. Cty Rd 75, Monticello, MN 55362 Expiration Date n/a Address

4. Identification of System Main Steam, Safety Relief Valve RV-2-71H, Class 1

5. (a) Applicable Construction Code ANSI B31.1 1977 Edition Year Addenda Winter 1978 Code Case n/a (b) Applicable Edition of Section XI Utilized for Repairs or Replacement 2001 Edition, No Addenda

6. Identification of Components Repaired or Replaced and Replacement Components ASME Repaired, Code Name of Name of Manufacturer National Other Year Replaced or Stamped Component Manufacturer Serial No. Board No. Identification Built Replacement YES NO Pilot Stage Target Rock 122 n/a n/a 2001 replaced [] .

Ass'v Pilot Stage Target Rock 194 n/a n/a 2005 replacement El M Ass'v 7I. tw

7. Description of Work Replace SRV Pilot Stage Ass'y (to pworks) with a refurbished spare from stock.

8. Tests Conducted: Hydrostatic LI Pneumatic LI Nominal Operating Pressure LI Other M Pressure n/a psi Test Temp n/a OF 3087 (DOCUMENT CHANGE, HOLD AND COMMENT FORM) incorporated: _

-A'-MINISTRATIVE RPeso Suov: PRGE I Assoc Ref: PRGE SP: N Free: 0 vrs

DoI ::

USEONLY ARMS: 3513 Dec Tvoe: REF ONLY j Admin initials: Date:

APPROVED (Signatures available in Master File)

MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS - FORM NIS-2 Page 2 of 2 ITEM 2004-22-0037

9. Remarks (Applicable Manufacturer's Data Reports to be Attached)

GE Spec 21A 1060 and 21A9206 including applicable referenced codes. Installed Topworks s/n 194 perprocedure 4280-PM (3/17/05). Topworks 194 was previously refurbed, tested, and certified on 3/31/03 per WO 0200996 and 4280-03-PM. No PSI required. No Pressure testing requiredper Relief Request #7 (rotatedspare previously in-service, no new mechanicaljoints made, e.g. welding in a new flange or installing a new component). Post installationfunctional testing performed per procedure 0112.

SToPew-OKs S/N 194 WAS /, TAU-C AT CT/Oi RV-2--7/9 WI7H ANOWeOllr'FR2 1 INrENAtL

~~LLOWA) W6L- w>. T06 WELD 9CX6D1UReUsE:D &As~ NOT ADE~GuA Eq 4,Un,/WIR.b. 7bP 0J KSi

,,4 5U S ECU CNITLY D..,JWlM4 T-'tE 2009 7?FO )PR 14LO RDE. 3 0817?.- 9qq9. (7ReFeX.NCCT CERTIFICATE OF COMPLIANCE C0/R qlf[01 95))1 We certify that the statements made in the report are correct and this 7Ri" I/RZEFPLAC E1-`1TVAc'r Vr(TY conforms to the rules on the ASME Code,Section XI. rep'air/replacement Signed iS6Crto1-9 .,S- cooa*:, Date j u. fL 2- , 2.005-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 b-;*fp1-,,f 7 and employed by FOV1.*

r ?,t - - -ff alt./ J7? cP CGvg C/Lc. of / ,-)o . r tzi-p have inspected the components described in this Owner's Report during the period *1it -i;,2- a-.# Y1 to T,

L* (4 -- , L7 .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 X1.

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~i)~ A 4- Commissions &//7f i/f .J Al, 7/ C&"k oL0-(6' Inspector's Signature National Board, Province and Endorsements Date d--S,ý .5;Ec-n01-4 A 14a_4, iA,-Pz Y-1c, /#,?

APPROVED (Signatures available in Master File)

Monticello Nuclear Generating Plant Cycle 24 Summary Report Inservice Inspection 2009 Refueling Outage VIII. Form NIS-1 Information Page 1 of 2 Form NIS-1 Owner's Data Report for Inservice Inspections

(**Supplement to Submittal for Cycle 21, 2003 RFO**)

As required by the Provisions of the ASME Code Rules

1. Owner: Xcel Energy, LLC / Nuclear Management Company, LLC Address: 800 Nicollet Mall, Mpls. MN 55402 / 700 1st St., Hudson WI 54016

2. Plant: Monticello Nuclear Generating Plant Address: Monticello, MN 55362

3. Plant Unit: 1 4. 0 wwner (Certificate of Authorization): N/A

5. Commercial Service Date: 6/30/71 6. National Board No. for Unit: N/A

7. Components Inspected:

Manufacturer Component or Manufacturer or Installer State or National Appurtenance or Installer Serial No. Province No. Board No.

Reactor Pressure Chicago Bridge B-4697 Vessel & Iron (See appendices for components inspected during the cycle)

8. Examination Dates: 12/16/01 to 05/26/03.

9. Inspection Interval: 06/01/92 to 05/31/03 . (3rd Interval) 05/01/03 to 05/31/12 ( 4 th Interval)

10. Applicable Edition of Section XI: 1986 Addenda: (none) . ( 3 rd Interval) 1995 Addenda: 1996 . (4th Interval)

11. Abstract of Examinations. Include a list of examinations and a statement concerning status of work required for current interval.

See Sections VIII and IX for supplemental Form NIS-2 Cycle 21 information

12. Abstract of Conditions Noted.

See Sections VIII and IX for supplemental Form NIS-2 Cycle 21 information

16. Abstract of Corrective Measures Recommended and Taken.

See Sections VIII and IX for supplemental Form NIS-2 Cycle 21 information

Monticello Nuclear Generating Plant Cycle 24 Summary Report Inservice Inspection 2009 Refueling Outage VIII. Form NIS-1 Information Page 2 of 2

(**Supplement to Submittal for Cycle 21, 2003 RFO**)

We certify that the statements made in this report are correct and the examinations and corrective measures taken conform to the rules of the ASME Code,Section XI.

Certification of Authorization No. (if applicable) N/A Expiration Date N/A Date 20 01 Signed MSPM!*/X i- EINCWEG. By_ _ _ _

Owner Section XI ISI Coordinator 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 /t it-",ve"sor,4 and employed by NAnrcogj STi4 r o ilt)e r*j -a- r of H4 XaiD , CI have inspected the components described in this Owner's Report during the period 1,i t/cj to - J 6 [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 measures described in this Owner'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.

&-7-AAda, Inspector's Signature Commissions A/O 1463 /1, 41,-t hiv../ootoazy -C" National Board, State, Province, Endorsements Date *4(,1F57r (, 20 oq

Monticello Nuclear Generating Plant Cycle 24 Summary Report Inservice Inspection 2009 Refueling Outage IX. Form NIS-2 Information Supplemental NIS-2 Form for Cycle 21 2003 RFO Summary Report Additional comments added for CAP A/R 01107745 WORK DESCRIPTION Replace Bellows, add weld metal (flange) to bellows &

seal weld bellows to topworks body for spare Main Steam SRV Topworks 194. Replace s/n 131 with s/n 1.

(2 pages to follow)

MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS - FORM NIS-2 Page 1 of 2 ITEM 2003-21-0397 NOTE 1: This form may not address all items needed for documentation of a repair/replacement program, see 4 AWI-09.04.03 (ASME SECTION XI REPAIR/REPLACEMENT PROGRAM) for further guidance.

NOTE 2:- 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 the number of sheets is recorded at the top of this form.

1. Owner Xcel Energy Company Date 8/4/03 Name

2. Plant Monticello Nuclear Generating Plant Sheet 1 of 2 Name 2807 W. Cnty. Rd. 75, Monticello, Minnesota 55362 Work Order 0200996 (4280-03-PM)

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

3. Work Performed By NMC/Xcel Energy Type Code Symbol Stamp n/a Company Name Authorization No. n/a 2807 W. Cty Rd 75, Monticello, MN 55362 Expiration Date n/a Address

4. Identification of System Main Steam, Spare SRV Topworks, s/n 194, Class I

5. (a) Applicable Construction Code ASME Section III 1968 Edition Year Addenda Winter 1968 Code Case n/a (b) Applicable Edition of Section XI Utilized for Repairs or Replacement 1986, no addenda

6. Identification of Components Repaired or Replaced and Replacement Components ASME Repaired, Code Name of Name of Manufacturer National Other Year Replaced or Stainped Component Manufacturer Serial No. Board No. Identification Built Replacement YES NO Bellows! Target Rock 131 n/a n/a un- Replaced EL Z Flanae " known Bellows! Target Rock 1 n/a n/a 2003 Replacement LI [

Flanae "_"_-

7. Description of Work Replace Bellows and its Flange on spare SRV Topworks 194 during rebuild

8. Tests Conducted: Hydrostatic EL Pneumatic. E] Nominal Operating Pressure LI Other Z Pressure psi Test Temp 3087 (DOCUMENT CHANGE, HOLD AND COMMENT FORM) incorporated: _

FOR ADMINISTRATIVE I Reso Suov: PRGE I Assoc Ref: PRGE " SR: N Frea: 0 vrs

~~~~ONLY' ..

....IUSE A RM S:

ARMS: 3 6...1..........3' 3613 Do c Tv o~e D : R E F O N LY I A d m in in itia ls : D a te : -

APPROVED (Signatures available in Master File)

MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS - FORM NIS-2 Page 2 of 2 ITEM 2003-21-0397

9. Remarks (Applicable Manufacturer's Data Reports to be Attached)

Bellows Flange changed perAlteration 99A043, Rev.2. High Pressure Nitrogen bench test of the hellows and Setpoint Press.re Teist of the topworks m.ina steeam nerformed per arocedure4280 PM I)y. Pne.trante.am ne.rfnrmP.d nn sel weld This ihs ;9 nrp ton works instelletinn tpsting and sy/stem le*akage teSt Will take Qlace u-nder seprate wAonrk nordrers wAhe-n intalletd in ihant at l2ter date.

-rJ8W&EU.k'S FLAN46 SEALWLWz- 45 I1is7Xteb wini4#L4e-i- A'acebiuE 'rHoqrw45 N0779110muneLV OJAAtjFe-P. 7hW(NOK01NFOPMING CcONDI7ON WVAS Wgc ~rr~Wi#,r Y2 'rPOftQKt MYe,WL4-S RM7OVeD_

r~ofl SE-0vice- ("oeATiovRv-2-71H,, Ri -mv~bPEIR Ld -3II39Y) (REFE ~erCPAIR 0)10O77,/5)J CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this conforms to the rules on the ASME Code,Section XI. repair/replacement

.Signed _ 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 h-L,I4"fJIA' and employed by

ýMTV-*T ~ kBSi7pi

1LeIY*' *0iv,.-Cr1C-I4 of k/1iTF-<I1C0 , have inspected the components described in this Owner's Report during the period 2./x 7 /03 to R /e -, foj , 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 N/a iona 3 4BPrv )

COEdrent Inspector's Signature National Board, Province and Endorsements Date kLULL V f

APPROVED (Signatures available in Master File)

Monticello Nuclear Generating Plant Cycle 24 Summary Report Inservice Inspection 2009 Refueling Outage APPENDIX A (17 pages to follow)

(in order as listed below)

Class 1 Category B-D

ISI Exams Class 1 Category B-G-1

PSI Exam Class 1 Category B-G-2

ISI and PSI Exams Class 1 Category B-K

ISI Exam Class 1 Category B-M-2

ISI Exams Class 1 Category B-N-I

ISI Exams Class 1 Category B-N-2

ISI Exams Class 1 Category F-A 0 ISI and PSI Exams Class 1 Category R-A

ISI Exams Class 2 Category C-A

ISI Exam Class 2 Category C-B

ISI Exam Class 2 Category F-A

ISI and PSI Exams

Page 1 of 17 NIS-1 Attachment (Appendix A)

Cycle 24 Inservice Inspection Report (2009 RFO)

Interval 4, Period 2, Ml_14-P2_RF24

1. Owner: Xcel Energy Inc., NSPM, 414 Nicollet Mall, Minneapolis, MN 55401 4. Owner Certificate of Authorization (If Req.): NIA

2. Plant: Monticello Nuclear Generating Plant Unit 1 5. Commercial Service Date: June 30, 1971

3. Plant Address: 2807 West County Road 75, Monticello, MN 55362 6. National Board Number for Unit: NIA Summary No. Comp. ID Comp. Desc. Item Procedure Scope/Method/ReportlResults System Dwg/ISO Exam Date Class 1 Category B-D, EXAMS PERFORMED FOR IS1 (4th Interval, Period 2 Credited Exams) 102376 N- 6B IR N- 68 Inner Radius B3.100 FP-PE-NDE-UT-03 ISI / UT / 2009UT020 / NRI Reactor Vessel ISI Fig 1 3/28/2009 102377 N- 6B NV N- 6B Noz/Head Weld B3.90 FP-PE-NDE-406 ISI / UT / 2009UT021 / NRI Reactor Vessel ISI Fig 1 3/29/2009 Comments: Single sided exam due to configuration. Limited exam less than 90% coverage - Relief Request required 102378 N- 7 IR N- 7 Inner Radius B3.100 FP-PE-NDE-UT-03 ISI / UT / 2009UT022 / NRI Reactor Vessel ISI Fig 1 3/29/2009 102379 N- 7 NV N- 7 Noz/Head Weld B3.90 FP-PE-NDE-406 ISI / UT / 2009UT023 / NRI Reactor Vessel ISI Fig 1 3/29/2009 Comments: Single sided exam due to configuration. Limited exam less than 90% coverage - Relief Request required 102622 N-10 IR N-10 Inner Radius B3.100 FP-PE-NDE-UT-03 ISI / UT/2009UT031 / NRI Reactor Vessel ISI Fig 3 4/10/2009 102623 N-1 0 NV N-10 NozTVsl Weld B3.90 FP-PE-NDE-406 ISI / UT / 2009UT030 / NRI Reactor Vessel ISI Fig 3 4/9/2009 Comments: Single sided exam due to configuration. Limited exam less than 90% coverage - Relief Request required 102655 N- 2A IR N- 2A Inner Radius B3.100 FP-PE-NDE-UT-03 ISI / UT / 2009UT032 / NRI Reactor Vessel ISI Fig 5 4/10/2009 102656 N- 2A NV N- 2A Noz/Vsl Weld B3.90 FP-PE-NDE-406 ISI / UT / 2009UT033 / NRI Reactor Vessel ISI Fig 5 4/10/2009 Comments: Single sided exam due to configuration. Limited exam less than 90% coverage - Relief Request required 102679 N- 3C IR N- 3C Inner Radius B3.100 FP-PE-NDE-UT-03 ISI / UT / 2009UT025 / NRI Reactor Vessel ISI Fig 5 4/8/2009 102680 N- 3C NV N- 3C Noz/Vsl Weld B3.90 FP-PE-NDE-406 ISI / UT / 2009UT024 / RI Reactor Vessel ISI Fig 5 4/9/2009 PEI-02.03.16 ISI / UT / 2009UT035 / RI Reactor Vessel ISI Fig 5 4/9/2009 Comments: 2009UT024: Acceptable per code table IWB-3512-1. Reference report 2009UT035. Single sided exam due to configuration. Limited exam less than 90% coverage - Relief Request required

Page 2 of 17 NIS-1 Attachment (Appendix A)

Cycle 24 Inservice Inspection Report (2009 RFO)

Interval 4, Period 2, Ml_14-P2_RF24

1. Owner: Xcel Energy Inc., NSPM, 414 Nicollet Mall, Minneapolis, MN 55401 4. Owner Certificate of Authorization (If Req.): N/A

2. Plant: Monticello Nuclear Generating Plant Unit 1 5. Commercial Service Date: June 30, 1971

3. Plant Address: 2807 West County Road 75, Monticello, MN 55362 6. National Board Number for Unit: N/A Summary No. Comp. ID Comp. Desc. Item Procedure Scope/Method/ReportlResults System Dwg/ISO Exam Date 102685 N- 4B IR N- 48 Inner Radius B3.100 FP-PE-NDE-UT-03 ISI / UT / 2009UT027 / NRI Reactor Vessel ISI Fig 5 4/9/2009 102686 N- 4B NV N- 4B Noz/Vsl Weld B3.90 FP-PE-NDE-406 IS] / UT / 2009UT026 / NRI Reactor Vessel ISI Fig 5 4/9/2009 Comments: Single sided exam due to configuration. Limited exam less than 90% coverage - Relief Request required 102697 N- 8B IR N- 8B Inner Radius B3.100 FP-PE-NDE-UT-03 ISI / UT / 2009UT029 / NRI Reactor Vessel ISI Fig 5 4/10/2009 102698 N- 8B NV N- 8B Vsl/Noz Weld 83.90 FP-PE-NDE-406 ISI / UT / 2009UT028 / NRI Reactor Vessel ISI Fig 5 4/10/2009 Comments: Single sided exam due to configuration. Limited exam less than 90% coverage - Relief Request required

Page 3 of 17 NIS-1 Attachment (Appendix A)

Cycle 24 Inservice Inspection Report (2009 RFO)

Interval 4, Period 2, Ml_14-P2_RF24

1. Owner: Xcel Energy Inc., NSPM, 414 Nicollet Mall, Minneapolis, MN 55401 4. Owner Certificate of Authorization (If Req.): N/A

2. Plant: Monticello Nuclear Generating Plant Unit 1 5. Commercial Service Date: June 30, 1971

3. Plant Address: 2807 West County Road 75, Monticello, MN 55362 6. National Board Number for Unit: N/A Summary No. Comp. ID Comp. Desc. Item Procedure Scope/Method/Report/Results System Dwg/ISO Exam Date Class I Category B-G-1, EXAMS PERFORMED FOR 181 (4th Interval, Period 2 Credited Exams) I 102713 Washers 64 Washers B6.50 FP-PE-NDE-510 PSI / V-T / 2009VT134 / NRI Reactor Vessel ISI Fig 6 4/25/2009

Page 4 of 17 NIS-1 Attachment (Appendix A)

Cycle 24 Inservice Inspection Report (2009 RFO)

Interval 4, Period 2, Ml_14-P2_RF24

1. Owner: Xcel Energy Inc., NSPM, 414 Nicollet Mall, Minneapolis, MN 55401 4. Owner Certificate of Authorization (If Req.): N/A

2. Plant: Monticello Nuclear Generating Plant Unit 1 5. Commercial Service Date: June 30, 1971

3. Plant Address: 2807 West County Road 75, Monticello, MN 55362 6. National Board Number for Unit: NIA Summary No. Comp. ID Comp. Desc. Item Procedure Scope/Method/Report/Results System Dwg/ISO Exam Date Class 1 Category B-G-2, EXAMS PERFORMED FOR IS1 (4th Interval, Period 2 Credited Exams)

Note for Cat. B7.80: MNGP performs exams on re-used and new bolting per B7.80 1995 Edition due to gap between 1995E I 1996A and 10CFR50.55a(b)(2)(xxi)(B) 100674 B- 3 Flange Bolts @ W-16 B7.50 FP-PE-NDE-510 ISI / VT / 2009VT010 / NRI Main Steam C IS1-13142-35-A 3/23/2009 100727 B- 3 Flange Bolts @ W-17 B7.50 FP-PE-NDE-510 ISI / V-1-/ 2009VT011 / RI Main Steam D ISI-13142-36-A 3/23/2009 FP-PE-NDE-510 ISI / VT / 2009VT148 / NRI Main Steam D IS1-13142-36-A 4/16/2009 Comments: 2009V-01 1: CAP 01174903, corrected during valve changeout per WO-344392, acceptable. Reference followup exam 2009VT1 48.

100726 B- 2 Flange Bolts @ W-15 B7.50 FP-PE-NDE-510 ISI / VT / 2009V1068 / NRI Main Steam D ISI-13142-36-A 3/23/2009 100728 B- 4 Flange Bolts @ W-19 B7.50 FP-PE-NDE-510 ISI / VT / 2009VT027 / NRI Main Steam D ISI-13142-36-A 3/26/2009 100732 B- 8 Valve Bolts B7.70 FP-PE-NDE-510 PSI / VT / 2009V-074 / RI Main Steam D IS1-13142-36-A 4/3/2009 FP-PE-NDE-510 ISI / VT / 2009VT086 / NRI Main Steam D IS1-13142-36-A 4/6/2009 Comments: 2009VT074: Disassembly damage. Replaced under WO-380817. Reference PSI report 2009VT086.

101491 B- 1 Flange Bolts B7.50 FP-PE-NDE-510 ISI / VT / 2009VT133 / NRI Head Vent ISI-782A-A 4/21/2009 101850 B- 3 Flange Bolts @ W 11 B7.50 FP-PE-NDE-510 ISI / VT / 2009VT008 / NRI RHR Return A ISI-97003-A 3/23/2009 101891 B- 2 Flange Bolts @ W-9 B7.50 FP-PE-NDE-510 ISI / VT / 2009VT009 / NRI RHR Suction A ISI-97003-B 3/23/2009 101930 B- 3 Flange Bolts B7.50 FP-PE-NDE-510 ISI / VT / 2009VT007 / NRI RHR Return B ISI-97004-A 3/23/2009 101972 B- 3 Flange Bolts @ W-17 B7.50 FP-PE-NDE-510 ISI / VT / 2009VT073 / NRI Recirculation A ISI-97005-A 3/23/2009 102404 06-19B CRD Housing Bolts B7.80 FP-PE-NDE-510 PSI / VT / BOP-Vr-09-001 / NRI CR0D ISI FIG 2 3/5/2009 102408 06-27B CRD Housing Bolts B7.80 FP-PE-NDE-510 PSI / V- / BOP-V--09-001 / NRI CR0D ISI FIG 2 3/5/2009

Page 5 of 17 NIS-1 Attachment (Appendix A)

Cycle 24 Inservice Inspection Report (2009 RFO)

Interval 4, Period 2, Ml_14-P2_RF24

1. Owner: Xcel Energy Inc., NSPM, 414 Nicollet Mail, Minneapolis, MN 55401 4. Owner Certificate of Authorization (If Req.): N/A

2. Plant: Monticello Nuclear Generating Plant Unit 1 5. Commercial Service Date: June 30, 1971

3. Plant Address: 2807 West County Road 75, Monticello, MN 55362 6. National Board Number for Unit: NIA Summary No. Comp. ID Comp. Desc. Item Procedure Scope/Method/ReportlResults System Dwg/ISO Exam Date 102415 06-35B CRD Housing Bolts B7.80 FP-PE-NDE-510 PSI / VI / BOP-VF-09-001 / NRI CRD ISI FIG 2 3/5/2009 102421 10-11B CRD Housing Bolts B7.80 FP-PE-NDE-510 PSI / VT / BOP-V--09-001 / NRI CRD ISI FIG 2 3/5/2009 102435 10-43B CRD Housing Bolts B7.80 FP-PE-NDE-510 PSI / VT / BOP-VT-09-001 / NRI CRD ISI FIG 2 3/5/2009 102441 14-11B CRD Housing Bolts B7.80 FP-PE-NDE-51 0 PSI / VT / BOP-VT-09-001 / NRI CRD ISI FIG 2 3/5/2009 102443 14-19B CRD Housing Bolts B7.80 FP-PE-NDE-510 PSI / VT / BOP-VT-09-001 / NRI CRD ISI FIG 2 3/5/2009 102447 14-35B CRD Housing Bolts B7.80 FP-PE-NDE-510 PSI / VT / BOP-VT-09-001 / NRI CRD ISI FIG 2 3/5/2009 102463 18-31B CRD Housing Bolts B7.80 FP-PE-NDE-510 PSI / VT / BOP-V--09-001 / NRI CR0D SI FIG 2 3/5/2009 102466 18-43B CRD Housing Bolts B7.80 FP-PE-NDE-510 PSI / VT / BOP-VT-09-001 / NRI CRD ISI FIG 2 3/5/2009 102472 22-03B CRD Housing Bolts B7.80 FP-PE-NDE-510 PSI / VT / BOP-VT-09-001 / NRI CRD ISI FIG 2 3/5/2009 102475 22-07B CRD Housing Bolts B7.80 FP-PE-NDE-510 PSI / VT / BOP-VT-09-001 / NRI CRD ISI FIG 2 3/5/2009 102476 22-11B CRD Housing Bolts B7.80 FP-PE-NDE-510 PSI / VT / BOP-VT-09-001 / NRI CRD ISI FIG 2 3/5/2009 102484 22-43B CRD Housing Bolts B7.80 FP-PE-NDE-510 PSI / VT / BOP-VT-09-001 / NRI CRD ISI FIG 2 3/5/2009 102493 26-03B CRD Housing Bolts B7.80 FP-PE-NDE-510 PSI / VT / BOP-VT-09-001 / NRI' CRD ISI FIG 2 3/5/2009 102504 26-47B CRD Housing Bolts B7.80 FP-PE-NDE-510 PSI / VT / BOP-VT-09-001 / NRI CRD ISI FIG 2 3/5/2009 102538 34-39B CRD Housing Bolts B7.80 FP-PE-NDE-510 PSI / VT / BOP-V--09-001 / NRI CRD ISI FIG 2 3/5/2009 102544 34-47B CRD Housing Bolts B7.80 FP-PE-NDE-510 PSI / VT / BOP-VT-09-001 / NRI CR0D SI FIG 2 3/5/2009 102550 38-11B CRD Housing Bolts B7.80 FP-PE-NDE-510 PSI / VT / BOP-VT-09-001 / NRI CRD ISI FIG 2 3/5/2009

Page 6 of 17

. NIS-1 Attachment (Appendix A)

Cycle 24 Inservice Inspection Report (2009 RFO)

Interval 4, Period 2, Ml_14-P2_RF24

1. Owner: Xcel Energy Inc., NSPM, 414 Nicollet Mall, Minneapolis, MN 55401 4. Owner Certificate of Authorization (If Req.): N/A

2. Plant: Monticello Nuclear Generating Plant Unit 1 5. Commercial Service Date: June 30, 1971

3. Plant Address: 2807 West County Road 75, Monticello, MN 55362 6. National Board Number for Unit: N/A Summary No. Comp. ID Comp. Desc. Item Procedure Scooe/Method/ReoortlResults System Dwg/ISO Exam Date Class 1 Category B-K, EXAMS PERFORMED FOR IS1 (4th Interval, Period 2 Credited Exams) 101256 H- 8 DbI Spring / 4 Lugs B10.20 PEI-02.02.01 ISI / MT / 2009MT002 / NRI Feedwater IS1-13142-53-A 4/14/2009

Page 7 of 17 NIS-1 Attachment (Appendix A)

Cycle 24 Inservice Inspection Report (2009 RFO)

Interval 4, Period 2, Ml_14-P2_RF24

1. Owner: Xcel Energy Inc., NSPM, 414 Nicollet Mall, Minneapolis, MN 55401 4. Owner Certificate of Authorization (If Req.): N/A

2. Plant: Monticello Nuclear Generating Plant Unit 1 5. Commercial Service Date: June 30, 1971

3. Plant Address: 2807 West County Road 75, Monticello, MN 55362 6. National Board Number for Unit: NIA Summary No. Comp. ID Comp. Desc. Item Procedure Scope/Method/Report/Results System Dwg/ISO Exam Date Class 1 Category B-M-2, EXAMS PERFORMED FOR IS1 (4th Interval, Period 2 Credited Exams) 100746 V- 4 Valve Int Surfaces B12.50 FP-PE-NDE-530 ISI / VT / 2009VT087 / NRI Main Steam D IS1-13142-36-A 4/1/2009 Comments: Identified conditions outside of exam boundary. Addressed by CAPs 01176319, 01176198, and WO-01176319

Page 8 of 17 NIS-1 Attachment (Appendix A)

Cycle 24 Inservice Inspection Report (2009 RFO)

Interval 4, Period 2, Ml_14-P2_RF24

1. Owner: Xcel Energy Inc., NSPM, 414 Nicollet Mail, Minneapolis, MN 55401 4. Owner Certificate of Authorization (If Req.): N/A

2. Plant: Monticello Nuclear Generating Plant Unit 1 5. Commercial Service Date: June 30, 1971

3. Plant Address: 2807 West County Road 75, Monticello, MN 55362 6. National Board Number for Unit: N/A Summary No. Comp. ID Comp. Desc. Item Procedure Scope/Method/Report/Results System Dwg/ISO Exam Date Class 1 Category B-N-I, EXAMS PERFORMED FOR IS1 (4th Interval, Period 2 Credited Exams) 102716 C- 1A Top Guide (areas made access., fuel cell B13.10 PEI-02.05.05 ISI / VT / AREVA Report / NRI Reactor Vessel ISI Fig 0 4/17/2009 vacated)

Comments: Various exam dates, date shown is final review signature date 107696 C- 1C Guide Rod Bracket @ 175 deg B13.10 PEI-02.05.05 ISI / VT / AREVA Report / NRI Reactor Vessel ISI Fig 0 4/2/2009 107697 C- 1D Guide Rod Bracket @ 355 deg B13.10 PEI-02.05.05 ISI / VT / AREVA Report / NRI Reactor Vessel ISI Fig 0 4/1/2009 102719 C- 4A Surveillance Sample Holder & Bracket @ B13.10 PEI-02.05.05 ISI / VT / AREVA Report / RI Reactor Vessel ISI Fig 0 4/8/2009 30 deg.

Comments: Previously reported, no change. Acceptable per CAP 038142 (TeamTrack) 107678 C- 4B Surveillance Sample. Holder & Bracket @ B13.10 PEI-02.05.05 ISI / VT / AREVA Report / NRI Reactor Vessel ISI Fig 0 4/8/2009 120 deg.

107679 C- 4C Surveillance Sample Holder & Bracket @ B13.10 PEI-02.05.05 ISI / VT / AREVA Report / NRI Reactor Vessel ISI Fig 0 4/1/2009 300 deg.

102723 C- 8A Stm Dryer Holddown Bracket @ 35 deg (in 813.10 PEI-02.05.05 ISI / VT / 2009VT097 / NRI Reactor Vessel ISI Fig 0 4/14/2009 Closure Head) 107723 C- 88 Stm Dryer Holddown Bracket @ 145 deg B13.10 PEI-02.05.05 ISI / VT / 2009VT098 / NRI Reactor Vessel ISI Fig 0 4/14/2009 (in Closure Head) 107724 C- 8C Stm Dryer Holddown Bracket @ 215 deg B13.10 PEI-02.05.05 ISI / VT / 2009VT099 / NRI Reactor Vessel ISI Fig 0 4/14/2009 (in Closure Head) 107725 C- 8D Stm Dryer Holddown Bracket @ 325 deg B13.10 PEI-02.05.05 ISI / VT / 2009VT096 / NRI Reactor Vessel ISI Fig 0 4/14/2009 (in Closure Head)

Page 9 of 17 NIS-1 Attachment (Appendix A)

Cycle 24 Inservice Inspection Report (2009 RFO)

Interval 4, Period 2, Ml_14-P2_RF24

1. Owner: Xcel Energy Inc., NSPM, 414 Nicollet Mall, Minneapolis, MN 55401 4. Owner Certificate of Authorization (If Req.): N/A

2. Plant: Monticello Nuclear Generating Plant Unit 1 5. Commercial Service Date: June 30, 1971

3. Plant Address: 2807 West County Road 75, Monticello, MN 55362 6. National Board Number for Unit: N/A Summary No. Comp. ID Comp. Desc. Item Procedure Scope/Method/ReportlResults System Dwg/ISO Exam Date 102724 C- 9A Stm Dryer Holddown Bracket @ 35 deg B13.10 PEI-02.05.05 ISI / VT / AREVA Report / NRI Reactor Vessel ISI Fig 0 4/1/2009 107730 C- 9B Stm Dryer Holddown Bracket @ 145 deg B13.10 PEI-02.05.05 ISI / VT / AREVA Report / NRI Reactor Vessel ISI Fig 0 4/2/2009 107731 C- 9C Stm Dryer Holddown Bracket @ 215 deg B13.10 PEI-02.05.05 ISI / VT / AREVA Report / NRI Reactor Vessel ISI Fig 0 4/2/2009 107732 C- 9D Stm Dryer Holddown Bracket @ 325 deg B13.10 PEI-02.05.05 ISI / VT / AREVA Report / NRI Reactor Vessel ISI Fig 0 4/1/2009 107738 C- 12A Core Plate (areas made access., fuel cell B13.10 PEI-02.05.05 ISI / VT / AREVA Report / NRI Reactor Vessel ISI Fig 0 4/17/2009 vacated)

Comments: Various exam dates, date shown is final review signature date 107706 C- 7B Shroud Support Leg Weld @ 010 deg B13.30 PEI-02.05.05 ISI / VT / AREVA Report / RI Reactor Vessel ISI Fig 0 4/12/2009 Comments: Acceptable per CAP A/R 01177677 and Structural Integrity analysis 107707 C- 7C Shroud Support Leg Weld @ 030 deg B13.30 PEI-02.05.05 ISI / V- / AREVA Report / RI Reactor Vessel ISI Fig 0 4/11/2009 Comments: Acceptable per CAP A/R 01177677 and Structural Integrity analysis 107708 C- 7D Shroud Support Leg Weld @ 060 deg B13.30 PEI-02.05.05 ISI / VT / AREVA Report / RI Reactor Vessel ISI Fig 0 4/11/2009 Comments: Acceptable per CAP A/R 01177677 and Structural Integrity analysis 107709 C- 7E Shroud Support Leg Weld @ 090 deg B13.30 PEI-02.05.05 ISI / VT / AREVA Report / NRI Reactor Vessel ISI Fig 0 4/11/2009

Page 10 of 17 NIS-1 Attachment (Appendix A)

Cycle 24 Inservice Inspection Report (2009 RFO)

Interval 4, Period 2, Ml_14-P2_RF24

1. Owner: Xcel Energy Inc., NSPM, 414 Nicollet Mall, Minneapolis, MN 55401 4. Owner Certificate of Authorization (If Req.): N/A

2. Plant: Monticello Nuclear Generating Plant Unit 1 5. Commercial Service Date: June 30, 1971

3. Plant Address: 2807 West County Road 75, Monticello, MN 55362 6. National Board Number for Unit: NIA Summary No. Comp. ID Comp. Desc. Item Procedure Scope/Method/Report/Results System Dwg/ISO Exam Date 107710 C- 7F Shroud Support Leg Weld @ 120 deg B133.30 PEI-02.05.05 ISI / VT / AREVA Report / RI Reactor Vessel ISI Fig 0 4/11/2009 Comments: Acceptable per CAP A/R 01177677 and Structural Integrity analysis 107711 C- 7G Shroud Support Leg Weld @ 150 deg B133.30 PEI-02.05.05 ISI / VT / AREVA Report / RI Reactor Vessel ISI Fig 0 4/10/2009 Comments: Acceptable per CAP A/R 01177677 and Structural Integrity analysis 107712 C- 7H Shroud Support Leg Weld @ 170 deg B13.30 PEI-02.05.05 ISI / VT / AREVA Report / RI Reactor Vessel ISI Fig 0 4/11/2009 Comments: Acceptable per CAP A/R 01177677 and Structural Integrity analysis 107713 C- 7J Shroud Support Leg Weld @ 190 deg B13.30 PEI-02.05.05 ISI / VT / AREVA Report / RI Reactor Vessel ISI Fig 0 4/9/2009 Comments: Acceptable per CAP A/R 01177677 and Structural Integrity analysis 107714 C- 7K Shroud Support Leg Weld @ 210 deg B13.30 PEI-02.05.05 ISI / VT / AREVA Report / RI Reactor Vessel ISI Fig 0 4/9/2009 Comments: Acceptable per CAP A/R 01177677 and Structural Integrity analysis 107715 C- 7L Shroud Support Leg Weld @ 240 deg B13.30 PEI-02.05.05 ISI / VT / AREVA Report / RI Reactor Vessel ISI Fig 0 4/10/2009 Comments: Acceptable per CAP A/R 01177677 and Structural Integrity analysis 107716 C- 7M Shroud Support Leg Weld @ 270 deg B13.30 PEI-02.05.05 ISI / VT / AREVA Report / RI Reactor Vessel ISI Fig 0 4/11/2009 Comments: Acceptable per CAP A/R 01177677 and Structural Integrity analysis 107717 C- 7N Shroud Support Leg Weld @ 300 deg B13.30 PEI-02.05.05 ISI / V-T / AREVA Report / RI Reactor Vessel ISI Fig 0 4/11/2009 Comments: Acceptable per CAP A/R 01177677 and Structural Integrity analysis

Page 11 of 17 NIS-1 Attachment (Appendix A)

Cycle 24 Inservice Inspection Report (2009 RFO)

Interval 4, Period 2, Ml_14-P2_RF24

1. Owner: Xcel Energy Inc., NSPM, 414 Nicollet Mall, Minneapolis, MN 55401 4. Owner Certificate of Authorization (If Req.): N/A

2. Plant: Monticello Nuclear Generating Plant Unit 1 5. Commercial Service Date: June 30, 1971

3. Plant Address: 2807 West County Road 75, Monticello, MN 55362 6. National Board Number for Unit: N/A Summary No. Comp. ID Comp. Desc. Item Procedure Scope/Method/Report/Results System Dwg/ISO Exam Date 107718 C- 7P Shroud Support Leg Weld @330 deg B13.30 PEI-02.05.05 SI /VT/AREVA Report / NRI Reactor Vessel SI Fig 0 4/11/2009 107719 C- 70 Shroud Support Leg Weld @ 350 deg B13.30 PEI-02.05.05 ISI / VT / AREVA Report / NRI Reactor Vessel ISI Fig 0 4/11/2009 107739 C- 12B Core Plate (areas made access., fuel cell B13.40 PEI-02.05.05 ISI / VT / AREVA Report / NRI Reactor Vessel ISI Fig 0 4/17/2009 vacated)

Comments: Various exam dates, date shown is final review signature date 107746 C- 18 Ctrl Rod Guide Tube (CRGT) - Int (when B13.40 PEI-02.05.05 ISI / VT / AREVA Report / RI Reactor Vessel ISI Fig 0 4/17/2009 access, fuel cell vacated)

Comments: Various exam dates, date shown is final review signature date Minor deformation identified in CRGT 26-11 and 18-07. Acceptable per CAP A/R 01176818

Page 12 of 17 NIS-1 Attachment (Appendix A)

Cycle 24 Inservice Inspection Report (2009 RFO)

Interval 4, Period 2, Ml_14-P2_RF24

i. Owner: Xte Energy Inc., NSP, 4`4 ,, Nkoet. Matt, Mnneapolis, MR 56401 4. Owner Certificate of Authorization (if Req.): NMA

2. Plant: Monticello Nuclear Generating Plant Unit 1 5. Commercial Service Date: June 30, 1971

3. Plant Address: 2807 West County Road 75, Monticello, MN 55362 6. National Board Number for Unit: NIA Summary No. Comp. ID Comp. Desc. Item Procedure Scope/Method/Report/Results System Dwg/ISO Exam Date Class 1 Category F-A, EXAMS PERFORMED FOR IS1 (4th Interval, Period 2 Credited Exams) 100427 H- 1 Restraint / Clamp F1.10a FP-PE-NDE-530 IS[I /VT / 2009VT017/ NRI Core Spray B IS1-13142-26-A 3/24/2009 100496 H- 2 Spring / Clamp FI. 10c FP-PE-NDE-530 ISI? VT / 2009VT072 / NRI Core Spray A ISI-13142-31-A 4/2/2009 100578 H-2 Snubber / Clamp F1.10b FP-PE-NDE-530 PSI /VT / 2009VT094/ NRI Main Steam A ISI-13142-33-A 4/11/2009 100583 H- 7 Snubber / Clamp FI. 10b FP-PE-NDE-530 PSI /VT / 2009VT085 / NRI Main Steam A ISI-13142-33-A 4/7/2009 100631 H- 2 Snubber ? Clamp F1.10b FP-PE-NDE-530 PSI i VT / 2009V-r091 / NRI Main Steam B ISI-13142-34-A 4/9/2009 101198 H- 4 Snubber / Clamp F1.10b FP-PE-NDE-530 PSI / VT / 2009VF022 / RI Feedwater ISI-13142-52-A 3/25/2009 Comments: CAP 01175433, Engineer rotated mechanically, acceptable.

101201 H- 7 Snubber/Clamp F1.10b FP-PE-NDE-530 PSI / VT / 2009VF001 / NRI Feedwater ISI-13142-52-A 3/21/2009 101253 H- 5 Snubber / Clamp F1.10b FP-PE-NDE-530 PSI / VT / 2009VT023 / RI Feedwater ISI-13142-53-A 3/25/2009 Comments: CAP 01175436, Engineer rotated mechanically, acceptable.

101255 H- 7 Snubber/Clamp F1.10b FP-PE-NDE-530 PSI / VT / 2009VT002 / NRI Feedwater ISI-13142-53-A 3/21/2009 101896 H- 2 Snubber / Clamp FI. 10b FP-PE-NDE-530 PSI / VT / 2009VT071 / NRI RHR Suction A ISI-97003-B 4/2/2009 101935 H- 3 Snubber / Clamp FI. 10b FP-PE-NDE-530 PSI / VT / 2009VT088 / NRI RHR Return B ISI-97004-A 4/8/2009 101936 H- 4 Snubber/ Clamp F1.10b FP-PE-NDE-530 PSI / VT / 2009VT089 / NRI RHR Return B ISI-97004-A 4/8/2009 FP-PE-NDE-530 ISI / VT / 2009VT090 / NRI RHR Return B ISI-97004-A 4/8/2009 102018 H- 1 Restraint Fl. 10a FP-PE-NDE-530 ISI / VT / 2009VT024 / NRI Recirc Manifold A ISI-97005-B 3/25/2009

Page 13 of 17 NIS-1 Attachment (Appendix A)

Cycle 24 Inservice Inspection Report (2009 RFO)

Interval 4, Period 2, Ml_14-P2_RF24

1. Owner: Xcel Energy Inc., NSPM, 414 Nicollet Mall, Minneapolis, MN 55401 4. Owner Certificate of Authorization (If Req.): NIA

2. Plant: Monticello Nuclear Generating Plant Unit 1 5. Commercial Service Date: June 30, 1971

3. Plant Address: 2807 West County Road 75, Monticello, MN 55362 6. National Board Number for Unit: N/A Summary No. Comp. ID Comp. Desc. Item Procedure Scope/Method/Report/Results System Dwg/ISO Exam Date 105022 H-17 Spring / Clamp F1.10c FP-PE-NDE-530 PSI / VT / 2009VT025 / NRI Head Vent ISI-782A 3/25/2009 105023 H- 1 Hanger F1.10a FP-PE-NDE-530 PSI / V-T / 2009V-1 36 / NRI Head Vent ISI-782A-A 4/26/2009 105024 H- 2 Spring / Clamp F1.10c FP-PE-NDE-530 PSI / V-I / 2009Vr135 / NRI Head Vent ISI-782A-A 4/26/2009 105025 H- 3 Hanger F1.10a FP-PE-NDE-530 PSI / V-T/ 2009VT1 37 / NRI Head Vent ISI-782A-A 4/26/2009 107522 H- 8 DbI Spring / 4 Lugs F1.10c FP-PE-NDE-530 ISI / Vr / 2009V-o100 / NRI Feedwater ISI-13142-53-A 4/14/2009 107528 H-8 Snubber / Lugs F1.10b FP-PE-NDE-530 PSI / V- / 2009Vr012 / RI Recirculation A ISI-97005-A 3/24/2009 Comments: CAP 01175429, Engineer rotated mechanically, acceptable.

107530 H- 2 Snubber / Lugs F1.10b FP-PE-NDE-530 PSI / VT / 2009V-r095 / NRI Recirc Manifold A ISI-97005-B 4/13/2009 107540 H- 7 Snubber / Lugs F1.40b FP-PE-NDE-530 PSI / VT / 2009V-003 / NRI Recirc Pump A ISI-97005-C 3/21/2009 107541 H- 8 Snubber / Lugs F1.40b FP-PE-NDE-530 PSI / V-T / 2009V-014 / NRI Recirc Pump A ISI-97005-C 3/24/2009 107542 H- 9 Snubber / Lugs F1.40b FP-PE-NDE-530 PSI / VT / 2009VT01 3 / NRI Recirc Pump A ISI-97005-C 3/24/2009 107547 H- 8 Snubber / Lugs Fl. 10b FP-PE-NDE-530 PSI / V-T / 2009V-004 / RI Recirculation B ISI-97006-A 3/21/2009 Comments: CAP 01174890, Engineer rotated mechanically, acceptable.

107559 H- 7 Snubber / Lugs F1.40b FP-PE-NDE-530 PSI / VT / 2009VT005 / NRI Recirc Pump B ISI-97006-C 3/21/2009

Page 14 of 17 NIS-1 Attachment (Appendix A)

Cycle 24 Inservice Inspection Report (2009 RFO)

Interval 4, Period 2, Ml_14-P2_RF24

1. Owner: Xcel Energy Inc., NSPM, 414 Nicollet Mali, Minneapolis, MN 55401 4. Owner Certificate of Authorization (If Req.): N/A

2. Plant: Monticello Nuclear Generating Plant Unit 1 5. Commercial Service Date: June 30, 1971

3. Plant Address: 2807 West County Road 75, Monticello, MN 55362 6. National Board Number for Unit: NIA Summary No. Comp. ID Comp. Desc. Item Procedure Scope/Method/ReportlResults System Dwg/ISO Exam Date Class I Category R-A, EXAMS PERFORMED FOR IS1 (4th Interval, Period 2 Credited Exams) 101009 W-17 Pipe-to-Valve R1.11-2 FP-PE-NDE-401 ISI / UT /2009UT009 (Page 1) / NRI HPCI Steam ISI-13142-42-A 3/20/2009 FP-PE-NDE-401 ISI / UT / 2009UT009 (Page 2) / GEO HPCI Steam ISI-13142-42-A 3/20/2009 Comments: Single sided exam - no scan on valve side due to configuration. Essentially 100% coverage.

101286 W-27 Reducer-to-Pipe R1.11-2 FP-PE-NDE-401 ISI / UT 2009UT019 (Page 1)/ NRI Feedwater ISI-13142-53-A 3/25/2009 FP-PE-NDE-401 ISI /UT / 2009UT019 (Page 2) / NRI Feedwater IS1-13142-53-A 3/26/2009 101875 W-16 Elbow-to-Pipe R1.11-2 FP-PE-NDE-401 ISI/ UT / 2009UT008 / NRI RHR Return A ISI-97003-A 3/22/2009 101950 W-11 Elbow-to-Pipe R1.11-2 FP-PE-NDE-401 ISI/ UT / 2009UT007 / NRI RHR Return B ISI-97004-A 3/22/2009 100502 W-3 Pipe-to-Pipe R1.20-4 FP-PE-NDE-401 ISI / UT / 2009UT01 0 (Page 1) / NRI Core Spray A ISI-13142-31-A 3/20/2009 FP-PE-NDE-401 ISI / UT / 2009UT010 (Page 2) / NRI Core Spray A IS1-13142-31-A 3/20/2009 Comments: Single sided exam - no scan on penetration side due to configuration. Essentially 100% coverage.

100592 W-4 Pipe-to-Elbow R1.20-4 FP-PE-NDE-401 ISI / UT /2009UT034 (Page 1) / NRI Main Steam A ISI-13142-33-A 4/11/2009 FP-PE-NDE-401 ISI / UT / 2009UT034 (Page 2) / NRI Main Steam A IS1-13142-33-A 4/11/2009 FP-PE-NDE-401 ISI / UT / 2009UT034 (Page 3) / NRI Main Steam A ISI-13142-33-A 4/11/2009 100715 W-25 Pipe-to-Elbow R1.20-4 FP-PE-NDE-401 ISI / UT /2009UT017 (Page 1) / NRI Main Steam C ISI-13142-35-A 3/25/2009 FP-PE-NDE-401 ISI / UT / 2009UT017 (Page 2) / GEO Main Steam C IS1-13142-35-A 3/26/2009 101218 W-1 2 Pipe-to-Elbow R1.20-4 FP-PE-NDE-401 ISI / UT / 2009UT01 8 (Page 1) / NRI Feedwater IS1-13142-52-A 3/25/2009 FP-PE-NDE-401 ISI / UT / 2009UT018 (Page 2) / NRI Feedwater IS1-13142-52-A 3/26/2009

Page 15 of 17 NIS-1 Attachment (Appendix A)

Cycle 24 Inservice Inspection Report (2009 RFO)

Interval 4, Period 2, Ml_14-P2_RF24

1. Owner: Xcel Energy Inc., NSPM, 414 Nicollet Mall, Minneapolis, MN 55401 4. Owner Certificate of Authorization (If Req.): N/A

2. Plant: Monticello Nuclear Generating Plant Unit 1 5. Commercial Service Date: June 30, 1971

3. Plant Address: 2807 West County Road 75, Monticello, MN 55362 6. National Board Number for Unit: N/A Summary No. Comp. ID Comp. Desc. Item Procedure Scope/Method/Report/Results System Dwg/ISO Exam Date Class 2 Category C-A, EXAMS PERFORMED FOR IS1 (4th Interval, Period 2 Credited Exams) 101602 W-3 Lower Head/Flange C1.20 FP-PE-NDE-401 ISI / UT / 2009UT004 / NRI RHR Heat Exchanger A ISI-7905-32A 3/21/2009

Page 16 of 17 NIS-1 Attachment (Appendix A)

Cycle 24 Inservice Inspection Report (2009 RFO)

Interval 4, Period 2, Ml_14-P2_RF24

1. Owner: Xcel Energy Inc., NSPM, 414 Nicollet Mall, Minneapolis, MN 55401 4. Owner Certificate of Authorization (If Req.): N/A

2. Plant: Monticello Nuclear Generating Plant Unit 1 5. Commercial Service Date: June 30, 1971

3. Plant Address: 2807 West County Road 75, Monticello, MN 55362 6. National Board Number for Unit: N/A Summary No. Comp. ID Comp. Desc. Item Procedure Scope/Method/ReportlResults System Dwg/ISO Exam Date Class 2 Category C-B, EXAMS PERFORMED FOR IS1 (4th Interval, Period 2 Credited Exams) 101595 N- 2 SheIl-Pad-Noz C2.31 PEI-02.02.01 ISI / MT / 2009MT001 / NRI RHR Heat Exchanger A ISI-7905-32A 3/27/2009

Page 17 of 17 NIS-1 Attachment (Appendix A)

Cycle 24 Inservice Inspection Report (2009 RFO)

Interval 4, Period 2, Ml 14-P2_RF24

1. Owner: Xcel Energy Inc., NSPM, 414 Nicollet Mall, Minneapolis, MN 55401 4. Owner Certificate of Authorization (If Req.): NIA

2. Plant: Monticello Nuclear Generating Plant Unit 1 5. Commercial Service Date: June 30, 1971

3. Plant Address: 2807 West County Road 75, Monticello, MN 55362 6. National Board Number for Unit: N/A Summary No. Comp. ID Comp. Desc. Item Procedure Scope/Method/ReportlResults System Dwg/ISO Exam Date Class 2 Category F-A, EXAMS PERFORMED FOR IS1 (4th Interval, Period 2 Credited Exams) 100131 H- 4 Slide F1.20b FP-PE-NDE-530 PSI / VT / 2009V-r092 / NRI RHR Suction B ISI-13142-17-C 4/10/2009 100263 H- 1 Snubber / Clamp F1.20b FP-PE-NDE-530 PSI / VTI/ 2009VT01 9 / NRI HPCI Steam Disch ISI-13142-19-A 3/23/2009 100264 H- 2 DbI Snubber / Clamp F1.20b FP-PE-NDE-530 PSI / Vr / 2009VT066 1 NRI HPCI Steam Disch ISI-13142-19-A 3/28/2009 100987 H-11 Snubber / Clamp F1.20b FP-PE-NDE-530 PSI / VT / 2009VT020 / NRI HPCI Steam ISI-13142-42-A 3/23/2009 FP-PE-NDE-530 PSI / VT / 2009VT063 / NRI HPCI Steam IS1-13142-42-A 3/28/2009 101139 H- 1 Snubber / Dbl Strut F1.20b FP-PE-NDE-530 PSI / VT / 2009VT067 / NRI RHR A ISI-13142-51-A 4/1/2009 101685 DVMX Supp D DVMX Pump Support F1.40a FP-PE-NDE-530 ISI / VT / 2009VTo06 / NRI HPCI Pumps ISI-8292-42A 3/22/2009 101713 H-12 Snubber/Clamp F1.20b FP-PE-NDE-530 PSI /VT /2009VT015 /NRI CRD Scram Header A ISI-93268-1A 3/24/2009 101715 H-14 Snubber / Clamp F1.20b FP-PE-NDE-530 PSI /VT /2009VT016 /NRI CRD Scram Header A ISI-93268-1A 3/24/2009 106810 H-1 Double Snubber F1.20b FP-PE-NDE-530 PSI /VT /2009VT069/ NRI RCIC Steam Discharge ISI-13142-19-B 4/2/2009 FP-PE-NDE-530 PSI / VT / 2009VT070 / NRI RCIC Steam Discharge IS1-13142-19-B 4/2/2009 106851 H-1B Restraint Hanger F1.20a FP-PE-NDE-530 PSI /VT /2009VT065/ RI Core Spray A Discharge ISI-13142-31-B 4/1/2009 Comments: Acceptable per CAP-01175351 Condition Evaluation.

106949 H- 4 Restraint Hanger F1.20a FP-PE-NDE-530 PSI / VT / 2009VT1 02 / NRI RHR B ISI-13142-51-C 4/10/2009 106972 H- 2 Restraint Hanger F1.20a FP-PE-NDE-530 PSI / VT / 2009VT1-01 / NRI RHR B ISI-13142-51-D 4/12/2009 107049 H- 2 Snubber F1.20b FP-PE-NDE-530 PSI / VT / 2009V-018 / RI RHR A IS1-13142-37-E 3/23/2009 FP-PE-NDE-530 PSI / VT / 2009VT093 / NRI RHR A IS1-13142-37-E 4/9/2009 Comments: 2009VI-018: RI -- New retainer clip installed per WO-325070-03. Reference NRI report 2009VT093 107582 Support B Support B,E200A 1800 F1.40a FP-PE-NDE-530 ISI / VT / 2009VI-084 / NRI RHR Heat Exchanger A ISI-7905-32A 4/5/2009

Monticello Nuclear Generating Plant Cycle 24 Summary Report Inservice Inspection 2009 Refueling Outage APPENDIX B Reactor Vessel IVVI Examinations (9 pages to follow)

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Monticello Nuclear GeneratingStation 2009 RFO-24 Refuel Outage In-Vessel Visual Examination Summary Report 1.0 In-Vessel Visual Examination Project Overview:

During the 2009 Monticello Nuclear Generating Station RFO-24 comprehensive visual examinations of reactor vessel internal components were conducted to ensure the continued integrity of the RPV internal components. These examinations were conducted in accordance with Monticello procedure PEI-02.05.05, Revision 1 including TCN-001-B.

Additionally, all enhanced visual inspections (EVT-1) were performed in accordance with the Examination Recommendations of TR-105696-R1O (BWRVIP-03) Revision 10. Details of the examinations performed can be found in the individual component data sheets contained in Section 3.0 of this report. A synopsis of the components examined, the methods utilized, and the examination results are provided below.

1.1 Scope The following table lists the scope of In-Vessel Visual Examinations, along with the examination method used.

Component Scope of Work Inspection Method Adapter to Shroud Baffle Plate (AD-2) EVT-1 Jet Pump Assemblies Diffuser to Backing Ring (AD-3a) EVT-1 11-15 Diffuse weld (DF-1) EVT-1 Diffuse weld (DF-2) EVT-1 Jet_________e___i Inlet Mixer weld (MX-1) EVT-1 Jet Pump Assemblies Inlet Mixer Mixer weld weld (MX-2)

(MX-4) EVT-1

___________Inlet . EV-I-1 Recirc Riser Welds @ Thermal Sleeve to Elbow (RS-1) EVT-1 300, 600, 900' Elbow to riser Pipe (RS-2) EVT-1 Riser Pipe to Transition Piece (RS-3) EVT-1 Recirc Riser Welds @ Restrainer Bkt to Riser Pipe (RS-4) EVT-1 2100, 2400 Restrainer Bkt to Riser Pipe (RS-5) EVT-1 Monitor indication in Shroud Support Leg VT-3 Shroud Support Legs Upper Weld (H-10) @ 2100 H -10, H -11 and H -12 on all 14 Support Legs VT-3 Clamp Assemblies on Tee Box Junctions at 900 VT-3 Measure previous known indication P3A EVT-1 Core Spray Header and VT-3, Downcomers welds on Bkt & Att welds at 300 and 1500 EVT-1 Div II Welds P1-90, P2-90, P3A, P3B, P4-B-a, P4-B-

.b, P4-B-c, P4-B-d, P5-A, P6-A, P7-A, P8-A-a, EVT-1 P8-A-b,P5-B, P6-B, P7-B, P8-B-a, P8-B-b,

A XceIEnergyo AREVA RESPONS1ILE MY NATURE-Clamp Assemblies on Tee Box Junctions at VT-3 2700 Core Spray Header and Bkt & Att welds at 2100 and 3300 VT-3, DowncomersDiv welds l on Welds P1-270, P2-270, P3C, P3D, P5-C, P6-C, P7-C, P8-C-a, P8-C-b, EVT-1 P5-D, P6-D, P7-D, P8-D-a, P8-D-b, Lower Core Spray Welds Si-B, S2-B-1, S2-B-2, S4-B-1, S4-B-2 EVT-1 Sparger 'B' BS3C-1, BS3C-2, BS3A, BS3B, VT-1 Upper Core Spray Welds Sl-C, S2-C-1, S2-C-2, S4-C-1, S4-C-2 EVT-1 Sparger'C' CS3C-1, CS3C-2, CS3A, CSB, VT-1 Core Spray Sparger CS-SB @ 930, 1260, 1660, 1930, 2340, and I Brackets 2670, VT-i Accessible Bolting and Hardware, Grid Beams:

06-19, 06-27, 06-35, 10-11, 10-43, 14-07, 14-Top Guide 11, 14-15, 14-19, 14-35, 18-07, 18-31, 18-43, (B-N-T) 22-03, 22-07, 22-11, 22-23, 22-31, 22-43, 26- VT-3 03, 26-11, 26-47, 30-23, 30-31, 34-07, 34-15, 34-39, 34-47, 38-07, 38-11, 38-15, 42-11, 42-15 Accessible surfaces including the tops of FSC (when available) and anti-rotation pins: 06-19, Core Plate 06-27, 06-35, 10-11, 10-43, 14-07 14-11, 14-(B-N-I, B-N-2) 15, 14-19, 14-35, 18-07, 18-31, 18-43, 22-03, VT-3 22-07, 22-11, 22-23, 22-31, 22-43, 26-03, 26-11, 26-47, 30-23, 30-31, 34-07, 34-15, 34-39, 34-47, 38-07, 38-11, 38-15, 42-11, 42-15 Dryer OD Previously Identified Ind. V3 @ 90',

V1 0 @900, V10 @2700, Jacking Bolt @ 3250, VT-1 Steam Dryer Vertical Guide@ 215 0 Dryer ID Previously Identified Ind. VT-i DC-F- Cover Plate @ 00 Steam Dryer Hold Down Brackets @

Top Head 35% 145', 215%, and 3250 VT-3

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0 1.2 Examination Results The examinations re-affirmed previously reported indications. Thorough evaluations concluded there were no discernable changes in the indications from the original discovery. The previously reported indications included:

" Crack indication in the 900 core spray t-box to header weld in the 800 side header.

" Crack indication in 3250 Jacking Bolt tack weld

Crack indication in Dryer Weld V3 90

Crack indication in Dryer Weld V1 0 90 4 Crack indication in Dryer Weld V1 0 270

Crack indication in 2150 Vertical Guide

" Crack indication in DC-F- Cover Plate @ 00 Current RFO-24 IVVI examinations identified the following new indications and/or conditions:

During the Guide Tube examinations two new indications were found on two separate Guide Tubes, cell locations 18 - 07 and 26 -11. These two new indications consisted of one minor indentation each in the Guide Tubes located in the area immediately above the CRGT-3 weld at the bottom of the Guide Tubes.

During the re-examination of the previously known indication located on the Shroud Support Leg in the H -10 weld at 210 degrees a new indication was discovered on the 200 degree side of this support at H -10. This prompted the requirement of an additional sampling of another Support Leg which also showed an additional new indication.

Subsequently this resulted in all 14 Shroud Support legs being examined, welds H-10, H -11 and H -12. These further examinations reveled all but two Support Legs, at 90 degrees and 350 degrees, showing new crack indications. All cracking was confined to the H -10 welds, Shroud Support to Shroud Support Cylinder.

A XcelEnergy" AREVA AtIFo0M$IOt BY NATUAC' 1.3 Equipment The equipment used during the Monticello RFO-24 In-Vessel Visual Examinations is as follows:

+ Camera Systems

> IST-DOTCAM

+ IST-DOTCAM with 6 LED lights, total wattage output of .43 watts

+Single 35 watt UL210

> RJ Electronics RJ-81 10 Color Camera System

+ RJ-81 10 Camera with Pan, Tilt, & Zoom

+ RJ Electronics CCU

+ RJ Electronics Twin 35 Watt Light Unit

> IST-Rees ETV-1250 Black and White Camera System

+ ETV-1250 Camera

+ IST-Reese Cable

+ IST-Reese CCU

Twin 50W Lighting System

> REES R93 Black and White Camera System

+ R93 Camera

+R93 Cable

+ R93 CCU

+Single 35 watt or Dual 20 watt lights

> AREVA NP ROV ROCKY ID (Camera Delivery System)

+VIT-4.5 Color Camera with Pan, Tilt, & Zoom

Twin 35 Watt Lights

+VIT CCU

. 100' Cable

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ACCURATE Inspection Station

> Intel Xeon E5405 2.00GHz CPU

1.96 GB of RAM

465 GB HD (system drive)

. 500 GB HD (IWI data drive)

Ethernet NIC

Matrox Vio Video Capture/Display

+ ROBOT MV99e Video Multiplexer (optional)

Microsoft Windows XP (Service Pack 2)

Microsoft Excel 2003

MySQL (Version 5.0)

Matrox Imaging Library - MIL 8.08 Lite

Microsoft Media Player

,Areva IWI Software

ACD Systems Canvas

(2) 20" LCD Flat-Panel Color Monitors

+ Communication Headsets

ACCURATE Level Ill and Server Stations

> Intel Xeon E5405 2.00GHz CPU

1.96 GB of RAM

. 465 GB HD (system drive)

. 500 GB HD (IVVI data drive)

Ethernet NIC

Matrox Vio Video Capture/Display

ROBOT MV99e Video Multiplexer (optional)

Microsoft Windows XP (Service Pack 2)

Microsoft Excel 2003

MySQL (Version 5.0)

Matrox Imaging Library - MIL 8.08 Lite

Microsoft Media Player

Areva IWI Software

ACD Systems Canvas

. 3 - 20" LCD Flat-Panel Color Monitors

Communication Headsets

HP Color Laser Jet 2600n Printer

Cleaning Equipment

> 10,000 PSI Hydro Laser Supplied by XcelEnergy with AREVA NP Supplied Foot Pedal, Wands, and Weights

> 12 volt Rotary Power Brushing System

UnderwaterLights and Power Supply

> PS-160 Power Supply

> Birns 500w Light w/cable

> Variac variable power supply

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+ Sensitivity, Resolution and ContrastStandards

> S/N 7001346 (DB# 14098)

+ Support Equipment

> AREVA 1"dia. Double Locking Handling Poles (various lengths)

) Various Cables

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AR EVA S AUV Monticello Nuclear Generating Station 2009 RFO-24 Refuel Outage In-Vessel Visual Examination Indication History The following table provides a history of the indications that have been identified prior to and during RFO-24 in the reactor vessel internal components at the Monticello Nuclear Generating Station.

Associated Component Indication Engineering Evaluations Steam Impingement Wear in Dryer Head in CR20000209 Areas of all Four Main Steam Nozzles Crack Indication in 3250 Jacking Bolt Tack CR98000794 Weld - Unrepaired Crack Indication at the top of weld V3 90 CAP 037603 Steam Dryer Crack Indication at the top of weld V10 90 CAP 037603 Crack Indication on Dryer Support Bracket CAP 037603 Guide weld at 215 Crack Indication at the top of weld V10 270 CAP 037603 Crack Indications adjacent to Drain Channel Ref. INR-R23-03

'F' Cover Plate Weld on Dryer ID Crack Indication in Jet Pump #10 vessel Side CR20000209 Tack Weld - Unrepaired Crack Indication in Jet Pump #14 Vessel Side SRI 94-019 Tack Weld - Repaired Crack indication in Jet Pump #15 Vessel Side SRI 94-019 Tack Weld - Repaired Crack indication in Jet Pump #18 Vessel Side SRI 94-019 Tack Weld - Repaired Crack indication in Jet Pump #14 Beam Bolt CR98000794 retainer Tack Weld - Unrepaired Jet Pumps Crack indication in Jet Pump #19 Beam Bolt CR98000794 retainer Tack Weld - Unrepaired Crack Indication in Jet Pump #8 Secondary Riser Brace Lower Leaf to Block Weld in Leaf SRI-89-028 Material - Unrepaired Crack Indication in Jet Pump #19 Secondary Riser Brace Lower Leaf to Block Weld in Block CR20000209 Material - Unrepaired Evaluated by Small 0.25 Inch Crack Indication Extending NSP as Oxide from Arc Strike in Jet Pump #20 Diffuser Weld Layer Break DF Unrepaired (Non-Relevant)

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AREVA IfE PON $ILE BtY ATUgAE Monticello Nuclear Generating Station 2009 RFO-24 Refuel Outage In-Vessel Visual Examination Indication History Associated Component Indication Engineering Evaluations Crack indication in 2100 Shroud Support Leg CAP 01177677 to Shroud Support Cylinder Weld - Unrepaired Crack indication in 2100 Shroud Support Leg CAP 01177677 to Shroud Support Cylinder Weld (New Ind.)

Crack indication in 2400Shroud Support Leg CAP 01177677 to Shroud Support Cylinder Weld (New Ind.)

Crack indication in 1500 Shroud Support Leg CAP 01177677 to Shroud Support Cylinder Weld (New Ind.)

Crack indication in 0100 Shroud Support Leg CAP 01177677 to Shroud Support Cylinder Weld (New Ind.)

Crack indication in 0300 Shroud Support Leg CAP 01177677 to Shroud Support Cylinder Weld (New Ind.)

Shroud Support Legs Crack indication in 0600 Shroud Support Leg CAP 01177677 to Shroud Support Cylinder Weld (New Ind.)

Crack indication in 1200 Shroud Support Leg CAP 01177677 to Shroud Support Cylinder Weld (New Ind.)

Crack indication in 1500 Shroud Support Leg CAP 01177677 to Shroud Support Cylinder Weld (New Ind.)

Crack indication in 1700 Shroud Support Leg CAP 01177677 to Shroud Support Cylinder Weld (New Ind.)

Crack indication in 1900 Shroud Support Leg CAP 01177677 to Shroud Support Cylinder Weld (New Ind.)

Crack indication in 2700 Shroud Support Leg CAP 01177677 to Shroud Support Cylinder Weld (New Ind.)

Crack indication in 3000 Shroud Support Leg CAP 01177677 to Shroud Support Cylinder Weld (New Ind.)

Core Spray Crack Indication in 900 Tee Box Junction to SRI-93-006 Header - Repaired N11A and N11B Removal of Typical Oxides from Nozzle Areas CR20000209 Nozzles Due to Steam Flashing or Other Phenomena Surveillance Sample Bent Alignment Bracket on the 30 degree Holder Surveillance Sample Holder (Removed during CAP 038142 RFO-23)

A Xcel Energy' AREVA RE$

PON$IVLE BY fATUIE-Monticello Nuclear Generating Station 2009 RFO-24 Refuel Outage In-Vessel Visual Examination Indication History Associated Component Indication Engineering Evaluations Core Location 26 -11, minor deformation in the CAP 01176818 Control Rod Guide area of CRGT-3 (New Ind.)

Tubes Core Location 18 - 07 minor deformation in the CAP 01176818 area of CRGT-3 (New Ind)

Monticello Nuclear Generating Plant Cycle 24 Summary Report Inservice Inspection 2009 Refueling Outage APPENDIX C Page 1 of I System Pressure Test Examinations credited to Period 2 Test Number Test Title Class Date Results 0255-02-IIC-1 Standby Liquid Control System Leakage Test 2 4/18/2009 Satisfactory 0255-02-IIC-2 Standby Liquid Control Suction Piping System 2 4/26/2009 Satisfactory Leakage Test 0255-03-IIC-1 Core Spray System Leakage Test - Loop A 2 12/22/2008 Satisfactory 0255-03-IIC-2 Core Spray System Leakage Test - Loop B 2 11/19/2008 Satisfactory 0255-04-IIC-1 RHR System Leakage Test - Loop A 2 4/6/2009 Satisfactory 0255-04-IIC-2 RHR System Leakage Test - Loop B 2 4/15/2009 Satisfactory (supplemented by Work Order-344201) 5/3/2009 Satisfactory 0255-04-IIC-3 RHR Shutdown Cooling Suction Piping System 2 4/6/2009 Satisfactory Leakage Test 4/5/2009 0255-05-IIC-1 RHR Service Water System Leakage Test - Loop A 3 5/3/2009 Satisfactory 0255-05-IIC-2 RHR Service Water System Leakage Test - Loop B 3 3/22/2009 Satisfactory 0255-1 1-IIC-1 Emergency Service Water System Leakage Test 3 3/31/2009 Satisfactory Loop A 0255-1 1-IIC-2 Emergency Service Water System Leakage Test 3 4/13/2009 Satisfactory Loop B 0255-11-11C-3-1 EDG-ESW System Leakage Test Loop A Accessible Pressure Boundary Components 3 10/15/2008 Satisfactory 0255-1 -IIC-3-2 EDG ESW System Leakage Test - Loop A Buried 3 7/14/2008 Satisfactory Piping (subtask to test/procedure 1404-01) 3 71/08 aifco EDG-ESW System Leakage Test Loop B 0255-11-11C-4-1 Accessible Pressure Boundary Components 3 10/29/2008 Satisfactory EDG ESW System Leakage Test - Loop B Buried 0255-1 1-IIC-4-2 Piping (subtask to test 1404-02 and procedure 3 7/28/2008 Satisfactory 1404-01) 0255-12-IIC-1 Feedwater System Leakage Test - Loop A 2 3/22/2009 Satisfactory 0255-12-IIC-2 Feedwater System Leakage Test - Loop B 2 3/22/2009 Satisfactory 0255-16-IIC-1 Drywell Floor Drain Sump System Leakage Test 2 4/24/2009 Satisfactory 0255-16-IIC-2 Drywell Equipment Drain Sump System Leakage 2 4/28/2009 I Satisfactory Test Reactor Coolant Pressure Boundary Leakage Test (includes Class 1 system Recirc Seal Injection per 0255-20-IIC-2 test 0255-09-11B-1, and Class 2 systems Control 1 and 2 4/27/2009 Satisfactory Rod Drive Hydraulic, Recirc Seal, and Reactor Water Cleanup)

Monticello Nuclear Generating Plant Cycle 24 Summary Report Inservice Inspection 2009 Refueling Outage APPENDIX D Page 1 of 1 Snubber Functional Testing The following snubbers were tested during Cycle 24 and the 2009 RFO to meet Technical Specifications, ASME Section XI requirements and verification testing as a result of replacement. There are 147 safety related snubbers at Monticello. The snubbers are placed into two groups: One main group of 146 (Bergen Paterson) and a second group of 1 (Lisega-Snubber SS-707). Fifteen snubbers from the main group and the single snubber from the second group resulted in 16 snubbers being tested per plant procedure 0251 during the 2009 RFO.

All snubbers were tested under one work order, 366382. Below is listed each individual work order that controlled removal, replacement, and re-installation if required.

No. Snubber Work Snubber Test Snubber Location Size Order No. Serial No. Results I PS2-H2 30 326521 516 Passed 2 SS-312-1 30 326527 522 Passed 3 SS-6AR 20 326531 464 Passed 4 SS-306 30 326533 517 Passed 5 SS-191 20 326577 112 Passed 6 SS-36A 10 326584 509 Passed 7 SS-560 10 326592 486 Passed 8 SS-707(Lisega) 3 343935 701 Passed 9 RV-26A-H2 10 326590 505 Passed 10 RV-25A-NS1 20 326588 172 Passed 11 RV-26-NS1 B 20 326581 306 Passed 12 RV-27A-NS3A 20 326580 480 Passed 13 SS-367 130 326526 180 Passed 14 SS-365 130 326525 187 Passed 15 CRD-H247 3 326524 458 Passed 16 RV-24A-NS1 20 326579 150 Passed

Monticello Nuclear Generating Plant Cycle 24 Summary Report Inservice Inspection 2009 Refueling Outage APPENDIX E Engineering Evaluations per Subsection IWB-3144 and 3142.4 (1995 Edition with 1996 Addenda)

1. CAP 01177677 Indications discovered in shroud support legs

Condition Evaluation (01177677-02), 5 pages

" Final Documentation of SIA Evaluation (sans vendor proprietary information)

(01177677-02), 11 pages (16 pages to follow)

Monticello Nuclear Generating Plant Cycle 24 Summary Report Inservice Inspection 2009 Refueling Outage CAP Number: 01177677 Condition Evaluation Number: CE-01177677 Description of problem:

During the 2009 RFO IVVI window, several shroud support legs were noted to have indications. The initial scope of inspection was the shroud leg at 210 degrees. The inspection of the 210 degree leg was a result of a requirement of the ASME section Xl code which requires examination of unremoved indications for three successive periods. Upon inspection of the 210 degree leg, additional indications were identified which requires scope expansion in accordance with ASME Section XI. The 240 degree leg was selected for scope expansion and it too had indications. The ASME section Xl code therefore requires scope expansion to 100% of the population of that weld location.

Evaluation Details:

Inspection of 100% of the accessible weld legs were performed by inserting a camera through the jet pumps. The inspection locations were H10, H11 and H12.

H-9 H-8

- - H-10 H-lI H-12

Monticello Nuclear Generating Plant Cycle 24 Summary Report Inservice Inspection 2009 Refueling Outage These are the shroud support ring to leg weld, the lower leg to transition piece, and transition piece to vessel weld, respectively. No indications were noted on the HI I and H12 welds using the same technique as those identifying indications at H10. Below is a table of inspection results for the H10 weld:

Location Inspection Notes (Degrees) 10 0 degree side inaccessible, 20 degree side has indication 30 Both sides have indications 60 50 degree side has no indications, 70 degree side has indication 90 No indications on either side 120 Both sides have indications 150 Both sides have indications 170 160 degree side has indication, 180 degree side in accessible 190 180 degree side inaccessible, 200 degree side has indication 210 200 degree side has indication, 220 degree side has no indications 240 230 degree side has no indications, 250 degree side has indication 270 260 degree side has no indications, 280 degree side has indication 300 290 degree side has indication, there is a vertical indication in the center of the weld, 310 degree side as no indications 330 320 degree side has no indications, 340 degree side inaccessible 350 Both sides inaccessible

Monticello Nuclear Generating Plant Cycle 24 Summary Report Inservice Inspection 2009 Refueling Outage

v. 3V~ W W 120, 150, 1i. 2air W~. 11. 30W 33(r W*

1i i t 1 I 1 I It

/H2

\ H3

-H4 N HS 41t IIT 1riHIt iit 1

- H7

-H11 3 r i*W 129 1W "rW 21T 24W30 0*

Below is an picture of a "typical" indication identified in the 2009 RFO.

Monticello Nuclear Generating Plant Cycle 24 Summary Report Inservice Inspection 2009 Refueling Outage The 2009 inspection report has indication notifications for all locations.

As can been seen in the inspection documentation, the indications are all in the fillet weld applied after the double bevel weld is completed across the width of the weld. The fillet weld is used to reduce the stress riser created by the corner at the H10 weld. It is believed that the flaws are induced in the fillet weld due to the heavily restrained nature of the weld. The double bevel weld provides great structural rigidity to the H10 from a lateral perspective. Application of the fillet weld on such a thick weldment will result in high residual stresses. These high residual stresses are believed to be the cause of the cracking.

Because the weld face (across the double bevel weld) is free of indications, it is reasonable to conclude that the back surface (which is inaccessible without significant core disassembly including the removal of fuel, fuel support piece, control rods, and control rod guide tubes) is free of defects.

In 2000, all accessible regions of the shroud legs were inspected as a result of the discovery of the vertical flaw on the 2100 leg. Many of the same types of indications were noted during the 2000 inspections as were noted in 2009 but were dispositioned as surface conditions left from construction (i.e. weld overlap, grinding ridges, et cetera). From the review of the 2000 data (which is archived on Super VHS tapes) indicates no change in flaw geometry. This may be the result of the excellent protection the lower plenum via hydrogen water chemistry.

Monticello Nuclear Generating Plant Cycle 24 Summary Report Inservice Inspection 2009 Refueling Outage Even though these flaws are postulated to be either construction surface conditions or cracking due to high residual stresses which may have resolved themselves during the first operating cycle, it is not uncommon for these types of indications to be initiation points for Intergranular Stress Corrosion Cracking (IGSCC). Therefore, flaw growth needs to be considered in future evaluations.

Noting that the evaluation was performed in support of an ASME inspection, ASME Section Xl was reviewed to determine if any guidance was present associated with flaw evaluation for a category B-N-2 exam. By following the guidance of the ASME code, the following is presented in paragraph IWB-3142.4:

"A component containing relevant conditions is acceptable for continued service if an analytical evaluation demonstrates the component's acceptability. The evaluation analysis and evaluation acceptance criteria shall be specified by the owner. A component accepted for continued service based upon analytical evaluation shall be subsequently examined in accordance with IWB-2420 (b) and (c)."

With this all considered, the results of the examination were sent to Structural Integrity Associates. Following flaw evaluation guidance in BWRVIP-38 and using standard flaw evaluation methods, the current condition of the shroud support legs is considered acceptable for several cycles. The letter attached in Sharepoint is a summary document from the approved vendor calculation.

Because the calculation was requested to be performed under SIA's appendix B program, the results of the calculation are considered appropriate for clearing the mode restraint and closing the CE. The results of the calculation indicates that the flaws can reduce the cross sectional area of all legs by 70% and code allowable margins will still be maintained. The fillet portion of the welds where the cracking has been predominantly located, was not consider part of the structural portion of the weld. Therefore, from a structural margin perspective, the weld are fully intact with the exception of the leg at 210 degrees which was evaluation as not being able to carry any load (consistent with the assumptions made in the 2000 evaluation).

Actions:

1. Formally accept the final report from Structural Integrity Associates filling out appropriate information associated with flaw evaluation and "use as is" documentation.

2. Revise the ISI plan and/or schedule to indicate follow up inspection lAW IWB-2420 (b) and (c).

3. Set up an appropriate component inspection schedule to maintain the flaw growth assumptions of the SIA evaluation.

Preparer's Name: David Potter Date: 4/17/2009

This cover sheet constitutes an alternative cover sheet for a vendor prepared document that will be incorporated into Xcel's EC process at MNGP. Per FP-E-MOD-l I section 5.4.5.2 an alternative coversheet to can be used to document the reviews within Xcel. This coversheet is for ECI4116 titled:

"Evaluation of the Monticello Shr-oud Support Leg Indications: 2009 Inspection" Prepared By: By Vendor (SIA)

Reviewed By (owners -- A acceptance): t. -"

Approved By:

StructuralIntegrity Associates, Inc. File No.: 0900485.301 CALCULATION PACKAGE Project No.: 0900485 Quality Program: N Nuclear O Commercial PROJECT NAME:

Monticello Shroud Support Leg Flaw Evaluation CONTRACT NO.:

00001005, Rev. 00008 CLIENT: PLANT:

XCEL Energy Monticello Nuclear Generating Plant CALCULATION TITLE:

Evaluation of the Monticello Shroud Support Leg Indications: 2009 Inspection Document Affected Project Manager Preparer(s) &

Pages Revision Description Approval Checker(s)

Revision Signature & Date Signatures & Date 01 - 10 Initial Issue A-I - A-13) Preparer:

Computer Files X_---

Marcos L. Herrera 04/24/09Peihua Jing 04/24/0904/24/09 Checker:

Stan S. Tang 04/24/09 Contains Vendor Proprietary Information Page 1 of 10 F0306-O1RO

Table of Contents 1.0 O B JE C T IV E ...................................................................................................................

2.0 D E SIG N IN PU T S ...........................................................................................................

2.1 Shroud Support Leg Design .........................................................................

3:0 METHODOLOGY ................................................................................................... 4 3.1 Shroud Support Leg Safety Factor Evaluation ............................................. 4 3.2 Future Crack Growth Predictions ................................................................. 6

4.0 CONCLUSION

S ................................................................................................ 6 5.0 RE FE R EN C E S ............................................................................... ...................... 6 Appendix A ANALYSIS COMPUTER FILES ............................... A-1 List of Tables Table 1: Shroud Support Leg Geometry and Calculations for Upset and Faulted C onditions [4] ........................................................................................... .......... 8 Table 2: Safety Factors for Monticello Shroud Support Leg Evaluation (50% of all legs cracked) ................................................................................................. 9 Table 3: Safety Factors for Monticello Shroud Support Leg Evaluation (72.5% of all legs cracked) ................................................................................................. 9 List of Figures Figure 1. Indication Found in Shroud Support Leg H-10 @ 2400 .................................... 10 File No.: 0900485.301 Page 2 of 10 Revision: 0

1.0 OBJECTIVE During the Spring 2009 inspections of the reactor internals at Monticello, Xcel Energy visually discovered indications in L1iof the 14 shroud support legs. Indications were observed in one or both ends of the H10 welds at the top end of the support legs at the following azimuths: 200, 300, 600, 1200, 1500, 1700, 1900, 2100, 240', 270', and 3000. Visual photographs obtained from the examination performed by Xcel Energy are documented in Reference 1.

A crack-like indication at the 2400 support leg is shown in Figure 1 as an example. Per Figure 1, the indication runs across the Alloy 182 weld. It is noteworthy that the flaw runs in a fillet weld applied to reduce stress between the HIO weld and support cylinder.

The objective of this calculation is to evaluate the indications in the shroud support legs found during the Spring 2009 inspection. A similar analysis was performed in 2000 in support of inspections at the time. At that time, only one leg was found to have an indication. The approach used then assumed one complete leg was cracked and that the support legs took the entire load without taking credit for the load sharing with the H8 and H9 welds. The results are documented in Reference 8. For the current calculation, cases were evaluated that conservatively bound the actual inspection results. One case was evaluated that assumed 50% of each leg width (in circumferential direction) was flawed through-wall and one leg was cracked 100% (consistent with the Reference 8 evaluation). In the second case, 72.5% of the leg width was assumed cracked through-wall along with one leg cracked 100%. These are very conservative assumptions regarding the flaw length given the observed indications that appear to be limited to a fillet weld applied to reduce the stress concentration between the H1O weld and the bottom of the shroud support cylinder.

2.0 DESIGN INPUTS 2.1 Shroud Support Leg Design The shroud support design implemented at Monticello is the Chicago Bridge & Iron Nuclear (CBIN) flat plate design with support legs that connect to the reactor pressure vessel (RPV) bottom head. A stub is welded to an attachment pad on the inside of the RPV lower head, and the leg is welded to the top of the stub and to the bottom face of the shroud support cylinder (refer to Figure 2.9.2.4 of Reference [3]). There are fourteen support legs, each with a thickness of 1.75 inches [4], located 200 or 300 apart (see Table 1). The legs are fabricated from Alloy 600 material (S,, = 23.3 ksi) with multiple Alloy 182 welds joining the various legsections to each other, and joining the legs to the low alloy steel RPV and the Alloy 600 shroud support cylinder.

The weld of interest for this analysis, as designated in BWRVIP-15 [3], is the weld attaching the leg to the shroud support cylinder (weld H 10).

All of the relevant geometry, load, and material information for the Monticello support legs are summarized in Table I for upset and faulted conditions [4]. The loads shown in Table I also apply to power rerate conditions, as confirmed by the Reference 5 report. Also included in this File No.: 0900485.301 Page 3 of 10 Revision: 0

table are primary stresses calculated for use in the structural evaluation of the support legs. The methodology used to compute these stresses is described in detail below. It should be noted that these loads do not consider the Extend Power Uprate planned to occur during the next operating cycle.

3.0 METHODOLOGY 3.1 Shroud Support Leg Safety Factor Evaluation Access to the shroud support legs is severely limited because of their location in the RPV bottom head region beneath the shroud support structure. For this reason, the structural analyses performed as a basis for the "BWR Shroud Support Inspection and Flaw Evaluation Guidelines (BWRVIP-38)" [6] conservatively assumed the presence of 50% through-wall cracking in all shroud support legs. This philosophy eliminates the need for support leg inspection, given that shroud support welds H8 and H9 are structurally adequate.

However, Xcel Energy has performed a visual inspection of the legs via access through the jet pump assemblies. Provision for inspecting the support legs in lieu of a detailed inspection of welds H8 and H9 was also addressed in BWRVIP-38. Flaw tolerance evaluations are provided in Section A.2.7 of BWRVIP-38 that can be used to structurally evaluate the support legs. The methodology conservatively assumes that all of the applied loading is structurally taken by the legs. Therefore, welds H8 and H9 are not structurally required, other than to maintain the support structure configuration (i.e., jet pump support, shroud repair, etc.). As a result, analyses similar to those shown in Section A.2.7 of BWRVIP-38 were performed for Monticello to confirm the structural adequacy of the support legs, for upset and faulted conditions, conservatively including assumptions regarding the support leg flaws. Structural acceptability was demonstrated by maintaining minimum ASME Code, Section X1 safety factors, as per the recommended approach documented in Section A.2.7 of BWRVIP-38.

The shroud support legs are located sufficiently below the core such that they do not receive significant amounts of radiation. Therefore, linear elastic fracture mechanics (LEFM) techniques are not necessary, and limit load techniques are valid due to material ductility. Since the shroud support legs are essentially "a cylindrical shell with holes," a limit load solution applicable to cylinders may be used. Therefore, the ANSC computer program [7] was selected for use. The ANSC program was used because of its ability to analyze cracks in cylindrical structures without taking benefit of the cracks taking compression. This was important for this evaluation since the spaces between legs, which are effectively treated as flaws in this analysis, have no capability to take compression.

Consistent with limit load techniques, two stresses were computed for use in the analysis: (1) the primary membrane stress, P,,, and (2) the primary bending stress, Pb. Consistent with BWRVIP-38 methodology, calculation of these stresses was based on the stresses for the shroud H7 weld, as those stresses were readily available from past shroud evaluations. The determination of each of these stresses is detailed below:

Prm: Pm-legs = Pir-shroud (t/tiegs)

File No.: 0900485.301 Page 4 of 10 Revision: 0

where: Pmiegs = primary membrane stress in the legs (psi).

Pirn-shroud = primary membrane stress in the shroud at weld H7 (psi).

t = shroud thickness at weld H7 (inches).

tlegs = support legs minimum thickness (inches).

Pb: Pb-legs = (Pb-shroud + Ms/Z) (t/tlegs) where: Pb-legs = primary bending stress in the legs (psi).

Pb-shroud = primary bending stress in the shroud at weld H7 (psi).

Ms = additional moment for legs due to the shear load applied at weld H7 (inch-lbs).

= FsH F, = shear load at weld H7 (lbs).

H = "lever arm" between shroud weld H7 and limiting leg cross section (inches).

z = section modulus for unflawed shroud cross section (inches3).

= *2t R = shroud mean radius (inches).

t = shroud thickness at weld H7 (inches).

tlegs support legs minimum thickness (inches).

The calculated values for each of the above stresses are included in Table 1. It should be noted that the shear term in the calculation of Pb was conservatively taken to the bottom of the shroud support legs (weld HI 1) versus weld H1O. This is consistent with the BWRVIP-38 methodology.

Also included in Table I are the computed azimuths for each support leg. This information, combined with the appropriate stress information, was input to ANSC to determine whether the assumed leg configuration maintains minimum required ASME Code, Section X1 safety factors (2.77 for upset conditions, 1.39 for faulted conditions [6]). Evaluations were performed for both the upset and faulted conditions, and the resulting ANSC output is included in Appendix A. It is noted from the output that through-wall flaws were placed in the spaces between the legs and the leg with the indication to represent the fact that there is actually no material present in these regions.

From the ANSC results, the safety factor was calculated using the following relationship:

Safety Factor, SF = Pb +Pm Pb +Pm where: Pb' minimum failure bending stress from ANSC output (psi).

The resulting safety factors are shown in Table 2 and 3. In Table 2, it was evaluated that assumed 50% of each leg width (in circumferential direction) was flawed through-wall and one leg was cracked 100% (consistent with the Reference 8 evaluation). In Table 3, 72.5% of the leg width File No.: 0900485.301 Page 5 of 10 Revision: 0

was assumed cracked through-wall along with one leg cracked 100%. These are very conservative assumptions regarding the flaw length given the observed indications that appear to be limited to a fillet weld applied to reduce the stress concentration between the H 10 weld and the bottom of the shroud support cylinder.

3.2 Future Crack Growth Predictions An evaluation of current operating conditions at Monticello was performed relative to predicted growth of the identified indication, with the results documented in Appendix B of Reference 8.

The current water chemistry conditions in the Monticello lower plenum were considered, and it is concluded that growth of the identified indication should be bounded by a crack growth rate of 5x10- 6 inches/hour, or 0.086" for' ne twenty-four month operating cycle. Use the leg width of 7" from Table 1, and conservatively assume that crack grows from both ends of a leg, the number of years cracks can grow before they reach 72.5% of the total width is given as:

72.5% 7" / (5 10 -6inches/hour 2) = 57.9 years

4.0 CONCLUSION

S Based on the safety factors shown in Table 2, it is seen that there is margin assuming 50% of the leg width was cracked along with one leg cracked 100%. In fact, as shown in Table 3, the safety factor limited was reached when 72.5% of the leg width was assumed cracked through-wall along with one leg cracked 100%. These results are considered to be extremely conservative because no structural support from welds H8 and H9 was considered. Therefore, if some structural support from welds H8 and H9 is considered (as a result of inspection of these welds),

it is expected that significantly larger margins would be obtained.

Based on the results of this conservative evaluation, up to 72.5% of each support leg H1O weld may be flawed and still meet the required safety factors of BWRVIP-38. The current indications are relatively small and essentially not propagating. Even if crack growth is postulated (@

5xl 06 in/hr) per Reference 8, the required safety factors would be met for several operating cycles.

5.0 REFERENCES

1. E-mail from David J. Potter (Xcel Energy) to Marcos Herrera (SI), "Official transmittal of Indications," Received on 4/13/09, SI File No. 0900485.201.

2. Chicago Bridge and Iron Company Drawing No. 34, Revision 8, "Shroud Support For 17'-2" ID x 63-2" Ins. Heads Nuclear Reactor for General Electric Co. For Northern States Power Co., Monticello, Minnesota," Contract No. 9-5624, SIFile No. NSP-28Q-203.

File No.: 0900485.301 Page 6 of 10 Revision: 0

3. EPRI Report No. TR-106368, BWR Vessel and Internals Project, "Configurations of Safety-Related BWR Reactor Internals (BWRVIP-15)," EPRI PROPRIETARY, March 1996, SI File No. BWRVIP-01-215P.

4. Structural Integrity Associates Calculation No. EPRI-98Q-3 14, Revision 1, "Shroud Support Legs Structural Evaluation," 6/16/97.

5. GE Nuclear Energy Report No. GE-NE-B 13-01805-27, "Evaluation and Screening Criteria at Rerate Conditions for the Monticello Shroud," DRF B113-01805, Class II, March 1996, SI File No. NSP-33Q-204.

6. EPRI Report No. TR-108823, BWR Vessel and Internals Project, "BWR Shroud Support Inspection and Flaw Evaluation Guidelines (BWRVIP-3 8)," EPRI PROPRIETARY, SI File No. BWRVIP-01-238P.

7. ANSC, "Arbitrary Net Section Collapse for Thin Cylinder," Version 2.0, Structural Integrity Associates, SI File No. QA-1900.

8. Structural Integrity Associates Report SIR-00-008, "Evaluation of the Monticello Shroud Support Leg Indication," January 21, 2000, SI File No. NSP-40Q-401.

File No.: 0900485.301 Page 7 of 10 Revision: 0

V.I, d,propr itn farmYt 16 Poo -...,o P w U N* C revie r-fo

I QF-0547 (FP-E-MOD-1 1) Rev. 2 Page 1 of 2 XceI Energy External Design Document Suitability Review Checklist External Design Document Being Reviewed:EC1 4116

Title:

Evaluation of the Monticello Shroud Support Leg Indications: 2009 Inspection 4/24/200 Number: 0900485.301 Rev: 0 Date:9 This design document was received from:

Organization Name: Structural Integrity PO or DIA

Reference:

Contract Req 65115 Associates The purpose of the suitability review is to ensure that a calculation, analysis or other design document provided by an External Design Organization complies with the conditions of the purchase order and/or Design Interface Agreement (DIA) and is appropriate for its intended use. The suitability review does not serve as an independent verification. Independent verification of the design document supplied by the External Design Organization should be evident in the document, if required.

The reviewer should use the criteria below as a guide to assess the overall quality, completeness and usefulness of the design document. The reviewer is not required to check calculations in detail.

REVIEW Reviewed N/A

1. Design inputs correspond to those that were transmitted to the External Design [] El Organization.

2. Assumptions are described and reasonable. H]

[] 1:

El

3. Applicable codes, standards and regulations are identified and met.

H] El

4. Applicable construction and operating experience is considered.

5. Applicable structure(s), system(s), and component(s) are listed. Zl El

[] El

6. Formulae and equations are documented. Unusual symbols are defined.

N] El

7. Acceptance criteria are identified, adequate and satisfied.

[] El

8. Results are reasonable compared to inputs.

9. Source documents are referenced. 21 El

[] El

10. The document is appropriate for its intended use.

11. The document complies with the terms of the Purchase Order and/or DIA.- 19 El

[] El

12. Inputs, assumptions, outputs, etc. which could affect plant operation are enforced by adequate procedural controls. List any affected procedures.

11 NL

13. Plant impact has been identified and either implemented or controlled. (e.g., For piping analyses, the piping and support database is updated or a tracking item has been initiated.)

El [L

14. Design and Operational Margin have been considered and documented.

Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-0547 (FP-E-MOD-1 1) Rev. 2 Pacie 2 of 2 XcelEnergy External Design Document Suitability Review Checklist Completed by: David Potter Date: 4/28/2009 Form retained in accordance with record retention schedule identified in FP-G-RM-01.

L-MT-09-078, Submittal of Cycle No. 24 Inservice Inspection Summary Report for Inservice Inspection and ASME Section Xl Repairs and Replacements

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L-MT-09-078, Submittal of Cycle No. 24 Inservice Inspection Summary Report for Inservice Inspection and ASME Section Xl Repairs and Replacements

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