Text

Cycle No. 23 Lnservice Inspection Summary Report for Lnservice Inspection and ASME Section XI Repairs and Replacements
	ML072110097
Person / Time
Site:	Monticello
Issue date:	07/27/2007
From:	O'Connor T; Nuclear Management Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	FOIA/PA-2010-0209, L-MT-07-058
	Download: ML072110097 (224)
	v • d • e

July 27, 2007 L-MT-07-058 10 CFR 50.55a U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Monticello Nuclear Generating Plant Docket 50-263 License No. DPR-22 Cycle No. 23 lnservice Inspection Summary Report for lnservice Inspection and ASME Section XI Repairs and Replacements Pursuant to 10 CFR Part 50, Section 50.55a and IWA-6240 of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI, 1995 Edition, with the 1996 Addenda, the Nuclear Management Company, LLC (NMC) hereby submits the Cycle No. 23 lnservice lnspection Summary Report for lnservice Inspections (ISI) and ASME Section XI Repairs and Replacements completed from April 13, 2005 to April 28, 2007. Pursuant to 10 CFR Part 50, Section 50.55a(b)(2)(ix)(D), evaluations for ASME Section XI, Subsection IWE Class MC components that did not meet the acceptance standards of IWE-3410-1 are included. The evaluations are applicable to the examinations performed during the refueling outage for the first interval of the metal containment inspection program. This summary report also provides amended information to the previously submitted Cycle No. 22 IS1 Summary Report, including a supplemental NIS-1 Form and a supplemental NIS-2 Form. This tter ake n new commitments or changes to any existing commitments.

&d e President, Monticello Nuclear Generating Plant Management Company, LLC 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) 2807 West County Road 75 Monticello, Minnesota 55362-9637 Telephone:

763.295.51 51 Fax: 763.295.1454 ENCLOSURE I NUCLEAR MANAGEMENT COMPANY, LLC MONTICELLO NUCLEAR GENERATING PLANT DOCKET 50-263 INSERVICE INSPECTION

SUMMARY

REPORT CYCLE NO. 23 REFUELING OUTAGE Nuclear Management Company, LLC 700 1st Street Hudson, WI 54016 Xcel Energy, LLC 800 Nicollet Mall Minneapolis, MN 55402 INSERVICE INSPECTION

SUMMARY

REPORT Monticello Nuclear Generating Plant 2807 West County Road 75 Monticello, MN 55362 Commercial Service Date: June 30,1971 Cycle No. 23 Refueling Outage Outage Dates: March 14,2007 to April 28,2007 rvlce inspection Interval 4, Periods 1 and 2 rreparea /Ozz, Site NDE Level I11 Manager, Program Engineering ANII: Hartford Steam Boiler - CT% Report Date: July 26,2007 Nuclear Management Company Cycle 23 Summary Report Monticello Inservice Inspection 2007 Refueling Outage TABLE OF CONTENTS SECTIONS I. Summary 1 .O Introduction 2.0 Personnel 3.0 Examination Reports, Equipment, and Materials 4.0 Inspection Summary 5.0 Abbreviations

11. NIS-1 Form for Cycle 23 111. NIS-2 Summary for Cycle 23 NIS-2 Forms for Cycle 23 IV. New NIS-1 Form for Cycle 22 Supplemental Information V. NIS-2 Form for Cycle 22 Supplemental Information APPENDICES A. Class 1,2, 3, Augmented, and Non-Code Examinations (Sorted by Class, Category, and Item No.)

B. Reactor Vessel IVVI Examinations C. System Pressure Test Examinations D. Snubber Functional Testing PAGES 4 PAGES 19 E. Engineering Evaluations per Subsection IWE-3 122.4 (1 992 Edition with 1992 Addenda) and 1 OCFR50.55a(b)(2)(ix)(D)

1. CAP CE 01 082766-03 for degraded containment nuclear coatings 2 8 CAP CE 01082766-03 Attachment 1 CAP CE 01082766-03 Attachment 2 CAP CE 01082766-03 Attachment 3

2. CAP CE 01084149-01 for Arc Strikes on Torus Shell Plates 2

Nuclear Management Company Monticello Inservice Inspection I. Summary Cycle 23 Summary Report 2007 Refueling Outage Page 1 of 4 1.0 Introduction This report encompasses all Inservice Inspection (ISI) activities performed during Cycle 23 of operation at Monticello Nuclear Generating Plant (MNGP). Cycle 23 began April 13,2005, immediately following completion of the 22nd refueling outage. This report also includes activities performed during the 23rd refueling outage that began March 14,2007 and ended April 28,2007. All examinations and tests for Cycle 23 were scheduled and conducted in accordance with the 4th Interval IS1 Plan. The majority of the exams and tests were credited to the 2nd period of the 4th IS1 Interval. Nine Class 2 and Class 3 system pressure tests conducted during Cycle 23 were credited to the lSt Period. Also included in this report is supplemental information for the Cycle 22 IS1 Summary Report submitted in July 2005.

2.0 Personnel Visual and nondestructive examinations for inservice inspection (ISI) and preservice inspection (PSI) activities were performed by Nuclear Management Company (NMC), Lambert-MacGill-Thomas (LMT), International Quality Consultants (IQC), Inc., and AREVA-NP. Hartford Steam Boiler Inspection

& Insurance Co. of Connecticut (HSB-CT) provided the Authorized Inspection.

Personnel certification records are maintained by NMC. 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 NMC. 4.0 Inspection Summary In accordance with the 4th Interval IS1 Plan and IS1 Relief Request #1, Class 1 and 2 piping welds were examined using methodologies applicable to Risk- Informed IS1 (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.

Nuclear Management Company Monticello Insewice Inspection Cycle 23 Summary Report 2007 Refueling Outage I. Summary (continued)

Page 2 of 4 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 (B WRVIP) guideline B WRVIP-03. Examinations performed during Cycle 23 are listed in attached appendices. Code Case N-460, which allows a reduction of examination volume coverage 40% to be considered essentially loo%, 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 1,2, and 3 IS1 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. Other non-code and augmented exams are also provided in the attached appendices for site information tracking purposes only. Evaluations were also performed during the 2007 outage for the Containment Inspection Examination Plan, Interval 1, Period 3, Cycle 23 examinations that 1 exceeded acceptance standards of Table IWE-3410-1. (Code of Record is ASME Section XI, 1992 Edition with 1992 Addenda) These evaluations were performed per IWE-3122.4 and per lOCFR50.55a(b)(2)(ix)(D) as an alternative to IWE- 2430. As required by lOCFR50.55a(b)(2)(ix)(D)(l), the evaluations are included in the attached appendices of this report. Results of system pressure tests and snubber functional tests performed during Cycle 23 are summarized in attached appendices. The pressure testing appendix includes 1 st Period pressure tests that were not completed prior to beginning Cycle 23. These test were subsequently completed during Cycle 23 prior to the end of the 1 st Period . Repair-replacement activities for Cycle 23 were performed to the requirements of the 4th IS1 Interval Relief Request #7 which is based on ASME Section XI, 200 1 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.

Nuclear Management Company Monticello Inservice Inspection Cycle 23 Summary Report 2007 Refueling Outage I. Summary (continued)

Page 3 of 4 During Cycle 23, an audit of Cycle 22's maintenance activities identified the replacement of a valve sub-component that constituted a repairlreplacement activity.

However, no RepairIReplacement Plan had been prepared prior to, or during performance of the work.

This condition was identified subsequent to submittal of the Cycle 22 IS1 Summary Report, thus no NIS-2 form for this activity was submitted with the Cycle 22 IS1 Summary Report. As part of the corrective action process, a RepairIReplacement Plan was prepared and approved for the activity.

An NIS-2 form was also prepared and signed to document the Repair/Replacement activity. This Cycle 22 supplement NIS-2 form, along with a new Cycle 22 supplemental NIS-1 form, are included in this Summary Report. In conclusion, based on the results of the Cycle 23 IS1 activities, the integrity of the plant systems has been adequately maintained.

Nuclear Management Company Monticello Inservice Inspection Cycle 23 Summary Report 2007 Refueling Outage I. Summary (continued)

Page 4 of 4 5.0 List of Abbreviations The Summary Report Examination Appendices contains several abbreviations identified below (System acronyms, 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 D = Downstream DC I EC = Design I Engineering Change DS = Downstream EVT = Enhanced Visual Examination GEO = Geometry I Geometric Reflector H- = Hanger (plus number identifier)

IS0 = IS1 Isometric Drawing IVVI = In-Vessel Visual Inspection LS = Longitudinal Seam MT = Magnetic Particle Examination NC = Non-Code Commitment Exam NRI = No Reportable Indications OE = Operating Experience PM = Preventative Maintenance PMT = Post-Maintenance Testing PSI = Pre-Service Inspection PT = Liquid Penetrant Examination PEI = Program Engineering Instruction PP = Passport RFO = Refueling Outage RI = Reportable Indication RPV = Reactor Pressure Vessel RJR = Repair I Replacement U&D = Upstream & Downstream U = Upstream 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 Nuclear Management Company Monticello Inservice Inspection Cycle 23 Summary Report 2007 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. LLC / Nuclear Mana~ement 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):

NIA 5. Commercial Service Date:

613017 1 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: 0411 3/05 to 04/28/07 . 9. Inspection Interval:

05/01/03 to 0513 1/12 . 10. Applicable Edition of Section XI: 1995 Addenda: 1996 . 1 1. Abstract of Examinations.

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

See appendices A through D (Attached)

12. Abstract of Conditions Noted. See appendices A through E (Attached)

13. Abstract of Corrective Measures Recommended and Taken. See appendices A through E (Attached)

Nuclear Management Company Monticello Inservice Inspection

11. Form NIS-1 Information Cycle 23 Summary Report 2007 Refueling Outage 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 JULY 2b 20 67 Signed XCEL'ENERGY

/ NM~ By Owner Section XI IS1 ~oordiiator 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 ~rx/rvc'~on and employed by PL~IZ)'F~PO nt~ BOIL~-R BJ OP co)oYc'cncui of +1~lqfi1~&@ , c r have inspected the components described in this Owner's Report during the period ~/IJ /or to 7/26/07 , 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 AfII (186 3 A, UL AUUO Y'(ILR AO Inspector's Signature National Board, State, Province, Endorsements 11 Date Y~L Y z(: 2007 Nuclear Management Company Monticello Insewice Inspection Cycle 23 Summary Report 2007 Refueling Outage 111. Form NIS-2 Information Cycle 23 NIS-2 Summary Page 1 of 5 RIR ITEM NUMBER 2005-23-0001 2005-23-0002 2005-23-0004 2005-23-0005 2005-23-0006 2006-23-0008 WORK DOCUMENT(S)

WO-3 1 1347 WO-507209 (PP 141066)

WO-SO6359 (PP 1404 1

8) WO-156335 WO-507758 WO-136399 WO-141353 WO-141354 WO-141355 WO-141356 WO-141357 WO-141358 WO-141359 WO-141360 WO-141361 WO-141362 WO-141363 WO-141365 WO-141366

-- COMPONENT OR SYSTEM P-109 (Spare Pump) # 12 Reclrc Pump (P-200B) TCV-4030B P-109B, #12 RHRSW Pump SR-26 SS-14 SS-184 SS-3 16 SS-13 SS-38A SS-17A SS-38B SS-121 SS-11 SS-12 SS-37 SS-17B CRD-H227 WORK DESCRIPTION Rebuilt spare RHRSW pump bowl assembly Replacement of stuffing box cover Replaced existing valve Replaced existing pump bowl assembly w/ rebuilt spare Removed welded stanchion, realigned and repaired by weld~ng Removed existing snubbers and replaced with rebuilt spares Nuclear Management Company Monticello Inservice Inspection 111. Form NIS-2 Information Cycle 23 NIS-2 Summary Cycle 23 Summary Report 2007 Refueling Outage Page 2 of 5 RIR ITEM NUMBER (Cont'd) 2006-23-0008 2006-23-0010 2006-23-001 1 2006-23-0013 2006-23-0014 2006-23-001 5 2006-23-0016 2006-23-001 7 2006-23-001 8 WORK DOCUMENT(S)

WO-141369 WO-141371 WO-141372 WO-141374 WO-141375 WO-141377 WO-141378 WO-141379 WO-141382 WO-141383 WO-153676 WO-153175 WO-153676 WO-151841 WO-285967 WO-285967 WO-265697 WO-289152 WO-289151 WO-285768 WO-286583 COMPONENT OR SYSTEM SS-303 CRD-H232 SS-8AR SS-8BR SS-2AR SS-1BR SS3AR SS-1AR SS-20 SS-35 P-200B P-200B MO-2373 MO-2374 ESW-1-2 TW(H)-12 TWH-86 CRH WORK DESCRIPTION (Cont'd) Removed exlstlng snubbers and replaced wrth rebu~lt spares Replaced pump stuffing box (EC-806 and EC-103 17) Replaced 16 pump case-to-stuffing box nuts (EC-806) Replaced valve and assoc~ated pip~ng (EC-748) Replaced valve and assoc~ated piplng (EC-748) Removed / restored disc stem-to-nut tack weld to permlt Inspection Modlfied support by welding, Integral attachment weld removed (EC-775) Mod~fied support by lnstall~ng replacement sprlng can (EC-775) Replaced 6 scram discharge volume level sw~tches (EC-901)

Cycle 23 Summary Report 2007 Refueling Outage Nuclear Management Company Monticello Inservice Inspection 111. Form NIS-2 Information Cycle 23 NIS-2 Summary Page 3 of 5 R/R ITEM NUMBER 2006-23-0019 2006-23-0020 2006-23-0021 2006-23-0022 2006-23-0023 2006-23-0024 2006-23-0025 2006-23-0026 2006-23-0027 2006-23-0028 2006-23-0029

2006-23-0030 2006-23-003 1 2006-23-0032 2006-23-0033 2006-23-0034 2006-23-0035 2006-23-0036 WORK DOCUMENT(S)

WO-140381 WO-285273 WO-267425 WO-284077 WO-289151 WO-152929 WO-139591 WO-142128

WO-141349 WO-280592 WO-280592 WO-280592 WO-280592 WO-280592 WO-135620 WO-280592 WO-280592 WO-280592 WO-280592 WO-280592 COMPONENT OR SYSTEM MO-2008 EDG-ES W A and B SR-852 P-111B ESW-32 ESW-3 1 SS-707 Snubber, s/n 529 Snubber, sln 044 Snubber, s/n 460 Snubber, sln 126 Snubber, s/n 157 RV-11-39B

(# 12 SBLC Pump Dlsch RV) Snubber, sln 13 1 Snubber, s/n 487 Snubber, s/n 466 Snubber, s/n 132 Snubber, s/n 148 WORK DESCRIPTION Replace bonnet Replaced 2 check valves (SW-16 and SW-18) wlth manual gate valves (SW-228 and SW-229) and assoc~ated piplng (EC-768) Installed new pipe restra~nt (EC-775) Replaced P-1 1 lB (EDG-ESW Pump 12) Replaced valve and pup plece Replaced valve and pup plece Changed out snubber w~th new spare and also replaced 2 end pins Replaced main cyl~nder Replaced maln cylmder, plston, plston rmgs, plston rod, plston rod nut Replaced valve man~fold Replaced valve manlfold Replaced main cylinder, plston rlngs, plston Replaced nozzle and dlsc Replaced valve manlfold Replaced valve manlfold Replaced valve manifold Replaced valve manifold Replaced valve manlfold Nuclear Management Company Monticello Inservice Inspection Cycle 23 Summary Report 2007 Refueling Outage 111. Form NIS-2 Information Cycle 23 NIS-2 Summary Page 4 of 5 R/R ITEM NUMBER 2006-23-0037 2006-23-0038 2006-23-0039 2006-23-0040 2006-23-0041 2006-23-0042 2006-23-0043 2007-23-0044 2007-23-0045 2007-23-0046 2007-23-0047 2007-23-0048 2007-23-0049 2007-23-0050 2007-23-005 1 2007-23-0052

2007-23-0053

2007-23-0054 WORK DOCUMENT(S)

WO-280592 WO-280592 WO-280592 WO-280592 WO-280592 WO-280592 WO-152929 WO-154343 WO-3 14220 WO-288806 WO-267368

WO-3 14233 WO-322082 WO-141889 WO-288859

WO-289152

WO-289154 WO-289151 COMPONENT OR SYSTEM Snubber, s/n 132 Snubber, s/n 102 Snubber, s/n 154 Snubber, s/n 174 Snubber, sln 133 Snubber, sln 125 P-1 1 1B (Spare) RPV - WRFM Main Steam CS RX Head Vent, Flange #3 RCIC Steam RHRSW-B Snubber, SIN 400 MO- 1742 MO-1987 MO-2009 MO-1750 WORK DESCRIPTION Replaced maln cyl~nder Replaced main cyl~nder Replaced maln cylinder Replaced main cylinder Replaced valve man~fold Replaced valve man~fold Repaired small crack

~n 1st ~ntermed~ate bowl Removed 2 abandoned

~n-place wide range flux monltors and replaced wlth new blank flanges and bolting (EC-7462)

Installed 64 striun gauges (2 locations on each of the 4 steam lines In the drywell, 8 striun gages per location) (EC-9174) Removed and re~nstalled a section of pipe due to Interference w~th adjacent work Replaced 1 stud and 2 nuts Removed / Reinstalled a section of p~pe to allow repalr work on AO-2-86D Replaced approx~mately 4 ft section of SW10-18"-GF PiPC Replaced main cylinder Replaced 14 bonnet studs and 28 nuts Replaced 18 bonnet studs and 36 nuts Replaced d~sc Removed / restored dlsc to nut tack weld to permit disassembly and reassembly Nuclear Management Company Monticello Inservice Inspection 111. Form NIS-2 Information Cycle 23 Summary Report 2007 Refueling Outage Page 5 of 5 Cycle 23 NIS-2 Summary R/R ITEM NUMBER 2007-23-0056 2007-23-0057 2007-23-0058 2007-23-0059 2007-23-0060 2007-23-0061 2007-23-0062

2007-23-0063 2007-23-0064 2007-23-0065

2007-23-0066 2007-23-0067 2007-23-0068 2007-23-0069 2007-23-0070 2007-23-007 1 COMPONENT OR SYSTEM RV-2-7 1C RV-2-71C RV-2-71B CV-1729 Drywell Head SS-17A CV-1729 RV-2-71E RV-2-7 1 G RV-2-71A MO-2035 RHRS W RHRSW V15-H3 (PH-28) ESWl-4fl-HBD ESW5-4"-HBD WORK DOCUMENT(S)

WO-322070 WO-322070 WO-291884 WO-29 1592 WO-267369 WO-141358 WO-291592 WO-291883 WO-291885 WO-322083 WO-142056 WO-141016 WO-324116 WO-323428 WO-325774 WO-326373 WORK DESCRIPTION Replaced main body w~th rebu~lt spare Replaced topworks with rebuilt spare Replaced 5 bolts and 6 nuts for main body to topworks flange Replaced valve body.

Replaced 2 bolts and 3 nuts Replaced 4 flange mounting bolts Replaced plug Replace 12 studs and 24 nuts for main body to piping inlet flange Replace 12 bolts and 12 nuts for main body to topworks flange Replace 12 bolts and 12 nuts for main body to topworks flange Replaced 1 stud and 16 nuts, and the pressure retaining disc Replaced approximately 4 ft section of pip~ng and removed I re-installed, by weldmg, portlon of restra~nt SR-396 Replaced approximately 4 ft section of piping Replaced slightly bent hanger rod Replaced approximately 6" section of pipe and adjacent 90 degree elbow Replaced 90 degree elbow Nuclear Management Company Monticello Inservice Inspection 111. Form NIS-2 Information NIS-2 Forms (140 pages to follow) Cycle 23 Summary Report 2007 Refueling Outage ITEM 2005-23-0001 NOTE This form may not address all items needed for documentation of a repairlreplacement program, see I 4 AWI-09.04.03 (ASME SECTION XI REPAINREPLACEMENT 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 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. 361 3 - Revision 4 Page 1 of 2 MONTICELLO NUCLEAR GENERATING PLANT 1. Owner Xcel Energy Company Date 1/17/2006 Name 2. Plant Monticello Nuclear Generating Plant Sheet 1 of 2 Name 2807 W. Cnty. Rd. 75, Monticello, Minnesota 55362 WO 031 1347, PO P502929, Job #05JC1401 Address Repair Organization P.O. No., Job No. etc. 3. Work Performed By See Comments Type Code Symbol Stamp n/a Company Name Authorization No.

n/a Expiration Date n/a Address TITLE: 4. ldentification of System RHR Service Water, Spare Pump Bowl Ass'y s/n PG-2265, Class 3 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 5. (a) Applicable Construction Code ANSI 831.1 1977 Edition Year Addenda Winfer 1978 Code Case n/a (b) Applicable Edition of Section XI Utilized for Repairs or Replacement 2001 Edition, No Addenda 6. ldentification of Components Repaired or Replaced and Replacement Components

7. Description of Work Refurbished spare pump, 2 new bowls installed, 1 exisfing bowl weld repaired.

Name of Component Interstage Bowl. Exist. 2 lnterstage Bowls Interstage Bowl Interstage Bowl 8. Tests Conducted:

Hydrostatic Pneumatic

[7 Nominal Operating Pressure Other Pressure n/a psi Test Temp n/a OF Name of Manufacturer Johnston Pumx, Co Johnston Pum~ Co Johnston Pum~ Co Johnston Pum~ Co APPROVED (Signatures available in 1 Master File) Manufacturer Serial No. unknown unknown 275604-2 275604-3 National Board No. n/a n/a n/a n/a Other ldentification n/a n/a N66807-2 N66807-3 Year Built 1979 1979 2005 2005 Repaired, Replaced or Replacement Repaired Replaced Replacement Replacement ASME Code Stamped YES NO [XI [XI [XI

9. Remarks ITEM 2005-23-0001 I (Applicable Manufacturer's Data Reports to be Attached) 361 3 Revision 4 Page 2 of 2 MONTICELLO NUCLEAR GENERATING PLANT Design Change 75M041 is applicable to existing pumps. Work was performed by NMCHcel Energy (2807 W. Cty Rd 75, Monticello, MN 55362) and Johnston Pump Co., Nuclear Service Div. (2601 East 34th Street, Chattanooga, TN 37407). Visual exam performed, as applicable, on weld repaired area. (out-of-round male register ground down, restored with welding, and machined to tolerances). Post-reassembly pump performance festing was performed by Johnston Pump Co.

per procedure JC- TP-0069, Rev. 8. L TITLE: Rebuild pump returned to stock for future use. Pressure testing and pump testing will be performed following installation under separate Work Order and R/R Plan. OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this 3?wCStR pw RWLACE~ZNT conforms to the rules on the ASME Code,Section XI. repairlreplacement Signed ' \

S&cr(ou XI IS1 CWLO Date 18, ZO6 Owner or ~bner's designee, Title a 7 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 Hvu&c'SoT4 and employed by /j4nipars SrLtflhad/ieP3+l?C'~

COJJYCC~ICY~

of M~tf'Ond,ci-have inspected the components described in this Owner's Report during the period Dc-c 3, ZJaj to TAM 18, P 0136 , 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 lnspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report. Furthermore, neither the lnspector 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 ki9 //&&3 A, 2 hhr/ J+ 90 ax -4'G Inspector's Signature National Board, Province and Endorsements Date 3nurcnflt/

16 2.006 APPROVED (Signatures available in Master File) d ITEM 2005-23-0002 NOTE This form may not address all items needed for documentation of a repairlreplacement program, see I 4 Awl-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 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. 361 3 Revision 4 Page 1 of 2 MONTICELLO NUCLEAR GENERA TlNG PLANT 1. Owner Xcel Energy Company Date 7/12/2007 Name 2. Plant Monticello Nuclear Generating Plant Sheet I of 2 Name TITLE: 2807 W. Cnty. Rd.

75, Monticello, Minnesota 55362 WO 0506359, 0507209 (PP 14041 8, 141066) Address Repair Organization P.O. No., Job No. etc. OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 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. ldentification of System Reactor Recirc (REC), Loop 6, Pump #I2 (P-2006), Class I 5. (a) Applicable Construction Code ASME Section 111, Class C 9 1965 Edition Year Addenda No Addenda Code Case n/a (b) Applicable Edition of Section XI Utilized for Repairs or Replacement 2001 Edition, No Addenda 6. ldentification of Components Repaired or Replaced and Replacement Components

7. Description of Work Replace stuffing box cover on Recirc Pump 12 (P-2006) as part of seal ass'y 8. Tests Conducted:

Hydrostatic Pneumatic C] Nominal Operating Pressure Other [XI Pressure da psi Test Temp n/a " F Name of Component Stuffing Box Cover Stuffing Box Cover APPROVED (Signatures available in Master File) Name of Manufacturer Sulzer Pump Co. Bingham Willamette Manufacturer Serial No. 5122530 I I N35-3 National Board No.

n/a n/a Other ldentification Ht. K564 Ht. 83852 Year Built 2004 2007 Repaired, Replaced or Replacement replaced replacement ASME Code Stamped YES NO ITEM 2005-23-0002 I 9. Remarks (Applicable Manufacturer's Data Reports to be Attached)

Pressure testing satisfied per WO 0506359 PMT (PP 141066), successful completion of 4290 OCD. No PSI or /ST required.

361 3 Revision 4 Page 2 of 2 MONTICELLO NUCLEAR GENERATING PLANT CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this ??E~~R/RCQLACUV~W hv~ry conforms to the rules on the ASME Code,Section XI. repairlreplacement Signed -, SmXI IS eocao Owner or ownets Designee, Title ate I Zm7 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 IY 6 ~OTA and employed by /-(~ltTFoEo

\Tt>hUOgL62 2e-P JFcou~c-CTICUT of CIAIZTFJ~ZAI ,cT have inspected the components described in this Owner's Report during the period 2 /r$/o~ to 7 1 /3 107 , 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 lnspector 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--~/&-ec.

omm missions lrrg3 A, KJ ,/4 N "3 ~r o 2 8- ro Inspector's Signature National Board, Province and Endorsements Date ICY (3 , 20°7 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 APPROVED (Signatures available in Master File)

ITEM 2005-23-0004 NOTE This form may not address all items needed for documentation of a repairlreplacement program, see I 4 Awl-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 I I 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. 361 3 Revision 4 Page 1 of 2 MONTICELLO NUCLEAR GENERATING PLANT 1. Owner Xcel Energy Company Date 7/12/2007 Name 2. Plant Monticello Nuclear Generating Plant Sheet 1 of 2 Name TITLE: 2807 W. Cnty. Rd. 75, Monticello, Minnesota 55362 WO 156335 Address Repair Organization P.O. No., Job No, etc. OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 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 EFT Emergency Service Water (FS W), Class 3 5. (a) Applicable Construction Code USAS 831.1 1 1977 Edition Year Addenda Winter 1978 Addenda 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

7. Description of Work Planned 4 year replacement of valve. Name of Component TCV-403OB TCV-40308

8. Tests Conducted:

Hydrostatic Pneumatic Nominal Operating Pressure Other Pressure 79.248 psi Test Temp n/a OF Name of Manufacturer Penn Penn ) 3087 (DOCUMENT CHANGE, HOLD AND COMMENT FORM) incorporated:

I Manufacturer Serial No. 60-07 704 I 60-07 704-1-5 APPROVED (Signatures available in Master File) - - FOR ADMIE5.l~TRATIVE Res~ Supv: PRGE 1 Assoc Ref:

PRGE I SR: N I Freq: 0 vrs :'USE@MCY

.-IARM~: 3613 I Doc Tvue: REF ONLY I Admin initials:

I Date: National Board No.

n/a n/a I Other ldentification n/a n/a Year Built 2002 2002 Repaired, Replaced or Replacement Replaced Replacement ASME Code Stamped YES NO 0 ITEM 2005-23-0004 I 9. Remarks (Applicable Manufacturer's Data Reports to be Attached) Planned 4-year like-for-like replacement of valve TCV-40306. System Leakage Test with VT-2 per work order PMT. No PSI or IS7 required.

361 3 Revision 4 Page 2 of 2 MONTICELLO NUCLEAR GENERATING PLANT CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this \R / REPMWT ACT I v conforms to the rules on the ASME Code,Section XI.

' repairlreplacement c- Signed , SECT^ C0oR.D. Date Owner or Owner's

~esignee, Title 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 NIPMC~D~'~

and employed by

/j~dj FOKP ST~M CP S+J el-' CLJN~X~~ of I-IA~~~oP~ICT have inspected the components described in this Owner's Report during the period q/t /dr to 7/15 107 , 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 lnspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report. Furthermore, neither the lnspector 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.

Cornmissions PO ,183 ~j,wI, A& oa 9rL8-Cd Inspector's Signature National Board, Province and Endorsements Date JclLY /3 , 2~07 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 APPROVED (Signatures available in Master File)

ITEM 2005-23-0005 NOTE This form may not address all items needed for documentation of a repairlreplacement program, see I 4 Awl-09.04.03 (ASME SECTION XI REPAIWREPLACEMENT 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 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. 1. Owner Xcel Energy Company Date 1M 8/2006 Name 2. Plant Monticello Nuclear Generating Plant Sheet 1 of 2 Name 2807 W. Cnty. Rd. 75, Monticello, Minnesota 55362 WO 0507758 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. ldentification of System RHR Service Water (RHRSW), Pump #I2 (P-109B), Class 3 5. (a) Applicable Construction Code ANSI B31. I 1977 Edition Year 361 3 Revision 4 Page 1 of 2 MONTICELLO NUCLEAR GENERAT/NG PLANT Addenda Winter1978 Code Case n/a TITLE: (b) Applicable Edition of Section XI Utilized for Repairs or Replacement 2001 Edition, No Addenda 6. ldentification of Components Repaired or Replaced and Replacement Components OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 7. Description of Work Replaced pump bowl assembly with rebuilt spare Name of Component Bowl Ass'y Bowl Ass'y

8. Tests Conducted: Hydrostatic C] Pneumatic Nominal Operating Pressure jXI Other Pressure 236 psi Test Temp n/a OF Name of Manufacturer Pum~ Co Johnston Pum~ Co -- 1 3087 (DOCUMENT CHANGE, HOLD AND COMMENT FORM) incorporated:

1 Manufacturer Serial No. NRW-6523 PG-2265 APPROVED (Signatures available in Master File) -- FOR ADMlNlSTWTlVE Resp Supv: PRGE 1 Assoc Ref: PRGE 1 SR: N I Frea: 0 vrs USE ONLY ARMS: 3613 I Doc Tv~e: REF ONLY I Admin initials:

I Date: National Board No. n/a n/a 1 Other ldentification n/a n/a Year Built 2003 2005 Repaired, Replaced or Replacement Replaced Replacement ASME Code Stamped YES NO [XI [XI ITEM 2005-23-0005 I 9. Remarks (Applicable Manufacturer's Data Reports to be Attached)

Design Change 75M041 is applicable to existing pumps. System leakage test with VT-2 was performed per the work order PMT. /ST was performed per the WO PMT Attachment. This satisfies post-repair/replacement testing for the spare which was rebuilt under WO 031 1347 and PO P502929 (ref. R/R Plan 2005-23-0001).

361 3 Revision 4 Page 2 of 2 MONTICELLO NUCLEAR GENERATING PLANT CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this ~PLEICEMENT conforms to the rules on the ASME Code,Section XI. repairlreplacement Signed 1 S~TI~ IS at J~roar~ 18 , 2006 Owner or Owner's Designee, Title 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 f-lr&u~SQ YA and employed by hdn'; hkfl S?E~M BOIL^^? $0 sF C&YL/FCP)C%~

of I-I~ETPJRY ,cr have inspected the components described in this Owner's Report during the period J'D-f T- Z / L*J to TAU I%, bod6 , 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 lnspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report. Furthermore, neither the lnspector 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.

ClA ~/accl Commissions A/f )lp/ 3 AM, 1' fi M 03 1/ OL g- co Inspector's Signature National ~oaid, Province and Endorsements Date ~A~/LC 18' , 2@b OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 APPROVED (Signatures available in Master File)

ITEM 2005-23-0006 I NOTE This form may not address all items needed for documentation of a repairlreplacement program, see 4 AWI-09.04.03 (ASME SECTION XI REPAIRIREPLACEMENT PROGRAM) for further guidance.

361 3 Revision 4 Page 1 of 2 MONTICELLO NUCLEAR GENERATING PLANT 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 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. TITLE: 1. Owner Xcel Energy Company Date 7/12/2007 Name 2. Plant Monticello Nuclear Generating Plant Sheet I of 2 Name OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 2807 W. Cnty.

Rd. 75, Monticello, Minnesota 55362 WO 136399 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. ldentification of System Emergency Service Water (ESW), Class 3 5. (a) Applicable Construction Code USAS 831.1 1 1967 Edition Year Addenda NoAddenda Code Case n/a (b) Applicable Edition of Section XI Utilized for Repairs or Replacement 2001 Edition, No Addenda 6. ldentification of Components Repaired or Replaced and Replacement Components

7. Description of Work Removed welded stanchion, realigned, and repaired by welding. 8. Tests Conducted:

Hydrostatic 0 Pneumatic Nominal Operating Pressure Other Pressure n/a psi Test Temp n/a " F Name of Component SR-26 SR-26 Stanchion SR-26 Stanchion 1 3087 (DOCUMENT CHANGE, HOLD AND COMMENT FORM) incorporated:

I Name of Manufacturer n/a n/a Dubose National APPROVED (Signatures available in Master File) FOR AI?MINISTMTWE Resu Suuv: PRGE I Assoc Ref: PRGE I SR: N I Frw: 0 vrs USE ONLY % 1 Doc Tvue:

REF ONLY 1 Admin initials:

1 Date: Manufacturer Serial No. n/a n/a n/a I National Board No.

n/a n/a n/a Other ldentification n/a n/a Ht #203524 Year Built 1969 1969 2005 Repaired, Replaced or Replacement Repaired Replaced Replacement ASME Code Stamped YES NO IXI ITEM 2005-23-0006 I 9. Remarks (Applicable Manufacturer's Data Reports to be Attached) Repair of SR-26 included removal of existing stanchion pipe and replacement with new stanchion pipe, minor weld repairs to baseplate, and final welding after realignment of components. No pre- service VT-3 required for the applicable pipe size. 361 3 Revision 4 Page 2 of 2 MONTICELLO NUCLEAR GENERATING PLANT CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this REPAIR / REPLAC~ENT Am v ITY conforms to the rules on the ASME Code,Section XI. repairlreplacement Signed - I , SECTXI IS( ~RD Owner or Owner's Designee, Title Date ~ 12, 2a7 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 MIM&C-SOTA and employed by k/p R~FQILL? ST~A~ flu~lt'n I'rZ ~f CO~~/~-CTIC~~

of fth~yf~ril , CT have inspected the components described in this Owner's Report during the period IT / I /d~- to 7 //,7/07 , 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 lnspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report. Furthermore, neither the lnspector nor his employer SHALL be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.

9 A~LL~. Commissions A@ 1~63 A,,/qj hc~ oo Y~Z~-CO Inspector's Signature National Board, Province and Endorsements Date SQLY 13 , ZOO7 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 APPROVED (Signatures available in Master File)

ITEM 2006-23-0008 NOTE This form may not address all items needed for documentation of a repairlreplacement program, see I 4 Awl-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 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. 361 3 Revision 4 Page 1 of 2 MONTICELLO NUCLEAR GENERATING PLANT

1. Owner Xcel Energy Company Date 7/7/2007 Name 2. Plant Monticello Nuclear Generating Plant Sheet I of 2 Name 2807 W. Cnty. Rd. 75, Monticello, Minnesota 55362 (See attachment for applicable Work Orders) Address Repair Organization P.O. No., Job No. etc. TITLE: 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 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2

4. ldentification of System (See attachment for applicable systems)

5. (a) Applicable Construction Code USAS B31.1 9 1967 Edition Year Addenda NoAddenda Code Case n/a (b) Applicable Edition of Section XI Utilized for Repairs or Replacement 2001 Edition, No Addenda 6. ldentification of Components Repaired or Replaced and Replacement Components

7. Description of Work Remove existing snubbers for seal life program, replaced with rebuilt spares. Name of Component SEE 8. Tests Conducted:

Hydrostatic Pneumatic Nominal Operating Pressure Other [XI Pressure n/a psi Test Temp n/a " F Name of Manufacturer ATTACH- MENT APPROVED (Signatures available in Master File) Manufacturer Serial No. National Board No. - Other Identification - Year Built - Repaired, Replaced or Replacement - ASME Code Stamped YES NO El ITEM 2006-23-0008

9. Remarks I (Applicable Manufacturer's Data Reports to be Attached) Functional Testing per procedure 0251. Pre-service VT-3 Examination as required by procedure 4903. 361 3 Revision 4 Page 2 of 2 MONTICELLO NUCLEAR GENERA TlNG PLANT CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this ~EPLAG~N~ conforms to the rules on the ASME Code,Section XI. repairlreplacement Signed , SEC XI ISL Cwm. Owner or Owner's Designee, Title 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

~L~J~~so?~

and employed by t-lnflFsAa s r6h ~orccn 272 of cdPk/C~2lc~T of 1-14 a J c, 7 have inspected the components described in this Owner's Report during the period 8 /ZC/~L to 7/10 (u7 , 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 lnspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report. Furthermore, neither the lnspector 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.

fu A& Commissions

//J 3 A, ~3, AN 00 YO LR- cu Inspector's Signature National Board, ~robince and Endorsements Date JWLY (o , L@rJ 7 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 APPROVED (Signatures available in Master File)

Monticello Nuclear Generating Plant Cycle 23 1 2007 Refueling Outage Snubber Changeout RepairIReplacement (RIR) Sequence Log RIR ltem Number 2006-23-0008 NIS-2 Attachment Attachment Page 1 of 2 R/R Item Number Sequence System Snubber Location Snubber Size (KIPS) A B C D E F G H I J K L M 10 10 10 I0 10 10 10 10 10 I0 10 10 20 ASME Class SS-14 SS-184 SS-316 SS-13 SS-38A SS-17A SS-38B SS-121 SS-11 SS-12 SS-37 SS-17B CRD- H227 1 2 2 1 2 1 2 2 1 1 2 1 2 CFW PCT CSP-B CFW RCI-STM RHR-B RCI-STM PCT CNV CFW HPC-STM RHR-B CRD-A Snubber Replacement WO ------.--

141353 141354 141355 141356 141357 141358 141359 141360 141361 141362 141 363 141365 141366 SIN of Removed Snubber 500 040 035 171 01 3 530 033 037 047 095 028 054-1 099 Installation Year of Removed Snubber 3/29/1998 3/31/1998 3/31/1998 312911 998 312511 998 3/31/1998 4/1/1998 312711 998 312711 998 312911 998 312511 998 3/31/1998 1/24/2000 S/N of Replacement Snubber Replacement Snubber Rebuild WO 533 042 534 044 536 157 535 007 039 043 003 012 128 280592 280592 280592 280592 280592 280592 280592 02-02066 280592 280592 03-1 1522 280592 03-1 1522 NX-14086-32,34 NL-94712 NL-95946 NX-14086-17, 31, 32 NX-14086-75 NL-97036-5-1 NX-14086-77 NX-14084-122 NX-14086-27, 28, 29 NX-14086-28,30 NX-14086-74 NL-97036-6-1 NQ-93567-37 ISI-13142-53-A H-5 ISI-94966-A H-4 ISI-13142-26-6 H-I ISl-13142-52A H-4 ISI-13142-19B H-I ISI-97004-A H-4 ISI-13142-19B H-I ISI-94966-A H-2 ISI-13142-52A H-7 ISI-13142-53A H-7 ISI-13142-19A H-I ISI-97004-A H-3 ISI-93268-IA H-14 Monticello Nuclear Generating Plant Cycle 23 12007 Refueling Outage Snubber Changeout RepairlReplacement (RIR) Sequence Log RIR ltem Number 2006-23-0008 NIS-2 Attachment Attachment Page 2 of 2 R/R Item Number Snubber Size Snubber ASME N 0 P Q R S T U V W Class 2 ----- 2 1 1 1 I 1 1 1 2 Snubber Replacement (KIPS) WO 141 369 141371 141372 141374 141375 141 377 141378 141379 141 382 141383 SS-303 SIN of Removed Snubber ------ 001 RHR-A Installation Year of Removed 10 Snubber Snubber 20 20 20 30 30 30 30 10 10 CRD- H232 SS-8AR SS-8BR SS-2AR SS-1BR SS-3AR SS-1AR SS-20 SS-35 SIN of Replacement 1/23/2000 CRD-A REC-A REC-B REC-A REC-B REC-A REC-A RHR-A HPC-WTR 214 307 152 005 470 145 468 539 540 Replacement Snubber 532 02066 280592 280592 280592 280592 280592 280592 280592 03-1 1522 1/24/2000 313011998 3/30/1 998 41211 998 41411 998 41211 998 41411 998 411 311 998 4/1/1998 Applicable 280592 - - NQ-9356742 NL-97033-20-1 NL-97035-20-1 NL-97033-13-1 NL-97035-12-1 NL-97033-14-1 NL-97033-12-1 NL-97034-12-1 NX-14086-72,-1 019A 132 126 154 146 050 1 02 529 202 IS1 Iso Dwg, ISI-93268-IA H-12 ISI-97005-A H-8 ISI-97006-A H-8 ISI-97005-C H-8 ISI-97006-C H-7 ISI-97005-C H-9 1st-97005-C H-7 ISI-97003-B H-2 ISI-1314240A H-5 NL-95936 ISI-13142-37E H-2 ITEM 2006-23-0010 I NOTE This form may not address all items needed for documentation of a repairlreplacement program, see 4 Awl-09.04.03 (ASME SECTION XI REPAIRIREPLACEMENT PROGRAM) for further guidance.

361 3 Revision 4 Page 1 of 2 MONTICELLO NUCLEAR GENERATING PLANT 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 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.

TITLE: 1. Owner Xcel Energy Company Date 7/13/2007 Name OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 2. Plant Monticello Nuclear Generating Plant Sheet I of 2 Name 2807 W. Cnty. Rd. 75, Monticello, Minnesota 55362 WO 153676 and 1531 75, EC-806 and 1031 7 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. ldentification of System Reactor Recirculation (REC), Loop B, Pump P-200B, Class 1 5. (a) Applicable Construction Code ANSI B31.1 1977 Edition Year Addenda Winter 1978 Addenda Code Case n/a (b) Applicable Edition of Section XI Utilized for Repairs or Replacement 2001 Edition, No Addenda

6. ldentification of Components Repaired or Replaced and Replacement Components

7. Description of Work Replaced Stuffing Box for pump PM and rotating assembly replacement

8. Tests Conducted:

Hydrostatic Pneumatic Nominal Operating Pressure Other [7 Pressure 1000 psi TestTemp 181.8 OF Name of Component Stuffing Box Stuffing Box - 1 3087 (DOCUMENT CHANGE, HOLD AND COMMENT FORM) incorporated:

I Name of Manufacturer Bingham Willamette Sulzer PU~DS APPROVED (Signatures available in Master File) *$OR ADPINISTRATJVE Resp Supv: PRGE I Assoc Ref: PRGE 1 SR: N 1 Frecl: 0 vrs " USE ONLY &$a ARMS: 3613 I Doc Tv~e: REF ONLY I Admin initials:

I Date: Manufacturer Serial No. Pmp 260969 Stfa Bx. n/a Pmp 260969 Stfa Bx. n/a I National Board No. ,,/a n/a Other ldentification n/a n/a Year Built 1969 2007 Repaired, Replaced or Replacement Replaced Replacement ASME Code Stamped - YES NO OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS - FORM NIS-2 Page 2 of 2 ITEM 2006-23-0010

9. Remarks I (Applicable Manufacturer's Data Reports to be Attached) Like-for-like replacement of the stuffing box in association with pump PM, including replacement of the rotating assembly. System Leakage Test with VT-2 during 025520-IlC-2.

Pressure and temperature listed are the minimum requirements for the Reactor Coolant Boundary System Leakage Test. No PSI or /ST required.

CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this REP~IR /&pLhCEMENT ArnVl~ conforms to the rules on the ASME Code,Section XI. repairlreplacement Signed I- SECT)(( IS1 boao Date PO I3 , m7 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 Atr/e's;nir and employed by CIAY~TP~KU 5'lr'~h OBIW ttt &F CCWIJCCTIC&

T of ~(AR rFoE&, Cr have inspected the components described in this Owner's Report during the period dkb6 to 7 I?.) j~7 , 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 lnspector 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.

2L.rr A d-~cr.~- Commissions X/17 11 k63 AJy F hk (35 L/c/zf - c u Inspector's Signature National Board, Province and Endorsements Date 'i'trCy LJ , Zcn>7 APPROVED (Signatures available in Master File)

ITEM 2006-23-001 1 NOTE This form may not address all items needed for documentation of a repairlreplacement program, see I 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 1 I 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. 361 3 Revision 4 Page 1 of 2 MONTICELLO NUCLEAR GENERATING PLANT 1. Owner Xcel Energy Company Date 7/13/2007 Name 2. Plant Monticello Nuclear Generating Plant Sheet I of 2 Name TITLE: 2807 W. Cnty. Rd. 75, Monticello, Minnesota 55362 WO 153676 and EC-806 Address Repair Organization P.O. No., Job No. etc. OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 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. ldentification of System Reactor Recirculation (REC), Loop B, Pump P-200B, Class I 5. (a) Applicable Construction Code ANSI B31. I 1 1977 Edition Year Addenda Winter 1978 Addenda Code Case n/a (b) Applicable Edition of Section XI Utilized for Repairs or Replacement 2001 Edition, No Addenda 6. ldentification of Components Repaired or Replaced and Replacement Components

7. Description of Work Replaced A194 Gr 2H with A194 Gr 7 in support of EC 806 (installed 2007)

Name of Component (1 6) Stuffing Rox Nuts (16) Stuffing Box Nuts 8. Tests Conducted:

Hydrostatic Pneumatic Nominal Operating Pressure Other Pressure n/a psi Test Temp n/a "F Name of Manufacturer Bingham Willamette Nova Machine APPROVED (Signatures available in Master File) Manufacturer Serial No.

n/a n/a National Board No. n/a n/a Other ldentification n/a Ht#7420672 Q1405 Year Built 1969 2006 Repaired, Replaced or Replacement Replaced Replacement ASME Code Stamped YES NO IXI ITEM 2006-23-001 1 I 9. Remarks (Applicable Manufacturer's Data Reports to be Attached)

PSI VT-I performed on replacement nuts. Reference IS1 Report 2007VT045.

No pressure testing or /ST required.

361 3 Revision 4 Page 2 of 2 MONTICELLO NUCLEAR GENERATING PLANT CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this %ML\.\R 1-r /Am J try conforms to the rules on the ASME Code,Section XI.

kepairlreplacement Signed \& . SEQX) Is1 b0Kb Owner o? owner% Designee, Title 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

~~wuE.s+~ and employed by jld)zrk~ru fii?htl BJ~LCX if2dF @&M>~ICLIJ of )~.~-QF~Pu, CT have inspected the components described in this Owner's Report during the period 3 /.job to 7 11 7 1~7 , 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 lnspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report. Furthermore, neither the lnspector 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.

Vl-4.i 4 A-VLL* Commissions

~8 [If63 P,~Z ~IM d~~l~~r-cu Inspector's Signature National Board, Province and Endorsements Date ULY 2.3 2007 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 APPROVED (Signatures available in Master File)

NOTE This form may not address all items needed for documentation of a repairlreplacement program, 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 (I) 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. 361 3 Revision 4 Page 1 of 23 MONTICELLO NUCLEAR GENERATING PLANT 1. Owner Xcel Energy Company Date 7/16/2007 Name TITLE: 2. Plant Monticello Nuclear Generating Plant Sheet I of 3 Name 2807 W. Cnty. Rd. 75, Monticello, Minnesota 55362 EC-748 and WO 151 841 Address Repair Organization P.O. No., Job No. etc. OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 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. ldentification of System Main Steam (MST), Class 1

5. (a) Applicable Construction Code ANSI 831.1 9 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. ldentification of Components Repaired or Replaced and Replacement Components

7. Description of Work Replaced MO-2373 and associated piping to improve Appx J performance.

8. Tests Conducted:

Hydrostatic Pneumatic Nominal Operating Pressure Other Pressure 1000 psi TestTemp 181.8 OF Name of Component MO-2373 MO-2373 PS 15-35ED oioe PS 15-3"-ED oioe SEE APPROVED (Signatures available in Master File) Name of Manufacturer BW/lP Flo wsenfe unknown Dubose PAGE Manufacturer Serial No. El 63A-1-1 BC-390 n/a n/a 2 National Board No. n/a n/a n/a n/a FOR Other ldentification n/a n/a n/a Ht # L40039 ADD'L Year Built 1998 2007 1998 2007 ITEMS Repaired, Replaced or Replacement replaced replacement replaced replacement ASME Code Stamped YES NO IXI IXI IXI Monticello Nuclear Generating Plant Form NIS-2 Continuation Sheet ITEM 2006-23-0013 Name of Component PSl5-3"-ED Elbow PS153'LED Elbow Name of Manufacturer Unknown Chicago Tube & Iron Manufacturer Serial No.

n/a n/a National Board No. n/a n/a Other Identification n/a Ht.# 5850A Year Built 1998 2007 Repaired, Replaced or Replacement replaced replacement ASME Code Stamped Yes No X X A MONTICELLO NUCLEAR GENERATING PLANT 1 3613 I I I OWNER'S REPORT FOR REPAIRS OR 1 Revision 4 L, REPLACEMENTS - FORM NIS-2 Paae;_L&33&3 ITEM 2006-23-0013

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

The existing double-disk gate valve, including the associated piping and elbow, was replaced with a globe valve to improve Appendix J performance per EC-748. PT and RT performed as applicable.

System leakage test with VT-2 during performance of 0255-20-llC-2.

/ST performed during work order pre-operational testing task (stroke time closed, position indication) and Appendix J Testing per 0137-07A.

CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this XEPR,R /RCPLA=W~-

Awu IV conforms to the rules on the ASME Code,Section XI.

repairlreplacement Signed , sea to^ XI IS\ Coem Date L~ \ 6 2007 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 IL1 I~UC'~ O?A and employed by FIAPTF*~Z@

~Tlcflh/jbllb'p

~f-~d~cObCE'C~fC41 of t(AfDt3gJ have inspected the components described in this Owner's Report during the period 9 /G /dd to 7 /L .~/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 XI.

By signing this certificate neither the lnspector 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.

K-T ALLLA<$ Commissions R/j /rgg 1 A, v,jl, ~LI OC)L/~Z~-CCJ Inspector's Signature National ~oard, Province and Endorsements Date 3QLY ZL , CJD7 APPROVED (Signatures available in Master File)

ITEM 2006-23-0014 NOTE 1: This form may not address all items needed for documentation of a repairlreplacement program, see I 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 (I) 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. 361 3 Revision 4 Page 1 of 2 MONTICELLO NUCLEAR GENERA TlNG PLANT 1. Owner Xcel Energy Company Date 7/16/2007 Name 2. Plant Monticello Nuclear Generating Plant Sheet I of 2 Name 2807 W. Cnty. Rd. 75, Monticello, Minnesota 55362 EC 748, WO's 15184 1 and 285967 Address Repair Organization P.O. No., Job No. etc. TITLE: 3. Work Performed By NMCMcel 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 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 4. ldentification of System Main Steam (MST), Class I 5. (a) Applicable Construction Code ANSI B31.1 3 1977 Edition Year Addenda Winter1978 Code Case n/a (b) Applicable Edition of Section XI Utilized for Repairs or Replacement 2001 Edition, No Addenda

6. ldentification of Components Repaired or Replaced and Replacement Components

7. Description of Work Replaced MO-2374 and associated piping to improve Appx J performance.

8. Tests Conducted:

Hydrostatic Pneumatic Nominal Operating Pressure Other C] Pressure 1000 psi Test Temp 181.8 OF Name of Component MO-2374 MO-2374 PSl5-3"ED oioe PS 153"-ED be APPROVED (Signatures available in Master File)

Name of Manufacturer B W/lP Flo wsen~e US Steel Dubose Manufacturer Serial No. El 63A-2-1 BC-39 I n/a n/a National Board No. n/a n/a n/a n/a Other Identification n/a n/a n/a Ht # L40039 Year Built 1998 2007 2003 2007 Repaired, Replaced or Replacement replaced replacement replaced replacement ASME Code Stamped YES NO IX] IX]

ITEM 2006-23-0014 I 9. Remarks (Applicable Manufacturer's Data Reports to be Attached)

The existing double-disk gate valve, including the associated piping, was replaced with a globe valve to improve Appendix J performance per EC-748. PT and RT performed as applicable.

System leakage test with VT-2 during performance of 0255-20-116-2.

/ST performed during work order pre- operational testing task (stroke time closed, position indication) and Appendix J Testing per 0137- 07A. 361 3 Revision 4 Page 2 of 2 MONTICELLO NUCLEAR GENERATING PLANT CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this ~ZCP(HL/W~A~I\~OW krlviry conforms to the rules on the ASME Code,Section XI. repairlreplacement Signed . Srcnor X( 1st COOED Date Owner or dwnerl$ Designee, Title .-+?&+I- 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 MWIC/FS 074 and employed by ClnnC~oRld rTt-ni21 ~~ILCR Sf-1 ~FCok/&Ec~lcarof

+IAP?FO~ZU,C~

have inspected the components described in this Owner's Report during the period

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

&i!A0&4t.

Commissions UB I/ 2-L 3 A , -C' lYl~ 03 Y ~284 " Inspector's Signature National Board, Province and Endorsements Date J~LY 2 L , Lo07 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 APPROVED (Signatures available in Master File)

ITEM 2006-23-0015 I NOTE This form may not address all items needed for documentation of a repairlreplacement program, see 4 Awl-09.04.03 (ASME SECTION XI REPAIRIREPLACEMENT PROGRAM) for further guidance.

361 3 Revision 4 Page 1 of 2 MONTICELLO NUCLEAR GENERATING PLANT 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 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. TITLE: 1. Owner Xcel Energy Company Date 7/16/2007 Name OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 2. Plant Monticello Nuclear Generating Plant Sheet I of 2 Name 2807 W. Cnty. Rd. 75, Monticello, Minnesota 55362 WO 265697 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. ldentification of System EDG Emergency Senlice Water (EDG-ESW), Valve ESW-1-2, Class 3 5. (a) Applicable Construction Code ANSI 831.1 1977 Edition Year Addenda Winter1978Addenda Code Case n/a (b) Applicable Edition of Section XI Utilized for Repairs or Replacement 2001 Edition, No Addenda 6. ldentification of Components Repaired or Replaced and Replacement Components

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

8. Tests Conducted:

Hydrostatic Pneumatic Nominal Operating Pressure Other Pressure n/a psi Test Temp n/a " F Name of Component ESW-1-2 1 3087 (DOCUMENT CHANGE, HOLD AND COMMENT FORM) incorporated:

I FOR ADMINISTRATIVE/

Resp Supv: PRGE I Assoc Ref: PRGE I SR: N I Freq: 0 yrs I I , 2 USE~FJL~'

.4:. I Doc Tvw: REF ONLY I Admin initials:

I Date: Name of Manufacturer OIC Cop APPROVED (Signatures available in Master File)

Manufacturer Serial No.

Valve s/n 10568 National Board No. n/a Other ldentification n/a Year Built 1969 Repaired, Replaced or Replacement Repaired ASME Code Stamped YES NO ITEM 2006-23-0015 I 9. Remarks (Applicable Manufacturer's Data Reports to be Attached)

DC 94A051 applies. No PSI or pressure testing required for valve internal components.

/ST close exercise per procedure 0187-02, open exercise per 0187-02B. (reference CAP'S 01099755 and 01 102080) CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this REPAIR /wCCM~~T fifftvlry conforms to the rules on the ASME Code,Section XI.

repairlreplacement - Signed -- , SECT XI [Sf COO(D Owner or Owner's Designee, Title 361 3 Revision 4 Page 2 of 2 MONTICELLO NUCLEAR GENERATING PLANT 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 ~~IM~/F.FOT~ and employed by CC~WF~KU 170~ ~OIL~-L 171 OF C~Q~~CT~ICU~

of h~~zi-rtno, c T have inspected the components described in this Owner's Report during the period Y/ I (JC to 7/c~ la7 , 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 lnspector 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.

KA A&.! Commissions A/L) 1 ,td rc/, 2 //L~YOO Y v~g-cc' Inspector's Signature National Board, Province and Endorsements Date TQLY 20 , Lou7 TITLE: APPROVED (Signatures available in Master File) OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 ITEM 2006-23-0016 NOTE This form may not address all items needed for documentation of a repairlreplacement program, see I 4 Awl-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 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. 361 3 Revision 4 Page 1 of 2 MONTICELLO NUCLEAR GENERATING PLANT

1. Owner Xcel Energy Company Date 7/18/2007 Name 2. Plant Monticello Nuclear Generating Plant Sheet 1 of 2 Name 2807 W. Cnty. Rd. 75, Monticello, Minnesota 55362 WO 289152, EC-775 Address Repair Organization P.O. No., Job No. etc. TITLE: 3. Work Performed By NMC /Xcel Energy Type Code Symbol Stamp n/a OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 Company Name Authorization No. n/a 2807 W. Cty Rd 75, Monticello, MN 55362 Expiration Date n/a Address 4. ldentification of System Residual Heat Removal (RHR), B Loop, Class 2 5. (a) Applicable Construction Code ANSI 831. I 1977 Edition Year Addenda Winter 1978 Addenda Code Case n/a (b) Applicable Edition of Section XI Utilized for Repairs or Replacement 2001 Edition, No Addenda 6. ldentification of Components Repaired or Replaced and Replacement Components

7. Description of Work Removed integral attachment and modified for Engineering Change (EC-775) Name of Component TW-12 8. Tests Conducted:

Hydrostatic Pneumatic Nominal Operating Pressure Other Pressure n/a .psi Test Temp n/a " F ) 3087 (DOCUMENT CHANGE, HOLD AND COMMENT FORM) incorporated:

I Name of Manufacturer n/a APPROVED (Signatures available in Master File)

Manufacturer Serial No. n/a Other ldentification TWH-12 1 Assoc Ref: PRGE I SR N I Freq: 0 vrs I Doc Tv~e: REF ONLY I Admin initials:

I Date. National Board No.

n/a Year Built 1987 Repaired, Replaced or Replacement Repaired I ASME Code Stamped YES NO ITEM 2006-23-001 6 I 9. Remarks (Applicable Manufacturer's Data Reports to be Attached)

This repair/replacement activity also included use of A WS Dl. 1, 1989 Edition.

EC-775 replaces several Rotork valve actuators with Limitorque actuators. Pipe support TW-12 required removal of the integrally welded stanchion and modification to meet piping analysis models. NDE was performed at the formerly welded pipe attachment area. VT-3 PSI was also performed. No pressure testing was required.

361 3 Revision 4 Page 2 of 2 MONTICELLO NUCLEAR GENERATING PLANT CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this R~AW(IR /UPW~P~T Ac..l~~-ry conforms to the rules on the ASME Code,Section XI. repairlreplacement Signed -SECT XI Is\ (born Owner o<~wner's Designee, Title 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 IYMS OTA and employed by ?-d~firl?rrt(l

~lt-nh odl~b~ $tS 0 F r;~wt~ncki of ~[~rzr~ofia have inspected he components described in this Owner's Report during the period 9 11 /d L I to 7/22 (77 , 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 lnspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report. Furthermore, neither the lnspector 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,u tr b-6 3 4, w. s\ &wddL/u~ k-rd Inspector's Signature National Board, Province and Endorsements Date by bL , 2-30> OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 APPROVED (Signatures available in Master File)

ITEM 2006-23-001 7 NOTE This form may not address all items needed for documentation of a repairlreplacement program, see I 4 Awl-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 ll 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. 361 3 Revision 4 Page 1 of 2 MONTICELLO NUCLEAR GENERATING PLANT 1. Owner Xcel Energy Company Date 7/18/2007 Name 2. Plant Monticello Nuclear Generating Plant Sheet I of 2 Name 2807 W. Cnty. Rd.

75, Monticello, Minnesota 55362 WO 289151, EC-775 Address Repair Organization P.O. No., Job No. etc. TITLE: 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 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 Address 4. ldentification of System Core Spray (CSP), Loop B, Class 2 5. (a) Applicable Construction Code ANSI B31. I 1 1977 Edition Year Addenda Winter 1978 Addenda Code Case n/a (b) Applicable Edition of Section XI Utilized for Repairs or Replacement 2001 Edition, No Addenda 6. ldentification of Components Repaired or Replaced and Replacement Components

7. Description of Work Replaced the spring can on support WH-86 as required by EC-775 Name of Component TWH-86 S~rina Can 7WH-86 S~rina Can 8. Tests Conducted:

Hydrostatic Pneumatic 0 Nominal Operating Pressure C] Other Pressure n/a psi Test Temp n/a " F Name of Manufacturer Bergen Patterson Bergen Patterson APPROVED (Signatures available in Master File)

Other ldentification Type Size 7 Type Size 71 3087 (DOCUMENT CHANGE, HOLD AND COMMENT FORM) incorporated:

x 4'0 ::p# /S)$l!P;,+;$

' 12$A /P / Res~ Suw: PRGE I Assoc Ref:

PRGE I SR: N I Freq: 0 vrs &4gh& h/#l ARMS: 3613 I Doc Tvpe: REF ONLY 1 Admin initials:

I Date: Manufacturer Serial No. n/a n/a I Year Built 1987 2007 National Board No. n/a n/a Repaired, Replaced or Replacement Replaced Replacement ASME Code Stamped YES NO IXI n ITEM 2006-23-001 7 1 9. Remarks (Applicable Manufacturer's Data Reports to be Attached)

This repair-replacement activity also included use of A WS Dl. I, 1989 Edition. EC-775 replaced several Rotork valve actuators with Limitorque actuators. Pipe support TWH-86 required a different spring can size to meet the revised piping analysis models. This included welding to structural components.

VT-3 PSI performed.

No pressure testing required. CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this REP(\(R /~cLr)ce~n~~

Ac*v\*y conforms to the rules on the ASME Code,Section XI. repairlreplacement Signed . SECTXI IS( COD^ Date Owner or owner'd Designee, Title 361 3 Revision 4 Page 2 of 2 MONTICELLO NUCLEAR GENERATING PLANT 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 ~'rrw~,~o TA and employed by t~arel/m sr~nm ~ot~t'rz hf JP CG&~/ECTIC~~T of u.\emrnu , c 7 have inspected the components described in this Owner's Report during the peiiod 711 Iw b to 7hl /u7 , 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 lnspector 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.

?KL, AL~ Commissions ug 11((, 3 4 , lv; s A/OP ~~UZ~-CO Inspector's Signature National Board, Province and Endorsements Date n-4I.r 2L , 7 TITLE: APPROVED (Signatures available in Master File) OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 ITEM 2006-23-001 8 I NOTE This form may not address all items needed for documentation of a repairlreplacement program, see 4 AWI-09.04.03 (ASME SECTION XI REPAIRIREPLACEMENT PROGRAM) for further guidance.

361 3 Revision 4 Page 1 of23 ,za, MONTICELLO NUCLEAR GENERATING PLANT 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 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. TITLE: 1. Owner Xcel Energy Company Date 7/21/2007 Name 2. Plant Monticello Nuclear Generating Plant Sheet 1 of 3 Name 2807 W. Cnty. Rd. 75, Monticello, Minnesota 55362 WO 285768 (Div I), 286583 (Div I/), EC-901 Address Repair Organization P.O. No., Job No. etc. OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 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. ldentification of System Control Rod Drive Hydraulics (CRDH), Scram Discharge Volume, Class 2 5. (a) Applicable Construction Code ANSI 631. I 1 1977 Edition Year Addenda No Addenda Code Case n/a (b) Applicable Edition of Section XI Utilized for Repairs or Replacement 2001 Edition, No Addenda 6. ldentification of Components Repaired or Replaced and Replacement Components

7. Description of Work Replaced obsolete CRD SDV level switches with new, equivalent switches

8. Tests Conducted:

Hydrostatic Pneumatic Nominal Operating Pressure Other Pressure 1000 psi Test Temp 181.8 OF APPROVED (Signatures available in Master File)

Monticello Nuclear Generating Plant Form NIS-2 Continuation Sheet ITEM 2006-23-001 8 WO Nos. 285768 Name of Component LS- 7429A (Div I) LS- 7429A (Div I) LS- 7430A (Div I) L S- 7430A (Div I) LS-7428C (~j,, 11) LS-7428C (~j,, 11) LS-7428D (~i,, 11) LS-7428D (D~V 11) LS-74298 (~i,, 11) LS-74298 (~i,, 11) LS-7430B (~i,, 11) L S- 7430B (Div 11) Name of Manufacturer Components Components Components Components Components Components Components Components Components Components Fluid Components Components National Board No. n/a n/a n/a n/a n/a n/a n/a n/a n/a n/a n/a Year Built 1981 2007 1981 2007 1981 2007 1981 2007 1981 2007 Manufacturer Serial No. 333 7- 1 7806-S 708 7808-S 872- 1 7804-S 873- 1 78058 707 7810-S ----- 709 7809-S Other Identification n/a n/a n/a n/a n/a n/a n/a n/a n/a n/a n/a n/a Repaired, Replaced or Replacement replaced replacement replaced replacement replaced replacement replaced replacement replaced replacement X ASME Stamped Yes n/a Code No X X X X X X X X X X -- X 2007 replacement 1 MONTICELLO NUCLEAR GENERATING PLANT 1 3613 I ITEM 2006-23-001 8 I 9. Remarks (Applicable Manufacturer's Data Reports to be Attached)

TITLE: Replaced obsolete level switches (FCI Model FR-72) with new, equivalent level switches (FCI Model FL T93) per Engineering Change (EC) 901. New mechanical joint (bolted) pressure tested per IWA-4540(c), 1998 Edition per IS1 Relief Request #7. System leakage test with VT-2 performed during 0255-20-llC-2.

OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS - FORM NIS-2 CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this REPA~R /REPLAY*E~T ACTI VlTy conforms to the rules on the ASME Code,Section XI. repairireplacement Signed , S E~~ON XI [S I b~ate 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 ~I,QU.G-&~IA and employed by k~1ZthrbU STt'jtb'~

gui~t% Jf3 d~ cvn/#it= Pcur of have inspected the components described in this Owner's Repo to 7lt3ku7 , 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 lnspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report. Furthermore, neither the lnspector 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.

yw 64 4.dk- Commissions b17 /1r63 4, % 3 rc?~ 00 qu L& 4u Inspector's Signature National Board, Province and Endorsements Date T~LY 23 , -3 APPROVED (Signatures available in Master File)

ITEM 2006-23-0019 NOTE This form may not address all items needed for documentation of a repairlreplacement program, see I 4 Awl-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 1 through 6 on this report is included on each sheet, and 1(3) each sheet is numbered and the number of sheets is recorded at the top of this form. 361 3 Revision 4 Page 1 of 2 MONTICELLO NUCLEAR GENERATING PLANT

1. Owner Xcel Energy Company Date 7/19/2007 Name 2. Plant Monticello Nuclear Generating Plant Sheet 1 of 2 Name TITLE: 2807 W. Cnty. Rd. 75, Monticello, Minnesota 55362 WO 140381 Address Repair Organization P.O. No., Job No. etc. OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2

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. ldentification of System RHR Torus Cooling

/ Test Return, Loop A, Class 2 5. (a) Applicable Construction Code ANSI 631. I 7 1977 Edition Year Addenda Winter 1978 Addenda Code Case n/a (b) Applicable Edition of Section XI Utilized for Repairs or Replacement 2001 Edition, No Addenda 6. ldentification of Components Repaired or Replaced and Replacement Components

7. Description of Work Replaced MO-2008 bonnet like for like (replacement built 2006, installed 2007) Name of Component M"-20q8 Bonne Mo-2008 . Bonnet 8. Tests Conducted: Hydrostatic Pneumatic Nominal Operating Pressure Other Pressure 110 psi Test Temp n/a " F Name of Manufacturer Flowserve Flowserve ) 3087 (DOCUMENT CHANGE, HOLD AND COMMENT FORM) incorporated:

1 Manufacturer Serial No. Valve s/n A Y260 Valve dn A Y260 APPROVED (Signatures available in Master File)

-- -- F,OR ADMINIST,WTJVE Resp Supv: PRGE I Assoc Ref: PRGE I SR: N I Frea: 0 vrs uSEDNLY " I Doc Tv~e: REF ONLY I Admin initials:

I Date: National Board No.

n/a n/a I Other ldentification Ht. # M3 156 Ht. # 227H096 Year Built 2005 2007 Repaired, Replaced or Replacement Replaced Replacement ASME Code Stamped YES 0 NO IXJ IXJ 0 ITEM 2006-23-0019 1 9. Remarks (Applicable Manufacturer's Data Reports to be Attached)

Design Change 04Q015 applies. MO-2008 bonnet replaced as a precautionary measure due to possible stresses induced by overthrusting during valve testing.

No NDE or PSI required.

361 3 Revision 4 Page 2 of 2 MONTICELLO NUCLEAR GENERATING PLANT System leakage test with VT-2 performed per work order PMT. /ST stroke time testing (ST0 and STC) and position indication testing (PIT) performed per work order PMT. TITLE: CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this %cpa~r /RE~L~CEMOIT ACTIVIV conforms to the rules on the ASME Code,Section XI.

repairlreplacement

Signed & I S*C~(ONX/

IS\ &OW Owner or Owner's Designee, Title OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 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 hl~~~~07.t and employed by I-(A@F~RII

~~~';C^/)~UV/LL~P 2$& 3F Cok~~c>\cwof j-(attP-4P,LT have inspected the components described in this Owner's Report during the period 4 /k to 7 (W 107 , 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 lnspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report. Furthermore, neither the lnspector 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.

f/-- Ah. Commissions - wh/(3~ /(td 3 p, .L , czp oo y g~g,co Inspector's Signature National Board, Province and Endorsements Date J(4~c.f W , 2~07 APPROVED (Signatures available in Master File)

ITEM 2006-23-0020 NOTE This form may not address all items needed for documentation of a repairlreplacement program, see I 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 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. 361 3 Revision 4 MONTICELLO NUCLEAR GENERATING PLANT 1. Owner Xcel Energy Company Date 7/23/2007 Name 2. Plant Monticello Nuclear Generating Plant Sheet I of 3 Name 2807 W. Cnty. Rd. 75, Monticello, Minnesota 55362 EC-768, WOs 267425, 284077, 285273 Address Repair Organization P.O.

No., Job No. etc. REPLACEMENTS - FORM NIS-2 Page 1 ofa3,!* TITLE: 3. Work Performed By NMCMcel 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 OWNER'S REPORT FOR REPAIRS OR 4. ldentification of System Emergency Senlice Water (EDG-ESW), Loops A and B, Class 3

5. (a) Applicable Construction Code ANSI B31. I 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. ldentification of Components Repaired or Replaced and Replacement Components

7. Description of Work Replaced check valves with manual gate valves

& associated pipe for EC-768 8. Tests Conducted:

Hydrostatic Pneumatic Nominal Operating Pressure Other Pressure Remark psi Test Temp n/a " F Name of Component SW-16 (Loor, A) w-22q Loor, A S W2 1-4"- HF (Loor, A) SEE APPROVED (Signatures available in Master File) Name of Manufacturer OIC Corp Flowserve Tioga PAGE Manufacturer Serial No.

n/a BC-455 n/a 2 National Board No. n/a n/a n/a FOR Other ldentification n/a n/a 52TA46652 S/N 1 LOOPB Year Built 1969 2007 2007 ITEMS Repaired, Replaced or Replacement replaced replacement replacement ASME Code Stamped YES NO IXI Monticello Nuclear Generating Plant Form NIS-2 Continuation Sheet ITEM 2006-23-0020 WO Nos. 267425 284077 Name of Component SW-18 (Loop B) S W-229 (Loop B) SW21-4'LHF (LOOP B) Name of Manufacturer OIC Corp Flo wserve Tioga Manufacturer Serial No. n/a BC-456 n/a National Board No. n/a n/a n/a Other Identification n/a n/a 52TA4665, S/N f Year Built 1969 2007 2007 Repaired, Replaced or Replacement replaced replacement replacement ASME Code Stamped Yes No X X X ITEM 2006-23-0020 1 9. Remarks (Applicable Manufacturer's Data Reports to be Attached)

Engineering Change (EC) 768 replaced Class 3 check valves with manual gate valves and a new section of upstream piping. The EC also replaced non-class items, not applicable to the Section XI boundary.

NDE performed as applicable. System leakage test with VT-2 performed per work order PMT attachments.

Loop A pressure:

47 psig, Loop B pressure:

48 psig. No /ST or PSI required.

361 3 Revision 4 MONTICELLO NUCLEAR GENERATING PLANT CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this KEPAIL/REPUK*WNT ACTW ty conforms to the rules on the ASME Code,Section XI. repairlreplacement Signed 7-A , SZCT~ON Y / 1st &RD Date , 2m.7 Owner dr Owner's Designee, Title 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 WUL'J a 1 and employed by k&rT neu 376 fih 8 U~LLH i t~ JF CflWt6CiZof , LT have inspected the components described in this Owner's Report during the period lC/ 3a /a& to 71 2.J ;Id7 , 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 lnspector 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/@ iff63 AJ U, J? hrC/ mYQZf-Q7 Inspector's Signature National Board, Province and Endorsements Date JOLT 23 , Zud 7 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 APPROVED (Signatures available in Master File)

NOTE This form may not address all items needed for documentation of a repairlreplacement program, see 4 Awl-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 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. 361 3 Revision 4 Page 1 of 2 MONTICELLO NUCLEAR GENERATING PLANT

1. Owner Xcel Energy Company Date 7/18/2007 Name 2. Plant Monticello Nuclear Generating Plant Sheet I of 2 Name TITLE: 2807 W. Cnty. Rd. 75, Monticello, Minnesota 55362 WO 289151, EC-775 Address Repair Organization P.O. No., Job No. etc. OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 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. ldentification of System Core Spray (CSP), Loop B, Class 2 5. (a) Applicable Construction Code ANSI 831. I 1 1977 Edition Year Addenda Winter1978Addenda Code Case n/a (b) Applicable Edition of Section XI Utilized for Repairs or Replacement 2001 Edition, No Addenda 6. ldentification of Components Repaired or Replaced and Replacement Components

7. Description of Work lnstallation of a new pipe restraint required by Engineering Change (EC) 775 . 8. Tests Conducted:

Hydrostatic Pneumatic Nominal Operating Pressure Other Pressure n/a psi Test Temp n/a OF Name of Component SR-852 APPROVED (Signatures available in Master File) Name of Manufacturer NMC National Board No. n/a Manufacturer Serial No.

n/a Other ldentification n/a Year Built 2007 Repaired, Replaced or Replacement Replacement (new) ASME Code Stamped YES NO [XI ITEM 2006-23-002 I 9. Remarks I (Applicable Manufacturer's Data Reports to be Attached)

This repair/replacement activity also included use of A WS Dl. 1, 1989 Edition. EC-775 replaced several Rotork valve actuators with Limitorque actuators. Pipe support SR-852 is a new support installed to meet the revised piping analysis models. VT-3 PSI performed, No pressure testing required.

CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this 'R~pfllp I RcPU\cf.WT Acwy conforms to the rules on the ASME Code,Section XI. rbpairlreplacement Signed C C , SEWON X( IS\ (00- Owner or 0wnei's Designee, Title 361 3 Revision 4 Page 2 of 2 MONTICELLO NUCLEAR GENERATING PLANT 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 hlt%~&~ot&

and employed by bltTf~li?~~T~%h

dl~t%! IaOF C(rWErTTLCqX of HAIS~FUIZ~,CT have inspected the components described in this Owner's Report during the period 4/r ld'L; to 7 1~2 , 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 lnspector nor his employer SHALL be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.

EL- P ALL& Commissions A/B /IS 3 A )v; t ~,+,voo~i V~&--CCI Inspector's Signature National Board, Province and Endorsements Date 'S'GLY 2-2 , ZdoJ TITLE: APPROVED (Signatures available in Master File)

OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 ITEM 2006-23-0022 NOTE This form may not address all items needed for documentation of a repairlreplacement program, see I 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 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. 361 3 Revision 4 Page 1 of 2 MONTICELLO NUCLEAR GENERATING PLANT 1. Owner Xcel Energy Company Name 2. Plant Monticello Nuclear Generating Plant Name 2807 W. Cnty. Rd. 75, Monticello, Minnesota 55362 Address TITLE: 3. Work Performed By NMC /Xcel Energy Company Name 2807 W. Cty Rd 75, Monticello, MN 55362 Address OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 Date 7/19/2007 Sheet WO 152929 Repair Organization P.O. No., Job No. etc. Type Code Symbol Stamp n/a Authorization No.

n/a Expiration Date n/a 4. Identificationofsystem EDGEmerg.

Service Water(EDG-ESW), Pump#l2(P-IIIB), Class3 5. (a) Applicable Construction Code ANSI B31.

I 9 1977 Edition Year Addenda Winter 1978 Addenda Code Case n/a (b) Applicable Edition of Section XI Utilized for Repairs or Replacement 2001 Edition, No Addenda 6. ldentification of Components Repaired or Replaced and Replacement Components

7. Description of Work Replaced EDG-ESW Pump #I2 (P-11 IB) with rebuilt spare. Name of Component P-1116 P-1116 8. Tests Conducted:

Hydrostatic Pneumatic Nominal Operating Pressure Other 0 Pressure 47 psi Test Temp n/a OF Name of Manufacturer Johnston Johnston APPROVED (Signatures available in Master File) Manufacturer Serial No. QD-6702 QD-6703 National Board No. n/a n/a Other ldentification n/a n/a Year Built 2004 2006 Repaired, Replaced or Replacement Replaced Replacement ASME Code Stamped YES 0 NO (XI (XI ITEM 2006-23-0022 I 9. Remarks (Applicable Manufacturer's Data Reports to be Attached) Pumps meet requirements of Design Change 920300. System leakage test with VT-2 of discharge flange joint per work order PMT attachment. IST pump performance testing per work order PMT. This satisfies post-repair/replacement testing for the spare which was rebuilt under WO 0403298. CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this 'RE;PA~P/PEPLA-N'~

A.crlvlT/

conforms to the rules on the ASME Code,Section XI. repairlreplacement Signed I-, SC~~WX~ 131 c~t?.B. Date $,&J 19 , 2007 Owner or Owner's Designee, Title 361 3 Revision 4 Page 2 of 2 MONTICELLO NUCLEAR GENERA TING PLANT 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 Hw~6.s oT4 and employed by CIAPT~~ d rr) J 70-A NO ILCM Cf 0 F rdk~6-ct lc cfl of b(fiflTfiK OJ c-i" have inspected the components described in this Owner's Report during the period

? I Ld6 to 7 ( L3 /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 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.

Y-A (C1AIb- Commissions ,ud 11 86 3 4,wJ h/r/ B dw W+C, Insp,ectorls Signature National Board, Province and Endorsements Date ~LY' 23 , Coo7 TITLE: APPROVED (Signatures available in Master File)

OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 ITEM 2006-23-0023 NOTE This form may not address all items needed for documentation of a repairlreplacement program, see 4 Awl-09.04.03 (ASME SECTION XI REPAIRIREPLACEMENT PROGRAM) for further guidance.

361 3 Revision 4 Page 1 of 2 MONTICELLO NUCLEAR GENERA TlNG PLANT 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 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. TITLE: 1. Owner Xcel Energy Company Date 7/18/2007 Name 2. Plant Monticello Nuclear Generating Plant Sheet I of 2 Name 2807 W. Cnty. Rd. 75, Monticello, Minnesota 55362 WO 139591 Address Repair Organization P.O. No., Job No. etc. OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 3. Work Performed By NMC /Xcel Energy Type Code Symbol Stamp n/a Company Name Authorization No.

n/a 2807 W. Cfy Rd 75, Monticello, MN 55362 Expiration Date n/a Address 4. ldentification of System EFT Emergency Service Wafer (FSW), Div. I, Class 3 5. (a) Applicable Construction Code ANSI B31.1 1 1977 Edition Year Addenda Winter 1978 Addenda Code Case n/a (b) Applicable Edition of Section XI Utilized for Repairs or Replacement 2001 Edition, No Addenda 6. ldentification of Components Repaired or Replaced and Replacement Components

7. Description of Work Replaced due to corrosion on valve internals (built 2006 /installed 2007) Name of Component ES W-32 ES W-32 ES W1-3"- HBD ESW1-3"- HBD 8. Tests Conducted:

Hydrostatic Pneumatic Nominal Operating Pressure Other Pressure 74.3 psi Test Temp n/a " F Name of Manufacturer Anchor Oarlina Flo wserve unknown Dubose 1 3087 (DOCUMENT CHANGE, HOLD AND COMMENT FORM) incorporated:

I Manufacturer Serial No. El241-1-2 AZ-899 n/a n/a APPROVED (Signatures available in Master File) Fog ADMIN1$TRATivE Resp Supv: PRGE 1 Assoc Ref:

PRGE I SR: N I Freq: 0 yrs %WE ONLY " '"G I Doc Tv~e: REF ONLY I Admin initials:

I Date: National Board No. n/a n/a n/a n/a 1 Other ldentification n/a n/a n/a HtpT L2 56 Year Built 1983 2007 1983 2007 Repaired, Replaced or Replacement Replaced Replacement Replaced Replacement AS ME Code Stamped YES C] C] 0 NO (XI (XI IXI -

ITEM 2006-23-0023 I 9. Remarks (Applicable Manufacturer's Data Reports to be Attached) 361 3 Revision 4 Page 2 of 2 MONTICELLO NUCLEAR GENERATING PLANT NDE performed as applicable. System leakage test with VT-2 performed per work order PMT attachment No PSI or /ST required.

TITLE: CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this R&PC)~R/REP-ACTI Ulry conforms to the rules on the ASME Code,Section XI. Fepairlreplacement c Signed + 3 SECT)(/ 13 c00bZD Owner or Owner's Designee, Title ate 5 , 2007 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 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 /vucrs07;9 and employed by kf~a~p~ tn 5l-t-9t-c fiorct~ L+~JJ= CO~,/WFCT~~Y~

of j-f-14/2t F O~ZQ, c T have inspe ted the components described in this Owner's Report during the period CF/C /dl; to 1 fZt107 , 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 lnspector 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.

YLCLXP~. Commissions

/JO II~G 3 A, IL/,,~ &t~a wr J-cu Inspector's Signature National Board, Province and Endorsements Date J-L~LY LL , 2.337 - APPROVED (Signatures available in Master File)

ITEM 2006-23-0024 I NOTE This form may not address all items needed for documentation of a repairlreplacement program, see 4 AWI-09.04.03 (ASME SECTION XI REPAIRIREPLACEMENT PROGRAM) for further guidance.

361 3 Revision 4 Page 1 of 2 MONTlCELLO NUCLEAR GENERATlNG PLANT 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 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. TITLE: 1. Owner Xcel Energy Company Date 7/18/2007 Name 2. Plant Monticello Nuclear Generating Plant Sheet 1 of 2 Name OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 2807 W. Cnty. Rd. 75, Monticello, Minnesota 55362 WO 142128 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. ldentification of System EFT Emergency Senlice Water (FSW), Div. 11, Class 3 5. (a) Applicable Construction Code ANSI B31. I 1 1977 Edition Year Addenda Winter 1978 Addenda Code Case n/a (b) Applicable

~dition of Section XI Utilized for Repairs or Replacement 2001 Edition, No Addenda 6. ldentification of Components Repaired or Replaced and Replacement Components

7. Description of Work Replaced due to corrosion on valve internals (built 2006 /installed 2007) 8. Tests Conducted:

Hydrostatic Pneumatic Nominal Operating Pressure Other Pressure 75.8 psi Test Temp n/a "F Name of Component ES W-31 ESW-31 ES W5-3"- HBD ES W5-3"- HBD 1 3087 (DOCUMENT CHANGE, HOLD AND COMMENT FORM) incorporated:

I Name of Manufacturer Anchor Darlina Flowserve unknown Dubose APPROVED (Signatures available in Master File) L Resp Su~v: PRGE 1 Assoc Ref:

PRGE I SR: N 1 Freq: 0 vrs ARMS: 3613 1 Doc Tvw: REF ONLY I Admin initials:

I Date: Manufacturer Serial No. E1241-1-1 AZ-532 n/a n/a I National Board No. n/a n/a n/a n/a Other ldentification n/a n/a n/a Ht Tde L22 69 Year Built 1983 2007 1983 2007 Repaired, Replaced or Replacement Replaced Replacement Replaced Replacement ASME Code Stamped YES NO IXI IX) IXI 0 ITEM 2006-23-0024 I 9. Remarks (Applicable Manufacturer's Data Reports to be Attached)

NDE performed as applicable. System leakage test with VT-2 performed per work order PMT attachment No PSI or IST required.

3613 Revision 4 Page 2 of 2 MONTICELLO NUCLEAR GENERATING PLANT CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this REP~~~~/~VMC*~HENT PCTIV)~~ conforms to the rules on the ASME Code,Section XI. r6pairlreplacement C Signed Date orL1 1s .ea7 Owner or Owner's Designee, Title 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 k-rn/d~~ OW and employed by /.lrlnt-~*ae s7Mh BOIL~SL Sf$ OF CoUI/677jQn of I-I~~rFuflu ,cT have inspected the components described in this Owner's Report during the period c/ lc lo6 to 7/ ~2ld7 , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI. By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report. Furthermore, neither the Inspector nor his employer SHALL be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.

4% &L!"Au ,- Commissions )JO I/ P6 3 9, lv; b ict M 33 Y~z.w-~ Inspector's Signature National Board, Province and Endorsements Date J'QW' 2L. , Zd07 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 APPROVED (Signatures available in Master File)

ITEM 2006-23-0025 NOTE This form may not address all items needed for documentation of a repairlreplacement program, see I 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 (I) 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. 361 3 Revision 4 Page 1 of 2 MONTICELLO NUCLEAR GENERATING PLANT 1. Owner Xcel Energy Company Date 7/7/200 7 Name 2. Plant Monticello Nuclear Generating Plant Sheet 1 of 2 Name 2807 W. Cnty. Rd. 75, Monticello, Minnesota 55362 WO-I41349 Address Repair Organization P.O. No., Job No. etc. TITLE: 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 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 4. ldentification of System High Pressure Coolant Injection (HPCI), Class 2 5. (a) Applicable Construction Code ANSI 631.1 1977 Edition Year Addenda No Addenda Code Case n/a (b) Applicable Edition of Section XI Utilized for Repairs or Replacement 2001 Edition, No Addenda 6. ldentification of Components Repaired or Replaced and Replacement Components

7. Description of Work Replace existing snubber and (2) end pins like-for-like with new. 8. Tests Conducted:

Hydrostatic Pneumatic Nominal Operating Pressure Other [XI Pressure n/a psi Test Temp n/a OF Name of Component SS-707 SS-707 (2) Snubber End Pins (2) Snubber End Pins APPROVED (Signatures available in Master File) Name of Manufacturer Lisega Lisega Bergen- Paterson Bergen- Paterson Manufacturer Serial No. 61 4900/052 61 5060/055 - - National Board No. - - - - Other ldentification MNGPdn 700 MNGPS/" 70 1 - Hf# 306610 Year Built 2001 2001 1969 1991 Repaired, Replaced or Replacement Replaced Replacement Replaced Replacement ASME Code Stamped YES NO IXI IXI IXI

9. Remarks (Applicable Manufacturer's Data Reports to be Attached) Functional Testing per procedure 0251.

Pre-service VT-3 Examination as required by procedure 4903. 361 3 Revision 4 Page 2 of 2 MONTICEL~NUCLEA R GE~A TlNG PLANT CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this RWLRWMFN r conforms to the rules on the ASME Code,Section XI. repairlreplacement Signed I rir emno. Date , 2007 Owner or Owner's Designee, Title 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 til L~J~PJ 3 I-9 and employed by #4 PT f 4 s ?t'nh ~3 u/ l.*~ 1 fly J F ~ouw6ci7r Q /l of &lnP POP , c/T have inspected the components described in this Owner's Report during the period 4 /&/& to 7/9/07 , 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 lnspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report. Furthermore, neither the lnspector 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 my Commissions bfi [/KG 3 A~ rv,~ , /cro 00 43~~- co Inspector's Signature National Board, Province and Endorsements Date . Scl Cy "r I 2a7 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 APPROVED (Signatures available in Master File)

ITEM 2006-23-0026 I NOTE This form may not address all items needed for documentation of a repairlreplacement program, see 4 Awl-09.04.03 (ASME SECTION XI REPAlRiREPLACEMENT PROGRAM) for further guidance.

361 3 Revision 4 Page 1 of 2 MONTICELLO NUCLEAR GENERATING PLANT 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 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. TITLE: 1. Owner Xcel Energy Company Date 7/10/2007 Name 2. Plant Monticello Nuclear Generating Plant Sheet I of 2 Name OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 2807 W. Cnty. Rd. 75, Monticello, Minnesota 55362 WO 280592 Address Repair Organization P.O. No., Job No. etc. 3. Work Performed By NMCLXcel Energy Type Code Symbol Stamp n/a Company Name Authorization No.

n/a 2807 W. Cnty. Rd. 75, Monticello, MN 55362 Expiration Date n/a Address 4. ldentification of System Spare - 10 Kip Snubber 5. (a) Applicable Construction Code USAS 831. I 1 1967 Edition Year Addenda NoAddenda Code Case n/a (b) Applicable Edition of Section XI Utilized for Repairs or Replacement 2001 Edition, No Addenda 6. ldentification of Components Repaired or Replaced and Replacement Components

7. Description of Work Replaced main cylinder during rebuild PM. 8. Tests Conducted:

Hydrostatic Pneumatic Nominal Operating Pressure Other (XI Pressure psi Test Temp " F Name of Component Main Cvlinder Main Cvlinder APPROVED (Signatures available in Master File)

Name of Manufacturer Bergen Paferson Bergen Paterson Manufacturer Serial No. 529 529 National Board No. n/a n/a Other ldentification n/a n/a Year Built un- known 2006 Repaired, Replaced or Replacement Replaced Replacement ASME Code Stamped YES NO [ql [ql ITEM 2006-23-0026 I 9. Remarks (Applicable Manufacturer's Data Reports to be Attached) 361 3 Revision 4 Page 2 of 2 MONTICELLO NUCLEAR GENERATING PLANT Functionallv tested Der 0251. VT-3 pre-senlice exam to be com~leted followina installation under TITLE: work order OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this RE&~R/ ~Q~LOW~~T ArrlV conforms to the rules on the ASME Code,Section XI. repairlreplacement Signed , Secs.XI IS I COOKD. 0wneior 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 Ylrr~r~/~-soZ.4 and employed by

~,AK.~-FoKP

>?C'4h BoIL~W ZYJ of cO&pi'/cq~

of l-I4XTFolw CT have inspected the components described in this Owner's

~e~ortd to 7 1 12 107 , 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 lnspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report. Furthermore, neither the lnspector 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.

ytc/Lr~ &A& Commissions A/BIC~GJ 4 , J /'ru 00 YO ~g-cc, Inspector's Signature National Board, Province and Endorsements Date ~ULY rl I Zoo7 APPROVED (Signatures available in Master File) - -

ITEM 2006-23-002 7 NOTE This form may not address all items needed for documentation of a repairlreplacement program, see I 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 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.

361 3 Revision 4 Page 1 of23 $&, MONTICELLO NUCLEAR GENERATING PLANT

1. Owner Xcel Energy Company Date 7/10/2007 Name 2. Plant Monticello Nuclear Generating Plant Sheet I of 3 Name TITLE: 2807 W. Cnty. Rd. 75, Monticello, Minnesota 55362 WO 280592 Address Repair Organization P.O. No., Job No. etc.

OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 3. Work Performed By NMCMcel Energy Type Code Symbol Stamp n/a Company Name Authorization No.

n/a 2807 W. Cnty. Rd.

75, Monticello, MN 55362 Expiration Date n/a Address 4. ldentification of System Spare - 10 Kip Snubber 5. (a) Applicable Construction Code USAS 831. I 7 1967 Edition Year Addenda No Addenda Code Case n/a (b) Applicable Edition of Section XI Utilized for Repairs or Replacement 2001 Edition, No Addenda 6. ldentification of Components Repaired or Replaced and Replacement Components

7. Description of Work Replaced Main Cylinder, Piston, Piston Rings

/Rod / Nut during rebuild.

Name of Component Main Cvlinder Main - Cvlinder Piston Piston See 8. Tests Conducted:

Hydrostatic

[7 Pneumatic Nominal Operating Pressure [7 Other Pressure psi Test Temp " F Name of Manufacturer Bergen Paterson Bergen Paterson Bergen Paterson Bergen Paterso n Page APPROVED (Signatures available in Master File)

Manufacturer Serial No. 044 044 044 044 2 National Board No. n/a n/a n/a n/a for Other ldentification n/a n/a n/a n/a add'l Year Built un- known 2006 un- known 2006 items Repaired, Replaced or Replacement Replaced Replacement Replaced Replacement ASME Code Stamped YES C] C] NO IX] IX] IX]

Monticello Nuclear Generating Plant Form NIS-2 Continuation Sheet ITEM 2006-23-002 7 Page2 of 3 WO No. 280592 Repaired, Replaced or Replacement replaced replacement replaced replacement replaced replacement ASME Code Name of Component Piston Rings Piston Rings Piston Rod Piston Rod Piston Nuf Piston Nut . Stamped Yes Other Identification n/a n/a n/a n/a n/a n/a No X X X X X X Year Built Un- known 2006 Un- known 2006 Un- known 2006 Name of Manufacturer Bergen Pa ferson Bergen Paterson Bergen Pa terson Bergen Paterson Bergen Paferson Bergen Paterson Manufacturer Serial No. 044 044 044 044 044 044 National Board No. n/a n/a n/a n/a n/a n/a ITEM 2006-23-0027 I 9. Remarks (Applicable Manufacturer's Data Reports to be Attached)

Functional test oer 0251, VT-3 to be completed when installed.

361 3 Revision 4 MONTICELLO NUCLEAR GENERATING PLANT CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this

~~PAI~/R~U~C~MENT Acsr lv fly conforms to the rules on the ASME Code,Section XI.

'repairlreplacement Signed -- a SECT XI IS( COO- Owner or 0wne?s Designee, Title 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 rt I~VGL oT4 and employed by Hd fl7Pdtb SCt'ah p o/l 2 7 OF @cu/J&tTnc~y of /-/~ILTF~JK~JCT have inspected the components described in this Owner's Report during the period

'f /L/ /UG to 7 1% /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 XI. By signing this certificate neither the lnspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report. Furthermore, neither the lnspector 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.

7l~ A Commissions A/alrr6J ,q,~r',rrw~uv~zg-cu Inspector's Signature National Board, Province and Endorsements Date TQLY 11 , 2-uu7 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 APPROVED (Signatures available in Master File)

NOTE This form may not address all items needed for documentation of a repairlreplacement program, see 4 Awl-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 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. 361 3 Revision 4 Page 1 of 2 MONTICELLO NUCLEAR GENERATING PLANT

1. Owner Xcel Energy Company Date 7/10/2007 Name 2. Plant Monticello Nuclear Generating Plant Sheet I of 2 Name 2807 W. Cnty. Rd. 75, Monticello, Minnesota 55362 WO 280592 Address Repair Organization P.O. No., Job No. etc. TITLE: 3. Work Performed By NMCMcel Energy Type Code Symbol Stamp n/a Company Name Authorization No. n/a 2807 W. Cnty. Rd. 75, Monticello, MN 55362 Expiration Date n/a Address OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 4. Identification of System Spare - 20 Kip Snubber 5. (a) Applicable Construction Code 1967 Year Edition Addenda No Addenda Code Case n/a (b) Applicable Edition of Section XI Utilized for Repairs or Replacement 2001 Edition, No Addenda 6. ldentification of Components Repaired or Replaced and Replacement Components

7. Description of Work Replaced valve manifold during rebuild PM. 8. Tests Conducted: Hydrostatic C] Pneumatic C] Nominal Operating Pressure Other Pressure psi Test Temp " F APPROVED (Signatures available in Master File)

ITEM 2006-23-0028 I 9. Remarks (Applicable Manufacturer's Data Reports to be Attached)

Functionallv tested Rer 0251. VT-3 pre-service exam to be com~leted followinu installation under 361 3 Revision 4 Page 2 of 2 MONTICELLO NUCLEAR GENERATING PLANT CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this %@R~R / W~CEME~T Aw~u I~ conforms to the rules on the ASME Code,Section XI.

repairlreplacement - Signed 7- SECT. 1 IS1 owner br Owner's Designee, Title i 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 19Ipa'SotA and employed by &I~~~OI~YJTEU~~OII~IZ OF T~A/&FCF/CU/'

of /~AP~~PD, Cr have inspected the components described in this Owner's Report during the period 3 /rcl /06 to 7 /IL 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 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 lnspector nor his employer SHALL be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.

<L, A &LLV Commissions

~g r /l(- 3 n , A/, 1 IVJJ a J L/d LB - c o Inspector's Signature National Board, Province and Endorsements Date JWY li~ , rw7 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 APPROVED (Signatures available in Master File) --- - -- -- -- A&--- -

ITEM 2006-23-0029 NOTE 1: This form may not address all items needed for documentation of a repairlreplacement program, see I 4 Awl-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 I I 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. 361 3 Revision 4 Page 1 of 2 MONTICELLO NUCLEAR GENERATING PLANT

1. Owner Xcel Energy Company Date 7/11/2007 Name 2. Plant Monticello Nuclear Generating Plant Sheet 1 of 2 Name 2807 W. Cnty. Rd. 75, Monticello, Minnesota 55362 WO 280592 Address Repair Organization P.O.

No., Job No. etc. TITLE: 3. Work Performed By NMC/Xcel Energy Type Code Symbol Stamp n/a Company Name Authorization No. n/a 2807 W. Cnty. Rd.

75, Monticello, MN 55362 Expiration Date n/a OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 Address 4. ldentification of System Spare - 20 Kip Snubber 5. (a) Applicable Construction Code USAS B31. I 9 1967 Edition Year Addenda No Addenda Code Case n/a (b) Applicable Edition of Section XI Utilized for Repairs or Replacement 2001 Edition, No Addenda 6. ldentification of Components Repaired or Replaced and Replacement Components Description of Work Name of Component Valve Manifold Valve Manifold Replaced valve manifold during rebuild PM. 8. Tests Conducted:

Hydrostatic Pneumatic Nominal Operating Pressure Name of Manufacturer Bergen Paferson Bergen Paterson Other Pressure psi Test Temp OF 1 3087 (DOCUMENT CHANGE, HOLD AND COMMENT FORM) incorporated:

I Manufacturer Serial No. 126 126 APPROVED (Signatures available in Master File)

National Board No. n/a n/a Other ldentification n/a n/a @FOR 'ADMifilj9xwTIVE Resp Supv: PRGE I Assoc Ref:

PRGE I SR: N I Freq: 0 vrs ,.' U$$E ON&+' . ARMS: 3613 1 Doc Tv~e: REF ONLY I Admin initials:

I Date: 7 ( Year Built un- known 2006 Repaired, Replaced or Replacement Replaced Replacement ASME Code Stamped YES 0 NO IX)

ITEM 2006-23-0029 I 9. Remarks (Applicable Manufacturer's Data Reports to be Attached)

Functionallv tested mr 0251. VT-3 me-service exam to be completed followina installation under 361 3 Revision 4 Page 2 of 2 MONTICELLO NUCLEAR GENERATING PLANT CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this REPAIR/ a*fWMENT Am v IT^ conforms to the rules on the ASME Code,Section XI. repairlreplacement Signed I -.sem.xl 1Sfcw~~. Date FO 11 . 2-04 Owner or ~wnelr's Designee, Title 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 YIKWCILJ'T/)

and employed by RAKSFQU~, 5WAh BUILt SJ~ coh~t'c).lcrT of b13 dr FO , er have inspected the components described in this Owner's Report during the period 4 lr4 106 to 7 1 it 107 , 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 lnspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report. Furthermore, neither the Inspector nor his employer SHALL be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.

Commissions I I& A, k/, 1 , IY~O o Vu LR-Co , Inspector's Signature National Board, Province and Endorsements Date Ij-uCLJ/ /z , zoo7 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 APPROVED (Signatures available in Master File)

NOTE This form may not address all items needed for documentation of a repairlreplacement program, see 4 Awl-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 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. 361 3 Revision 4 Page 1 of33 ,G7 MONTICELLO NUCLEAR GENERATING PLANT

1. Owner Xcel Energy Company Date 7/11/2007 Name 2. Plant Monticello Nuclear Generating Plant Sheet I of 3 Name 2807 W. Cnty. Rd. 75, Monticello, Minnesota 55362 WO 280592 Address Repair Organization P.O.

No., Job No. etc. TITLE: 3. Work Performed By NMC/Xcel Energy Type Code Symbol Stamp n/a Company Name Authorization No. n/a 2807 W. Cnty. Rd. 75, Monticello, MN 55362 Expiration Date n/a Address OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 4. ldentification of System Spare - 10 Kip Snubber 5. (a) Applicable Construction Code USAS B31. I 1 1967 Edition Year Addenda No Addenda Code Case n/a (b) Applicable Edition of Section XI Utilized for Repairs or Replacement 2001 Edition, No Addenda 6. ldentification of Components Repaired or Replaced and Replacement Components

7. Description of Work Replaced Main Cylinder, Piston, Piston Rings during rebuild.

Name of Component Main Cvlinde r Main Cvlinder Piston Pisfon - See 8. Tests Conducted:

Hydrostatic Pneumatic Nominal Operating Pressure Other [XI Pressure psi Test Temp " F Name of Manufacturer Bergen Paferson Bergen Pa ferson Bergen Paferson Bergen Paferson Page APPROVED (Signatures available in Master File) Manufacturer Serial No. 157 157 157 157 2 National Board No. n/a n/a n/a n/a for Other ldentification n/a n/a n/a n/a add'l Year Built un- known 2006 un- known 2006 items Repaired, Replaced or Replacement Replaced Replacemenf Replaced Replacement ASME Code Stamped YES 0 NO IXI IXI IXI -

Monticello Nuclear Generating Plant Form NIS-2 Continuation Sheet ITEM 2006-23-0030 Name of Component Piston Rings Piston Rings Name of Manufacturer Bergen Paterson Bergen Paterson Manufacturer Serial No. 157 157 National Board No. n/a n/a Other Identification n/a n/a Year Built Un- known 2006 Repaired, Replaced or Replacement replaced replacement ASME Code Stamped Yes No X X ITEM 2006-23-0030 I 9. Remarks (Applicable Manufacturer's Data Reports to be Attached) 361 3 Revision 4 MONTICELLO NUCLEAR GENERATING PLANT Functional test oer 0251, VT-3 to be comoleted when installed.

TITLE: CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this WEPAIR /'R~~cE'M~N T A CTI v I TY conforms to the rules on the ASME Code,Section XI. repairlreplacement Signed a SECT XI 1s) &OD Owner or Owner's besignee, Title Date &, !I , 'LM7 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 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 fi "~/Y~'sT& and employed by b1.9 ~7 fg $0 J T ~'nh 8 01 cc'tt ~'rf oC co MW.C;C CUT of FI~~~TFQK .Q I LT have inspected the components described in this Owner's Report during the period 9 /LI 106 to 7 /1~/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 XI.

By signing this certificate neither the lnspector 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.

74L-3 A/~Y(-~L.

Commissions h/P l1%63 A , N~ l MA/ 0 UYO L& -Co Inspector's Signature National Board, Province and Endorsements Date mL4, 12- , 2uo 7 APPROVED (Signatures available in Master File) - - -

NOTE This form may not address all items needed for documentation of a repairlreplacement program, 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 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.

361 3 Revision 4 Page 1 of 2 MONTICELLO NUCLEAR GENERATING PLANT 1. Owner Xcel Energy Company Date 7/8/2007 Name TITLE: 2. Plant Monticello Nuclear Generating Plant Sheet I of 2 Name 2807 W. Cnty. Rd. 75, Monticello, Minnesota 55362 WO 135620, GE 21A5829 Rev?, DC 96Q065 Address Repair Organization P.O. No., Job No. etc. OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 3. Work Performed By NMC/Xcel Energy Type Code Symbol Stamp n/a Company Name Authorization No. n/a 2807 W. Cnty. Rd.

75, Monticello, MN 55362 Expiration Date n/a Address 4. ldentification of System Standby Liquid Control (SBL), Class 2 5. (a) Applicable Construction Code ANSI B31.1 9 1977 Edition Year Addenda Winter 1978 Addenda 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

7. Description of Work Replaced nozzle and disc during normal PM

8. Tests Conducted:

Hydrostatic C] Pneumatic C] Nominal Operating Pressure Other Pressure psi Test Temp " F APPROVED (Signatures available in Master File)

Name of Component RV- 1 1-398 Disc RV- I 1-398 Disc RV- I 1-398 Nozzle RV- 1 1-398 Nozzle Repaired, Replaced or Replacement Replaced Replacement Replaced Replacement Name of Manufacturer Consolidated Dresser. Inc.

Consolidated Dresser. Inc. Consolidated Dresser. Inc. Consolidated Dresser. Inc.

ASME Code Stamped YES Manufacturer Serial No. Valve dn TM 41591 Valve dn TM 4 1 591 Valve s/n TM 4 I 59 1 Valve s/n TM 41591 NO IXI Other Identification AOD71 S/"ADV03 Ht Cd 67269 ADD47 S/" Ht Cd 72470 National Board No. n/a n/a n/a n/a Year Built 2001 2005 2001 2005 ITEM 2006-23-0031 1 9. Remarks (Applicable Manufacturer's Data Reports to be Attached)

Set~oint and Leak Check wer 0255-02-18.

No Dressure testinu, this is a ware returned to stock. 361 3 Revision 4 Page 2 of 2 MONTICELLO NUCLEAR GENERATING PLANT CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this 7?* PLC)C(~-I@EN 7 conforms to the rules on the ASME Code,Section XI. repairlreplacement Signed I S*cr DISz La. Date Owner or Owner's Designee, Title 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~uuz- saJh and employed by ~~fihbifo

~TIc.A~ ~~ILCX S+$ of Cds/&~-c]~c~;

of ~IAPT~~PU , CT have inspected the components described in this Owner's Report during the period lo /6 jol: to 7 107 , 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.

,%LA& Commissions

~/g /I 86 3 , hp cw Y rpro Inspector's Signature National ~oaid, Province and Endorsements Date J-(JL~ Ci , 2007 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 APPROVED (Signatures available in Master File)

ITEM 2006-23-0032 NOTE This form may not address all items needed for documentation of a repairlreplacement program, see I 4 Awl-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 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. 361 3 Revision 4 Page 1 of 2 MONTICELLO NUCLEAR GENERATING PLANT

1. Owner Xcel Energy Company Date 7/11/2007 Name 2. Plant Monticello Nuclear Generating Plant Sheet I of 2 Name 2807 W. Cnty. Rd. 75, Monticello, Minnesota 55362 WO 280592 Address Repair Organization P.O. No., Job No. etc. TITLE: 3. Work Performed By NMC/Xcel Energy Type Code Symbol Stamp n/a OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 Company Name Authorization No. n/a 2807 W. Cnty. Rd. 75, Monticello, MN 55362 Expiration Date n/a Address 4. ldentification of System Spare - 20 Kip Snubber 5. (a) Applicable Construction Code USAS B31.1 1 1967 Edition Year Addenda No Addenda Code Case n/a (b) Applicable Edition of Section XI Utilized for Repairs or Replacement 2001 Edition, No Addenda 6. ldentification of Components Repaired or Replaced and Replacement Components

7. Description of Work Replaced valve manifold during rebuild PM. Name of Component Valve Manifold Valve Manifold 8. Tests Conducted:

Hydrostatic Pneumatic Nominal Operating Pressure Other Pressure psi Test Temp " F Name of Manufacturer Bergen Paferson Bergen Pa ferson ( 3087 (DOCUMENT CHANGE, HOLD AND COMMENT FORM) incorporated:

I APPROVED (Signatures available in Master File)

Manufacturer Serial No. 131 131 Res~ Supv: PRGE I Assoc Ref: PRGE I SR: N 1 Freq: 0 vrs ,, I Doc Tvw: REF ONLY I Admin initials:

I Date: National Board No.

n/a n/a Other ldentification n/a n/a I Year Built un- known 2006 Repaired, Replaced or Replacement Replaced Replacement ASME Code Stamped YES I7 I7 NO IXI IXI ITEM 2006-23-0032 I 9. Remarks (Applicable Manufacturer's Data Reports to be Attached) Functionallv tested per 0251. VT-3 re-senlice exam to be com~leted followinu installation under 361 3 Revision 4 Page 2 of 2 MONTICELLO NUCLEAR GENERATING PLANT CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this T(EPI)IR IREPLPCEMENT

~WY rp/ conforms to the rules on the ASME Code,Section XI. repairlreplacement Signed r X 1 1 S\ &oQD Date Owner or Owner's Designee, Title L 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 /%wlyo'.~

074 and employed by O4PT FdRU r7Ynh a dtt I 9-1 Cul~rT Icoi' of bIA P )Fdp O cr have inspected the components described in this Owner's Report during the period 1' /Y /d t to 7 //L lo7 , 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 lnspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report. Furthermore, neither the lnspector 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.

PL-7 A /eLd. Commissions p/~ 1/84 3 A, w, L - , I\ w 00 w 21 -CCJ Inspector's Signature National Board, Province and Endorsements Date T'uL~ Ir , Zod7 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 APPROVED (Signatures available in Master File)

ITEM 2006-23-0033 NOTE This form may not address all items needed for documentation of a repairlreplacement program, see I 4 Awl-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 I I 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. L 1. Owner Xcel Energy Company Date 7/11/2007 Name 2. Plant Monticello Nuclear Generating Plant Sheet I of 2 Name 2807 W. Cnty. Rd. 75, Monticello, Minnesota 55362 WO 280592 Address Repair Organization P.O.

No., Job No, etc.

361 3 Revision 4 Page 1 of 2 MONTICELLO NUCLEAR GENERATING PLANT

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

n/a 2807 W. Cnty. Rd.

75, Monticello, MN 55362 Expiration Date n/a Address TITLE: 4. Identification of System Spare - 20 Kip Snubber OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 5. (a) Applicable Construction Code USAS B31. I 1967 Edition Year Addenda No Addenda 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

7. Description of Work Replaced valve manifold during rebuild PM. Name of Component Valve Manifold Valve Manifold 8. Tests Conducted:

Hydrostatic Pneumatic Nominal Operating Pressure Other Pressure psi Test Temp " F Name of Manufacturer Bergen Paterson Bergen Paterson APPROVED (Signatures available in Master File) Manufacturer Serial No. 487 487 National Board No. n/a n/a Other ldentification n/a n/a Year Built un- known 2006 Repaired, Replaced or Replacement Replaced Replacement ASME Code Stamped YES (7 NO - rn cl ITEM 2006-23-0033 I 9. Remarks (Applicable Manufacturer's Data Reports to be Attached)

Functional& tested oer 0251.

VT-3 ore-sewice exam to be comoleted followina installation under 361 3 Revision 4 Page 2 of 2 MONTICELLO NUCLEAR GENERATING PLANT rate work order _r TITLE: CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this RWA IR /REPCACEMENT h VITY conforms to the rules on the ASME Code,Section XI.

repairlreplacement

.. Signed SECT XI IS\ COORY Owner or Owner's Designee, Title Date pa 11 , 2007 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 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 PI /U~JC'JJ~A and employed by H nd; FJR~ -17t'4k UDILC'K ZtS of cokwt5TlckT of l-/d~j ~u&J) CJ- have inspected the components described in this Owner's Report during the period 11 1 Y /UL to 7 //a /u7 , 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.

A&-' Commissions A/d /I&(; J 4, n/, lt , 15 X/ JCJ YOZJ-CU Inspector's Signature National Board, Province and Endorsements Date TUyl lr , zoo7 APPROVED (Signatures available in Master File)

ITEM 2006-23-0034 1 NOTE This form may not address all items needed for documentation of a repairlreplacement program, see 4 Awl-09.04.03 (ASME SECTION XI REPAIRIREPLACEMENT PROGRAM) for further guidance.

361 3 Revision 4 Page 1 of 2 MONTICELLO NUCLEAR GENERATING PLANT 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 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. TITLE: 1. Owner Xcel Energy Company Date 7/11/2007 Name 2. Plant Monticello Nuclear Generating Plant Sheet I of 2 Name 2807 W. Cnty. Rd. 75, Monticello, Minnesota 55362 WO 280592 Address Repair Organization P.O. No., Job No. etc. OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 3. Work Performed By NMCMcel Energy Type Code Symbol Stamp n/a Company Name Authorization No.

n/a 2807 W. Cnty. Rd. 75, Monticello, MN 55362 Expiration Date n/a Address 4. ldentification of System Spare - 20 Kip Snubber 5. (a) Applicable Construction Code USAS 531. I 1967 Edition Year Addenda No Addenda Code Case n/a (b) Applicable Edition of Section XI Utilized for Repairs or Replacement 2001 Edition, No Addenda 6. ldentification of Components Repaired or Replaced and Replacement Components

7. Description of Work Replaced valve manifold during rebuild PM. 8. Tests Conducted: Hydrostatic Pneumatic Nominal Operating Pressure Other [XI Pressure psi Test Temp OF Name of Component Valve Manifold Valve Manifold 1 3087 (DOCUMENT CHANGE, HOLD AND COMMENT FORM) incorporated:

I Name of Manufacturer Bergen Paterson Bergen Paterson APPROVED (Signatures available in Master File) 2$FqF AQ&IIINIdSBRATIVE 7 W I Assoc Ref: PRGE I SR: N I Freq: 0 VIS 4. Y9A~~uS6^FarbL~J , 1 Doc Tvw: REF ONLY 1 Admin initials:

1 Date: Manufacturer Serial No. 466 466 I National Board No.

n/a n/a Other ldentification n/a n/a Year Built un- known 2006 Repaired, Replaced or Replacement Replaced Replacement ASME Code Stamped YES C] C] NO ITEM 2006-23-0034

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

Functionallv tested per 0251.

VT-3 pre-senlice exam to be com~leted followina installation under ork order 361 3 Revision 4 Page 2 of 2 MONTICELLO NUCLEAR GENERATING PLANT CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this Rrppla /~apr~cnnw h y ln conforms to the rules on the ASME Code,Section XI.

repairlreplacement Signed Owner or owndr's Designee, Title Date Fa 11 , 1M7 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 1'1 lul~~d 74 and employed by ~/~\RTFLIRY))T~A~IPO/~P~$~~OFCO~&C'CTILQT of ~/~IITEoJZD,C~

have inspected the components described in this Owner's Report during the period 11 I Y /d6 to 7 /lz 167 , 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 lnspector 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 Commissions bfi 118~3 A, ,v, 1. &A/ &L/ ozr-co Inspector's Signature National Board, Province and Endorsements Date JULY (L , 2337 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 APPROVED (Signatures available in Master File)

ITEM 2006-23-0035 NOTE This form may not address all items needed for documentation of a repairlreplacement program, see I 4 Awl-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 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. 361 3 Revision 4 Page 1 of 2 MONTICELLO NUCLEAR GENERATING PLANT 1. Owner Xcel Energy Company Date 7/11/2007 TITLE: Name 2. Plant Monticello Nuclear Generating Plant Sheet 1 of 2 Name OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 2807 W. Cnty. Rd. 75, Monticello, Minnesota 55362 WO 280592 Address Repair Organization P.O. No., Job No. etc. 3. Work Performed By NMCHcel Energy Type Code Symbol Stamp n/a Company Name Authorization No. n/a 2807 W. Cnty. Rd. 75, Monticello, MN 55362 Expiration Date n/a Address 4. ldentification of System Spare - 20 Kip Snubber 5. (a) Applicable Construction Code USAS B31.1 1 1967 Edition Year Addenda No Addenda Code Case n/a (b) Applicable Edition of Section XI Utilized for Repairs or Replacement 2001 Edition, No Addenda 6. ldentification of Components Repaired or Replaced and Replacement Components

7. Description of Work Replaced valve manifold during rebuild PM. 8. Tests Conducted:

Hydrostatic Pneumatic Nominal Operating Pressure Name of Component Valve Valve Manifold Other Pressure psi Test Temp OF APPROVED (Signatures available in Master File) Name of Manufacturer Bergen Bergen Paterson Manufacturer Serial No. 132 132 National Board No. n/a ManrfoldPafersonm---

n/a Other ldentification n/a n/a Year Built un- 2006 Repaired, Replaced or Replacement Replaced Replacement ASME Code Stamped YES NO IXj

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

Funcfionallv tested per 0251. VT-3 ore-service exam to be com~leted followina installation under 361 3 Revision 4 Page 2 of 2 MONTICELLO NUCLEAR GENERATING PLANT te work or& -~ TITLE: CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this P&PA~P/REPLUKNT Acrr ulrl conforms to the rules on the ASME Code,Section XI.

i-epairlreplacement Signed SE~T.XI ISI COD- Owner or owner'd~esignee, Title OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 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 /Lc~*lvFsoTP and employed by ~,A@TF~JJ sT,fk~y&?o/~tjB

~*~JFCWW%~ICCIT of E-rrlnTFaa~, C7- have inspected the components described in this Owner's Report during the period C// t9 Id6 to 71 1~1~7 , 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 lnspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report. Furthermore, neither the lnspector 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.

dkT &fc4- Commissions blJ /I& 3 4, % ..? , &/J dd YOL-B-CU Inspector's Signature National Board, Province and Endorsements Date Tb~7 /z. I 200 7 APPROVED (Signatures available in Master File)

ITEM 2006-23-0036 NOTE This form may not address all items needed for documentation of a repairlreplacement program, see I 4 Awl-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 I I 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. 361 3 Revision 4 Page 1 of 2 MONTICELLO NUCLEAR GENERATING PLANT 1. Owner Xcel Energy Company Date 7/11/2007 Name 2. Plant Monticello Nuclear Generating Plant Sheet 1 of 2 Name 2807 W. Cnty. Rd. 75, Monticello, Minnesota 55362 WO 280592 Address Repair Organization P.O. No., Job No. etc. TITLE: 3. Work Performed By NMCLXcel Energy Type Code Symbol Stamp n/a Company Name Authorization No. n/a 2807 W. Cnty. Rd. 75, Monticello, MN 55362 Expiration Date n/a Address OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 4. ldentification of System Spare - 20 Kip Snubber i 5. (a) Applicable Construction Code USAS B31. I 1967 Edition Year Addenda No Addenda Code Case n/a (b) Applicable Edition of Section XI Utilized for Repairs or Replacement 2001 Edition, No Addenda 6. ldentification of Components Repaired or Replaced and Replacement Components

7. Description of Work Replaced valve manifold during rebuild PM. 8. Tests Conducted: Hydrostatic Pneumatic Nominal Operating Pressure Other Pressure psi Test Temp " F Name of Component Valve Manifold Valve Manifold ) 3087 (DOCUMENT CHANGE, HOLD AND COMMENT FORM) incorporated:

I National Board No. n/a n/a Name of Manufacturer Bergen Paterson Bergen Pa terson APPROVED (Signatures available in Master File)

Other ldentification n/a n/a Manufacturer Serial No. 148 148 FOR %? Resp Supv: PRGE 1 Assoc Ref:

PRGE 1 SR: N I Freq: 0 vn 1 ARMS: 3613 I Doc Tvpe: REF ONLY I Admin initials:

I Date: I Year Built un- known 2006 Repaired, Replaced or Replacement Replaced Replacemenf ASME Code Stamped YES NO ITEM 2006-23-0036 I 9. Remarks (Applicable Manufacturer's Data Reports to be Attached)

Functionallv tested per 0251. VT-3 re-service exam to be com~leted followina installation under CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this RPA~(I /R@~~EJT h~lv conforms to the rules on the ASME Code,Section XI. iepairlreplacement Signed -. SECr Kf ISI COORD Owner or 0wne.r'~ Designee, Title 361 3 Revision 4 Page 2 of 2 MONTICELLO NUCLEAR GENERATING PLANT 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 +VJVF.@,J~T,~ and employed by kl~fl~frr~d f7c',+h BUI~ ZtJ 4Jt COUIAX~ICQT of /-/qr~Fc)rSlJ, cT have inspected the components described in this Owner's Report during the period Q kc /a& to 7 112 /o 7 , 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 lnspector 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.

kL~h4~* Commissions

//kg3 4, fv,1' , />A/ 00 Y J 2 2 -CO Inspector's Signature National Board, Province and Endorsements Date TyLy 12 , 2u07 TITLE: APPROVED (Signatures available in Master File)

OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 ITEM 2006-23-0037 NOTE This form may not address all items needed for documentation of a repairlreplacement program, see I 4 AWI-09.04.03 (ASME SECTION XI REPAIRIREPLACEMENT PROGRAM) for further guidance.

I 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 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. 1. Owner Xcel Energy Company Date 7/11/2007 361 3 Revision 4 Page 1 of 2 MONTICELLO NUCLEAR GENERATING PLANT Name 2. Plant Monticello Nuclear Generating Plant Sheet I of 2 Name 2807 W. Cnty. Rd. 75, Monticello, Minnesota 55362 WO 280592 Address Repair Organization P.O. No., Job No. etc. TITLE: 3. Work Performed By NMCHcel Energy Type Code Symbol Stamp n/a Company Name Authorization No. n/a 2807 W. Cnty. Rd.

75, Monticello, MN 55362 Expiration Date n/a OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 Address 4. ldentification of System Spare - 20 Kip Snubber

5. (a) Applicable Construction Code USAS 831. I I 1967 Edition Year Addenda No Addenda Code Case n/a (b) Applicable Edition of Section XI Utilized for Repairs or Replacement 2001 Edition, No Addenda 6. ldentification of Components Repaired or Replaced and Replacement Components

7. Description of Work Replaced main cylinder during rebuild PM. 8. Tests Conducted:

Hydrostatic C] Pneumatic Nominal Operating Pressure C] Name of Component Main Cvlinder Main Cvlinder Other Pressure psi Test Temp " F Repaired, Replaced or Replacement Replaced Replacement APPROVED (Signatures available in Master File)

Name of Manufacturer Bergen Paterson Bergen Paterson ASME Code Stamped Manufacturer Serial No. 132 132 YES C] C] NO (XI National Board No. n/a n/a Other ldentification n/a n/a Year Built un- known 2006 ITEM 2006-23-0037 I 9. Remarks (Applicable Manufacturer's Data Reports to be Attached)

Functionall~v tested Der 0251. VT-3 re-senlice exam to be com~leted followinu installation under r 361 3 Revision 4 Page 2 of 2 MONTICELLO NUCLEAR GENERATING PLANT CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this -14 /g~~~ce&wr A at vfy conforms to the rules on the ASME Code,Section XI. repairlreplacement Signed I* , SECTXI IS\ COOED Owner or Owner's Designee, Title Oate %!+ 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 MIMU&$ oTn and employed by

~nkTfoKM flt>~go~~c'~JtJof cok&r-cJrrur of br4ntp~Ku CT have inspected the components described in this Owner's ~eportc to 7 112 /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 XI.

By signing this certificate neither the lnspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report. Furthermore, neither the lnspector 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&& Commissions pfi if~~_y A, /(/J' , ~b ode/ 0 2r -CO Inspector's Signature National Board, Province and Endorsements Date TQLY 12 , 2007 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 APPROVED (Signatures available in Master File)

ITEM 2006-23-0038 I NOTE This form may not address all items needed for documentation of a repairlreplacement program, see 4 Awl-09.04.03 (ASME SECTION XI REPAIRIREPLACEMENT PROGRAM) for further guidance.

361 3 Revision 4 Page 1 of 2 MONTICELLO NUCLEAR GENERATING PLANT 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 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. TITLE: 1. Owner Xcel Energy Company Date 7/11/2007 Name 2. Plant Monticello Nuclear Generating Plant Sheet I of 2 Name OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 2807 W. Cnty. Rd. 75, Monticello, Minnesota 55362 WO 280592 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. Cnty. Rd. 75, Monticello, MN 55362 Expiration Date n/a Address 4. ldentification of System Spare - 30 Kip Snubber

5. (a) Applicable Construction Code USAS B31.1 1 1967 Edition Year Addenda NoAddenda Code Case n/a (b) Applicable Edition of Section XI Utilized for Repairs or Replacement 2001 Edition, No Addenda 6. ldentification of Components Repaired or Replaced and Replacement Components

7. Description of Work Replaced main cylinder during rebuild PM. Name of Component Main Cvlinder Main Cvlinder 8. Tests Conducted: Hydrostatic Pneumatic Nominal Operating Pressure Other Pressure psi Test Temp " F APPROVED (Signatures available in Master File)

Name of Manufacturer Bergen Paterson Bergen Paterson Other ldentification n/a n/a Manufacturer Serial No. 1 02 102 National Board No. n/a n/a Year Built un- known 2006 Repaired, Replaced or Replacement Replaced Replacement ASME Code Stamped YES C] C] NO ' IXI IXI ITEM 2006-23-0038

9. Remarks I (Applicable Manufacturer's Data Reports to be Attached) Functionallv tested r>er 0251. VT-3 me-senlice exam to be completed followina installation under CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this Rs~pt~ /RG~EM~~ htvy conforms to the rules on the ASME Code,Section XI. repairlreplacement Signed 4. : SEWXI IS1 COORD Date Owner or Owner's Designee, Title 361 3 Revision 4 Page 2 of 2 MONTICELLO NUCLEAR GENERATING PLANT 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 /-jlh/~P for4 and employed by PlAlZT Fonu rr ZA~ B JjJ dF CDU@C-C~I~L~~

of I/.~/z~~%FM

., C 7 have inspected the components described in this Owner's Report during the period lo / L jc, 6 to 7 1 /t Id7 , 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 lnspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report. Furthermore, neither the lnspector nor his employer SHALL be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.

?,L+4- 1. &A'. Commissions

/J& 1/66 J A,y2, f~cuo@~/u~~-t.Cr Inspector's Signature National Board, Province and Endorsements Date TULY' 12. , tOd7 TITLE: APPROVED (Signatures available in Master File) OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 ITEM 2006-23-0039 This form may not address all items needed for documentation of a repairlreplacement program, see I 4 Awl-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 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. 361 3 Revision 4 Page 1 of 2 MONTICELLO NUCLEAR GENERATING PLANT 1. Owner Xcel Energy Company Name 2. Plant Monticello Nuclear Generating Plant Name 2807 W. Cnty. Rd. 75, Monticello, Minnesota 55362 Address TITLE: 3. Work Performed By NMC/Xcel Energy Company Name 2807 W. Cnty. Rd. 75, Monticello, MN 55362 Address OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 Date 7/11/2007 Sheet WO 280592 Repair Organization P.O. No., Job No. etc. Type Code Symbol Stamp n/a Authorization No. n/a Expiration Date n/a 4. ldentification of System Spare - 30 Kip Snubber 5. (a) Applicable Construction Code USAS B31.1 1967 Edition Year Addenda No Addenda Code Case n/a (b) Applicable Edition of Section XI Utilized for Repairs or Replacement 2001 Edition, No Addenda 6. ldentification of Components Repaired or Replaced and Replacement Components

7. Description of Work Replaced main cylinder during rebuild PM. Name of Component Main Cvlinder Main Cvlinder 8. Tests Conducted:

Hydrostatic Pneumatic Nominal Operating Pressure Other Pressure psi Test Temp " F Name of Manufacturer Bergen Paterson Bergen Pa terson APPROVED (Signatures available in Master File)

Manufacturer Serial No. 1 54 1 54 National Board No. n/a n/a Other ldentification n/a n/a Year Built un- known 2006 Repaired, Replaced or Replacement Replaced Replacement ASME Code Stamped YES NO ITEM 2006-23-0039 I 9. Remarks (Applicable Manufacturer's Data Reports to be Attached)

Functionallv tested per 0251. VT-3 pre-senlice exam to be com~leted followina installation under 361 3 Revision 4 Page 2 of 2 MONTICELLO NUCLEAR GENERATING PLANT CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this RSPA~R/RR)~ENT AcT\u~~ conforms to the rules on the ASME Code,Section XI.

repairlreplacement Signed , SE~ XI IS I COO- Owner or Owner's Designee, Title Date fi 11 , 2007 r 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 PlNuf~07n and employed by t-I~i%haa STalch BO/L@72 3+1 of COWWC'C~~CL,~

of J-~~RTFOKP , c have inspected the components described in this Owner's Report during the period to / 6 106 to 7 / 1~ /37 , 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 lnspector 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.

h Addq Commissions

B Ut6 3 P,N,$ . /~-l w so 43 ~g-co Inspector's Signature National Board, Province and Endorsements Date 7t~y' IZ , zdo7 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 APPROVED (Signatures available in Master File)

ITEM 2006-23-0040 I NOTE This form may not address all items needed for documentation of a repairlreplacement program, see 4 Awl-09.04.03 (ASME SECTION XI REPAIRIREPLACEMENT PROGRAM) for further guidance.

361 3 Revision 4 Page 1 of 2 MONTICELLO NUCLEAR GENERATING PLANT NOTE 2: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (I) 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. TITLE: 1. Owner Xcel Energy Company Date 7/11/2007 Name 2. Plant Monticello Nuclear Generating Plant Sheet 1 of 2 Name 2807 W. Cnty. Rd. 75, Monticello, Minnesota 55362 WO 280592 Address Repair Organization P.O. No., Job No. etc. OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 3. Work Performed By NMC/Xcel Energy Type Code Symbol Stamp n/a Company Name Authorization No.

nla 2807 W. Cnty. Rd. 75, Monticello, MN 55362 Expiration Date n/a Address ldentification of System Spare - 130 Kip Snubber 5. (a) Applicable Construction Code USAS 831.1 7 1967 Edition Year Addenda NoAddenda Code Case n/a (b) Applicable Edition of Section XI Utilized for Repairs or Replacement 2001 Edition, No Addenda

6. ldentification of Components Repaired or Replaced and Replacement Components Description of Work Name of Component Main Cvlinder Main Cvlinder Replaced main cylinder during rebuild PM. 8. Tests Conducted:

Hydrostatic Pneumatic Nominal Operating Pressure [7 Name of Manufacturer Bergen Paterso n Bergen Paterson Other Pressure psi Test Temp " F ( 3087 (DOCUMENT CHANGE, HOLD AND COMMENT FORM) incorporated:

I Manufacturer Serial No. 1 74 1 74 APPROVED (Signatures available in Master File)

National Board No. n/a n/a Other ldentification n/a n/a Year Built un- known 2006 Repaired, Replaced or Replacement Replaced Replacement ASME Code Stamped YES NO ITEM 2006-23-0040 I 9. Remarks (Applicable Manufacturer's Data Reports to be Attached) Functionallv tested oer 0251. VT-3 ore-service exam to be como/eted followina installation under 361 3 Revision 4 Page 2 of 2 MONTICELLO NUCLEAR GENERATING PLANT CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this REP& IP /~EQU~WM&HT

/JCIIV IN conforms to the rules on the ASME Code,Section XI. repairlreplacement Signed 1 . SE~ XI ISI C~ORD Owner or owner's Designee, Title Date PJ-J ff . DO7 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 ~)~&WOTA and employed by Cl~lzr~anu STC'~~ BOIIC-IZ S~JQF ~o&~.~&cric~r of NAPTFo~PD cj- have inspected the components described in this Owner's Report during the period 1' 1 Y /d6 to 7/12 /o 7 , 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 lnspector 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.

K--T A,,~I.JAA Commissions M5 l/b6 3 A , )d, 2 , hw oo Vo2f-Go Inspector's Signature National Board, Province and Endorsements Date JCr L,Yr It , 2-037 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 APPROVED (Signatures available in Master File)

NOTE This form may not address all items needed for documentation of a repairlreplacement program, see 4 Awl-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 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. 361 3 Revision 4 Page 1 of 2 MONTICELLO NUCLEAR GENERATING PLANT

1. Owner Xcel Energy Company Date 7/11/2007 Name 2. Plant Monticello Nuclear Generating Plant Sheet I of 2 Name 2807 W. Cnty. Rd. 75, Monticello, Minnesota 55362 WO 280592 Address Repair Organization P.O. No., Job No. etc. TITLE: 3. Work Performed By NMC/Xcel Energy Type Code Symbol Stamp n/a Company Name Authorization No. n/a 2807 W. Cnty. Rd. 75, Monticello, MN 55362 Expiration Date n/a Address OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 4. ldentification of System Spare - 20 Kip Snubber 5. (a) Applicable Construction Code USAS 531.1 9 1967 Edition Year Addenda No Addenda Code Case n/a (b) Applicable Edition of Section XI Utilized for Repairs or Replacement 2001 Edition, No Addenda

6. ldentification of Components Repaired or Replaced and Replacement Components

7. Description of Work Replaced valve manifold during rebuild PM. 8. Tests Conducted:

Hydrostatic Pneumatic Nominal Operating Pressure Other Pressure psi Test Temp " F Name of Component Valve Manifold Valve - Manifold APPROVED (Signatures available in Master File) Name of Manufacturer Bergen Paterson Bergen Paterson Manufacturer Serial No. 133 133 National Board No. n/a n/a Other ldentification n/a n/a Year Built un- known 2006 Repaired, Replaced or Replacement Replaced Replacement ASME Code Stamped YES NO IXJ ITEM 2006-23-004 1 9. Remarks I (Applicable Manufacturer's Data Reports to be Attached)

Functionally tested oer 0251. VT-3 pre-senlice exam to be comdeted followina installation under 361 3 Revision 4 Page 2 of 2 MONTICELLO NUCLEAR GENERATING PLANT CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this REP*II/RCRPCEHEN~

ACnUln conforms to the rules on the ASME Code,Section XI. repairlreplacement Signed SE~ %I I S\ boa Owner or Owner's Designee, Title 11 , 2007 Date + 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 I9 IUU~ s and employed by tJdRtForZO STC4ibc &?gll6% r+3 &f Cur~l~~tr(ff~T of !~AH$P~J~/J~

~7 have inspected the components described in this Owner's Report during the period If /LOT to 7/12. 107 , 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 lnspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report. Furthermore, neither the lnspector 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.

7/* A &L&~, Commissions DB tlf63 rs,n/,.i', hU 30 902 b -(a Inspector's Signature National Board, Province and Endorsements Date Toby 12, , LOO7 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 APPROVED (Signatures available in Master File)

ITEM 2006-23-0042 NOTE This form may not address all items needed for documentation of a repairlreplacement program, see I 4 Awl-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 I I 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. 361 3 Revision 4 Page 1 of 2 MONTICELLO NUCLEAR GENERATING PLANT

1. Owner Xcel Energy Company Name 2. Plant Monticello Nuclear Generating Plant Name 2807 W. Cnty. Rd. 75, Monticello, Minnesota 55362 Address TITLE: 3. Work Performed By NMC/Xcel Energy Company Name 2807 W. Cnty. Rd.

75, Monticello, MN 55362 Address OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 Date 7/11/2007 Sheet I of 2 WO 280592 Repair Organization P.O. No., Job No. etc. Type Code Symbol Stamp n/a Authorization No. n/a Expiration Date n/a 4. ldentification of System Spare - 20 Kip Snubber 5. (a) Applicable Construction Code USAS 831. I 1967 Edition Year Addenda No Addenda Code Case n/a (b) Applicable Edition of Section XI Utilized for Repairs or Replacement 2001 Edition, No Addenda 6. ldentification of Components Repaired or Replaced and Replacement Components

7. Description of Work Replaced valve manifold during rebuild PM. 8. Tests Conducted:

Hydrostatic Pneumatic Nominal Operating Pressure Other Pressure psi Test Temp OF Name of Component Valve Manifold Valve Manifold APPROVED (Signatures available in Master File) Name of Manufacturer Bergen Paterso n Bergen Paterson Manufacturer Serial No. 125 125 National Board No. n/a n/a Other ldentification n/a n/a Year Built un- known 2006 Repaired, Replaced or Replacement Replaced Replacement ASME Code Stamped YES 0 NO (XI o ITEM 2006-23-0042 I 9. Remarks (Applicable Manufacturer's Data Reports to be Attached)

Functionallv tested per 0251.

VT-3 pre-service exam to be completed followina installation under 361 3 Revision 4 Page 2 of 2 MONTICELLO NUCLEAR GENERATING PLANT work order TITLE: CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this REPA,(( /%FPLACQ&N T A~TIVI-~~ conforms to the rules on the ASME Code,Section XI. repairlreplacement - Signed -,~GcTX(I~~~QD Date If ,uo7 Owner or Owner's Designee, Title OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 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-t IOMFJO~A and employed by /I~p?f~gu STt'4h (3U/L6\R JFJ JF ~~~4~tVlC6f blnb?Pd-'JR~J ,LT have inspec ed the components described in this Owner's Report during the period t/ F 10'7 to 7 1 ll Id7 , 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 lnspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report. Furthermore, neither the lnspector 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 A-J-4'. Commissions MI I/&& J 4, b, r, /YX/ .W ~~28 - d;o Inspector's Signature National Board, Province and Endorsements Date zGLY iL , Lob7 APPROVED (Signatures available in Master File)

NOTE This form may not address all items needed for documentation of a repairlreplacement program, see 4 Awl-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 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. 361 3 Revision 4 Page 1 of 2 MONTICELLO NUCLEAR GENERATING PLANT 1. Owner Xcel Energy Company Date 7/19/2007 TITLE: Name 2. Plant Monticello Nuclear Generating Plant Sheet 1 of 2 Name 2807 W. Cnty. Rd. 75, Monticello, Minnesota 55362 WO 152929 Address Repair Organization P.O. No., Job No. etc. OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2

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. Identificationof System EDGEmerg.

Senlice Water(EDG-ESW), SpareP-Ill Pump, Class3 5. (a) Applicable Construction Code ANSI 631.1 I 1977 Edition Year Addenda Winter 19 78 Addenda Code Case n/a (b) Applicable Edition of Section XI Utilized for Repairs or Replacement 2001 Edition, No Addenda

6. ldentification of Components Repaired or Replaced and Replacement Components

7. Description of Work Repaired small crack in 1 intermediate bowl during rebuild.

Name of Component Spare P-I 1 I 8. Tests Conducted: Hydrostatic C] Pneumatic Nominal Operating Pressure 0 Other Pressure n/a psi Test Temp n/a " F APPROVED (Signatures available in Master File) Name of Manufacturer Johnston Other ldentification 02686-7 Manufacturer Serial No. Pump Assly OD 6702 National Board No.

n/a Year Built 2007 Repaired, Replaced or Replacement Repaired ASME Code Stamped YES NO u 0 ITEM 2006-23-0043 I 9. Remarks (Applicable Manufacturer's Data Reports to be Attached) Pump meets requirements of Design Change 920300. During rebuild, excavated small crack in 1 intermediate bowl's impeller shroud, performed NDE to verify removal, and repaired by welding. No PSI or Pressure Testing required per this activity.

Pre-senlice testing will be performed under separate work order when removed from spare stock and installed in plant. CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this 'REPA IA /RPL~CEM~T A~~lutry conforms to the rules on the ASME Code,Section XI. repairlreplacement C Signed , SEC~INXI IS( Date Owner or Owner's Designee, Title 361 3 Revision 4 Page 2 of 2 MONTICELLO NUCLEAR GENERATING PLANT 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/~x/rC t 074 and employed by /-lqfltod/ll

~~c-nrsrbvl~t~

zt~'of Co~~~CT/rc.l[

of ~I.-+L~FRCI,CT have inspected he components described in this Owner's Report during the period I/ Y /a7 1. to 7/13 07 , 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 lnspector 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 A &dL* Commissions 1/13 //&j~ 3 , A , &,.I h Q 00 ~OLJ-CO Inspector's Signature National Board, Province and Endorsements Date Ycl LY 23 , 2607 TITLE: APPROVED (Signatures available in Master File) OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 ITEM 2007-23-0044 NOTE 1: This form may not address all items needed for documentation of a repairlreplacement program, see I 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 I I 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. 361 3 Revision 4 Page 1 MONTICELLO NUCLEAR GENERATING PLANT 1. Owner Xcel Energy Company Date 7/20/2007 Name 2. Plant Monticello Nuclear Generating Plant Sheet I of 3 Name 2807 W. Cnty. Rd. 75, Monticello, Minnesota 55362 WO 154343, EC-7462 Address Repair Organization P.O. No., Job No. etc. TITLE: 3. Work Performed By NMC /Xcel Energy Type Code Symbol Stamp n/a Company Name Authorization No. n/a 2807 W. Ctv Rd 75, Monticello.

MN 55362 Ex~iration Date n/a OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 Address 4. ldentification of System Reactor Vessel (RPV), Wide Range Flux Monitor Housing, Class I 5. (a) Applicable Construction Code ASME Section 111 7 1965 Edition Year Addenda Summer 1966 Addenda Code Case n/a (b) Applicable Edition of Section XI Utilized for Repairs or Replacement 2001 Edition, No Addenda 6. ldentification of Components Repaired or Replaced and Replacement Components

7. Description of Work Removed (2) abandoned WRFM's, replaced with blind flanges including bolting Name of Component WRFM 12-45 Blind Flange soare 12-45 WRFM 20-05 Blind Flange soare7G05 SEE 8. Tests Conducted:

Hydrostatic Pneumatic Nominal Operating Pressure Other Pressure 1000 psi Test Temp 181.8 OF Name of Manufacturer GE Reuter Sfokes GE Reuter Stokes GE Reuter Stokes GE Reuter Stokes PAGE ) 3087 (DOCUMENT CHANGE, HOLD AND COMMENT FORM) incorporated:

3 APPROVED (Signatures available in Master File) Manufacturer Serial No. Marking 6549798 s/n 11- 76748-1 Marking 6549 796 s/n 12- 76748-1 2 -- -- FQR ADMIN,!$TRATIVE, R~SD SLID~: PRGE 1 Assoc Ref: PRGE I SR: N 1 Freq: 0 yrs - USE ONLY ' ARMS: 3613 I Doc Tv~e: REF ONLY I Admin initials:

I Date: National Board No.

n/a n/a n/a n/a FOR 1 Other ldentification Ht. # 132567 Hf. # 2F353 Ht. # 132567 Hf. # 2F353 ADD'L Year Built 1984 2007 1984 2007 ITEMS Repaired, Replaced or Replacement Replaced Replacement Replaced Replacement ASME Code Stamped YES NO IXI IXI Monticello Nuclear Generating Plant Form NIS-2 Continuation Sheet ITEM 2007-23-0044 Page2 of 3 WO No. 154343 Name of Component WFRM 12-45 (4) capscre ws Blind Flange spare 12-45 (4) capscre ws WFRM 20-05 (4) capscre ws Blind Flange spare 20-05 (4) capscre ws Name of Manufacturer GE Reuter Stokes GE Reuter Stokes GE Reuter Stokes GE Reuter Stokes Manufacturer Serial No.

n/a n/a n/a n/a National Board No. n/a n/a n/a n/a Repaired, Replaced or Replacement replaced replacement replaced replacement Other Identification Ht. # 85483 Ht. # 96903 Ht. # 85483 Ht. # 96903 Year Built 1984 2007 1984 2007 ASME Code Stamped Yes No X X X X ITEM 2007-23-0044 I 9. Remarks (Applicable Manufacturer's Data Reports to be Attached) Replaced abandoned wide range flux monitors with blind flanges to restore the original configuration per Engineering Change (EC) 7462. No PSI required. System leakage test with VT-2 performed during 0255-20-llC-2.

IW ,1,,1,, CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this T~FA~R/ R*i'~acdv\-

dfllv try conforms to the rules on the ASME Code,Section XI.

repairlreplacement Signed w, &C~OLI~/ IS\ cooeo. 0ate PJ 2-l , m7 Owner or Owner's Designee, Title 361 3 Revision 4 PageM3al:3 MONTICELLO NUCLEAR GENERATING PLANT 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 AIkM s o7A and employed by )(A AT ~~pr, 57'c-&13 do/ /LC% 2 *r crF co~k/bct IC~T of t-f/tpi-hBu, e 7 have inspected the components described in this Owner's Report during the period 3 123 117 to 7/~3 107 , 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 lnspector 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.

742 dA4S Commissions h/f NX 7 A, US 4~ o d l/az ,f- -co Inspector's Signature National Board, Province and Endorsements Date JULY 23 , Zdd? TITLE: APPROVED (Signatures available in Master File) OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 ITEM 2007-23-0045 I NOTE 1: This form may not address all items needed for documentation of a repairlreplacement program, see 4 Awl-09.04.03 (ASME SECTION XI REPAIRIREPLACEMENT PROGRAM) for further guidance.

361 3 Revision 4 . Page I of 2 MONTICELLO NUCLEAR GENERATING PLANT 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 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. TITLE: 1. Owner Xcel Energy Company Date 7/23/2007 Name 2. Plant Monticello Nuclear Generating Plant Sheet I of 2 Name 2807 W. Cnty. Rd. 75, Monticello, Minnesota 55362 WO 314220, EC-9174 Address Repair Organization P.O. No., Job No. etc. OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 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. ldentification of System Main Steam (MST)); Loops A, B, C, D; Class I 5. (a) Applicable Construction Code ANSI 831.7 1 1977 Edition Year Addenda Winter 1978 Addenda Code Case n/a (b) Applicable Edition of Section XI Utilized for Repairs or Replacement 2001 Edition, No Addenda 6. ldentification of Components Repaired or Replaced and Replacement Components

7. Description of Work Spot welded 64 strain gages to Main Steam Piping for EC-9174 Name of Component Strain Gage PSI-1 8'LED =in Gage PS2- 18"-ED Strain Gage PS3- 1 8"-ED Sfrain Gage PS4- 18"-ED 8. Tests Conducted:

Hydrostatic Pneumatic C] Nominal Operating Pressure Other Pressure n/a psi Name of Manufacturer HlTEC Prod~cf HlTEC Product HlTEC Product HlTEC Product Test Temp n/a " F Manufacturer Serial No. n/a n/a n/a n/a National Board No.

n/a n/a n/a n/a APPROVED (Signatures available in Master File) Other ldentification See Remarks See Remarks See Remarks See Remarks Year Built 2007 2007 2007 2007 Repaired, Replaced or Replacement Repair Repair Repair Repair ASME Code Stamped YES CI CI NO *3 ISI ISI IXI ITEM 2007-23-0045 I 9. Remarks (Applicable Manufacturer's Data Reports to be Attached)

In support of Engineering Change (EC) 91 74, 64 (total) Hastaloy X strain gages and covers were spot welded by capacitive discharge methods to the main steam piping per ASME Section 111 2001 Edition NB-4311.2 provisions.

8 strain gages were installed around the circumference at 2 location on each the 4 loops of main steam piping. The strain gages are part of a new data acquisition system that will provide dynamic pressure measurement for current conditions to compare to increased flow associated with future extended power uprate. With the exception of having the strain gages attached to it, the Main Steam system is not affected. The HlTEC strain gage part number is HB WAK-35-250-6-IOFG-SHIELD.

No pressure testing or PSI was required.

361 3 Revision 4 Page 2 of 2 MONTICELLO NUCLEAR GENERA TlNG PLANT CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this REPAIR /U~PLAOEMW IT ACTIU ITY conforms to the rules on the ASME Code,Section XI. repairlreplacement Signed SECTION%( \S) Goo Owner or Owner's Designee, Title 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 /cl6~&65 bT4 and employed by ,BA rcir~nll s~t~dh .UO/LC& d rS 01~ cawd'~ j~cq,-of +idn r FV/~~/JJCI-have inspected t e components described in this Owner's Report during the period Y //kid 7 to 71LJlcr7 , 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 lnspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report. Furthermore, neither the lnspector 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.

?lqN 4 &- Commissions

B /I $6 2 2 h WOO Y o L X - CU Inspector's Signature National Board, Province and Endorsements Date ThLY 2-,r , 2-Ua7 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 APPROVED (Signatures available in Master File)

ITEM 2007-23-0046 NOTE This form may not address all items needed for documentation of a repairlreplacement program, see I 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 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. 361 3 Revision 4 Page 1 of 2 MONTICELLO NUCLEAR GENERATING PLANT 1. Owner Xcel Energy Company Date 7/20/2007 Name 2. Plant Monticello Nuclear Generating Plant Sheet 1 of 2 Name TITLE: 2807 W. Cnty. Rd. 75, Monticello, Minnesota 55362 WO 288806 Address Repair Organization P.O.

No., Job No. etc. OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 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. ldentification of System Core Spray (CSP), Min Flow Loop B, Class 2 5. (a) Applicable Construction Code ANSI B31.

I 1 1977 Edition Year Addenda Winter '78 Addenda Code Case n/a (b) Applicable Edition of Section XI Utilized for Repairs or Replacement 2001 Edition, No Addenda 6. ldentification of Components Repaired or Replaced and Replacement Components

7. Description of Work Removed/ Reinstalled piping due to interference with adjacent work.

Name of Component TW9-2 1/2"- HE 8. Tests Conducted:

Hydrostatic Pneumatic Nominal Operating Pressure (XI Other Pressure 300 psi TestTemp n/a OF ) 3087 (DOCUMENT CHANGE, HOLD AND COMMENT FORM) incorporated:

I Name of Manufacturer unknown Manufacturer Serial No. n/a National Board No. n/a APPROVED (Signatures available in Master File) - - FOR AJMINISTRATIVE Reso Su~v: PRGE I Assoc Ref: PRGE I SR: N I Frea: 0 vn ' ' ^US~ONLY ,+2 I Doc Tvoe:

REF ONLY I Admin initials:

I Date: I Other ldentification n/a Year Built 1969 Repaired, Replaced or Replacement Repaired ASME Code Stamped YES NO ITEM 2007-23-0046 I 9. Remarks (Applicable Manufacturer's Data Reports to be Attached) Piping removed and reinstalled due to ingress /egress interference with adjacent Torus interior work. Also disassembled and reassenbled associated supports TWH- 7 35 and TWH- 736. RT performed following reinstallation of piping. Owner-elected VT-3 performed on supports. (reference IS1 Report BOP-VT-07-053 and

-054) System leakage test with VT-2 performed per work order PMT attachment.

361 3 Revision 4 Page 2 of 2 MONTICELLO NUCLEAR GENERATING PLANT CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this REPA\R /RE~UW~T Am~y conforms to the rules on the ASME Code,Section XI. reljairlreplacement Signed , SECTUN X( 61 coo@ Date 20 , 2007 Owner or Owner's Designee, Title 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 /\-r cicrwF5b 774 and employed by ClnflF-fiP ITt-hh gd/irQ" rf-J ~Fcowl~pl-lctri of HqfiWdO,CT have inspected the components described in this Owner's Report during the period 3 /9 /u7 to 71 22 /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 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.

h A UC 1,. Commissions 116~3 A , /$S ~ln/ oo YO ~g -cd Inspector's Signature National Board, Province and Endorsements Date .Tl/L'f 23 , Zoo7 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 APPROVED (Signatures available in Master File)

ITEM 2007-23-0047 I NOTE This form may not address all items needed for documentation of a repairlreplacement program, see 4 AWI-09.04.03 (ASME SECTION XI REPAIRIREPLACEMENT PROGRAM) for further guidance.

361 3 Revision 4 Page 1 of 2 MONTICELLO NUCLEAR GENERATING PLANT 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 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. TITLE: 1. Owner Xcel Energy Company Date 7/20/2007 Name 2. Plant Monticello Nuclear Generating Plant Sheet 1 of 2 Name 2807 W. Cnty. Rd. 75, Monticello, Minnesota 55362 WO 267368 Address Repair Organization P.O. No., Job No. etc. OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 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. ldentification of System Reactor Head Vent, Flange

3 (2" Cavity Flange), Class 1

5. (a) Applicable Construction Code ANSI 831. I 9 1977 Edition Year Addenda Winter1978 Code Case n/a (b) Applicable Edition of Section XI Utilized for Repairs or Replacement 2001 Edition, No Addenda 6. ldentification of Components Repaired or Replaced and Replacement Components - 7. Description of Work Like for like replacement of I stud and 2 nuts due to disassembly damage. 8. Tests Conducted:

Hydrostatic Pneumatic Nominal Operating Pressure Other Pressure n/a psi Test Temp n/a " F Name of Component (I) 5/811 Stud (I) 518" Stud (2) 5/8" Nuts (2) 5/8" Nuts APPROVED (Signatures available in Master File)

Name of Manufacturer Nova Nova Nova Nova Manufacturer Serial No. n/a n/a n/a n/a National Board No.

n/a n/a n/a n/a Other ldentification Ht. # 7404456 Ht. # 2301 1 I Ht. # 887035 Ht. # 7220464 Year Built 2005 2007 2005 2007 Repaired, Replaced or Replacement Replaced Replacement Replaced Replacement ASME Code Stamped YES 0 n NO IXI IXJ IXJ IXI ITEM 2007-23-0047 I 9. Remarks (Applicable Manufacturer's Data Reports to be Attached)

VT-7 PSI performed on replacement bolting.

No pressure testing required.

361 3 Revision 4 Page 2 of 2 MONTICELLO NUCLEAR GENERATING PLANT CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this R~PA\R /R~~*-E~JT An\~q conforms to the rules on the ASME Code,Section XI.

repairlreplacement r . Signed -, SECTION XI 18 \ born. Date Owner or Owner's Designee, Title 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 htrvrv~~d 73 and employed by 60izY) s76 4h frolr tY rrl .IF CWM~TICLIT of H,~ett% ~2 /J , c T have inspected the components described in this Owner's Report during the period '11 3 /v) to '7(~l(/7 , 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 lnspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report. Furthermore, neither the lnspector 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- Ah%- Commissions

~8 icfi ,I A J &W & qdu-co Inspector's Signature National Board, Province and Endorsements Date Tct~Lf ti9 , 2307 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 APPROVED (Signatures available in Master File)

ITEM 2007-23-0048 NOTE This form may not address all items needed for documentation of a repairlreplacement program, see I 4 AWI-09.04.03 (ASME SECTION XI REPAIRIREPLACEMENT PROGRAM) for further guidance.

I I NOTE 2: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8-112 in x I I 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. 1. Owner Xcel Energy Company Date 7/21/2007 Name 2. Plant Monticello Nuclear Generating Plant Sheet 1 of 2 Name 2807 W. Cnty. Rd. 75, Monticello, Minnesota 55362 WO 314233 Address Repair Organization P.O. No., Job No. etc. 361 3 Revision 4 Page 1 of 2 MONTICELLO NUCLEAR GENERATING PLANT 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 TITLE: 4. Identification of System Reactor Core Isolation Cooling (RCIC), Steam Supply, Class 2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 5. (a) Applicable Construction Code ANSI 631. I 1 1977 Edition Year Addenda Winter '78 Addenda Code Case n/a (b) Applicable Edition of Section XI Utilized for Repairs or Replacement 2001 Edition, No Addenda 6. ldentification of Components Repaired or Replaced and Replacement Components

7. Description of Work Removed / Reinstalled piping due to interference with adjacent work.

Name of Component PSl7-3"ED

8. Tests Conducted:

Hydrostatic Pneumatic Nominal Operating Pressure IXJ Other Pressure 1040 psi Test Temp n/a " F Name of Manufacturer unknown APPROVED (Signatures available in Master File) Manufacturer Serial No. n/a National Board No. n/a Other ldentification n/a Year Built 2001 Repaired, Replaced or Replacement Repaired ASME Code Stamped YES 17 NO

9. Remarks (Applicable Manufacturer's Data Reports to be Attached) Piping removed and reinstalled due to interference with adjacent MSlV AO-2-86D actuator maintenance activities. Also disassembled and reassembled associated supports PSH-I 14, PSH- 1 15, and SR-564. 361 3 Revision 4 Page 2 of 2 MONTICELLO NUCLEAR GENERA TlNG PLANT RT performed following reinstallation of piping.

No PSI required. System leakage test with VT-2 performed per work order PMT attachment

/ work plan. TITLE: CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this REQA~R(REP~A~E~E;NT Ac~rvt~y conforms to the rules on the ASME Code,Section XI. repairlreplacement Signed m- ,,~ECT~DN IS1 bw . Owner or Owner's Designee, Title OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 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 )uwf on and employed by 57c~1- &)I~C% $9~ CO~VFTICLIT of fir 1=0fu , c r have inspected the components described in this Owner's Report during the period 3 It1 lo7 to 7/21 1d-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 lnspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report. Furthermore, neither the lnspector 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 42wL.L~ Commissions p,p /1&63 A ,%J by OQ~ 2~ Inspector's Signature National Board, Province and Endorsements Date Jwy 22, , 2037 APPROVED (Signatures available in Master File)

ITEM 2007-23-0049 NOTE 1: This form may not address all items needed for documentation of a repairlreplacement program, see I 4 AWI-09.04.03 (ASME SECTION XI REPAIRIREPLACEMENT PROGRAM) for further guidance.

1 I 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 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. 1. Owner Xcel Energy Company Date 7/20/2007 Name 2. Plant Monticello Nuclear Generating Plant Sheet I of 2 Name 2807 W. Cnty. Rd. 75, Monticello, Minnesota 55362 WO 322082 Address Repair Organization P.O. No., Job No. etc. 361 3 Revision 4 Page 1 of 2 MONTICELLO NUCLEAR GENERA TING PLANT 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 TITLE: Address OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 4. ldentification of System Residual Heat Removal Senfice Water (RHRSW, Loop B, Class 3 5. (a) Applicable Construction Code ANSI 831.1 1977 Edition Year Addenda Winter 1978 Addenda 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

7. Description of Work Replaced approx 4 ft of A-106 Gr. B pipe (line designation SW10-18"-GF located in the intake) like-for-like by welding due to localized ID corrosion (replacement pipe built 2000, installed 2007).

8. Tests Conducted:

Hydrostatic Pneumatic Nominal Operating Pressure Other Pressure 253 psi Test Temp n/a " F APPROVED (Signatures available in Master File) Name of Component S W10-18"- GF SW10-18"-

GF Manufacturer Serial No. n/a n/a Year Built 1969 2007 Name of Manufacturer n/a Dubose Repaired, Replaced or Replacement Replaced Replacement ASME Code Stamped National Board No. n/a n/a YES Other Identification n/a HMA83222 NO IX] IX]

ITEM 2007-23-0049 I 9. Remarks (Applicable Manufacturer's Data Reports to be Attached)

NDE of welds performed as applicable.

Support SR-385 was also disassembled and re-assembled to accommodate access for the piping replacement. VT-3 PSI performed following re-installation. System leakage test with VT-2 in lieu of a hydro per IWA-4540(a)(2) per WO PMT attachment.

361 3 Revision 4 PageJ20f 2 wMb MONTICELLO NUCLEAR GENERATING PLANT CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this R*PAIR/R~PW~EMENT ,L)c~~utry conforms to the rules on the ASME Code,Section XI.

repairlreplacement Signed ,SECI-IONX~

IS1 Coo- Date ~ 20 , 2007 Owner or dwner's Designee, Title 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 AIM- ~OV and employed by khn~~saa n6.m no/~c-fl J~J #F WUU~C?IL~~

of ~MIYFOW ,u4 have inspected the components described in this Owner's Report during the period 3 / tz b7 to 3 (LO 1u7 , 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 lnspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective megsure 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-J-b Commissions p t J 3 ~uooqotk -cd Inspector's Signature National Board, Province and Endorsements Date Tqcr 2u , LUO~ OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 APPROVED (Signatures available in Master File)

ITEM 2007-23-0050 NOTE This form may not address all items needed for documentation of a repairlreplacement program, see I 4 Awl-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 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. 361 3 Revision 4 Page 1 of 2 MONTICELLO NUCLEAR GENERATING PLANT 1. Owner Xcel Energy Company Date 7/8/2007 TITLE: Name 2. Plant Monticello Nuclear Generating Plant Sheet I of 2 Name 2807 W. Cnty.

Rd. 75, Monticello, Minnesota 55362 WO 141889 Address Repair Organization P.O. No., Job No. etc.

OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 3. Work Performed By NMCKcel Energy Type Code Symbol Stamp n/a Company Name Authorization No. n/a 2807 W. Cnty. Rd. 75, Monticello, MN 55362 Expiration Date n/a Address 4. ldentification of System Spare - 130 Kip Snubber

5. (a) Applicable Construction Code USAS 831.1 1 1967 Edition Year Addenda No Addenda Code Case n/a (b) Applicable Edition of Section XI Utilized for Repairs or Replacement 2001 Edition, No Addenda 6. ldentification of Components Repaired or Replaced and Replacement Components

7. Description of Work Replaced main cylinder during rebuild.

Name of Component Main Cvlinder Main Cvlinder 8. Tests Conducted:

Hydrostatic Pneumatic Nominal Operating Pressure Other [XJ Pressure psi Test Temp " F Name of Manufacturer Bergen Paterson Bergen Paterson APPROVED (Signatures available in Master File)

Manufacturer Serial No. 400 400 National Board No. n/a n/a Other ldentification n/a n/a Year Built un- known 2007 Repaired, Replaced or Replacement Replaced Replacement ASME Code Stamped YES 0 NO IXJ IXJ -

ITEM 2007-23-0050 I 9. Remarks (Applicable Manufacturer's Data Reports to be Attached)

Functional test oer 0251. VT-3 to be com~leted when installed.

361 3 Revision 4 Page 2 of 2 MONTICELLO NUCLEAR GENERATING PLANT CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this aeQ~~cpMnvT conforms to the rules on the ASME Code,Section XI. repairlreplacement Signed ' . SccsX XSI born. Date Owner or 0wnei's Designee, Title 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~hn/es OTA and employed by @A n7~oLD 5164fi Bolltn .2 $x o F Cuukrrrlc~

7 of H~nTfaCZA, C7 have inspected the components described in this Owner's Report during the period J / 23 107 to ,719 107 , 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 lnspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report. Furthermore, neither the Inspector nor his employer SHALL be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.

4 h. omm missions I IJ~ 3 A", /v, 5 , yl u 40 w~k-ccl Inspector's Signature National Board, Province and Endorsements Date T~-cL)/ 9 , 2007 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 APPROVED (Signatures available in Master File)

ITEM 2007-23-0051 NOTE This form may not address all items needed for documentation of a repairlreplacement program, see I 4 Awl-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 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. 361 3 Revision 4 Page 1 of 2 MONTICELLO NUCLEAR GENERATING PLANT 1. Owner Xcel Energy Company Date 7/18/2007 TITLE: Name 2. Plant Monticello Nuclear Generating Plant Sheet 1 of 2 Name 2807 W. Cnty. Rd. 75, Monticello, Minnesota 55362 WO 288859, EC-775 Address Repair Organization P.O. No., Job No. etc. OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 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. ldentification of System Core Spray (CSP), Loop 5, Class 2 5. (a) Applicable Construction Code ANSI 531.1 9 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. ldentification of Components Repaired or Replaced and Replacement Components

7. Description of Work Like for like replacement of 14 bonnet studs and 28 nuts on valve MO-1742 8. Tests Conducted:

Hydrostatic Pneumatic Nominal Operating Pressure Name of Component MO- 1 742 studs (14) MO- 1 742 studs (1 4) MO- 1 742 nuts (28) MO- 1 742 nuts (28) Other Pressure n/a psi Test Temp n/a " F ( 3087 (DOCUMENT CHANGE, HOLD AND COMMENT FORM) incorporated:

I Name of Manufacturer Wm Po well Valve Cardinal Wm Po well Valve Nova APPROVED (Signatures available in Master File) -.- - Manufacturer Serial No. Valve dn 7 5876 n/a Valve dn 58767 n/a ppppp F$R AD,MINISTWTlVE, Resu SUUV: PRGE I Assoc Ref:

PRGE I SR: N I Freq: 0 vrs " USE ONLY ""* :, I Doc Tvpe: REF ONLY I Admin initials:

I Date: I National Board No.

n/a n/a n/a n/a Other ldentification n/a 042339 n/a B87035 Year Built 1969 2007 1969 2007 Repaired, Replaced or Replacement Replaced Replacement Replaced Replacement ASME Code Stamped YES NO IXI IXI ITEM 2007-23-0051

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

Like for like replacement of studs and nuts due to damage during removal in support of activities for Engineering Change (EC) 775. Studs built 1984, installed 2007. Nuts built 2002, installed 2007. No pressure testing or PSI required, IST stroke time testing and position indication test performed per Work Order preoperational testing instructions.

361 3 Revision 4 Page 2 of 2 MONTICELLO NUCLEAR GENERATING PLANT CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this EQAIE/REP~M~

htv ri-y conforms to the rules on the ASME Code,Section XI. repairlreplacement

Signed I-, SE~ * &OW Date ~ [ q , Owner or owner's Designee, Title 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 +II~IJF 5074 and employed by U+nrFd'JRJ sI'c'A~ /3alLEK ri$ dF cdh/k/FtTlchT of j/~~~FoMtf,tr have inspected the components described in this Owner's Report during the period 3 /td/u'.l to 1 123 147 , 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 lnspector nor his employer SHALL be liable in any manner for any persqnal injury of property damage or a loss of any kind arising from or connected with this inspection.

Commissions vh /(fi J A, w,S rc-rw O~Y uzf--to Inspector's Signature National Board, Province and Endorsements Date if-qcy 2.2 - , Zdu7 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 APPROVED (Signatures available in Master File)

ITEM 2007-23-0052 I NOTE This form may not address all items needed for documentation of a repairlreplacement program, see 4 Awl-09.04.03 (ASME SECTION XI REPAIRIREPLACEMENT PROGRAM) for further guidance. 361 3 Revision 4 Page 1 of 2 MONTICELLO NUCLEAR GENERATING PLANT NOTF 7. S~lnnlemantal aheek in fnrm nf lizk akatchaa nr rlrawinna mav ha 11a4 nrnvirlarl II\ ai7n ic TITLE: ..-. - -. --rr.-...-..--.

-..--- ... .- .... -. ..-I, -..---..--, -. -.-.....a-

... " J -- ----, r.-..--- 1.1 -.-" .-. 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. OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 1. Owner Xcel Energy Company Date 7/18/2007 Name 2. Plant Monticello Nuclear Generating Plant Sheet I of 2 Name 2807 W. Cnty. Rd. 75, Monticello, Minnesota 55362 WO 289152, EC-775 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. ldentification of System Residual Heat Removal (RHR), B Loop, Valve MO-1987, Class 2 5. (a) Applicable Construction Code ANSI 831.1 1 1977 Edition Year Addenda Winter1978Addenda Code Case n/a (b) Applicable Edition of Section XI Utilized for Repairs or Replacement 2001 Edition, No Addenda 6. ldentification of Components Repaired or Replaced and Replacement Components

7. Description of Work Replaced 18 Studs and 36 Nuts that were damaged during disassembly, 8. Tests Conducted:

Hydrostatic Pneumatic Nominal Operating Pressure Other Pressure n/a psi Test Temp n/a " F ) 3087 (DOCUMENT CHANGE, HOLD AND COMMENT FORM) incorporated:

I Name of Component M0-1987 MO-1987 Studs (12) MO-1987 . Studs (6) M0-1987 MO-1987 Nuts (36) National Board No.

n/a n/a n/a n/a n/a APPROVED (Signatures available in Master File) Name of Manufacturer unknown Nova Nova unknown Nova : FPR PIDVINISTRATIVE , Resp Supv: PRGE 1 Assoc Ref: PRGE I SR: N I Freq: 0 vrs ,&:USE ~NLY;~*+~

(4 ARMS: 3613 I Doc Tvpe: REF ONLY I Adrnin initials:

I Date: Other ldentification n/a Ht. #240902 Ht. # 53410 n/a Ht. tit8994826 Manufacturer Serial No. n/a n/a n/a n/a n/a I Year Built 1969 2007 2007 2007 2007 Repaired, Replaced or Replacement Replaced Replacement Replacement Replaced Replacement ASME Code Stamped YES NO IXI IXI IXI IXI IX]

ITEM 2006-23-001 6 9. Remarks I (Applicable Manufacturer's Data Reports to be Attached)

EC-775 replaces several Rotork valve actuators with Limitorque actuators.

No PSI or pressure testing required for bolting replacement. Stroke Time and Position Indication testing for IST performed per work order PMT attachment.

361 3 Revision 4 Page 2 of 2 MONTICELLO NUCLEAR GENERATING PLANT CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this RE+~~R/RE~W~?MFW AC~U by conforms to the rules on the ASME Code,Section XI. repairlreplacement Signed -. SECTXI COORD Date , 2007 Owner dr 0wne'r's Designee, Title 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 Islv&-so7d and employed by rlfi~ r ~i5 97~~ O/I/LCP J~x s~ hwmc rrcur of H~~TFPKB , cT have inspected the components described in this Owner's Report during the period ,I /26/07 to ~/ZL/O~ , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section 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 lnspector 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.

LAAJw~ Commissions v,a I~~LJ A , u 2 AW LLOL&-CU Inspector's Signature National Board, Province and Endorsements Date TQLY LL , 2307 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 APPROVED (Signatures available in Master File)

ITEM 2007-23-0053 NOTE This form may not address all items needed for documentation of a repairlreplacement program, see I 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 (I) 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. 361 3 Revision 4 Page 1 of 2 MONTICELLO NUCLEAR GENERATING PLANT 1. Owner Xcel Energy Company Date 7/18/2007 Name 2. Plant Monticello Nuclear Generating Plant Sheet 1 of 2 Name 2807 W. Cnty. Rd. 75, Monticello, Minnesota 55362 WO 289154 Address Repair Organization P.O. No., Job No, etc. TITLE: 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 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 4. ldentification of System Residual Heat Removal (RHR), Div 11, Class 2 5. (a) Applicable Construction Code ANSI B31. I 1977 Edition Year Addenda Winter 1978 Addenda Code Case n/a (b) Applicable Edition of Section XI Utilized for Repairs or Replacement 2001 Edition, No Addenda

6. ldentification of Components Repaired or Replaced and Replacement Components

7. Description of Work Replacement of disc and weld connecting the steel tube portion of the skirt to the disc in valve MO-2009 (replacement built 1989, installed 2007).

Name of Component MO-2009 Disc MO-2009 Disc 8. Tests Conducted:

Hydrostatic Pneumatic Nominal Operating Pressure Other Pressure n/a psi Test Temp n/a " F Name of Manufacturer Anchor Darlina Anchor Darlina APPROVED (Signatures available in Master File)

Manufacturer Serial No. n/a n/a National Board No. n/a n/a Other ldentification n/a /-/#A34626 Year Built 1989 1989 Repaired, Replaced or Replacement Replaced Replacement ASME Code Stamped YES NO ITEM 2007-23-0053 I 9. Remarks (Applicable Manufacturer's Data Reports to be Attached)

Disc replaced to accommodate maintenance activities in support of EC-775 to replace the stem and actuator.

No PSI or pressure testing required for internal valve components.

ISTposition indication (PIT) and stroke time testing (ST0 and STC) completed per work order Testing Instruction.

361 3 Revision 4 Pagesof 2 +$ , MONTICELLO NUCLEAR GENERATING PLANT CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this R~PA~Q /REPL~-ENT kmu 1-r~ conforms to the rules on the ASME Code,Section XI. repairlreplacement Signed p, k~ XI I SI beg Owner or Owner's Designee, Title 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 ?I ILJUC^ gal2 and employed by JIAI~TF~RIJ Jft\Ah #@~GX ~+C~WMFCT~CR~

of HfiCSARD CT have inspected the components described in this Owner's Report during the period 3 /z6 10 to 3/47 , 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 lnspector 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.

f/- A ~~LL,A* Commissions ,Up 1cr6 3 A, r(/, j AX/ 00 40~t-td Inspector's Signature National Board, Province and Endorsements Date TbLy W , Lo07 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 APPROVED (Signatures available in Master File)

ITEM 2007-23-0054 NOTE This form may not address all items needed for documentation of a repairlreplacement program, see I 4 Awl-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 (I) size is 8-112 in x I I 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. 361 3 Revision 4 Page I of 2 MONTICELLO NUCLEAR GENERATING PLANT

1. Owner Xcel Energy Company Date 7/18/2007 Name L TITLE: 2. Plant Monticello Nuclear Generating Plant Sheet I of 2 Name 2807 W. Cnty. Rd. 75, Monticello, Minnesota 55362 WO 289151, EC-775 Address Repair Organization P.O. No., Job No, etc. OW'NER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 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. ldentification of System Core Spray (CSP), Loop B, Class 2 5. (a) Applicable Construction Code ANSI 831.1 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. ldentification of Components Repaired or Replaced and Replacement Components - 7. Description of Work Welding on MO-1750 disc nut to disc for disassembly/reassembly.

8. Tests Conducted:

Hydrostatic Pneumatic Nominal Operating Pressure Other Pressure n/a psi Test Temp n/a OF APPROVED (Signatures available in Master File)

Name of Component MO- 1 750 d~sc Manufacturer Serial No. n/a Name of Manufacturer Anchor Darlina National Board No. n/a Other Identification n/a Year Built 1969 Repaired, Replaced or Replacement Repair ASME Code Stamped YES NO IXI ITEM 2007-23-0054 I 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 Engineering Change (EC) 775. No pressure testing or PSI required.

/ST position indication testing was performed per work order preoperational testing instructions.

361 3 Revision 4 Page 2 of 2 MONTICELLO NUCLEAR GENERATING PLANT CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this amIR/~~~*tW AcrlVf~~ conforms to the rules on the ASME Code,Section XI. repairlreplacement Signed . S~crXl 1st boa Owner or ~wner's'~esignee, Title Date p, \7 , 2007 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 ~II~/A/E J 3TA and employed by ficrlhflTF0~4 g'rcdh ~~DJICPX'

~'tt o~ ccrww~c~/c hi of p~~ttt f6& U, CT have inspected the components described in this Owner's Report during the period 3 /2l to 7(1~(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 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 lnspector 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 ALL, Commissions A/(J 1~ 6% 3 A ,/e s /Y~V 00 VO.L~~-CO Inspector's Signature National Board, Province and Endorsements Date TCcLY 22 , 2Jd7 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 APPROVED (Signatures available in Master File)

ITEM 2007-23-0056 NOTE 1: This form may not address all items needed for documentation of a repairlreplacement program, see I 4 Awl-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 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. 361 3 Revision 4 Page 1 of 2 MONTICELLO NUCLEAR GENERATING PLANT 1. Owner Xcel Energy Company Date 7/23/2007 TITLE: Name 2. Plant Monticello Nuclear Generating Plant Sheet 1 of 2 Name OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 2807 W. Cnty. Rd. 75, Monticello, Minnesota 55362 WO 322070 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. ldentification of System Automatic Pressure Relief (APR); Class I 5. (a) Applicable Construction Code ANSI 831.1 9 1977 Edition Year Addenda Winter1978Addenda 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

7. Description of Work Replaced Main Stage Body for RV-2-71 C with rebuilt spare

8. Tests Conducted:

Hydrostatic Pneumatic Nominal Operating Pressure Name of Component Mag Stage Main Stage Bodv Other C] Pressure n/a psi Test Temp n/a OF 1 3087 (DOCUMENT CHANGE, HOLD AND COMMENT FORM) incorporated:

3 Name of Manufacturer Target Rock Target Rock APPROVED (Signatures available in Master File) Manufacturer Serial No. 1458 53 . - FOR#@~NW?ATIM Resp Supv: PRGE I Assoc Ref:

PRGE I SR: N I Freq: 0 yrs "/ 7 BE ONkL'fi Mm I Doc Tv~e: REF ONLY I Admin initials:

I Date: I National Board No. n/a n/a Other ldentification Year Built 2005 2007 Repaired, Replaced or Replacement Replaced Replacement ASME Code Stamped YES C] C] NO IXI IXI ITEM 2007-23-0056 I 9. Remarks (Applicable Manufacturer's Data Reports to be Attached) Replacement was preemptive and valve showed no signs of leakage at normal operating conditions.

Though no pressure test is required per Relief Request #7, a VT-2 was performed as part of the RCPB System Leakage Test 0255-20-116-2.

361 3 Revision 4 Page 2 of 2 MONTICELLO NUCLEAR GENERATING PLANT -

CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this rb,, :F/~~/rcrrrAP&~:~:cs conforms to the rules on the ASME Code,Section XI. I rebair~rep~acement Hh Signed , Srcno~ %I IS1 &ORB ate Owner or Owner's Designee, Title 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,w~/6~oTA and employed by k1AflrFollu ClCC4h Bu\u'/l 275 d F Co~M-ct~~cof HqdT FoRe) , ~7 have inspected the components described in this Owner's Report during the peiod C/ /3 h 7 to '7/ 27 /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 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 lnspector 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 3 A J~S h~' 0 d Yo 26- C.G ' Inspector's Signature National Board, Province and Endorsements Date Shdy 23 , Zdd 7 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 APPROVED (Signatures available in Master File)

ITEM 2007-23-0057 NOTE This form may not address all items needed for documentation of a repairlreplacement program, see I 4 Awl-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 I I in, (2) infonnation 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. 361 3 Revision 4 Page 1 of 2 MONTICELLO NUCLEAR GENERATING PLANT 1. Owner Xcel Energy Company Date 7/23/2007 Name 2. Plant Monticello Nuclear Generating Plant Sheet I of 2 Name TITLE: 2807 W. Cnty. Rd. 75, Monticello, Minnesota 55362 WO 322070 Address Repair Organization P.O. No., Job No. etc. OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 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. ldentification of System Automatic Pressure Relief (APR); Class 1 5. (a) Applicable Construction Code ANSI B31.1 1977 Edition Year Addenda Winter 1978 Addenda Code Case n/a (b) Applicable Edition of Section XI Utilized for Repairs or Replacement 2001 Edition, No Addenda 6. ldentification of Components Repaired or Replaced and Replacement Components

7. Description of Work Replaced SRV Pilot Stage (Topworks) for RV-2-71 C with rebuilt spare Name of Component ST aae 8. Tests Conducted:

Hydrostatic C] Pneumatic Nominal Operating Pressure C] Other Pressure n/a psi Test Temp n/a OF Name of Manufacturer Target Rock Target Rock pp 1 3087 (DOCUMENT CHANGE, HOLD AND COMMENT FORM) incorporated:

I Manufacturer Serial No.

208 217 APPROVED (Signatures available in Master File) ' FOR ADMlysTRA'fIvE$

R~SD Supv: PRGE 1 Assoc Ref: PRGE I SR: N 1 Freq: 0 vrs USED~LY ; - 1 Doc Tv~e: REF ONLY I Admin initials:

1 Date: National Board No. n/a n/a 1 Other ldentification Year Built 2005 2007 Repaired, Replaced or Replacement Replaced Replacement ASME Code Stamped YES NO IX]

ITEM 2007-23-0057 I 9. Remarks (Applicable Manufacturer's Data Reports to be Attached)

Replacement was pre-emptive and valve showed no signs of leakage at normal operating conditions.

Though no pressure test is required per Relief Request #7, a VT-2 was performed as part of the RCPB System Leakage Test 025520-IlC-2.

361 3 Revision 4 Page 2 of 2 MONTICELLO NUCLEAR GENERATING PLANT CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this reA,-t /Fu~~dMp,&&

&&,IT conforms to the rules on the ASME Code,Section XI.

I rebairlrep~acement Signed , SECTION K( is1 Owner or Owner's Designee, Title 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 hrw~fsa-M and employed by STC'~~ DO^ t91l.E. oF CVUWT)~C Y r of ~dpt F PJ c T- have inspected the components described in this Owner's Report during the period Ll 13 1d7 to 7 /~.3 Id7 , 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 lnspector 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 ,~QILL. Commissions k/d rty6) fi,vX &~/~QYJ%~-cc) Inspector's Signature National Board, Province and Endorsements Date J' ~1 CY 23 , ZCo7 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 APPROVED (Signatures available in Master File)

ITEM 2007-23-0058 NOTE This form may not address all items needed for documentation of a repairlreplacement program, see I 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 I I 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. 361 3 Revision 4 Page 1 of 2 MONTICELLO NUCLEAR GENERATING PLANT

1. Owner Xcel Energy Company Date 7/23/2007 TITLE: Name 2. Plant Monticello Nuclear Generating Plant Sheet 1 of 2 Name 2807 W. Cnty. Rd. 75, Monticello, Minnesota 55362 WO 291 884 Address Repair Organization P.O. No., Job No. etc. OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 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. ldentification of System Automatic Pressure Relief (A PR);

Safety Relief Valve RV-2-715, Class I 5. (a) Applicable Construction Code ANSI 531. I 1977 Edition Year Addenda Winter1978Addenda Code Case n/a (b) Applicable Edition of Section XI Utilized for Repairs or Replacement 2001 Edition, No Addenda 6. ldentification of Components Repaired or Replaced and Replacement Components 7. Description of Work Partial replacement of topworks flange bolting due to disassembly damage

8. Tests Conducted:

Hydrostatic Pneumatic Nominal Operating Pressure Name of Component (5) topworks flanae bolts (5) topworks flanae bolts (6) topworks flanae nuts (6) topworks flanae nuts Other Pressure n/a psi Test Temp n/a OF Name of Manufacturer Nova Nova Nova Nova APPROVED (Signatures available in Master File) Manufacturer Serial No. n/a n/a n/a n/a Year Built 2003 2007 2003 2007 National Board No. n/a n/a n/a n/a Other ldentification Ht 'Ode H250 Ht 'Ode HZ50 Ht 'Ode H25 1 Ht 'Ode HZ5 1 Repaired, Replaced or Replacement Replaced Replacement Replaced Replacement AS ME Code Stamped YES NO rn rn rn ITEM 2007-23-0058 I 9. Remarks (Applicable Manufacturer's Data Reports to be Attached)

GE SPEC 27/1\9206 and Alteration 97AO11 Rev. 1 apply. Like for like, partial replacement of bolting damaged during disassembly for procedure 4280-PM, (built 2003, installed 2007)

PSI VT-I performed on replacement bolting. (reference IS1 Report 2007VT459)

No pressure testing or /ST required for bolting replacement. Although no pressure testing or /ST is required for bolting replacement, the valve was tested per Operational Test 01 12 and a VT-2 was performed as part of the RCPB System Leakage Test 0255- 20-IlC-2.

361 3 Revision 4 Page 2 of 2 MONTICELLO NUCLEAR GENERATING PLANT CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this RWRIR /R~CE&WT kn~t-p/ conforms to the rules on the ASME Code,Section XI.

repairlreplacement Signed I Q~QN XI 1s 1 60- Date Owner or Owner's Designee, Title 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 )-l~wbfGpe and employed by HA PTFo iLJ1 6-t~- l*1 or wfi ~?f3 & 0 uh1~-crIccc~f H&(ZT%TcB J CT have inspected t e components described in this Owner's Report during the period 3 /,f /h7 to ~[LYIJJ~ , 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 lnspector 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.

d &-$7 Commissions U 4 3 A,, , FA/ 00 YO2 8 - C o Inspector's Signature National Board, Province and Endorsements Date ?11~q 2q , &d07 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 APPROVED (Signatures available in Master File)

ITEM 2007-23-0059 NOTE This form may not address all items needed for documentation of a repairlreplacement program, see I 4 Awl-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 I I 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. 361 3 Revision 4 Page 1 of 2 MONTICELLO NUCLEAR GENERATING PLANT

1. Owner Xcel Energy Company Date 7/17/2007 Name 2. Plant Monticello Nuclear Generating Plant Sheet 1 of 2 Name 2807 W. Cnty. Rd. 75, Monticello, Minnesota 55362 WO 29 1592 Address Repair Organization P.O. No., Job No, etc. TITLE: 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 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 4. ldentification of System RHR Senlice Water (RSW), Loop B, Class 3 5. (a) Applicable Construction Code ANSI B31. I 1 1977 Edition Year Addenda Winter 1978 Addenda Code Case n/a (b) Applicable Edition of Section XI Utilized for Repairs or Replacement 2001 Edition, No Addenda 6. ldentification of Components Repaired or Replaced and Replacement Components

7. Description of Work Replaced CV-1729 valve body like-for-like. (built 1998, installed 2007) Name of Component CV-1729 CV-1 729 8. Tests Conducted: Hydrostatic Pneumatic Nominal Operating Pressure Other Pressure n/a psi Test Temp n/a " F APPROVED (Signatures available in Master File) Name of Manufacturer Valfek Valtek Manufacturer Serial No. 47907.001.1 n/a National Board No.

n/a n/a Repaired, Replaced or Replacement Replaced Replacement Other ldentification n/a Ht. #ZFE Year Built 1987 2007 ASME Code Stamped YES NO ITEM 2007-23-0059 I 9. Remarks (Applicable Manufacturer's Data Reports to be Attached)

Design Change 872015 applies. New mechanical joint pressure tested per IWA-4540(c), 1998 Edition per IS1 Relief Request #7. System Leakage Test with VT-2, IST position indication test (PIT) and open exercise test (STO) performed per work order PMT, 361 3 Revision 4 Page 2 of 2 MONTICELLO NUCLEAR GENERATING PLANT CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this REPRIR/R~PCA~M~~T

~)~TIUIT~ conforms to the rules on the ASME Code,Section XI.

repairlreplacement Signed -, SECT )( / SI Date Owner or ~wner's'~esignee, Title 7 , 2007 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 hwu6;lor~

and employed by h~ rzr k118 3 TCU~ BI~ILCX 1-1 & 0 F cd~~~71~~1Y of k~nrFcrnR, C 7 have inspected the components described in this Owner's Report during the period 3 130 $9 7 to 7 / (9 107 , 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 lnspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report. Furthermore, neither the lnspector 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 bfl 1/@J A,, lvi k , 00 YUtb-Cd Inspector's Signature National Board, ~rovihce and Endorsements Date TUL~ L4 , 2/807 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 APPROVED (Signatures available in Master File)

NOTE This form may not address all items needed for documentation of a repairlreplacement program, see 4 Awl-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 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. 361 3 Revision 4 Page 1 of 2 MONTICELLO NUCLEAR GENERATING PLANT 1. Owner Xcel Energy Company Date 7/20/2007 Name 2. Plant Monticello Nuclear Generating Plant Sheet 1 of 2 Name 2807 W. Cnty. Rd. 75, Monticello, Minnesota 55362 WO 267369 Address Repair Organization P.O. No., Job No. etc.

TITLE: 3. Work Performed By NMC /Xcel Energy Type Code Symbol Stamp n/a OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 Company Name Authorization No.

n/a 2807 W. Cty Rd 75, Monticello, MN 55362 Expiration Date n/a Address 4. ldentification of System Primary Containment, Drywell Head, Class 2iMC 5. (a) Applicable Construction Code ASME Section 111 1 1965 Edition Year Addenda Winter '65 Addenda Code Case n/a (b) Applicable Edition of Section XI Utilized for Repairs or Replacement 2001 Edition, No Addenda 6. ldentification of Components Repaired or Replaced and Replacement Components

7. Description of Work Replaced 2 Bolts and 3 Nuts on the Drywell Head main flange.

8. Tests Conducted:

Hydrostatic Pneumatic Nominal Operating Pressure Other Pressure n/a psi Test Temp n/a " F 1 3087 (DOCUMENT CHANGE, HOLD AND COMMENT FORM) incorporated:

I APPROVED (Signatures available in Master File) FOR pMINIgRATIVE, Res~ Su~v: PRGE 1 Assoc Ref: PRGE I SR: N I Freq: 0 vrs - +USEONLY I Doc Tv~e: REF ONLY I Admin initials:

I Date: 1 ITEM 2007-23-0060 I 9. Remarks (Applicable Manufacturer's Data Reports to be Attached)

(2) Bolts and (3) nuts replaced due to normal wear, nicks, gouges, thread damage, etc. resulting from multiple disassembly

/reassembly occurances since original installation.

VT-1 PSI performed on replacement bolting items. (reference IS1 Report BOP-VT-07-051)

No pressure testing required.

361 3 Revision 4 Page 2 of 2 MONTICELLO NUCLEAR GENERATING PLANT CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this R~RIR /REPLACEMEW ACTIV(T~ conforms to the rules on the ASME Code,Section XI.

repairlreplacement Signed 4 '-, &TION&! Is/ b. Owner or owner'k Designee, Title Date ~ , 2007 - 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 jLl/lr/l/Gse~~ and employed by j+~prForzYI 5rc~r-1 JI OILCW ItL OF co~~d~c)rc~c~

of - Nqnl Fdlt8 , CT have inspected the components described in this Owner's Report during the period

'1 /,I 147 to 7/rol07 , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI. By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report. Furthermore, neither the Inspector nor his employer SHALL be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.

J P~LLL, Commissions kt? 1/86] A, W, .T A JJ 03 YLJL 8 - 6 u Inspector's Signature National Board, Province and Endorsements Date ~-,L.Y 20 , 2J 32 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 APPROVED (Signatures available in Master File)

ITEM 2007-23-0061 NOTE This form may not address all items needed for documentation of a repairlreplacement program, see I 4 AWIQ9.04.03 (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 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. 361 3 Revision 4 Page 1 of 2 MONTICELLO NUCLEAR GENERATING PLANT 1. Owner Xcel Energy Company Date 7/3/200 7 L TITLE: Name 2. Plant Monticello Nuclear Generating Plant Sheet 1 of 2 Name 2807 W. Cnty. Rd. 75, Monticello, Minnesota 55362 WO- 14 1358 Address Repair Organization P.O. No., Job No. etc. OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 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. ldentification of System Residual Heat Removal (RHR), Class 1 5. (a) Applicable Construction Code USAS 831.1 1967 Edition Year Addenda No Addenda Code Case n/a (b) Applicable Edition of Section XI Utilized for Repairs or Replacement 2001 Edition, No Addenda 6. ldentification of Components Repaired or Replaced and Replacement Components

7. Description of Work Replaced 4 flange mounting bolts that were misplaced during maintenance.

8. Tests Conducted:

Hydrostatic Pneumatic Nominal Operating Pressure Other Pressure n/a psi Test Temp n/a OF Repaired, Replaced or Replacement replaced replacement Name of Component SS- 1 7A Ss- 7A 1 3087 (DOCUMENT CHANGE, HOLD AND COMMENT FORM) incorporated:

I National Board No. - - Name of Manufacturer Bergen Patterson Bergen Patterson ASME Code Stamped APPROVED (Signatures available in Master File) Other ldentification 4 bolts, HI% unknown 8868492 Manufacturer Serial No. 157 157 YES 0 -- Res~ Suw: PRGE I Assoc Ref:

PRGE I SR: N I ~re~: 0 vrs w ARMS: 3613 1 Doc Tv~e: REF ONLY 1 Admin initials:

1 Date: Year Built un- known 2007 NO IX1 I

) MONTICELLO NUCLEAR GENERATING PLANT 1 3613 3 ITEM 2007-23-0061 I 9. Remarks (Applicable Manufacturer's Data Reports to be Attached)

Revision 4 Page 2 of 2 TITLE: Installation performed per procedure 4903. OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this ~*PLACE.MLNT conforms to the rules on the ASME Code,Section XI.

repairlreplacement Signed I ' , IS1 b~DWa*a Date 3-.r 3 , 2007 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 r? 1pw2 s 074 and employed by NnPTFoSo ~~*~I\~~~~LC;?~'~~~~FC~~KFC~IC~P of blAPT PPY , C7 have inspe ted the components described in this Owner's Report during the period 3/30 107 to 7 fio/a7 , 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.

?dW A u. Commissions ug r/z J A,A/;/I, A~A/~Q~/uLB-co Inspector's Signature National Board, Province and Endorsements Date ~WY ((I , ZOO] APPROVED (Signatures available in Master File) - -

NOTE This form may not address all items needed for documentation of a repairlreplacement program, see 4 Awl-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 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. 361 3 Revision 4 Page 1 of 2 MONTICELLO NUCLEAR GENERATING PLANT 1. Owner Xcel Energy Company Date 7/17/2007 Name 2. Plant Monticello Nuclear Generating Plant Sheet 1 of 2 Name 2807 W. Cnty. Rd. 75, Monticello, Minnesota 55362 WO 291592 Address Repair Organization P.O. No., Job No. etc. TITLE: 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 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 4. ldentification of System RHR Senlice Water (RSW), Loop 6, Class 3 5. (a) Applicable Construction Code ANSI 631. I 1 1977 Edition Year Addenda Winter 1978 Addenda Code Case n/a (b) Applicable Edition of Section XI Utilized for Repairs or Replacement 2001 Edition, No Addenda

6. ldentification of Components Repaired or Replaced and Replacement Components

7. Description of Work Replaced CV-I 729 plug. (built 2006, installed 2007)

8. Tests Conducted:

Hydrostatic C] Pneumatic C] Nominal Operating Pressure Other C] Pressure n/a psi Test Temp n/a OF Name of Component CV-1729 Plua 729 Plua APPROVED (Signatures available in Master File) Name of Manufacturer Valtek Flowsen~e Manufacturer Serial No. V12499 n/a National Board No. n/a n/a Other ldentification n/a Ht-Code 86966- 1 Year Built 1995 2007 Repaired, Replaced or Replacement Replaced Replacement ASME Code Stamped YES 0 NO IE3 ITEM 2007-23-0062 I 9. Remarks (Applicable Manufacturer's Data Reports to be Attached) Design Changes 872015 and 95AOl I apply. No pressure testing required for valve internal components.

IST position indication test (PIT) and open exercise test (STO) performed per work order PMT. CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this PA\ R /U*F~=**~T Amvl?y conforms to the rules on the ASME Code,Section XI.

repairlreplacement Signed m- , SKTX( IS\ Coom Date d 7 , 2.007 Owner or Owner's Designee, Title 361 3 Revision 4 Page 2 of 2 MONTICELLO NUCLEAR GENERATING PLANT 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 ~?J~/WSJ'TA and employed by ~~AR~FoLU Sk4k DIIL~?Z L\tj OK Coy&~cTlcccr of f{,+fi~t=olZD, GY have inspected the components described in this Owner's Report during the period 3 /30/0 7 to 7 / 17/07 , 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 lnspector 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.

Yu A&! Commissions 11k6 ,? A, W, $ h w 90 2 g -CU Inspector's Signature National Board, Province and Endorsements Date 34LV 49 , 20(37 TITLE: APPROVED (Signatures available in Master File)

OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 ITEM 2007-23-0063 NOTE This form may not address all items needed for documentation of a repairlreplacement program, see I 4 Awl-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 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. 361 3 Revision 4 Page 1 of 2 MONTICELLO NUCLEAR GENERATING PLANT 1. Owner Xcel Energy Company Date 7/23/2007 Name 2. Plant Monticello Nuclear Generating Plant Sheet I of 2 Name 2807 W. Cnty. Rd. 75, Monticello, Minnesota 55362 WO 29 1 883 Address Repair Organization P.O. No., Job No. etc. TITLE: 3. Work Performed By NMC /Xcel Energy Type Code Symbol Stamp n/a OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 Company Name Authorization No. n/a 2807 W. Cty Rd 75, Monticello, MN 55362 Expiration Date n/a Address 4. ldentification of System Automatic Pressure Relief (APR); Safety Relief Valve RV-2-71E, Class 1 5. (a) Applicable Construction Code ANSI 831.1 7 1977 Edition Year Addenda Winter 1978 Addenda Code Case n/a (b) Applicable Edition of Section XI Utilized for Repairs or Replacement 2001 Edition, No Addenda 6. ldentification of Components Repaired or Replaced and Replacement Components

7. Description of Work Replaced inlet flange bolting due to disassembly damage & thread pitch spec Name of Component lnlet flange 8. Tests Conducted:

Hydrostatic C] Pneumatic Nominal Operating Pressure Other Pressure n/a psi Test Temp n/a OF APPROVED (Signatures available in Master File)

Name of Manufacturer Nova Other Identification n/a Ht# 3M41345 n/a Ht# M92614 Manufacturer Serial No. n/a Inlet flange studs (12) lnlet flange nuts (24) lnlet flange nuts (24) National Board No.

n/a n/a n/a n/a Year Built 1969 Nova Nova Nova n/a n/a n/a 2007 1969 2007 Repaired, Replaced or Replacement Replaced Replacement Replaced Replacement ASME Code Stamped YES -- NO IXI IXI IX]

ITEM 2007-23-0063 I 9. Remarks (Applicable Manufacturer's Data Reports to be Attached)

GE Spec 21A9206 applies. Replaced all inlet flange bolting (built 2004, installed 2007): some damaged during disassembly for procedure 4280-PM, and all had a thread pitch different than specified by drawings specs.

PSI VT-1 performed on replacement bolting. (reference IS1 Report 2007VT486).

No pressure testing or /ST required for bolting replacement.

Although no pressure testing or IST is required for bolting replacement, the valve was tested per Operational Test 01 12 and a VT-2 was performed as part of the RCPB System Leakage Test 0255- 20-llC-2.

361 3 Revision 4 Page 2 of 2 MONTICELLO NUCLEAR GENERATING PLANT CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this F?XP&I R/REPLAC~-/HEW C~TIVIT~ conforms to the rules on the ASME Code,Section XI. repairlreplacement Signed p, SECT~ON n 6lhooar, Date )t+$ 23 2007 Owner or Owner's Designee, Title 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 j~ ~r/kcio P4 and employed by k/4flfF6fiY

~T<~~,Ro/L~H 3f~drc~lul~~C~1~tlrof F(ARs-~~~)~,cT have inspect d the components described in this Owner's Report during the period 7 / 7 /@7 to 7f2'I/07 , 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 lnspector 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.

g& A kc+ Commissions

~6 i I~G 3 A , I\l, 2 AX/ oo L~LILJ -CU Inspector's Signature National Board, Province and Endorsements Date JoLY '27 , LOO? OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 APPROVED (Signatures available in Master File)

ITEM 2007-23-0064 This form may not address all items needed for documentation of a repairlreplacement program, see I 4 Awl-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 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. 1. Owner Xcel Energy Company Date 7/23/2007 Name 2. Plant Monticello Nuclear Generating Plant Sheet I of 2 Name 2807 W. Cnty. Rd. 75, Monticello, Minnesota 55362 WO 29 1 885 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. ldentification of System Automatic Pressure Relief (APR); Safety Relief Valve RV-2-71G, Class I 5. (a) Applicable Construction Code ANSI B31. I 1 1977 Edition Year Addenda Winter 1978 Addenda Code Case n/a (b) Applicable Edition of Section XI Utilized for Repairs or Replacement 2001 Edition, No Addenda 6. ldentification of Components Repaired or Replaced and Replacement Components 361 3 Revision 4 Page 1 of 2 MONTICELLO NUCLEAR GENERATING PLANT TITLE: 7. Description of Work Replacement of topworks flange bolting due to disassembly damage OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 Name of Component topworks flg bolts (12) topworks flg bolts (121 topworks flg nuts (12) topworksflg nuts (12) 8. Tests Conducted:

Hydrostatic Pneumatic Nominal Operating Pressure Other Pressure n/a psi Test Temp n/a " F Name of Manufacturer Nova Nova Nova Nova APPROVED (Signatures available in Master File)

Manufacturer Serial No. n/a n/a n/a n/a National Board No. n/a n/a n/a n/a Other ldentification

'H250 Ht# 84013 H251 Ht # 66036 Year Built 2003 2007 2003 2007 Repaired, Replaced or Replacement Replaced Replacement Replaced Replacement ASME Code Stamped YES NO (XI (XI ITEM 2007-23-0064 I 9. Remarks (Applicable Manufacturer's Data Reports to be Attached)

GE SPEC 21A9206 and Alteration 97A011 Rev. 1 apply. Like for like, replacement of bolting damaged during disassembly for procedure 4280-PM. (built 1998, installed 2007)

PSI VT-I performed on replacement bolting. (reference IS1 Report 2007VT488) 361 3 Revision 4 Page 2 of 2 MONTICELLO NUCLEAR GENERATING PLANT No pressure testing or IST required for bolting replacement.

Although no pressure testing or /ST is required for bolting replacement, the valve was tested per Operational Test 01 12 and a VT-2 was performed as part of the RCPB System Leakage Test 0255- 20-IlC-2.

TITLE: CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this ~cppl~ /REPM~MEMT ficflu~~ conforms to the rules on the ASME Code,Section XI.

repairlreplacement Signed *. S~rno~)(/

If\ Owner 6r ~wn'er's Designee, Title OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 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 .&/C~QC~OTA and employed by I-lnllTF~d3 S?c-4b pv~rcw i*S dFokkscr\c~i of fI41 T FJ#~I CT have inspected th components described in this Owner's Report during the period Y /3 /d'l 7 to 7 124 07 , 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 lnspector 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.

7dx fi -~i~.+4- Commissions jV8 //a 6 2 A, .C/, /c/w od L/ ii 28-co Inspector's Signature National Board, Province and Endorsements Date 3UL.Y 27 , 2437 APPROVED (Signatures available in Master File)

ITEM 2007-23-0065 NOTE This form may not address all items needed for documentation of a repairlreplacement program, see I 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 I I 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. 361 3 Revision 4 Page 1 of 2 MONTICELLO NUCLEAR GENERATING PLANT 1. Owner Xcel Energy Company Date 7/23/2007 TITLE: Name 2. Plant Monticello Nuclear Generating Plant Sheet 1 of 2 Name 2807 W. Cnty. Rd. 75, Monticello, Minnesota 55362 WO 322083 Address Repair Organization P.O. No., Job No. etc. OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 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. ldentification of System Automatic Pressure Relief (APR); Safety Relief Valve RV-2-71A, Class I 5. (a) Applicable Construction Code ANSI B31.1 1977 Edition Year Addenda Winter 1978 Addenda Code Case n/a (b) Applicable Edition of Section XI Utilized for Repairs or Replacement 2001 Edition, No Addenda 6. ldentification of Components Repaired or Replaced and Replacement Components

7. Description of Work Replacement of topworks flange bolting due to disassembly damage 8. Tests Conducted:

Hydrostatic Pneumatic Nominal Operating Pressure Other Pressure n/a psi Test Temp n/a OF Name of Component topworks flg bolts (12) topworks flg bolts (12) topworks flg nuts (12) topworks flg nuts (12) APPROVED (Signatures available in Master File)

Name of Manufacturer Nova Nova Nova Nova Manufacturer Serial No. n/a n/a n/a n/a National Board No. n/a n/a n/a n/a Other ldentification n/a Ht# 84013 n/a Ht# 66036 Year Built various 2007 various 2007 Repaired, Replaced or Replacement Replaced Replacement Replaced Replacement ASME Code Stamped YES [3 [3 [3 NO IXI IXI IXJ ITEM 2007-23-0065 I 9. Remarks (Applicable Manufacturer's Data Reports to be Attached)

GE SPEC'S 21A1060, 21A9206, and Alteration 97A011 Rev. 1 apply. Like for like, replacement of bolting damaged during disassembly for procedure 4280-PM. (built 1998, installed 2007) PSI VT-I performed on replacement bolting. (reference IS1 Report 2007VT487) No pressure testing or /ST required for bolting replacement. Although no pressure testing or IST is required for bolting replacement, the valve was tested per Operational Test 01 12 and a VT-2 was performed as part of the RCPB System Leakage Test 0255- 20-llC-2.

361 3 Revision 4 Page 2 of 2 MONTICELLO NUCLEAR GENERATING PLANT CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this Rm~l P/WW~T htvl~y conforms to the rules on the ASME Code,Section XI.

repairlreplacement , SE~WON XI &a Date Owner or Owner's Designee, Title L 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 M IWUF~ OTA and employed by L~A~TF~P~~T~EA~DOILH~~L~FCONWELPI~~~~

of M~~.~JJ?u,cT have inspected the components described in this Owner's Report during the period

~/3 /47 to ~/LY /JI , 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.

PU4ki Commissions A/@ (/ti6 3 A , MJ /~ru OJ 11v ZJ-cu Inspector's Signature National Board, Province and Endorsements Date S'UL-Y 2Y , 2007 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 APPROVED (Signatures available in Master File)

ITEM 2007-23-0066 NOTE This form may not address all items needed for documentation of a repairlreplacement program, see I 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 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.

361 3 Revision 4 Page 1 of 2 MONTICELLO NUCLEAR GENERATING PLANT

1. Owner Xcel Energy Company Date 7/19/2007 Name 2. Plant Monticello Nuclear Generating Plant Sheet I of 2 Name 2807 W. Cnty. Rd. 75, Monticello, Minnesota 55362 WO 142056 Address Repair Organization P.O.

No., Job No, etc. L TITLE: 3. Work Performed By NMC /Xcel Energy Type Code Symbol Stamp Ma Company Name Authorization No. n/a 2807 W. Cty Rd 75, Monticello, MN 55362 Expiration Date n/a Address OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2

4. ldentification of System High Pressure Coolant Injection (HPC), Class 1 5. (a) Applicable Construction Code ANSI B31. I 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. ldentification of Components Repaired or Replaced and Replacement Components

7. Description of Work Like for like replacement of I bonnet stud and 16 nuts on valve MO-2035 Name of Component MO-2035 stud. nuts MO-2035 stud, nuts M0-2035 Disc M%2035 8. Tests Conducted:

Hydrostatic C] Pneumatic C] Nominal Operating Pressure Other Pressure n/a psi Test Temp n/a " F Name of Manufacturer Nova/ Flowserve Nova/ Flowserve Flowserve Flowserve APPROVED (Signatures available in Master File) Manufacturer Serial No. n/a n/a S/N 2 S/N I National Board No. n/a n/a n/a n/a Other ldentification n/a n/a Ht. 'Ode TRH- 1 Ht Code TRH-2 Year Built various 2007 2000 2007 Repaired, Replaced or Replacement Replaced Replacement Replaced Replacement ASME Code Stamped YES CI NO IXI IXI ITEM 2007-23-0066 I 9. Remarks (Applicable Manufacturer's Data Reports to be Attached) 361 3 Revision 4 Page 2 of 2 MONTICELLO NUCLEAR GENERA TlNG PLANT Like for like replacement of stud and nuts due to damage during removal.

TITLE: Like for like replacement of disc due to slight warpage visually observed during removal. Studs built 2004, installed 2007.

Nuts built 2004, installed 2007.

Disc built 1999, installed 2007 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 No pressure testing required, VT-I PSI performed on replacement bolting. /ST stroke time testing and position indication test performed per Work Order PMT. Appendix J L L RT performed per applicable steps of 0 137-07A (4/7/2007) CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this REP&R/REPLACE:MC~J~

Acnv cry conforms to the rules on the ASME Code,Section XI.

repairlreplacement Signed , S ECT~ON )(I 1s 1 eoo~3. Date Owner or 0wneis 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

& IUUF so T4 and employed by f-~cl~tr=ons s~t'~., gor~~~r. J+~~FC~~M-C~IC~~

of H~RT.FORD , ct- have inspected the components described in this Owner's Report during the period CI ( /o 7 to 71 ~2 Id7 , 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 lnspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report. Furthermore, neither the lnspector nor his employer SHALL be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.

%L-T- A d.t.4-1;.

Commissions I/~GJ A, wit k w &a Y OLK - co Inspector's Signature National Board, Province and Endorsements Date J4Ly Zc , 2dd7 APPROVED (Signatures available in Master File)

ITEM 2007-23-0067 NOTE This form may not address all items needed for documentation of a repairlreplacement program, see I 4 Awl-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 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. 361 3 Revision 4 Page 1 of 2 MONTICELLO NUCLEAR GENERATING PLANT

1. Owner Xcel Energy Company Date 7/1 4/2007 Name 2. Plant Monticello Nuclear Generating Plant Sheet 7 of 2 Name 2807 W. Cnty. Rd. 75, Monticello, Minnesota 55362 WO 147016 Address Repair Organization P.O. No., Job No. etc. TITLE: 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 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 Address 4. ldentification of System Residual Heat Removal Senlice Water (RHRS w, Loop A, Class 3 5. (a) Applicable Construction Code ANSI B31.7 1977 Edition Year Addenda Winter 19 78 Addenda 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

7. Description of Work Replaced approx 4ft of A-106 Gr. B pipe (line designation SW9-78"-GF in the Torus Room) like-for-like by welding due to localized ID corrosion (replacement pipe built 2000, installed 2007).

Removed portions of SR-396 to facilitate piping replacement and reinstalled by welding.

8. Tests Conducted:

Hydrostatic Pneumatic Nominal Operating Pressure Name of Component S W9- 1 8"-GF S W9-18"-GF SR-396 Other Pressure 235-240 psi Test Temp n/a OF APPROVED (Signatures available in Master File) Name of Manufacturer n/a Dubose n/a Manufacturer Serial No. n/a n/a n/a National Board No. n/a n/a n/a Other ldentification n/a H#A83222 n/a Year Built 1969 2007 2007 Repaired, Replaced or Replacement Replaced Replacemenf Repaired ASME Code Stamped YES NO (XI IX( (XI ITEM 2007-23-0067 I 9. Remarks (Applicable Manufacturer's Data Reports to be Attached)

PSI VT-3 performed on SR-396. Reference IS1 Report 2007VT733.

System leakage test in lieu of a hydro per IWA-4540(a)(2) per WO PMT attachment.

361 3 Revision 4 Page-3l0f 2 ?f&ior MONTICELLO NUCLEAR GENERATING PLANT CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this REP& IR/ RFPLAC*MENT AcXlvly conforms to the rules on the ASME Code,Section XI. repairlreplacement Signed . SECT )O IS/ 60- Date Owner or 0wner"s Designee, Title (Idi 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 ~r WIL&~ arA and employed by

/M&~F*FIJ rrf'nrs aoi~lt ti3 JF cY&-~t'crlcu2 of bheTt=J3&, cT have inspected the components described in this Owner's Report during the period

&/!7 /d-) to 71 t$ Id7 , 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.

~LT ,4.hLk. Commissions PV I( kc) A, IV, 2 hv3d ~IUZ t-co Inspector's Signature National Board, Province and Endorsements Date SlN' L3 , 2337 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 APPROVED (Signatures available in Master File)

ITEM 2007-23-0068 NOTE This form may not address all items needed for documentation of a repairlreplacement program, see I 4 Awl-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 I I 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. 361 3 Revision 4 Page 1 of 2 MONTICELLO NUCLEAR GENERATING PLANT

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 324116 Address Repair Organization P.O. No., Job No. etc. TITLE: 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 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 Address 4. ldentification of System Residual Heat Removal Senlice Water (RHRSW), Loop A, Class 3 5. (a) Applicable Construction Code ANSI B31. I 1 1977 Edition Year Addenda Winter 1978 Addenda 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

7. Description of Work Replaced approx 2 ff of A-706 Gr. B pipe (line designation SW9-78"-GF in the Turbine Building) like-for-like by welding due to localized ID corrosion (replacement pipe built 2000, installed 2007).

8. Tests Conducted:

Hydrostatic Pneumatic Nominal Operating Pressure Name of Component S W9-18"-GF S W9-18"-GF Other Pressure 235-240 psi Test Temp n/a " F APPROVED (Signatures available in Master File) Name of Manufacturer n/a Dubose Manufacturer Serial No. n/a n/a National Board No.

n/a n/a Other ldentification n/a HHA83222 Year Built 1969 2007 Repaired, Replaced or Replacement Replaced Replacement ASME Code Stamped YES NO IXJ I I REPLACEMENTS - FORM NIS-2 MONTICELLO NUCLEAR GENERATING PLANT TITLE: I OWNER'S REPORT FOR REPAIRS OR ITEM 2007-23-0068

9. Remarks I (Applicable Manufacturer's Data Reports to be Attached) 361 3 Revision 4 System leakage test in lieu of a hydro per IWA-4540(a)(2) per WO PMT attachment. CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this RE?~&EPL~~MNT Acrhvrry conforms to the rules on the ASME Code,Section XI. repairlreplacement Signed I - SECTXI Is\ bow Owner or ~'wner's besignee, 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 )r,y~/~'~oTn and employed by

/j~gj-~~flu J?-cenn rlolcr2~'jJ'dPcflwc'cT~cyT of ~(ACTFU&.JJ,C~

have inspected the components described in this Owner's Report during the period Y/? Id7 to ~/LJ 107 , 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.

LPL* Commissions IY~ I( 663 A ,MA- /7 M 30 % L&-CO Inspector's Signature National Board, Province and Endorsements Date ~QLY 23 I ZOQ7 APPROVED (Signatures available in Master File)

ITEM 2007-23-0069 NOTE This form may not address all items needed for documentation of a repairlreplacement program, see I 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 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. 1. Owner Xcel Energy Company Date 7/15/2007 Name 2. Plant Monticello Nuclear Generating Plant Sheet 1 of 2 Name 2807 W. Cnty. Rd.

75, Monticello, Minnesota 55362 WO 323428 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. ldentification of System Reactor Head Vent (RPV), Class I 5. (a) Applicable Construction Code ANSI 831. I 1977 Edition Year Addenda Winter 19 78 Addenda Code Case n/a 361 3 Revision 4 Page 1 of 2 MONTICELLO NUCLEAR GENERATING PLANT (b) Applicable Edition of Section XI Utilized for Repairs or Replacement 2001 Edition, No Addenda TITLE: 6. ldentification of Components Repaired or Replaced and Replacement Components OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 7. Description of Work Replaced upper hanger rod due to bend identified by IS/. Name of Component Vl5-H3, umer rod Vf5H3, u~oer rod 8. Tests Conducted:

Hydrostatic Pneumatic Nominal Operating Pressure Other Pressure n/a psi Test Temp n/a OF Name of Manufacturer Bergen Paterson Bergen Paterson APPROVED (Signatures available in Master File) Manufacturer Serial No. n/a n/a National Board No. n/a n/a Other ldentification n/a Po E46743j Ln. 10 Year Built 1969 2007 Repaired, Replaced or Replacement Replaced Replacement ASME Code Stamped YES NO rn ITEM 2007-23-0069 I 9. Remarks (Applicable Manufacturer's Data Reports to be Attached)

Initial IS1 VT-3 exam reported a bend in the upper rod. (reference IS1 Report 2007VT023 and CAP- 01082758). Condition evaluated as acceptable, but recommendation was made to replace the rod. Preservice VT-3 performed following rod replacement. (reference IS/ Report 2007V7-7'47) 361 3 Revision 4 Page 2 of 2 MONTICELLO NUCLEAR GENERATING PLANT CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this RE~A~R/R~P~~~~

\/cry conforms to the rules on the ASME Code,Section XI. repairlreplacement Signed , Seer Xl ISI bog,) Date fi ic , w"T Owner or Owner's Designee, Title 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 PIWWSBFA and employed by IIA vlm PB ~tr;s~~ ba~m It& 31: COWGCTIC 4~ of F/*QP'~' ~CJI~IJ , L r have inspected t e components described in this Owner's Report during the period Y /[J 107 to -7 1 ~~10~ , 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. I By signing this certificate neither the lnspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report. Furthermore, neither the lnspector 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.

~~~ AAL& Commissions Plt r r 4-6 j 4, N, t h tv o o YUZ 6 -~0 Inspector's Signature National Board, Province and Endorsements Date TQL~ ZC , 2-007 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 APPROVED (Signatures available in Master File) -

ITEM 2007-23-0070 I NOTE This form may not address all items needed for documentation of a repairlreplacement program, see 4 Awl-09.04.03 (ASME SECTION XI REPAIRIREPLACEMENT PROGRAM) for further guidance.

361 3 Revision 4 Page 1 of 2 MONTICELLO NUCLEAR GENERATING PLANT 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 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. TITLE: 1. Owner Xcel Energy Company Date 7/14/2007 Name 2. Plant Monticello Nuclear Generating Plant Sheet I of 2 Name OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 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. ldentification of System Emergency Senlice Water (ESW, Div I, Class 3 5. (a) Applicable Construction Code ANSI B31. I 5 1977 Edition Year Addenda Winter 1978 Addenda Code Case n/a (b) Applicable Edition of Section XI Utilized for Repairs or Replacement 2001 Edition, No Addenda 6. ldentification of Components Repaired or Replaced and Replacement Components

7. Description of Work Replaced approx 6 inches of A-106 Gr, B pipe and adjacent A-234 WPB elbow (line designation ES Wl-4"-HBD) like-for-like by welding due to localized ID corrosion (replacement pipe built 2000, replacement elbow built 1991 , both installed 2007).

8. Tests Conducted:

Hydrostatic Pneumatic Nominal Operating Pressure Other Pressure 77 psi Test Temp n/a " F APPROVED (Signatures available in Master File) 1 MONTICELLO NUCLEAR GENERA TlNG PLANT 1 3613 3 1 TITLE: 1 OWNER'S REPORT FOR REPAIRS OR ( Revision 4 1 I I REPLACEMENTS - FORM NIS-2 I pag-~ 1 ITEM 2007-23-0070 I 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 REPAIR/ RFPWCEMENT PCS~V~ conforms to the rules on the ASME Code,Section XI. repairlreplacement Signed 2 sw $1 IS[ Owner or owner's Designee, Title APPROVED (Signatures available in Master File) 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 /1cv~,420 TA and employed by C(A~~TFOKO 9rc~114 QOI la J'~J' crrto~~~litlcrlr of ?-i~~fJlble~, Cr have inspected the components described in this Owner's Report during the ~eriod /o 7 to 7120 167 , 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 lnspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report.

Furthermore, neither the lnspector 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.

7&7T A hLL4t.A. Commissions t!/t /1&$3 A, & 2 A~OO Yap- cd Inspector's Signature National Board, Province and Endorsements Date TCcLv 'iW , Ld07

A NOTE This form may not address all items needed for documentation of a repairlreplacement program, see 4 Awl-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 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. 361 3 Revision 4 Page 1 of 2 MONTICELLO NUCLEAR GENERATING PLANT 1. Owner Xcel Energy Company Date 7/14/2007 Name 2. Plant Monticello Nuclear Generating Plant Sheet 1 of 2 Name TITLE: 2807 W. Cnty. Rd. 75, Monticello, Minnesota 55362 WO 326373 Address Repair Organization P.O. No., Job No. etc. OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 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. ldentification of System Emergency Senlice Water (ESW, Div 11, Class 3 5. (a) Applicable Construction Code ANSI 831. I 9 1977 Edition Year Addenda Winter 1978 Addenda 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

7. Description of Work Replaced A-234 WPB elbow (line designation ESW5-4"-HBD) like-for-like by welding due to localized ID corrosion (replacement elbow built 1991, installed 200 7). Name of Component ES W5-4"- HRD Elbow ES W5-4"- HBD Elbow 8. Tests Conducted:

Hydrostatic Pneumatic Nominal Operating Pressure Other Pressure 76 psi Test Temp n/a " F Name of Manufacturer unknown Consolidated Power APPROVED (Signatures available in Master File)

Manufacturer Serial No. n/a n/a National Board No.

n/a n/a Other ldentification n/a Ht# 7662 Year Built 1981 2007 Repaired, Replaced or Replacement Replaced Replacemenf ASME Code Stamped YES NO ITEM 2007-23-0071 I 9. Remarks (Applicable Manufacturer's Data Reports to be Attached) System leakage test in lieu of a hydro per IWA-4540(a)(2) per WO PMT attachment.

CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this TCP&\R/ Rwuwwr ACTIUIV conforms to the rules on the ASME Code,Section XI.

repairlreplacement Signed -, SECT KI 131 COORD Owner or Owner's Designee, Title Date a-e, 14 , 2007 361 3 Revision 4 Page%oB ,,iq/q MONTICELLO NUCLEAR GENERATING PLANT 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 Ntuoby o TA and employed by t-1.sRbFuICU JXah BOIL@ ~'1.4' OF c-w&rnckT of [Ia~t FUK~ , CT have inspected the components described in this Owner's Report during the period '?/L+/U~ to 71 L~IJ~ , 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 lnspector 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/& //&63 4, /1.; 5 h-c~/ d0Vo LF -C 0 Inspector's Signature National Board, Province and Endorsements Date ~C/LY LO I Zd3) TITLE: APPROVED (Signatures available in Master File)

OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 Nuclear Management Company Monticello Inservice Impation IV. Form NIS-1 Information Cycle 23 Summary Report 2007 Refueling Outage 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 Page 1 of 2 1. Owner: Xcel Energy. LLC / Nuclear Management Company, LLC Address: 800 Nicollet Mall. Mpls. MN 55402 / 700 1 st St., Hudson WI 540 16 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: 6130171 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 0411 3/05 . 9. Inspection Interval: 05/01/03 to 0513 1/12 . 10. Applicable Edition of Section XI: 1995 Addenda: 1996 . 1 1. 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 Form NIS-2 Cycle 22 information

12. Abstract of Conditions Noted. See Sections IV and V for supplemental Form NIS-2 Cycle 22 information

14. Abstract of Corrective Measures Recommended and Taken. See Sections IV and V for supplemental Form NIS-2 Cycle 22 information Nuclear Management Company Monticello Inservice Inspection Cycle 23 Summary Report 2007 Refueling Outage IV. Form NIS-1 Information

(**Supplement to Submittal for Cycle 22,2005 RF'O**) 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 JULY % 20 07 Signed XCEL~ERW INNC By w- Owner Section XI IS1 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

/-IIPWC-SOTA and employed by rr~ rb nu ~rchp, J~WI~=R~Y~

OF C~UVS I kwi of +3wj\ F4 a, c T have inspected the components described in this Owner's Report during the period u J 3 to 7 116 /07 , 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 E/ II 111-6 3 A, M. J' /QU C/~YW~-CU National Board, State, Province, Endorsements Date 741,~ 26 2007 Nuclear Management Company Monticello Inservice Inspection Cycle 23 Summary Report 2007 Refueling Outage V. Form NIS-2 Information Supplemental NIS-2 Form for Cycle 22 2005 RFO Summary Report Previously unsubmitted Form NIS-2 (2 pages to follow) WORK DESCRIPTION Replaced valve plug note: replaced during 2005 RFO (reference CAP 01006064)

COMPONENT OR SYSTEM CV-1728 RIR ITEM NUMBER 2006-22-0007 WORK DOCUMENT WO-0307010 ITEM 2006-22-0007 I NOTE This form may not address all items needed for documentation of a repairlreplacement program, see 4 Awl-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 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. 361 3 Revision 4 Page I of 2 MONTICELLO NUCLEAR GENERATING PLANT 1. Owner Xcel Energy Company Date 7/13/2006 Name 2. Plant Monticello Nuclear

~enerating Plant Sheet 1 of 2 Name TITLE: 2807 W. Cnty. Rd. 75, Monticello, Minnesota 55362 WO 0307010 Address Repair Organization P.O. No., Job No.

etc. OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 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. ldentification of System RHR Senlice Water (RHRSW, CV-1728, Class 3 5. (a) Applicable Construction Code ANSI B31. I 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. ldentification of Components Repaired or Replaced and Replacement Com ponents 7. Description of Work Replaced plug Name of Component CV- 1 728 CV- 1 728 8. Tests Conducted:

Hydrostatic 0 Pneumatic Nominal Operating Pressure Other Pressure n/a psi TestTemp n/a OF Name of Manufacturer Valtek Flo wserve APPROVED (Signatures available in Master File)

Manufacturer Serial No.

47907-001 (valve) 47907-001 (valve) National Board No.

n/a n/a Other ldentification 0411236- 9970-01 O4 1236- 29970-01 Year Built 1987 2005 Repaired, Replaced or Replacement Replaced Replacement ASME Code Stamped YES NO jXI (XI ITEM 2006-22-0007 I 9. Remarks (Applicable Manufacturer's Data Reports to be Attached)

Design Change 8720 15 is applicable to valve and Alteration 95A 0 1 I is applicable to plug. No pressure testing required for internal component.

IST was performed per the WO PMT Attachment.

This R/R was performed during 2005 refueling outage (Cycle 22). This NIS-2 will be submitted with the Cycle 23 IS1 Summary Report noting amendment. (Ref.

CAP AIR 01006064).

361 3 Revision 4 Page 2 of 2 MONTICELLO NUCLEAR GENERATING PLANT CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this rep\a,cernent conforms to the rules on the ASME Code,Section XI. 'repair/replacement Signed , SEC XI I SI C- Date ~LL~ /'/ 2007 Owner or Owner's Designee, Title 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 MIU~ 6l ~'TA and employed by HA&~FQ~PO STL~~W 4,o/~b12 ~~~~FCOU~E;CT~~&~

t-(AZi-PaP-U, CT have inspected the components described in this Owner's Report during the period UBc& M Lf Qg l c, Ldo3" to 3~j~y ly, too^ I and state that to the best of my knowledge and belief, the Owner has performed examinationssand 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 lnspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report. Furthermore, neither the lnspector nor his employer SHALL be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.

i Commissions A/D (//KG 3 A, h/a 40 tx- - co Inspector's Signature National Board, Province and Endorsements Date ~CCL'P lY , coo6 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - FORM NIS-2 APPROVED (Signatures available in Master File)

Nuclear ~anagement Company Monticello Inservice Inspection APPENDIX A (19 pages to follow) (in order as listed below1 Class 1 Category B-A IS1 and PSI Exams Class 1 Category B-D IS1 and PSI Exams Class 1 Category B-G-1 IS1 and PSI Exams Class 1 Category B-G-2 IS1 and PSI Exams Class 1 Category B-L-2 IS1 Exams Class 1 Category B-M-2 IS1 Exams Class 1 Category B-N-I IS1 Exams Class 1 Category B-N-2 IS1 Exams Class 1 Category F-A IS1 and PSI Exams Class 1 Category R-A(H) IS1 Exams Class 1 Category R-A(L) ISI, PSI, and AUG Exams Class 1 Category R-A(M) ISI, PSI, and AUG Exams Class 2 Category C-C IS1 and PSI Exams Class 2 Category F-A IS1 and PSI Exams Class 2 Category R-A(M) 8 IS1 Exams Class 3 Category F-A IS1 and PSI Exams Cycle 23 Summary Report 2007 Refueling Outage Non-Code Exams AUGExams NIS-1 Attachment (Appendix A) Cycle 22 Inservice Inspection Report (2007 RFO) Owner: Xcel Energy, LLC, 800 Nicollet Mall, Minneapolis, MN 55402 Operator: Nuclear Management Company, LLC, 700 First Street, Hudson, WI 54016 Plant: Monticello Nuclear Generating Plant, Unit 1, 2807 West County Rd

75, Monticello, MN 55362 Owner Certificate of Authorization (If Req.): N/A Commercial Service Date:

6/30/1971 National Board Number for Unit: N/A Summary No. Comp ID Comp Desc. Category item Procedure MethodISheetlResults System IS0 Num Exam Date Class 1 Category BA, EXAMS PERFORMED FOR IS1 (4th Interval, Period 2 Credited Exams) and PSI 102643 VLAA-2 Long Seam PEI-02.03.15 UT 2007UT059 NRI Reactor Vessel IS1 Fig 4 3/22/2007 81.12 IS1 Comments:

Limited exam, Supplemental for future ID exam, no relief request required at this time.

Class 1 Category B-D, EXAMS PERFORMED FOR IS1 (4th Interval, Period 2 Credited Exams) and PSI 102374 N- 6A IR N- 6A Inner Radius B3.100 FP-PE-NDE-UT-03 UT 2007UT105 NRI IS1 Reactor Vessel IS1 Fig 1 3/25/2007 B3.90 - 102375 N-6A NV NoulelHead Weld PEI-02.03.15 UT 2007UT104 NRI Reactor Vessel IS1 Fig 1 3/25/2007 IS1 Comments:

Limited exam less than 90% coverage - Relief Request required 102657 N-28 IR N- 2B Inner Radius B3'100 FP-PE-NDE-UT-03 UT 2007UT057 NRI Reactor Vessel IS1 Fig 5 312 112007 IS1 102658 N- 2B NV N- 2B Noz 1 Vsl Weld PEI-02.03.15 UT 2007UT058 NRI Reactor Vessel IS1 Fig 5 3/21 12007 83.90 IS1 Comments:

Limited exam less than 90% coverage - Relief Request required 102667 N- 2G IR N- 2G Inner Radius 83'100 FP-PE-NDE-UT-03 UT 2007UT060 NRI IS1 Reactor Vessel IS1 Fig 5 3/22/2007 102668 N- 2G NV N- 2G NozNsl Weld PEI-02.03.15 UT 2007UT061 NRI Reactor Vessel IS1 Fig 5 3/22/2007 83.90 IS1 Comments:

Limited exam less than 90% coverage - Relief Request required Page 1 of 19 NIS-1 Attachment (Appendix A) Cycle 22 Inservice Inspection Report (2007 RFO) Owner: Xcel Energy, LLC, 800 Nicollet Mall, Minneapolis, MN 55402 Operator: Nuclear Management Company, LLC, 700 First Street, Hudson, WI 54016 Plant: Monticello Nuclear Generating Plant, Unit 1, 2807 West County Rd

75, Monticello, MN 55362 Owner Certificate of Authorization (If Req.): N/A Commercial Service Date:

6/30/1 971 National Board Number for Unit: N/A -- Summary No. Comp ID Comp Desc. Category Item Procedure MethodISheetlResults System IS0 Num Exam Date - 102683 N-4A IR N- 4A Inner Radius B3.1 O0 FP-PE-NDE-UT-03 UT 2007UT101 NRI IS1 Reactor Vessel IS1 Fig 5 3/24/2007 102684 N- 4A NV N- 4A NozNsl Weld 83.90 IS1 PEI-02.03.15 UT 2007UT103 NRI Reactor Vessel IS1 Fig 5 3/24/2007 Comments:

Limited exam less than 90% coverage - Relief Request required 102699 N- 9 IR N- 9 Inner Radius B3.100 FP-PE-NDE-UT-03 UT 2007UT100 NRI IS1 Reactor Vessel IS1 Fig 5 3/24/2007 102700 N- 9 NV N- 9 VesINoz Weld 83.90 IS1 PEI-02.03.15 UT 2007UT102 NRI Reactor Vessel IS1 Fig 5 3/24/2007 Comments:

Limited exam less than 90% coverage - Relief Request required - Class 1 Category 6-G-I, EXAMS PERFORMED FOR IS1 (4th Interval, Period 2 Credited Exams) and PSI 102076 8- 2 RC Pump B Studs, Nuts PEI-02.03.06 UT 2007UT125 NRI Recirculation B ISI-97006-A 3/25/2007 86.180 IS1 IS1 PEI-02.05.01 VT 200M044 NRI Recirculation B ISI-97006-A 3/25/2007 PSI PEI-02.05.01 VT 200M045 NRI Recirculation B 1st-97006-A 3/25/2007 1071 84 P200-B Flange Surface Recirculation B ISI-97006-A 3/25/2007 B6.190 IS1 PEI-02.05.01 VT 2007Vr475 NRI Page 2 of 19 NIS-1 Attachment (Appendix A) Cycle 22 Inservice Inspection Report (2007 RFO)

Owner: Xcel Energy, LLC, 800 Nicollet Mall, Minneapolis, MN 55402 Operator: Nuclear Management Company, LLC, 700 First Street, Hudson, WI 54016 Plant: Monticello Nuclear Generating Plant, Unit 1, 2807 West County Rd

75, Monticello, MN 55362 Owner Certificate of Authorization (If Req.): NIA Commercial Service Date: 6/30/1971 National Board Number for Unit:

N/A Summary No. Comp ID Comp Desc. Category Item Procedure MethodISheetlResults System IS0 Num Exam Date 1 Class 1 Category 84-2, EXAMS PERFORMED FOR IS1 (4th Interval, Period 2 Credited Exams) and PSI 100567 B- 2 Flange Bolts

@ W-14 PEI-02.05.01 VT 2007VT032 NRI Main Steam A ISI-I 31 42-33-A 311 912007 B7.50 IS1 100568 B-3 Flange Bolts @ W-16 Main Steam A ISI-13142-33-A 4/3/2007 87.50 PSI PEI-02.05.01 VT 200M486 NRI 100574 B- 9 Valve Bolts Main Steam A ISI-13142-33-A 4/3/2007 87.70 PSI PEI-02.05.01 VT 200M487 NRI 100622 B-2 Flange Bolts @ W-15 Main Steam B ISI-13142-34-A 311 912007 B7.50 IS1 PEI-02.05.01 VT 2007VT031 NRI 100626 B-6 Valve Bolts Main Steam B ISI-13142-34-A 4/3/2007 87.70 PSI PEI-02.05.01 VT 200M488 NRI 100629 B-7 Valve Bolts Main Steam B ISI-13142-34-A 4/1/2007 87.70 PSI PEI-02.05.01 VT 2007VT459 NRI 100974 B-2 Valve Bolts PEI-02.05.01 VT 2007VT494 NRI HPCl Steam ISI-13142-42-A 4/4/2007 B7.70 PSI IS1 PEI-02.05.01 VT 2007Vr495 NRI HPCl Steam ISI-13142-42-A 4/4/2007 101408 B-I Flange Bolts PEI-02.05.01 VT 2007Vr732 NRI Recirc B Drain Line 87.50 IS1 ISI-74210-1A 411 112007 101492 B-2 Flange Bolts PEI-02.05.01 VT 2007VT477 NRI Head Vent ISI-782A-A 4/3/2007 B7.50 PSI 101 929 B- 2 Valve Bolts RHR Return B B7.70 IS1 PEI-02.05.01 VT 2007Vr474 NRI ISI-97004-A 3/27/2007 Page 3 of 19 NIS-1 Attachment (Appendix A) Cycle 22 Inservice Inspection Report (2007 RFO)

Owner: Xcel Energy, LLC, 800 Nicollet Mall, Minneapolis, MN 55402 Operator: Nuclear Management Company, LLC, 700 First Street, Hudson, WI 54016 Plant: Monticello Nuclear Generating Plant, Unit 1, 2807 West County Rd

75, Monticello, MN 55362 Owner Certificate of Authorization (If Req.): N/A Commercial Service Date: 613011 971 National Board Number for Unit: N/A Summary No. Comp ID Comp Desc. Category Item Procedure MethodlSheetlResults System IS0 Num Exam Date Class 1 Category B-L-2, EXAMS PERFORMED FOR IS1 (4th Interval, Period 2 Credited Exams) 102099 P200-B Pump Casing Internal Surfaces PEI-02.05.04 VT 2007VT043 NRI Recirculation B B12.20 IS1 ISI-97006-A 3/25/2007 Class 1 Category B-M-2, EXAMS PERFORMED FOR IS1 (4th Interval, Period 2 Credited Exams) 100992 Valve Int Surfaces HPCl Steam ISI-13142-42-A 4/4/2007 812.50 v- 2 IS1 PEI-02.05.04 VT 2007Vr493 NRI 101 938 Valve Int Surfaces PEI-02.05.04 VT 2007M-446 NRI RHR Return B ISI-97004-A 3/27/2007 B12.50 v- 2 IS1 Class 1 Category 6-N-1, EXAMS PERFORMED FOR IS1 (4th Interval, Period 2 Credited Exams) 102716 Top Guide (areas made access., fuel cell 81 3.1 0 C-1A vacated) IS1 PEI-02.05.05 VT-3 AREVA-RPT NRI Reactor Vessel IS1 Fig 0 3/31 12007 Shroud Shelf 0-180 deg 813.10 102718 C-3A PEI-02.05.05 VT-3 AREVA-RPT NRI Reactor Vessel IS1 Fig 0 3/31/2007 IS1 Shrd Shlf 180-360 deg B13.10 107690 C-3B PEI-02.05.05 VT-3 AREVA-RPT NRI Reactor Vessel IS1 Fig 0 3/31 12007 IS1 lncore Dry Tubes (if made accessible B13.10 107737 C-I I during RFO) IS1 PEI-02.05.05 VT-3 AREVA-RPT NRI Reactor Vessel IS1 Fig 0 313 112007 Core Plate (areas made access., fuel cell B13.10 107738 C-12A vacated) IS1 PEI-02.05.05 VT-3 AREVA-RPT NRI Reactor Vessel IS1 Fig 0 3/31/2007 102668 N- 2G NV Core Plate (areas made access., fuel cell 813.10 vacated) IS1 PEI-02.05.05 VT-3 AREVA-RPT NRI Reactor Vessel IS1 Fig 0 3/31 I2007 Page 4 of 19 NIS-1 Attachment (Appendix A) Cycle 22 Inservice Inspection Report (2007 RFO) Owner: Xcel Energy, LLC, 800 Nicollet Mall, Minneapolis, MN 55402 Operator: Nuclear Management Company, LLC, 700 First Street, Hudson, WI 54016 Plant: Monticello Nuclear Generating Plant, Unit 1, 2807 West County Rd

75, Monticello, MN 55362 Owner Certificate of Authorization (If Req.): N/A Commercial Service Date:

613011 971 National Board Number for Unit:

N/A Summary No. Comp ID Comp Desc. Category Item Procedure Method/Sheet/Results System IS0 Num Exam Date Class 1 Category B-N-2, EXAMS PERFORMED FOR IS1 (4th Interval, Period 2 Credited Exams) 107691 C-3C Shroud Shelf H-9 Weld 0-180 deg PEI-02.05.05 VT-3 AREVA-RPT NRI Reactor Vessel IS1 Fig 0 3/31 12007 B13.30 IS1 107692 C-3D Shroud Shelf H-9 Weld 180-360 deg PEI-02.05.05 VT-3 AREVA-RPT NRI Reactor Vessel IS1 Fig 0 3/31 12007 B13.30 IS1 107739 Core Plate (areas made access., fuel cell B13.40 C-12B vacated) IS1 PEI-02.05.05 VT-3 AREVA-RPT NRI Reactor Vessel IS1 Fig 0 3/31/2007 107744 Fuel Spt Cast (areas access, fuel cell B13.40 C-I 7A vacated) IS1 PEI-02.05.05 VT-3 AREVA-RPT NRI Reactor Vessel IS1 Fig 0 3/31 12007 107746 Ctrl Rod Guide Tube - Int (when B13.40 C-18 accessible) PEI-02.05.05 VT-3 AREVA-RPT NRI Reactor Vessel IS1 Fig 0 3/31/2007 IS1 107747 Shroud Shelf 0-180 deg PEI-02.05.05 VT-3 AREVA-RPT NRI Reactor Vessel IS1 Fig 0 3/31 12007 B13.40 C-3E IS1 107748 C-3F Shroud Shelf 180-360 deg PEI-02.05.05 VT-3 AREVA-RPT NRI Reactor Vessel IS1 Fig 0 3/31 12007 813.40 IS1 Class 1 Category F-A, EXAMS PERFORMED FOR IS1 (4th Interval, Period 2 Credited Exams) and PSI 100582 Snubber 1 Clamp PEI-02.05.02 VT 200M022 NRI Main Steam A ISI-13142-33-A 311 512007 Fl.lOb H- 6 PSI IS1 PEI-02.05.02 VT 2007VT021 NRI Main Steam A ISI-13142-33-A 311 512007 100682 H- 2 Snubber 1 Clamp PEI-02.05.02 VT 200M013 NRI Main Steam C ISI-13142-35-A 311 512007 Fl.lOb PSI 100683 H- 3 Snubber I Clamp PEI-02.05.02 VT 200M012 NRI Main Steam C ISI-I 3142-35-A 311 512007 Fl.lOb PSI 101198 H- 4 Snubber / Clamp PEI-02.05.02 VT 2007VT717 NRI Feedwater ISI-13142-52-A 313012007 Fl.lOb PSI 101201 H- 7 Snubber I Clamp PEI-02.05.02 VT 2007Vr713 NRI Feedwater Fl.lOb PSI ISI-13142-52-A 3/30/2007 Page 5 of 19 NIS-1 Attachment (Appendix A) Cycle 22 Inservice Inspection Report (2007 RFO) Owner: Xcel Energy, LLC, 800 Nicollet Mall, Minneapolis, MN 55402 Operator: Nuclear Management Company, LLC, 700 First Street, Hudson, WI 54016 Plant: Monticello Nuclear Generating Plant, Unit 1, 2807 West County Rd #75, Monticello, MN 55362 Owner Certificate of Authorization (If Req.): NIA Commercial Service Date:

613011 971 National Board Number for Unit:

NIA Summary No. Comp ID Comp Desc. Category Item Procedure MethodISheetlResults System IS0 Num Exam Date 101253 H- 5 Snubber I Clamp PEI-02.05.02 VT 2007VT710 NRI Feedwater ISI-13142-53-A 313012007 Fl.lOb PSI 101 255 H- 7 Snubber I Clamp PEI-02.05.02 VT 2007VT482 NRI Feedwater Fl.lOb PSI ISI-13142-53-A 3/31/2007 101 855 Snubber I Clamp PEI-02.05.02 VT 200M016 NRI RHR Return A ISI-97003-A 311 412007 Fl.lOb H- 3 PSI 101 896 H- 2 Snubber I Clamp RHR Suction A ISI-97003-B 41512007 Fl.lOb PSI PEI-02.05.02 VT 2007VT709 NRI PSI PEI-02.05.02 VT 2007VT014 NRI RHR Suction A ISI-97003-B 311 412007 101 934 H- 2 VariablelSlidelClamp PEI-02.05.02 VT 2007VT030 NRI RHR Return B ISI-97004-A 411 412007 Fl.10~ IS1 101 935 H- 3 Snubber I Clamp PEI-02.05.02 VT 2007VT484 NRI RHR Return B ISI-97004-A 313012007 Fl.lOb PSI 101 936 H- 4 Snubber I Clamp PEI-02.05.02 VT 200M481 NRI RHR Return B ISI-97004-A 313012007 Fl.lOb PSI 102027 Restraint PEI-02.05.02 VT 200M041 NRI Recirc Manifold A ISI-97005-B 312512007 Fl .lOa H-10 IS1 -- 105020 H-5A Hanger PEI-02.05.02 VT 200M026 NRI Head Vent ISI-782A 311 812007 Fl.lOa IS1 105022 Spring I Clamp PEI-02.05.02 VT 2007VT023 RI Head Vent ISI-782A 311 812007 Fl.10~ H-17 IS1 PSI PEI-02.05.02 VT 200M747 NRI Head Vent ISI-782A 411 412007 105023 Hanger PEI-02.05.02 VT 200M745 NRI Head Vent ISI-782A-A 411 212007 Fl.lOa H- I PSI 105024 H- 2 Spring I Clamp PEI-02.05.02 VT 2007W748 NRI Head Vent ISI-782A-A 411 212007 Fl.10~ PSI 105025 H- 3 Hanger PEI-02.05.02 VT 200M746 NRI Head Vent ISI-782A-A 411 212007 Fl.lOa PSI 107523 Dbl Spring 14 Lugs PEI-02.05.02 VT 200M029 NRI Reactor Wtr Cleanup ISI-73880-A 311 812007 Fl.10~ H- 3 IS1 Page 6 of 19 NIS-1 Attachment (Appendix A) Cycle 22 Inservice Inspection Report (2007 RFO) Owner: Xcel Energy, LLC, 800 Nicollet Mall, Minneapolis, MN 55402 Operator: Nuclear Management Company, LLC, 700 First Street, Hudson, WI 54016 Plant: Monticello Nuclear Generating Plant, Unit 1, 2807 West County Rd

75, Monticello, MN 55362 Owner Certificate of Authorization (If Req.): N/A Commercial Service Date: 6/30/1 971 National Board Number for Unit: NIA Summary No. Comp ID Comp Desc. Category Item Procedure MethodlSheetlResults System IS0 Num Exam Date Snubber / Lugs Fl.lOb 107528 H- 8 PEI-02.05.02 VT 2007VT712 NRI Recirculation A ISI-97005-A 3/31/2007 PSI PSI PEI-02.05.02 VT 200M020 NRI Recirculation A ISI-97005-A 311 512007 IS1 PEI-02.05.02 VT 2007VT019 NRI Recirculation A ISI-97005-A 311 512007 RodlClevis GriplLugslConstant-Support F1.40~ 107534 H- I PEI-02.05.02 VT 2007W-034 NRI Recirc Pump A ISI-97005-C 311 912007 IS1 107535 H- 2 RodlClevis GriplLugslConstant-Support PEI-02.05.02 VT 2007VT033 NRI Recirc Pump A ISI-97005-C 311 912007 F1.40~ IS1 H- 7 Snubber 1 Lugs PEI-02.05.02 VT ZOOM024 NRI Recirc Pump A ISI-97005-C 311 812007 F1.40b 107540 PSI H- 8 Snubber 1 Lugs PEI-02.05.02 VT 2007VT714 NRI Recirc Pump A ISI-97005-C 4/6/2007 F1.40b 107541 PSI 107542 H- 9 Snubber 1 Lugs PEI-02.05.02 VT 2007VT715 NRI Recirc Pump A ISI-97005-C 4/6/2007 F1.40b PSI H- 8 Snubber 1 Lugs PEI-02.05.02 VT ZOOM480 NRI Recirculation B Fl.lOb 107547 PSI ISI-97006-A 3/31/2007 RodIClevis GriplLugslConstant-Support F1.40~ 107555 H- 3 PEI-02.05.02 VT 2007VT485 NRI Recirc Pump B ISI-97006-C 3/29/2007 PSI Snubber / Lugs F1.40b 107559 H- 7 PEI-02.05.02 VT 200M025 NRI Recirc Pump B ISI-97006-C 311 812007 PSI I Class 1 Category RA(H), EXAMS PERFORMED FOR IS1 (4th Interval, Period 2 Credited Exams) 101874 W-I 5 Pipe-to-Elbow R1'l FP-PE-NDE-401 UT 2007UT118 NRI RHR Return A ISI-97003-A 3/27/2007 IS1 Page 7 of 19 NIS-1 Attachment (Appendix A) Cycle 22 Inservice Inspection Report (2007 RFO)

Owner: Xcel Energy, LLC, 800 Nicollet Mall, Minneapolis, MN 55402 Operator: Nuclear Management Company, LLC, 700 First Street, Hudson, WI 54016 Plant: Monticello Nuclear Generating Plant, Unit 1, 2807 West County Rd

75, Monticello, MN 55362 Owner Certificate of Authorization (If Req.): NIA Commercial Service Date: 613011 971 National Board Number for Unit: NIA Summary No. Comp ID Comp Desc.

Category Item Procedure Method/Sheet/Results System IS0 Num Exam Date Class 1 Category RA(L), EXAMS PERFORMED FOR IS1 (4th Interval, Period 2 Credited Exams), PSI, and AUGMENTED (HELB I SUPERPIPE) 10061 8 W-30 Pipe-to-Pipe R1'20 FP-PE-NDE-401 UT 2007UT068 NRI Main Steam A ISI-13142-33-A 311 712007 AUG AUG FP-PE-NDE-401 UT 2007UT067 NRI Main Steam A ISI-13142-33-A 311712007 10061 9 W-31 Pipe-to-Pipe R1'20 FP-PE-NDE-401 UT 2007UT066 NRI Main Steam A ISI-13142-33-A 311 712007 AUG AUG FP-PE-NDE-401 UT 2007UT065 GEO Main Steam A ISI-13142-33-A 311 712007 AUG FP-PE-NDE-401 UT 2007UT064 NRI Main Steam A ISI-13142-33-A 311 712007 100668 W-30 Pipe-to-Pipe R1.20 FP-PE-NDE-401 UT 2007UT005 NRI Main Steam B ISI-I 3142-34-A 311 612007 AUG AUG FP-PE-NDE-401 UT 2007UT004 GEO Main Steam B ISI-13142-34-A 3/16/2007 AUG FP-PE-NDE-401 UT 2007UT003 NRI Main Steam B ISI-13142-34-A 311612007 100669 W-31 Pipe-to-Pipe R1'20 FP-PE-NDE-401 UT 2007UT008 NRI Main Steam B ISI-13142-34-A 311 612007 AUG AUG FP-PE-NDE-401 UT 2007UT009 GEO Main Steam B ISI-I 3142-34-A 3/16/2007 AUG FP-PE-NDE-401 UT 2007UT010 NRI Main Steam B ISI-13142-34-A 311 612007 100670 W-32 Pipe-to-Pipe R1'20 FP-PE-NDE-401 UT 2007UT007 NRI Main Steam B ISI-13142-34-A 311 612007 AUG AUG FP-PE-NDE-401 UT 2007UT006 NRI Main Steam B ISI-13142-34-A 3/16/2007

_ - Page 8 of 19 NIS-1 Attachment (Appendix A) Cycle 22 Inservice Inspection Report (2007 RFO) 1 Owner: Xcel Energy, LLC. 800 Nicollet Mall, Minneapolis. MN 55402 i / Operator: Nuclear Management Company, LLC, 700 First Street, Hudson, WI 54016 I I Plant: Monticello Nuclear Generating Plant, Unit I, 2807 West County Rd #75, Monticello, MN 55362 Owner Certificate of Authorization (If Req.): NIA Commercial Service Date: 613011 971 National Board Number for Unit: NIA Summary No. Comp ID Comp Desc.

Category Item Procedure MethodISheetlResults System IS0 Num Exam Date 100720 W-30 Pipe-to-Pipe R1'20 FP-PE-NDE-401 UT 2007UT030 NRI AUG Main Steam C ISI-13142-35-A 311 612007 AUG FP-PE-NDE-401 UT 2007UT031 GEO Main Steam C ISI-13142-35-A 311 612007 AUG FP-PE-NDE-401 UT 2007UT032 NRI Main Steam C ISI-13142-35-A 3/16/2007 10072 1 W-31 Pipe-to-Pipe R1'20 FP-PE-NDE-401 UT 2007UT035 NRI AUG Main Steam C ISI-13142-35-A 3/16/2007 AUG FP-PE-NDE-401 UT 2007UT033 NRI Main Steam C ISI-13142-35-A 3/16/2007 AUG FP-PE-NDE-401 UT 2007UT034 NRI Main Steam C ISI-13142-35-A 311 612007 .- 100722 W-32 Pipe-to-Pipe R1.20 FP-PE-NDE-401 UT 2007UT037 NRI AUG Main Steam C ISI-13142-35-A 311 612007 AUG FP-PE-NDE-401 UT 2007UT038 NRI Main Steam C ISI-I 3142-35-A 311 612007 AUG FP-PE-NDE-401 UT 2007UT036 NRI Main Steam C ISI-13142-35-A 311 612007 100723 W-33 Pipe-to-Pipe R1'20 FP-PE-NDE-401 UT 2007UT039 NRI AUG Main Steam C ISI-13142-35-A 3/16/2007 AUG FP-PE-NDE-401 UT 2007UT040 NRI Main Steam C ISI-13142-35-A 311 612007 AUG FP-PE-NDE-401 UT 2007UT041 NRI Main Steam C 1st-13142-35-A 311 612007 100778 W-32 Pipe-to-Pipe R1.20 FP-PE-NDE-401 UT 2007UT002 GEO AUG Main Steam D ISI-I 3142-36-A 311 612007 AUG FP-PE-NDE-401 UT 2007UT023 NRI Main Steam D ISI-13142-36-A 3/16/2007 AUG FP-PE-NDE-401 UT 2007UT001 NRI Main Steam D ISI-13142-36-A 3/16/2007 100779 W-33 Pipe-to-Pipe R1'20 FP-PE-NDE-401 UT 2007UT026 NRI AUG Main Steam D ISI-13142-36-A 3/16/2007 AUG FP-PE-NDE-401 UT 2007UT025 NRI Main Steam D ISI-I 3142-36-A 311 612007 AUG FP-PE-NDE-40f UT 2007UT024 NRI Main Steam D ISI-13142-36-A 311 612007 100780 W-34 Pipe-to-Pipe R1.20 FP-PE-NDE-401 UT 2007UT028 GEO AUG Main Steam D ISI-I 3142-36-A 311612007 AUG FP-PE-NDE-401 UT 2007UT027 NRI Main Steam D ISI-13142-36-A 311612007 AUG FP-PE-NDE-401 UT 2007UT029 NRI Main Steam D ISI-I 3142-36-A 3/16/2007 Page 9 of 19 NIS-1 Attachment (Appendix A) Cycle 22 Inservice Inspection Report (2007 RFO) Owner: Xcel Energy, LLC, 800 Nicollet Mall, Minneapolis, MN 55402 Operator: Nuclear Management Company, LLC, 700 First Street, Hudson, WI 54016 Plant: Monticello Nuclear Generating Plant, Unit 1, 2807 West County Rd

75, Monticello, MN 55362 Owner Certificate of Authorization (If Req.): NIA Commercial Service Date:

6/30/1971 National Board Number for Unit: NIA Summary No. Comp ID Comp Desc. Category Item Procedure MethodISheetlResults System IS0 Num Exam Date 101 056 W-14 Pipe-to-Valve R1.20 FP-PE-NDE-401 UT 2007UT062 NRI RClC Steam lsl-13142-43-A 3/21/2007 AUG AUG FP-PE-NDE-401 UT 2007UT063 GEO RClC Steam 181-13142-43-A 3/21/2007 101 529 W- 7 Tee-to-Pipe PEI-02.01 .O1 PT 2007PT003 NRI MS Condensate Lkoff ISI-786A 4/1/2007 R1.20 PSI 101530 W- 8 Valve-to-Pipe PEI-02.01 .O1 PT 2007PT004 NRI MS Condensate Lkoff ISI-786A 1 12512007 R1.20 PSI 101 531 W- 9 Elbow-to-Pipe PEI-02.01 .O1 PT 2007PT005 NRI MS Condensate Lkoff ISI-786A 1 /25/2007 R1.20 PSI 101 535 W-I 3 Pipe-to-Pipe PEI-02.01 .O1 PT 2007PT006 NRI MS Condensate Lkoff ISI-786A 4/4/2007 R1.20 PSI 101 536 W-14 Pipe-to-Valve MS Condensate Lkoff ISI-786A 2/6/2007 R1.20 PSI PEI-02.01 .O1 PT 2007PT007 NRI 107749 W-29~ pipe-to-pipe R1.20 FP-PE-NDE-~OI UT 2007UT082 NRI Main Steam A ISI-13142-33~

311 712007 IS1 IS1 FP-PE-NDE-401 UT 2007UT081 GEO Main Steam A ISI-13142-33-A 311 712007 AUG FP-PE-NDE-401 UT 2007UT080 NRI Main Steam A ISI-I 3142-33-A 311 712007 AUG FP-PE-NDE-401 UT 2007UT079 GEO Main Steam A ISI-13142-33-A 311 712007 AUG FP-PE-NDE-401 UT 2007UT077 NRI Main Steam A ISI-13142-33-A 311 712007 IS1 FP-PE-NDE-401 UT 2007UT078 NRI Main Steam A ISI-13142-33-A 3/17/2007 107751 W- 7A Pipe-to-Valve PEI-02.01 .O1 PT 2007PT008 NRI MS Condensate Lkoff ISI-786A 1 12512007 R1.20 PSI 107752 W- 9A Pipe-to-Pipe PEI-02.01 .O1 PT 2007PT009 NRI MS Condensate Lkoff ISI-786A 411 12007 R1.20 PSI Page 10 of 19 NIS-1 Attachment (Appendix A) Cycle 22 Inservice Inspection Report (2007 RFO) Owner: Xcel Energy, LLC, 800 Nicollet Mall, Minneapolis, MN 55402 Operator:

Nuclear Management Company, LLC, 700 First Street, Hudson, WI 54016 Plant: Monticello Nuclear Generating Plant, Unit 1, 2807 West County Rd

75, Monticello, MN 55362 Owner Certificate of Authorization (If Req.): N/A Commercial Service Date:

6/30/1 971 National Board Number for Unit: NIA I Summary No. Comp ID Comp Desc. Category Item Procedure Method/Sheet/Results System IS0 Num Exam Date Class 1 Category RA(M), EXAMS PERFORMED FOR IS1 (4th Interval, Period 2 Credited Exams), PSI, and AUGMENTED (HELB I SUPERPIPE) 100439 W- 6 Valve-to-Pipe R1'20 FP-PE-NDE-401 UT 2007UT122 GEO Core Spray B ISI-13142-26-A 3/25/2007 AUG AUG FP-PE-NDE-401 UT 2007UT120 NRI Core Spray B ISI-13142-26-A 3/25/2007 AUG FP-PE-NDE-401 UT 2007UT121 GEO Core Spray B ISI-13142-26-A 3/25/2007 100440 W- 7 Pipe-to-Pipe R1.20 FP-PE-NDE-401 UT 2007UT128 GEO Core Spray B ISI-13142-26-A 3/25/2007 AUG I AUG FP-PE-NDE-401 UT 2007UT126 NRI Core Spray B ISI-13142-26-A 3/25/2007 AUG FP-PE-NDE-401 UT 2007UT127 GEO Core Spray B ISI-13142-26-A 3/25/2007 100500 W- I Valve-to-Pipe R1'20 FP-PE-NDE-401 UT 2007UT072 GEO Core Spray A ISI-I 3142-31-A 3/18/2007 AUG AUG FP-PE-NDE-401 UT 2007UT071 NRI Core Spray A ISI-13142-31-A 3/18/2007 100501 W- 2 Pipe-to-Pipe R1'20 FP-PE-NDE-401 UT 2007UT074 GEO Core Spray A ISI-13142-31-A 3/18/2007 IS1 I IS1 FP-PE-NDE-401 UT 2007UT073 NRI Core Spray A ISI-13142-31-A 3/18/2007 100591 W- 3 Elbow-to-Pipe R1'20 FP-PE-NDE-401 UT 2007UT137 NRI Main Steam A ISI-13142-33-A 3/27/2007 IS1 IS1 FP-PE-NDE-401 UT 2007UT133 NRI Main Steam A ISI-13142-33-A 3/27/2007 100642 W- 4 Pipe-to-Elbow R1'20 FP-PE-NDE-401 UT 2007UT132 NRI Main Steam B ISI-13142-34-A 3/27/2007 IS1 IS1 FP-PE-NDE-401 UT 2007UT136 NRI Main Steam B ISI-13142-34-A 3/27/2007 101219 W-I 3 Elbow-to-Pipe R1'20 FP-PE-NDE-401 UT 2007UT076 GEO Feedwater ISI-13142-52-A 3/22/2007 IS1 IS1 FP-PE-NDE-401 UT 2007UT075 NRI Feedwater ISI-13142-52-A 3/22/2007 I 1 Page 11 of 19 NIS-1 Attachment (Appendix A) Cycle 22 Inservice Inspection Report (2007 RFO) Owner: Xcel Energy, LLC, 800 Nicollet Mall, Minneapolis, MN 55402 Operator: Nuclear Management Company, LLC, 700 First Street, Hudson, WI 54016 Plant: Monticello Nuclear Generating Plant, Unit 1, 2807 West County Rd

75, Monticello, MN 55362 Owner Certificate of Authorization (If Req.): N/A Commercial Service Date: 613011971 National Board Number for Unit: NIA Summary No. Comp ID Comp Desc. Category Item Procedure MethodISheetlResults System IS0 Num Exam Date - 101232 W-26 Tee-to-Reducer R1.18 FP-PE-NDE-401 UT 2007UT021 NRI Feedwater ISI-13142-52-A 311 712007 IS1 IS1 FP-PE-NDE-401 UT 2007UT022 NRI Feedwater ISI-13142-52-A 311 712007 101233 W-27 Reducer-to-Pipe R1 FP-PE-NDE-401 UT 2007UT020 NRI IS1 Feedwater ISI-13142-52-A 311 712007 IS1 FP-PE-NDE-401 UT 2007UT019 NRI Feedwater ISI-13142-52-A 311 712007 101 371 W- 6 LS U Pipe-to-Elbow R1.20 FP-PE-NDE-401 UT 2007UT088 NRI Reactor Wtr Cleanup ISI-73880-A 311 812007 IS1 IS1 FP-PE-NDE-401 UT 2007UT087 NRI Reactor Wtr Cleanup ISI-73880-A 311 812007 101 379 W-14 LS pipe-to-pipe Reactor Wtr Cleanup ISI-73880-A 311 812007 U&D R1 '20 FP-PE-NDE-401 UT 2007UT085 NRI IS1 IS1 FP-PE-NDE-401 UT 2007UT086 NRI Reactor Wtr Cleanup ISI-73880-A 311 812007 101 380 W-15 LS U Pipe-to-Elbow R1.20 FP-PE-NDE-401 UT 2007UT084 NRI Reactor Wtr Cleanup ISI-73880-A 311 812007 IS1 IS1 FP-PE-NDE-401 UT 2007UT083 NRI Reactor Wtr Cleanup ISI-73880-A 311 812007 101 391 W-26 Pipe-to-Valve R1 '20 FP-PE-NDE-401 UT 2007UT124 GEO Reactor Wtr Cleanup ISI-73880-A Y IS1 IS1 FP-PE-NDE-401 UT 2007UT123 NRI Reactor Wtr Cleanup ISI-73880-A 3/26/2007 101 860 W- 1 Valve-to-Pipe R1 .20 FP-PE-NDE401 UT 2007UT129 NRI RHR Return A ISI-97003-A 3/28/2007 AUG AUG FP-PE-NDE-401 UT 2007UT131 NRI RHR Return A ISI-97003-A 3/28/2007 AUG FP-PE-NDE-401 UT 2007UT130 GEO RHR Return A ISI-97003-A 312812007 101866 W- 7 Elbow-to-Pipe R1'll FP-PE-NDE-401 UT 2007UT119 NRI RHR Return A ISI-97003-A 3/27/2007 IS1 101 997 W- LS Pipe-to-Elbow Recirculation A ISI-97005-A 311 712007 U&D R1'20 FP-PE-NDE-402 UT 2007UT048 NRI IS1 IS1 FP-PE-NDE-402 UT 2007UT047 NRI Recirculation A ISI-97005-A 311 712007 101 998 W- LS Elbow-to-Pipe Recirculation A ISI-97005-A 311 712007 U&D R1 .20 FP-PE-NDE-402 UT 2007UT046 NRI IS1 IS1 FP-PE-NDE-402 UT 2007UT045 NRI Recirculation A ISI-97005-A 311 712007 Page 12 of 19 NIS-1 Attachment (Appendix A) Cycle 22 Inservice Inspection Report (2007 RFO)

I I Owner: Xcel Energy, LLC, 800 Nicollet Mall, Minneapolis, MN 55402 1 Operator: Nuclear Management Company.

LLC, 700 First Street. Hudson. WI 54016 1 Plant: Monticello Nuclear Generating Plant, Unit 1, 2807 West County Rd

75, Monticello, MN 55362 Owner Certificate of Authorization (If Req.): N/A Commercial Service Date: 6/3011971 National Board Number for Unit: N/A I Summary No. Comp ID Comp Desc. Category Item Procedure MethodlSheetlResuIts System IS0 Num Exam Date 102003 W- LS Pipe-to-Bent Pipe Recirculation A ISI-97005-A 311 812007 U&D R1'20 FP-PE-NDE-402 UT 2007UTOll NRI IS1 IS1 FP-PE-NDE-402 UT 2007UT012 NRI Recirculation A ISI-97005-A 311 812007 102041 W-1 I Safe End-to-Nozzle PEI-02.01 .O1 PT 2007PT002 NRI Recirc Manifold A 1st-97005-B 312612007 R1.20 PSI IS1 FP-PE-NDE-410 UT 2007UT108 NRI Recirc Manifold A ISI-97005-B 3/26/2007 IS1 FP-PE-NDE-410 UT 2007UT106 NRI Recirc Manifold A ISI-97005-B 3/26/2007 IS1 FP-PE-NDE-410 UT 2007UT107 NRI Recirc Manifold A ISI-97005-B 312612007 Comments:

Limited exam, reference Code Case N-460 102164 W-25 Safe End-to-Nozzle R1'20 FP-PE-NDE-410 UT 2007UT110 NRI Recirc Manifold B ISI-97006-B 3/22/2007 IS1 IS1 FP-PE-NDE-410 UT 2007UT109 NRI Recirc Manifold B ISI-97006-B 3/22/2007 IS1 FP-PE-NDE-410 UT 2007UTl I I NRI Recirc Manifold B ISI-97006-B 3/22/2007 Comments:

Limited exam less than 90% coverage - Relief Request required 10221 1 W-14 Pipe-to-Elbow R1'20 FP-PE-NDE-401 UT 2007UT090 GEO IS1 RHR Equalizer ISI-97027-A 311 812007 IS1 FP-PE-NDE-401 UT 2007UT089 GEO RHR Equalizer ISI-97027-A 311 812007 IS1 FP-PE-NDE-401 UT 2007UT091 GEO RHR Equalizer ISI-97027-A 311 812007 10221 2 W-I 5 Pipe-to-Elbow R1.20 FP-PE-NDE-401 UT 2007UT094 NRI IS1 RHR Equalizer ISI-97027-A 311 812007 IS1 FP-PE-NDE-401 UT 2007UT093 GEO RHR Equalizer ISI-97027-A 311 812007 IS1 FP-PE-NDE-401 UT 2007UT092 GEO RHR Equalizer 1st-97027-A 311 812007 -- Page 13 of 19 NIS-1 Attachment (Appendix A) Cycle 22 Inservice Inspection Report (2007 RFO) Owner: Xcel Energy, LLC, 800 Nicollet Mall, Minneapolis, MN 55402 Operator: Nuclear Management Company, LLC, 700 First Street, Hudson, WI 54016 Plant: Monticello Nuclear Generating Plant, Unit 1, 2807 West County Rd

75, Monticello, MN 55362 Owner Certificate of Authorization (If Req.): N/A Commercial Service Date: 6/30/1 971 National Board Number for Unit: N/A Summary No. Comp ID Comp Desc. Category Item Procedure Method/Sheet/Results System IS0 Num Exam Date Class 2 Category C-C, EXAMS PERFORMED FOR IS1 (4th Interval, Period 2 Credited Exams) and PSI 10081 5 H- 3 Strut 18 Lugs Containment Spray C3.20 IS1 PEI-02.02.01 MT 2007MT003 NRI ISI-13142-37-B 313012007 100978 H- 3 Dbl Spring 14 Lugs HPCI Steam C3.20 IS1 PEI-02.02.01 MT 2007MT002 NRI ISI-13142-42-A 3/20/2007 102753 Support' pump support C3.30 Pump A IS1 PEI-02.02.01 MT 2007MT004 NRI Core Spray Pumps ISI-49 4/4/2007 107616 H- 5 Variable I Support PEI-02.02.01 MT 2007MT001 NRI Core Spray B C3.20 IS1 ISI-I 3142-20-B 311 812007 107650 H- 4 Slide PEI-02.01 .O1 PT 2007PT001 NRI RHR Suction B C3.20 PSI ISI-13142-17-C 4/7/2007 Class 2 Category FA, EXAMS PERFORMED FOR IS1 (4th Interval, Period 2 Credited Exams) and PSI 100098 H- I Rod 1 Clevis PEI-02.05.02 VT 200M040 NRI HPCl Water Side Sctn ISI-13142-17-B 3/22/2007 F1.20a IS1 1001 31 H- 4 Slide PEI-02.05.02 VT 2007!ll720 NRI RHR Suction B F1.20b PSI ISI-13142-17-C 4/7/2007 1001 32 H- 5 Strut I Clamp PEI-02.05.02 VT 200M721 NRI RHR Suction B F1.20b PSI ISI-13142-17-C 4/7/2007 100168 H-I Spring I Clamp PEI-02.05.02 VT 2007W-750 NRI RHR Discharge B F1.20~ IS1 ISI-13142-18-A 3/22/2007 100263 H-I Snubber 1 Clamp PEI-02.05.02 VT 200M483 NRI HPCl Steam Disch F1.20b PSI ISI-13142-19-A 4/1/2007 100365 H- 5 Variable I Support PEI-02.05.02 VT 2007VT027 NRI Core Spray B F1.20a IS1 ISI-13142-20-B 3/18/2007 Page 14 of 19 NIS-1 Attachment (Appendix A) Cycle 22 Inservice Inspection Report (2007 RFO) Owner: Xcel Energy, LLC, 800 Nicollet Mall, Minneapolis, MN 55402 Operator: Nuclear Management Company, LLC, 700 First Street, Hudson, WI 54016 Plant: Monticello Nuclear Generating Plant, Unit 1, 2807 West County Rd

75, Monticello, MN 55362 -. Owner Certificate of Authorization (If Req.): NIA Commercial Service Date: 613011 971 National Board Number for Unit: NIA Summary No. Comp ID Comp Desc. Category Item Procedure MethodISheetlResults System IS0 Num Exam Date 100824 H- 9 Spring I Clamp Containment Spray ISI-13142-37-B 3/29/2007 F1.20~ IS1 PEI-02.05.02 VT 2007VT456 NRI 100879 H- 5 Snubber I Clamp PEI-02.05.02 VT 2007VT749 NRI HPCl Water Side Dsch ISI-13142-40-A 4/6/2007 F1.20b PSI 100987 H-1 1 Snubber I Clamp PEI-02.05.02 VT 2007VT015 NRI HPCl Steam ISI-13142-42-A 311 612007 F1.20b PSI PSI PEI-02.05.02 VT 2007VT716 NRI HPCl Steam ISI-13142-42-A 4/7/2007 101 682 DVMX Supp DVMX pump support F1.40a A IS1 PEI-02.05.02 VT 2007VT008 NRI HPCl Pumps 181-8292-42A 311 412007 101683 DVMX DVMX pump support F1.40a B IS1 PEI-02.05.02 VT 2007VT005 NRI HPCl Pumps 181-8292-42A 311 412007 101684 DVMX Supp DVMX pump support F1.40a C IS1 PEI-02.05.02 VT 2007VT006 NRI HPCl Pumps ISI-8292-42A 311 412007 101688 DVS Supp C DVS Pump Support PEI-02.05.02 VT 2007VT007 NRI HPCl Pumps lSl-82924%

311 412007 F1.40a IS1 101689 DVS Supp D DVS Pump Support PEI-02.05.02 VT 2007VT009 NRI HPCl Pumps 181-8292-42A 311 412007 F1.40a IS1 101710 H- 9 Strut I Clamp CRD Scram Header A ISI-93268-1A 311 512007 F1.20b IS1 PEI-02.05.02 VT 2007VT018 NRI 101713 H-12 Snubber1 Clamp PEI-02.05.02 VT 200M017 NRI CRD Scram Header A ISI-93268-1A 311 512007 F1.20b PSI 101715 H-14 Snubber I Clamp PEI-02.05.02 VT 2007VT028 NRI CRD Scram Header A ISI-93268-1A 311 912007 F1.20b PSI 102741 Pump Supp pump support F1.40a A IS1 PEI-02.05.02 VT 2007VT002 NRI RClC Turbine & Pump ISI-47 311 412007 102742 Pump Supp pump support F1.40a B IS1 PEI-02.05.02 VT 200NT001 NRI RClC Turbine & Pump ISI-47 311 412007 102743 Pump Supp pump support F1.40a C IS1 PEI-02.05.02 VT 2007VT004 NRI RClC Turbine & Pump ISI-47 311 412007 102744 Pump pump support F1.40a D IS1 PEI-02.05.02 VT 2007VT003 NRI RClC Turbine & Pump ISI-47 311 412007 Page 15 of 19 NIS-1 Attachment (Appendix A) Cycle 22 Inservice Inspection Report (2007 RFO) Owner: Xcel Energy, LLC, 800 Nicollet Mall, Minneapolis, MN 55402 Operator: Nuclear Management Company, LLC, 700 First Street, Hudson, WI 54016 Plant: Monticello Nuclear Generating Plant, Unit 1, 2807 West County Rd

75, Monticello, MN 55362 Owner Certificate of Authorization (If Req.): N/A Commercial Service Date:

6/30/1 971 National Board Number for Unit:

N/A Summary No. Comp ID Comp Desc. Category Item Procedure Method/Sheet/Results System IS0 Num Exam Date 106042 H- 2 Snubber I Clamp F1.20b PEI-02.05.02 VT 2007VT708 NRI Vacuum Relief & CGCS ISI-94966-A PSI Outlet Div.1 4/6/2007 106044 H-4 Snubber I Clamp F1.20b PEI-02.05.02 VT 2007VT707 NRI Vacuum Relief & CGCS PSI Outlet Div.

I ISI-94966-A 4/6/2007 10681 0 H- I Double Snubber PEI-02.05.02 VT 2007VT719 NRI RClC Steam Discharge ISI-13142-19-B 4/5/2007 F1.20b PSI PSI PEI-02.05.02 VT 2007VT718 NRI RClC Steam Discharge ISI-13142-19-8 4/5/2007 106820 H-I Snubber PEI-02.05.02 VT 2007VT042 NRI CORE SPRAY B ISI-13142-26-B 3/25/2007 F1.20b PSI 106825 H- 6 RESTRAINT HANGER TWH-121 PEI-02.05.02 VT 2007VT476 NRI CORE SPRAY B 181-1 3142-26-8 3/22/2007 F1.20a IS1 106838 H- 9 Restraint Hanger PEI-02.05.02 VT 2007VT445 NRI Core Spray B Discharge ISI-13142-264 3/27/2007 F1.20a PSI 106881 H-2 Restraint Hanger PEI-02.05.02 VT 2006VT001 NRI Core Spray A Discharge ISI-13142-31-D 12/19/2006 F1.20a PSI 106996 H- 7 Seismic Restraint PEI-02.05.02 VT 200M478 NRI F1.20a Fuel Pool Emergency IS1 Cooling 181-1 3142-67 4/2/2007 107049 H-2 Snubber PEI-02.05.02 VT 2007W711 NRI RHR A ISI-13142-37-E 4/6/2006 F1.20b PSI 107573 H- 2 Strut 18 Lugs PEI-02.05.02 VT 2007VT458 NRI Containment Spray ISI-13142-37-B 313012007 F1.20b IS1 107574 H- 3 Strut 18 Lugs PEI-02.05.02 VT 200M457 NRI Containment Spray ISI-13142-37-B 313012007 F1.20b IS1 107579 H- 3 Dbl Spring 14 Lugs PEI-02.05.02 VT 200M039 NRI HPCl Steam ISI-13142-42-A 312012007 F1.20~ IS1 107589 H-14 Tanksupport PEI-02.05.02 VT 2007VT010 NRI CRD Scram Header B lSl-93268-3A 311 512007 F1.20a IS1 107594 SuppOrtl pump support F1.40a Pump A IS1 PEI-02.05.02 VT 200M699 NRI Core Spray Pumps ISI-49 4/4/2007 107750 H-1A SEISMIC RESTRAINT HANGER PEI-02.05.02 VT 2007W700 NRI CORE SPRAY B 181-1 3142-26-8 3/29/2007 F1.20a PSI Page 16 of 19 NIS-1 Attachment (Appendix A) Cycle 22 Inservice Inspection Report (2007 RFO) Owner: Xcel Energy, LLC, 800 Nicollet Mall, Minneapolis, MN 55402 Operator: Nuclear Management Company, LLC, 700 First Street, Hudson, Wl 54016 Plant: Monticello Nuclear Generating Plant, Unit 1, 2807 West County Rd #75, Monticello, MN 55362 ! Owner Certificate of Authorization (If Req.): N/A Commercial Service Date: 613011971 National Board Number for Unit: NIA I Summary No. Comp ID Comp Desc. Category Item Procedure MethodISheetlResults System IS0 Num Exam Date I Class 2 Category R-A(M), EXAMS PERFORMED FOR IS1 (4th Interval, Period 2 Credited Exams) 100945 W-20 Pipe-to-Elbow R1.20 FP-PE-NDE-401 UT 2007UT015 NRI IS1 HPCl Water Side Dsch 181-1 314240-8 312012007 IS1 FP-PE-NDE-401 UT 2007UT016 NRI HPCl Water Side Dsch ISI-13142-40-B 312012007 1 1 100948 W-23 Elbow-to-Pipe R1.20 FP-PE-NDE-401 UT 2007UT044 GEO IS1 HPCl Water Side Dsch ISI-13142-40-8 312012007 1 I IS1 FP-PE-NDE-401 UT 2007UT043 GEO HPCl Water Side Dsch 181-13142-40-8 312012007 1 IS1 FP-PE-NDE-401 UT 2007UT042 NRI HPCl Water Side Dsch 181-13142-40-8 312012007 100962 W-I 3 Pipe-to-Tee R1'20 FP-PE-NDE-401 UT 2007UT070 NRI RClC Water Suction ISI-13142-41-A 311 812007 IS1 IS1 FP-PE-NDE-401 UT 2007UT069 NRI RClC Water Suction ISI-13142-41-A 3/18/2007 Class 3 Category FA, EXAMS PERFORMED FOR IS1 (4th Interval, Period 2 Credited Exams) and PSI 102243 SWH-304 Double Spring nd-isi-I 02 3/29/2007 F1.30~ IS1 PEI-02.05.02 VT 200M455 NRI RHR Service Water 102244 SWH-305 Base Plate RHR Service Water nd-isi-I 02 311 512007 F1.30a IS1 PEI-02.05.02 VT 200MOll NRI 102251 SR-396 Seismic Restraint RHR Service Water nd-isi-I03 411 112007 F1.30a PSI PEI-02.05.02 VT 2007VT733 NRI 102303 SR-385 Strut RHR Service Water nd-isi-108 312812007 F1.30b PSI PEI-02.05.02 VT 2007Vr447 NRI 102326 SR-88 Stanchion PEI-02.05.02 VT 2007VT038 NRI RHR Service Water nd-isi-1 11 311 812007 F1.30b IS1 Page 17 of 19 Owner: Xcel Energy, LLC, 800 Nicollet Mall, Minneapolis, MN 55402 Operator: Nuclear Management Company, LLC, 700 First Street, Hudson, WI 54016 Plant: Monticello Nuclear Generating Plant, Unit 1, 2807 West County Rd

75, Monticello, MN 55362 NIS-1 Attachment (Appendix A) Cycle 22 Inservice Inspection Report (2007 RFO) Owner Certificate of Authorization (If Req.): NIA Commercial Service Date: 613011971 National Board Number for Unit: NIA Summary No. Comp ID Comp Desc. Category Item Procedure MethodISheetlResults System IS0 Num Exam Date Class nla Category NON CODE, AUGMENTED EXAMS PERFORMED FOR THERMAL FATIGUE 105009 W- 1 Pipe-to-Pipe NCR95-068 FP-PE-NDE-401 UT 2007UT017 NRI RClC Feedwater NC-ISI-37 311 712007 AUG AUG FP-PE-NDE-401 UT 2007UT018 NRI RClC Feedwater NC-61-37 311 712007 10501 0 W- 2 Pipe-to-Tee NCR95-068 FP-PE-NDE-401 UT 2007UT014 GEO RClC Feedwater NC-ISI-37 311 712007 AUG AUG FP-PE-NDE-401 UT 2007UT013 NRI RClC Feedwater NC-ISI-37 311 712007 10501 I W- 3 ~ee-to-pipe NCR95-068 FP-PE-NDE-~OI UT 2007UT049 NRI RCIC Feedwater NC-ISI-37 311 712007 AUG AUG FP-PE-NDE-401 UT 2007UT050 GEO RClC Feedwater NC-ISI-37 311 712007 10501 2 W- 4 Tee-to-Elbow NCR95-068 FP-PE-NDE-401 UT 2007UT053 NRI RClC Feedwater NC-ISI-37 311 712007 AUG AUG FP-PE-NDE-401 UT 2007UT054 GEO RClC Feedwater NC-ISI-37 311 712007 10501 3 W-12 Pipe-to-Pipe NCR95-068 FP-PE-NDE-401 UT 2007UT055 NRI AUG RClC Feedwater NC-ISI-37 311 712007 AUG FP-PE-NDE-401 UT 2007UT056 GEO RClC Feedwater NC-ISI-37 311 712007 105014 W-12A Pipe-to-Tee NCR95-068 FP-PE-NDE-401 UT 2007UT052 NRI RClC Feedwater NC-ISI-37 311 712007 AUG AUG FP-PE-NDE-401 UT 2007UT051 NRI RClC Feedwater NC-ISI-37 311 712007 10501 6 W-1 1 Pipe-to-Tee CRD TO RWCU NC-ISI-51 312412007 NCR95-068 PEI-02.03.11 UT 2007UT112 NRI AUG I AUG PEI-02.03.11 UT 2007UT116 NRI CRD TO RWCU NC-ISI-51 3/24/2007 I AUG PEI-02.03.11 UT 2007UT117 GEO CRD TO RWCU NC-ISI-51 3/24/2007 AUG PEI-02.03.11 UT 2007UT115 NRI CRD TO RWCU NC-ISI-51 3/24/2007 AUG PEI-02.03.11 UT 2007UT114 NRI CRD TO RWCU NC-ISI-51 3/24/2007 AUG PEI-02.03.11 UT 2007UT113 NRI CRD TO RWCU NC-ISI-51 312412007 Page 18 of 19 NIS-1 Attachment (Appendix A) Cycle 22 Inservice Inspection Report (2007 RFO) Owner: Xcel Energy, LLC, 800 Nicollet Mall, Minneapolis, MN 55402 Operator:

Nuclear Management Company, LLC, 700 First Street, Hudson, WI 54016 Plant: Monticello Nuclear Generating Plant, Unit 1, 2807 West County Rd

75, Monticello, MN 55362 Owner Certificate of Authorization (If Req.): NIA Commercial Service Date: 6/30/1971 National Board Number for Unit: N/A Summary No. Comp ID Comp Desc. Category Item Procedure MethodISheetlResults System IS0 Num Exam Date 10501 7 W-12 Pipe-to-Tee NCR95-068 FP-PE-NDE-402 UT 2007UT098 NRI CRD TO RWCU NC-ISI-51 3/24/2007 AUG AUG FP-PE-NDE-402 UT 2007UT099 NRI CRD TO RWCU NC-ISI-51 3/24/2007 10501 8 W-13 Tee-to-Pipe NCR95-068 FP-PE-NDE-402 UT 2007UT096 NRI CRD TO RWCU NC-ISI-51 3/24/2007 AUG AUG FP-PE-NDE-402 UT 2007UT097 NRI CRD TO RWCU NC-ISI-51 3/24/2007 Page 19 of 19 Nuclear Management Company Monticello Inservice Inspection Cycle 23 Summary Report 2007 Refueling Outage APPENDIX B Reactor Vessel IWI Examinations (7 pages to follow)

AREVA Committed to N~rcloar Monticello Nuclear Generating Plant 2007 RFO-23 Refuel Outage In-Vessel Visual Examination Summary Report I. 0 In- Vessel Visual Examination Project Overview:

During the 2007 RFO-23 Monticello Nuclear Generating Plant refueling outage, comprehensive visual examinations of reactor vessel internal components were conducted to ensure the continued integrity of the RPV internals.

These examinations were conducted in accordance with Monticello procedure PEI-02.05.05, Revision 1. Additionally, all enhanced visual inspections (EVT-1) were performed per the recommendations set forth in BWRVIP-03.

Details of the examinations performed can be found in the individual component data sheets contained in Section 3 of this report. A synopsis of the components examined, the methods utilized, and the examination results are provided below. The following table shows the final scope of In-Vessel Visual Examinations, along with the examination techniques employed:

Core Spray Headers and Core Spray Headers and Downcomers on Loop B Committed to Nuclear Core Spray Sparger - D lncore Dry Tubes Shroud Head Bolts 1 - 36 Cornmittod to Nuclear H3,V7,V8,V9, J-H 1, J-H2, J-H3,V9AI K-HI , K-H2, K-H3,VIO,Vl 1, M-HI, M- H2, M-H3,Vl IA, N-HI, N-H2, N- H3,V12,V1 3,V14, P-HI, P-H2, P- H3,VI4Al Q-HI , Q-H2, Q-H3,V14BI R-HI , R-H2, R-H3,V14C, S-HI , S-H2, S-H3,V15,V16, T-HI , T-H2, T- H3,V16AI U-HI, U-H2, U- H3,V17,V18,V19, V-HI , V-H2, V- 1.2 Examination Results The examinations confirmed 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 90' core spray t-box to header weld in the 80°side header. e Crack indication in Lifting Lug 325" Jacking Bolt tack weld Crack indication in Dryer Weld V3 90 Crack indication in Dryer Weld V10 90 Crack indication in Dryer Weld VlO 270 Crack indication in 21 5" Dryer support Bracket Guide Channel Current RFO-23 lWl examinations identified the following new indications andlor conditions:

Crack indication in Dryer Weld VIO 90. Fifteen Shroud Head Bolts are incorrectly installed (Indicator window facing the Separator).

Crack indication on Drain Channel F access plate adjacent to Drain Pipe weld HI.

Committed to Nucfcar The equipment used during the Monticello In-Vessel Visual Examinations is as follows: Camera Systems k RJ Electronics RCS-8110 Camera System - RJ Electronics Camera with Pan and Tilt - RJ Electronics CCU - RJ Electronics Twin 35 Watt Light Unit > RJ Electronics RCS-600 Color Camera System - RCS 600 Camera - RJ Cable - RJCCU > [ST-Rees EN-1250 Black and White Camera System - IST-Reese 1250 Camera - IST-Reese Cable - IST-Reese CCU - Twin 50W Lighting System k REES B&W Camera System - R93 Camera - R93 Cable - R93 CCU > Deep Ocean Engineering ROV - Firefly Submersible - Sony IX-I I, CCD Camera - Quad 20W Onboard Lights - 175' Cable - CCU Monitors and Recording Equipment N Sharp 20" LCD Flat-Panel Color Monitors N Sony RDR-GX3OO DVD Recorders k Microphones Cleaning Equipment

> 10,000 PSI Hydrolazer Supplied by Monticello with AREVA NP Supplied Foot Pedal, Wands, and Weights AREVA Underwater Lights and Power Supply

> UL-212 35w Light > UL-210 35w Light > UL-210Cable

> PS-160 Power Supply > Birns 500w Light wlcable > Variac Sensitivity, Resolution and Contrast Standards

> SIN 7001 343 (DB# 14081) > SIN 7001 342 (DB# 14097) Support Equipment

> AREVA I" dia. Handling Poles (various lengths) > Videonics Titlemaker 3000 Character Generator

> Various Cables Level Ill Computer Work Station > I -Dell, PentiumTM 2.4G Computer Sony DVD & WRW CD-RAN Pinnacle Graphics Card Canon MP830 Color Printer 30 G Hard Drive 1 10 G Hard Drive > 2- 20 LCD Flat Panel Color Monitors

> 2-Sony DVD Recorder RDR-GX300

> I-Alera Technologies DVD Copy Cruiser, DVDICD Duplicator Committed ro Nuclear Monticello Nuclear Generating Plant 2007 RFO-23 Refuel Outage In-Vessel Visual Examination lndication History The following table provides a history of the indications that have been identified prior to RFO- 23 in the reactor vessel internal components at the Monticello Nuclear Generating Plant.

Component Steam Dryer Jet Pumps Shroud Legs Indication Steam Impingement Wear in Dryer Head in Areas of all Four Main Steam Nozzles Crack lndication in 325' Jacking Bolt Tack Weld - Unrepaired Crack lndication at the top of weld V3 90 Crack Indication at the top of weld VIO 90 Crack Indication on Dryer Support Bracket Guide weld at 215 Crack Indication at the top of weld V10 270 Crack lndication in Jet Pump #I 0 vessel Side Tack Weld - Unrepaired Crack lndication in Jet Pump #I4 Vessel Side Tack Weld - Repaired Crack indication in Jet Pump #I 5 Vessel Side Tack Weld - Repaired Crack indication in Jet Pump #I 8 Vessel Side Tack Weld - Repaired Crack indication in Jet Pump #I4 Beam Bolt retainer Tack Weld - Unrepaired Crack indication in Jet Pump #I9 Beam Bolt retainer Tack Weld - Unrepaired Crack lndication in Jet Pump #8 Secondary Riser Brace Lower Leaf to Block Weld in Leaf Material - Unrepaired Crack lndication in Jet Pump #I9 Secondary Riser Brace Lower Leaf to Block Weld in Block Material - Unrepaired Small 0.25 Inch Crack lndication Extending from Arc Strike in Jet Pump #20 Diffuser Weld DF Unrepaired Crack indication in 210' Shroud Support Leg to Shroud Support Cylinder Weld - Unrepaired Associated Engineering Evaluations CR20000209 CR98000794 CAP 037603 CAP 037603 CAP 037603 CAP 037603 CR20000209 SRI 94-019 SRI 94-01 SRI 94-01 CR98000794 CR98000794 SRI-89-028 CR20000209 Evaluated by NSP as Oxide Layer Break (Non-Relevant)

CR20000209 AREVA Comrnttcd fo Nuclear Associated Engineering Evaluations SRI-93-006 CR20000209 CAP 0381 42 Component Core Spray N11A and N11B Nozzles Surveillance Sample Holder Indication Crack lndication in 90' Tee Box Junction to Header - Repaired Removal of Typical Oxides from Nozzle Areas Due to Steam Flashing or Other Phenomena Bent Alignment Bracket on the 30 degree Surveillance Sample Holder Nuclear Management Company Monticello Inservice Inspection Cycle 23 Summary Report 2007 Refueling Outage APPENDIX C Page 1 of 2 System Pressure Test Examinations credited to Period 1 Note 1 : Partial test, when combined with the partial test performed during Cycle 22 (3/20/2005), satisfies completion of 4th Interval, Period 1 requirements.

Note 2: Partial tests, when combined, satisfy completion of 4@' Interval, Period 1 requirements.

Note 3: Partial test, when combined with the partial tests performed during Cycle 22 (3/19/05 and 3/20/05), satisfies completion of 4fi Interval, Period 1 requirements. System Pressure Test Examinations credited to Period 2 Results Satisfactory Satisfactory Satisfactory Partial, Satisfactory (see note 1) Partial, Satisfactory Partial, Satisfactory (see note 2) Partial, Satisfactory Partial Satisfactory (see note

2) Partial, Satisfactory (see note 3) Satisfactory Satisfactory Date(s) 12/20/05 11/16/05 5/22/06 9/9/05 11/3/05 4/21/06 2/26/06 3/14/06 10/5/05 1 011 0105 10/24/05 Test Number 0255-03-IIC-1 0255-03-IIC-2 0255-04-IE-3 0255-05-IIC-1 0255-05-IIC-2 0255-06-IIC-1 0255-1 1-1E-1 0255-1 1-11C-3-1 0255-1 1-11c-4-1 Procedure Title Core Spray System Leakage Test - Loop A Core Spray System Leakage Test - Loop B RHR Shutdown Cooling Suction Piping System Leakage Test RHR Service Water System Leakage Test - Loop A RHR Service Water System Leakage Test - Loop B HPCI System Leakage Test Emergency Service Water System Leakage Test - Loop A EDG-ESW System Leakage Test Loop A Accessible Pressure Boundary Components EDG-ESW System Leakage Test Loop B Accessible Pressure Boundary Components Results Satisfactory Date(s) 4/14/07 Test Number 0255-20-IIC-2 Title Reactor Coolant Boundary System Leakage Test Nuclear Management Company Monticello Inservice Inspection Cycle 23 Summary Report 2007 Refueling Outage APPENDIX C (continued) Page 2 of 2 Class 2 System Pressure Tests Per Code Case N-522 Credited to Period 2 Performed in accordance with 10CFR50, Appendix J Methodology Procedure No. 0 137-04 (0255-10-IIB-1) 0137-05 (0255-~o-IIB-~)

0137-18 (0255-17-IIB-1) 0137-19 (0255-17-IIB-2) 0137-22 (0255-26-IIB-

1) 0 137-24 (0255-10-IIB-3) 0137-27 ( 0255-18-IIB-1) 0137-30 (0255-17-IIB-3) 0137-3 1 (0255-13-IIB- 1) 0138 (0255-1 0-IIB-4) Results SAT Sec XI Boundary SAT Sec XI Boundary SAT Sec XI Boundary SAT Sec XI Boundary SAT Sec XI Boundary SAT Sec XI Boundary SAT Sec XI Boundary SAT Sec XI Boundary SAT Sec XI Boundary SAT Sec XI Boundary Procedure Title Primary Containment Purge and Vacuum Breaker, Pressure and Isolation Valve LLRT Test Primary Containment Nitrogen Control and Sampling System Valves Pressure and Local Leak Rate Test Instrument Air System Isolation Valves Pressure And Local Leak Rate Test Service Air System Isolation Valve Pressure and Local Leak Rate Test Demineralized Water Supply to Drywell Isolation Valve Pressure and Leak Rate Test Primary Containment Vent and Hard Pipe Vent Local Leak Rate Test TIP System Isolation Valves and Local Leak Rate Test Alternate N2 Supply Pressure and Local Leak Rate Test RBCCW System Isolation Valve Pressure and Local Leak Rate Test Drywell Personnel Airlock Pressure and Leak Test Test Date 411 1/07 313 1/07 3/27/07 3/22/07 4/10/07 4/13/07 3/16/07 3/24/07 3/26/07 411 5/07 Nuclear Management Company Monticello Inservice Inspection APPENDIX D Cycle 23 Summary Report 2007 Refueling Outage Page 1 of 1 Snubber Functional Testing The following snubbers were tested during Cycle 23 and the 2007 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 grouped into two groups: One main group of 146 (Bergen-Paterson) and 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 025 1 during the 2007 RFO. All snubbers were tested under one work order, 141385. Below is listed each individual work order that controlled removal, replacement if required and re-installation.

No. 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 Snubber Location SS-707 SS-357 CRD-H2 10 SS-14 SS-184 SS-3 16 SS-13 SS-38B CRD-H227 CRD-H232 RV-25-NS2 SS-2AR SS3AR SS-20 RV-25A-H2A RV-24-H5 Size 3 130 3 10 10 10 10 10 20 20 3 0 3 0 3 0 10 20 20 Test Results Passed Passed Passed Passed Passed Passed Passed Passed Passed Passed Passed Passed Passed Passed Passed Passed Work Order No. 141349 141350 141351 141353 141354 141355 141356 141359 141366 141371 141373 141375 141378 141382 153475 153475 Snubber Serial No.

700 400 538 500 040 03 5 171 033 099 214 020 005 145 539 478 016 Nuclear Management Company Monticello Inservice Inspection Cycle 23 Summary Report 2007 Refueling Outage APPENDIX E Engineering Evaluations per Subsection IWE-3122.4 (1992 Edition with 1992 Addenda) and lOCFR50.55a(b)(2)(ix)(D)

1. CAP CE 01 082766-03 for degraded containment nuclear coatings CAP CE 01082766-03 Attachment 1 CAP CE 01082766-03 Attachment 2 CAP CE 01082766-03 Attachment 3 (28 pages to follow) 411 2107 and 611 5107 Condition Evaluation Page 1 of 10 CAP Number: 0 1082766 Condition Evaluation Number:

0 1082766-03 Description of problem:

Subject:

Numerous small areas of PCT coatings failed acceptance Criteria Assignment Description Prepare a condition evaluation for the containment coatings that did not meet acceptance criteria. Evaluation Details:

==

Description:==

Numerous small areas of the Containment interior coatings did not meet the inspection procedure acceptance criteria. Comparison with previous performance of procedures 0135 and 0140 and IWE IS1 exams shows expected deterioration from the degradation already discussed in previous CAPS (Reference 8).

This condition has occurred because of the following:

1. Torus environment of -80 degrees F and 100% RH is harsh on the coating system. 2. Installation and removal of scaffolding over numerous outages have left the coating chipped in high traffic areas. 3. Lack of coating maintenance over the last several outages has lead to continue coating degradation.

The evaluation will address the following:

1. ASME code requirements.

2. Containment pressure boundary evaluation.

3. Containment debris loading and ECCS pump performance.

4. Future coating repair plans Page 1 of 10 4/12/07 and 6/15/07 Condition Evaluation Page 2 of 10 Evaluation Details: This Condition Evaluation (CE) was initiated to document the required engineering evaluation per ASME,Section XI IWE-3 122.4 (1992 edition with 1992 Addenda), lOCFR50.55a(b)(2)(ix)(D), and to satisfy the requirements of Fleet procedure FP-PA-ARP-01, CAP Action Request Process. Procedure FP-PA-ARP-0 1, section

3.4 states

"All personnel are responsible for identiQing conditions adverse to quality, such as failures, malfunctions, deficiencies, deviations, defective material and equipment, and non conformances." Areas in containment were identified that did not meet the acceptance criteria of the inspection procedures.

The inspection acceptance criteria is that the surface has no bare metal, little or no rusting on shell, and no flaking, peeling, blistering, cracking, or checking in excess of values established in CA 156. Primary Containment (Drywell and Suppression chamber) internal coated surfaces were inspected by plant engineering staff, and ASME IWE inspectors during the 2007 refueling outage. These examinations included the coated surfaces of the drywell, the vent lines and vent header, downcomers and the entire suppression pool surfaces. The procedures used were, 0140 DRYWELL INTERIOR SURFACE INSPECTION, 0135 PRESSURE SUPPRESSION CHAMBER PAINTED SURFACE INTERNAL INSPECTION, 1367 PRESSURE- SUPPRESSION CHAMBER BELOW WATER LINE PAINTED SURFACE INTERNAL INSPECTION and 05 15 PRIMARY CONTAINMENT VISUAL EXAMINATION FOR STRUCTURAL PROBLEMS. The observations made by these procedures include IWE inspection observations from work orders 135253 and 288456. These examinations satisfied ASME Table IWE-2500-1 examination categories El. 11, El .12, El .20 and E4.11.

Technical Specification compliance is not an issue associated with condition. MNGP Technical Specifications no longer contains the requirements of MNGP Custom Technical Specification 4.7.A.2.d and 4.7.A.l.c.

ASME Code Requirements The ASME,Section XI Table IWE-2500-1 requires general visual and VT-3 visual examinations of coated and uncoated surfaces of the containment vessel. IWE-35 10.2 VT-3 Visual Examinations of Coated areas states in part the following: "The inspected area, when painted or coated, shall be examined for evidence of flaking, blistering, peeling, discoloration, and other signs of distress.

Areas that are suspect shall be accepted by engineering evaluation or corrected by repair or replacement..

." The ASME,Section XI IWE-3 122.4, Acceptance by Evaluation states in part the following: "Components whose examination results reveal flaws or areas of degradation that do not meet the acceptance standards listed in Table IWE-3410-1 shall be acceptable for service without the removal or repair of the flaw or area of degradation or replacement if an engineering evaluation indicates that the flaw or area of degradation is nonstructural in nature or has no effect on the structural integrity of the containment. . . " Page 2 of 10 4/12/07 and 611 5/07 Condition Evaluation Page 3 of 10 CONTAINMENT PRESSURE BOUNDARY EVALUATION The following items provide facts concerning the containment pressure boundary: Ultrasonic testing performed by MDC in 1986 (MDC Document No. NSPT- 12-462

1) showed that the plate material used in the construction of the containment shell was thicker than that assumed in the design. Generally the plate thickness was at least 0.026" greater than that used in the CBI Certified Stress Report. Pacific Nuclear Calculation MN.9201 .0104 determined that a 0.00 1 " overall torus shell thickness reduction relative to design was acceptable for the pressure rating and Mark I hydrodynamic loads. Structural Integrity Associates justified localized shell reduction up to 0.3 12". When metallurgical boat samples of the torus shell were taken in 1991, cavities up to maximum depth of 0.3 12" were initially produced. These cavities were weld repaired but the structural integrity of the torus shell was evaluated without the cavities repaired. Structural Integrity Associates determined that the cavities could have been left in the torus in an unrepaired condition without violating required ASME Code margins.

Calculation CA-97-004 indicates that for carbon steel in the containment atmosphere the corrosion rate would be 0.0006" per year.

Automated Engineering Services Corp. determined the allowable pitting depth in the Torus shell and Submerged portions of the vent system downcorners, (Ref 9). The analysis determined the following as acceptable:

The containment pressure boundary including the suppression chamber, drywell, vent line and vent header and downcomers had General Visual examinations, VT-1 examinations, and VT-3 visual examinations during the 2007 refueling outage. These examinations are required by Table IWE-2500-1 Examinations Categories.

The general visual examinations were performed to satisfl Item El. 1 1 (General Visual Examination shall be performed prior to each Type A test). The VT-3 visual examinations were performed to satisfy Items El .12 and El .20 (VT-3 Description of Region Torus upper clean shell region Torus lower clean shell region Torus upper shell region near discontinuities Torus lower shell region near discontinuities Downcomer clear region Downcomer region near discontinuities examinations of coated and uncoated accessible surfaces of the containment vessel and vent system). Additionally, VT-1 examinations were performed as applicable to satisfy Item'E4.11 for areas previously identified by IWE that were dispositioned use-as-is. The observed areas of degradation (coatings and surface rust) are nonstructural in nature. No conditions that could affect the structural integrity were observed.

Thinning area diameter (inches) 12 13 15 16 1.25 2.5 Thinning depth (inches) 0.2 1 0.23 0.07 0.09 0.17 0.08 4/12/07 and 6/15/07 Condition Evaluation Page 4 of 10 DRYWELL EVALUATION The observations made by 0140 DRYWELL INTERIOR SURFACE INSPECTION are attached to this evaluation, Attachment

1. Coating degradation, consisting of rusting, flaking, discoloration and peeling were noted. In most areas of flaking, discoloration or peeling coatings the base coats were still intact. Work order 0291 852 was initiated to remove flaking and peeling coatings from the SRV discharge lines and to repair the degraded drywell, vent line and vent header coating. This work order removed the loose coatings from the SRV discharge lines. Repairs to the degraded drywell, vent line and vent header coating was not accomplished during the current 2007 refueling outage. The internal surfaces of the drywell, vent lines, vent header, and downcomers had General Visual, VT-3, and VT-1 visual examinations performed on them as applicable. The observed areas of degradation (coatings and surface rust) are nonstructural in nature. No conditions that could affect the structural integrity were observed. SUPPRESSION CHAMBER EVALUATION The observations made by 01 35 PRESSURE SUPPRESSION CHAMBER PAINTED SURFACE INTERNAL INSPECTION and 1367 PRESSURE-SUPPRESSION CHAMBER BELOW WATER LINE PAINTED SURFACE INTERNAL INSPECTION are attached to this evaluation, Attachments 2 & 3. Coating degradation, consisting of rusting, flaking, discoloration and peeling were noted. In most areas of flaking, discoloration or peeling coatings the base coats were still intact. The suppression chamber, vent lines, and vent header assembly had VT-3 visual examinations performed on them that identified areas of degraded coatings.

No conditions that could affect the structural integrity were observed.

Work order 01 348 19 to repair coatings in the torus was performed.

All of the submerged portions of the torus shell and approximately 113 of the vapor region near the torus catwalk was restored. All of degraded coating in those areas was removed, prepared for coating, VT-3 visually examined prior to coating, then coated and cured per the manufacture's requirements.

Large sections of coating discoloration were removed by scrubbing the area. This action removed the red-oxide stain fiom the intact coating system. The remaining 213 of the suppression chambers vapor region, vent header and downcomers were left in their as-found state. The areas of degraded coatings that still remain were: light rust bleed through at the top of the torus shell interior; rust inside the downcomers fiom where the coating system was burnt off during downcomer support installation welding, and also slightly above the waterline where the coating is degraded; and several areas of flaking paint located near the top of the torus shell interior. The estimated total area of flaking paint remaining is estimated to be less than 50 square feet. Ultrasonic shell thickness measurements (UT) were taken in accessible areas where rust has bled through the topcoat, and coating discoloration has occurred. These ultrasonic measurements taken during the 2007 refueling outage are contained in Table 1. Page 4 of 10 4/12/07 and 611 5/07 Condition Evaluation Page 5 of 10 Although essentially no evidence of pitting was identified in the areas where degraded coatings were removed and subsequently recoated, any UT measurements less than design values are well within the acceptance criteria for pits as shown above.

Table 1 I Bay I Component I Design Thickness I UT Measurement I 1 I Downcomers I 0.250" 1 0.250"/0.268/

0.254"/0.284" 1 1 Upper Shell Plate Lower Shell Plate 2 - 2 I 3 I Downcomers I 0.250" 1 0.296"/0.256"/

0.279"/0.278" 2 3 3 - - I Upper Shell Plate 1 0.533" 0.533" 0.584" Upper Shell Plate Lower Shell Plate I 4 I Lower Shell Plate I 0.584" 1 0.63 1"/0.669"/

0.628" 0.579" 0.61 8"/0.578"/

0.618" Downcomers Upper Shell Plate Lower Shell Plate

-- - 0.533" 0.584" I 5 I Lower Shell Plate I 0.584" I 0.606"/0.576" - - -- 0.617" 0.655"/0.593"/

0.584" 0.250" 0.533" 0.584" 4 5 0.256"/0.251"/

0.246"/0.277" 0.574" 0.633"/0.629" 1 6 ( Lower Shell Plate 1 0.584" ( 0.582"/0.632"/

0.623"/0.592" Downcomers Upper Shell Plate 5

6 0.250" 0.533" Downcomers Upper Shell Plate 6 7 0.340"/0.256"/

0.248"/0.267" 0.602" 7 7 0.250" 0.533" Downcomers Upper Shell Plate 8 8 8 9 I 10 I Upper Shell Plate I 0.533" I 0.586" - 0.285"/0.293"/

0.3 12"/0.302" 0.572" Lower Shell Plate Downcomers 9 9 0.250" 0.533" Upper Shell Plate Lower Shell Plate Downcomers Upper Shell Plate 0.290"/0.324"/

0.301"/0.270" 0.562" 0.584" 0.250" Lower Shell Plate Downcomers 10 10 Page 5 of 10 0.618"/0.596"/

0.625"/0.640" 0.298"/0.297"/

0.346"/0.298" 0.533" 0.584" 0.250" 0.533" 11 11 0.578" 0.604"/0.606"/

0.593"/0.619" 0.287"/0.260"/

0.265"/0.274" 0.626" 0.584" 0.250" Lower Shell Plate Downcomers 0.590"/ 0.607" 0.258"/0.295"/

0.292"/0.265" Upper Shell Plate Lower Shell Plate 0.584" 0.250" 0.604"/0.675" 0.26lY'/0.3 14"/ 0.257"/0.307" 0.533" 0.584" 0.579" 0.652"/0.681" 4/12/07 and 6/15/07 Condition Evaluation Page 6 of 10 The internal surfaces of the Suppression chamber, external surfaces of the vent lines, vent header and downcomers had General Visual and VT-3 visual examinations performed on them. In addition, the visual examinations, ultrasonic (UT) measurements were taken. The UT measurement confirmed that no degradation of the pressure boundary was occurring.

As identified above, localized areas on the torus shell could have significant thickness reduction and still meet code allowables. The small areas of bare metal on the torus shell were estimated to be less than 112- inch in diameter with most being very small nicks. Inspection of these bare metal areas showed only light rust film without evidence of corrosion pitting.

The VT-3 inspections of the surfaced prepared areas for coating found several minor arc strikes and no areas of corrosion pitting. The arc strikes were further inspected by a mag-particle examination and were found to be acceptable with no indications. The observed areas of degradation (coatings) are nonstructural in nature. No conditions that could affect the structural integrity were observed.

Containment Debris Loading and ECCS Pump Performance Evaluation 11 12 12 12 13 13 13 14 14 14 15 15 15 16 16 16 Calculation CA-0 1 - 135 Evaluation of Effect of Paint Chips on Debris Loading of ECCS Suction Strainers assumes 1000 square feet of paint chip debris can collect on the ECCS suction strainers following an accident. Calculation CA-01-177 evaluated the impact of debris loading on the suction strainers with respect to post accident NPSH for the ECCS pumps and determined that the assumed debris loading was acceptable.

0.250" 0.533" 0.584" 0.250" 0.533" 0.584" 0.250" 0.533" 0.584" 0.250" 0.533" 0.584" 0.250" 0.533" 0.584" 0.250" Downcomers Upper Shell Plate Lower Shell Plate Downcomers Upper Shell Plate Lower Shell Plate Downcomers Upper Shell Plate Lower Shell Plate Downcomers Upper Shell Plate Lower Shell Plate Downcomers Upper Shell Plate Lower Shell Plate Downcomers The results fiom the coated surfaces examinations of the drywell, the vent lines and vent header, downcomers and suppression pool surfaces are shown in Table 2. 0.298"/0.335"/

0.271"/0.357" 0.554" 0.581"/0.61 I"/ 0.709"/0.646" 0.298"/0.330"/

0.308"/0.256" 0.606" 0.638"/0.600"/

0.622"/0.605" O.279"/0.29Oy'/

0.248"/0.27lY' 0.562" 0.7 1 8"/0.620"/

0.645" 0.285"/0.294"/

0.269"/0.273" 0.574" 0.630"/0.750" 0.273"/0.295"/

0.257"/0.2717' 0.589" 0.63 1"/0.622"/

0.601"/0.649" 0.269"/0.288"/

0.279"/0.245" Page 6 of 10 -- -- - --

411 2/07 and 6/15/07 Condition Evaluation Table 2 Page 7 of 10 Note 1 : Degraded coatings were documented in procedures 0 135,O 140 and 1367. Inspection 0 135, PRESSURE SUPPRESSION CHAMBER PAINTED SURFACE INTERNAL INSPECTION (Note 2) 1367, PRESSURE-SUPPRESSION CHAMBER BELOW WATER LINE PAINTED SURFACE INTERNAL INSPECTION (Note 2) 0140, DRYWELL INTERIOR SURFACE INSPECTION (Note 2) 05 15, PRIMARY CONTAINMENT VISUAL EXAMINATION FOR STRUCTURAL PROBLEMS Totals Note 2: The observations made by these procedures include IWE inspection observations from work orders 135253 and 288456. The results show that the as-found degraded coating did not exceed the 1000 ft2 of coating chips assumed in Calculation CA-0 1 - 1 3 5. Therefore, the as-found condition was within the calculation limits for debris loading on the ECCS suction strainers. The results show that the as-left degraded coating did not exceed the 500 ft2 administrative limit of degraded coating that could become paint chips. Therefore, the as-left condition is acceptable and will not challenge the debris loading on the ECCS suction strainers.

Coating repaired (ft2) 277.4 240.27 35 552.67 As-Found Degraded coatings (ft2) 365.8 453.76 96 Note 1 915.56 During the inspections, the coatings were classified as being "loose" if the coatings were flaking or peeling. Areas identified as light rust bleed through the top coat or discoloration was checked for adhesion and was found as tightly bonded as the non-degraded coatings. The other type of degraded coatings was the small areas where the coating had been chipped off and bare metal was exposed. Of these types of degraded coating only the "loose" coating are expected to add to the debris loading on the ECCS suction strainers. The amount of identified "loose" coating left inside primary containment is approximately 50 ft2. As-Left Degraded coatings (ft2) 88.4 213.49 6 1 Note 1 362.89 Therefore, since the as-left degraded coatings are a fraction of the amount of degraded coatings assumed to contribute to the ECCS suction strainer debris loading, the as-left condition is acceptable.

Page 7 of 10 4/12/07 and 6/15/07 Condition Evaluation Page 8 of 10 For the conditions identified that have not been repaired, they are acceptable for further service since the observed areas of degradation (coatings and surface rust) are nonstructural in nature and no conditions that could affect the structural integrity were observed. Future Coating Repair Plans Accessible areas of the drywell and suppression chamber will continue to be inspected each refueling outage. Degraded coatings will be identified, evaluated, and totaled to assure the amount of degraded coating remains within the established administrative limit and that there is no impact to the structural integrity of the containment. Repairs to the drywell coatings should be scheduled and completed as needed to minimize the amount of degraded coatings inside the containment. Containment coating inspections will be performed per procedures 01 35, 140 and reexamination requirements of IWE-3 122.4 during the 2009 RFO. It is predicted that approximately 50 to 60 ft2 of additional degraded coats will be identified during those inspections.

For repairs to the torus, vent header and downcomers this would be at the next scheduled drain down of the torus. The next scheduled torus drain down for coating repairs should be performed when evaluations determine that the administrative limit of 500 ft2 may be exceeded, or if degradation is observed that could impact structural integrity.

Conclusion Based on results of the extensive scope of examinations performed on the various components of the Primary Containment and the engineer evaluation presented above, there is sufficient evidence that degraded areas of coatings is not leading to degradation of the base metal, is nonstructural in nature, and has no effect on the structural integrity of the containment. (IWE- 3 122.4) Therefore, it is acceptable for continued service. The reported degraded coatings are non-structural in nature, and are not affecting the structural integrity of the underlying containment base metal. Therefore, there is no evidence to suggest possible degradation of the base metal in inaccessible areas. Additionally, with the exception of plant shutdown conditions where containment entry is necessary, the Drywell and Suppression Chamber interiors are maintained in an inerted atmosphere (nitrogen) which provides environmental conditions that are not conducive to oxidation of exposed base metal at areas of degraded coatings. 10CFR50.59 Screening SCR-01-0553 Rev. 3 was prepared for this Condition Report with a "Use-As-Is" disposition. The examination conducted inspected 100%

of the suppression chambers and nearly 100% of the drywell internal surfaces. No supplemental examinations are specified as a result of this engineering evaluation or 1 OCFR50.55a(b)(2)(ix)(D).

4/12/07 and 6/15/07 Condition Evaluation Page 9 of I0 Actions: Repairs of the suppression chamber and drywell coatings during the 2007 refueling outage were conducted under work orders 0 1 348 19 and 29 1 852 respectively.

No additional actions are required at this time.

REFERENCES:

1. Procedure 0135, Pressure-Suppression Chamber Painted Surface Internal Inspection, completed March 2007. 2. Procedure 0140, Drywell Internal Surface Inspection, completed March 2007. 3. Procedure 1367, Pressure-Suppression Chamber Below water line Painted Surface Internal Inspection, completed March 2007. 4. Procedure 05 15, Primary Containment Visual Examination for Structural Problems, completed April 2007.

5. Work Order 00 1348 19, REPAIR TORUS INTERNAL COATINGS.

6. Work Order 00291 852, DRYWELL COATING REPAIR

7. Calculation -CA-01-156, ADD 0; IWE Recording Criteria. Approved 1 111 3/01. 8. CAPS 691537,625896,634151,636491, and 819170

9. Calculation - AES calculation number MN02-PO 1747 1-1 00; Rev. 0 Determination of Torus Pitting Acceptance Criteria. Dated 04/25/03.

10. Calculation - AES calculation number MN02-PO 1747 1-200; Rev. 0, Pitting Acceptance Criteria for the Submerged Portions of the downcomers. Dated 04/25/03.

11. Work Orders 135253 and 288456 for Visual Examination of IWE Surfaces.

12. ASME, 1992 Edition, 1992 addenda,Section XI, IWE-3 122.4 13. Torus Painting Procedure 8280, Revision

9. 14. Data Sheet for Phenoline 368WG paint. 15. MDC Document No. NSPT-12-4621, Monticello Plant Life Extension 16. Program - Ultrasonic wall Thickness Survey or the Drywell shell Test Results Package, July 1986. 17. CBI Certified Stress Report Monticello Project

-11, Rev. 1, 3/7/69. 18. Pacific Nuclear Calculation MN.9201 .0104, Calculate the Minimum Wall Thickness for the Monticello Torus for an Internal Pressure of 56 PSI and for Mark I Long Term Program Hydrodynamic Loadings, 7/6/92. 19. Letter from P. Riccardella (Structural Integrity Associates, Inc.) to B. Day (NSP), Torus Crack Indication - Final Evaluation and Recommendations, 511 6/91 (Appendix 2 to 611 719 1 letter to NRC). 20. NSP-74-103, MNGP Plant Unique Analysis Report (PUAR), Volume 3, Vent System, Revision 1, November 1982.

Page 9 of 10 4/12/07 and 6/15/07 Condition Evaluation Page 10 of 10 2 1. Calculation CA-97-004, Corrosion Allowances for Primary Containment Components.

22. Calculation CA-0 1-1 35, Evaluation of Effect of Paint Chips on Debris Loading of ECCS Suction Strainers.

23. Calculation CA-0 1 - 1 77, Determination of Containment Overpressure Required for Adequate NPSH of Low Pressure ECCS Pumps Updated for Suction Strainer Debris Loading. 24. FP-PA-ARP-01, CAP Action Request Process Preparer's Name: Alan Wojchouski Date: April 12,2007 No human performance, process, organizational errors were identified.

No training needs were identified.

Attachment 1 0140 Dwwell Interior Attachment 2 Attachment 3 1367-COMMENTS-wit h downcomers

-2007- Page 10 of 10 CE-0 1082766-03 Embedded Attachment 1 0140 Drywell Interior Surface Inspection Results Area 1 - 920'-6" SRV Tailpipe inside X-5A, flaking, 10 sq ft, recommend remove X5A, floor support to left as you face X-5A, 6 sq in degraded, recommend remove Shell above X-5B, Behind SRV Tailpipe, 2 sq ft degraded, recommend no rework X-5B, vent tube, 2 sq in plus 2 sq in, marked, recommend no rework X-5B, SRV tailpipe, 5 sq ft degraded, recommend remove X-5B, floor support to right as you face X-5B, 4 sq in degraded, recommend remove Two small bare spots between X5C and X5D, marked, recommend no rework X-5 D brackets in vent tube, 6 sq in degraded, recommend remove X-5D vent tube, 4 sq in degraded on bottom below SRV tailpipe penetration, marked, recommend remove. X-5E vent tube, 2 sq in degraded on bottom below SRV tailpipe penetration, marked, recommend remove. X-5E, SRV tailpipe inside vent tube, 20 sq ft degraded, recommend remove X-5E, SRV tailpipe outside vent tube, 5 sq ft degraded, recommend remove Floor support to left of X-5E as you face X-5E, 2 sq ft degraded, recommend remove. X-5E, 9 o'clock, 4 sq in degraded, recommend remove X-5E, X-5F, sheel behind duct, 6 sq in degraded, recommend no rework HVAC Support near X-5F, 2 sq ft degraded, recommend remove Floor support to right of X-5F as you face X-5F ,6 sq in degraded, recommend remove Floor support to left of X-SF as you face X-5F ,4 sq in degraded, recommend remove X-5F, SRV tailpipe, 10 sq ft degraded, recommend remove X-5F, floor support to left as you face X-5F, 1 sq ft degraded, recommend remove CE-01082766-03 Embedded Attachment 1 X-5F, bracket above SRV tailpipe, 2 sq in degraded, recommend no rework SRV tailpipe, inside X-5G, 3 sq ft degraded, recommend remove.

SRV Tailpipe above X-5G, 10 sq ft degraded, recommend remove X-5G, vent tube, several degraded areas marked, 6 sq in, recommend remove Tailpipe inside X5H, 5 sq ft degraded, recommend remove Shell above X-5H, Behind SRV Tailpipe, 2 sq ft degraded, recommend no rework Shell near X-5H, between X-5H and X-5A, near concrete, 1 sq ft degraded, recommend repair Support between X-5H and X-5A degraded 5 sq ft, recommend remove X-5H, SRV tailpipe inside vent tube, 10 sq fl degraded, recommend remove Area 5 - 984" AZ 60, Refuel Cavity floor support, 6 sq in flaky, not marked SW cover plates recessed area, 3 sq in each flaky, 24 sq in total, not marked AZ 180, about 989, small spots top coat missing, no corrosion, marked AZ 193, under refuel cavity floor, small spot missing top coat, not marked AZ 240, Refbel Cavity floor support, 1 sq ft flaky, not marked AZ 347, neck area, small spot missing topcoat, no corrosion, not marked AZ 167, about 992 elev, large spot and small spot missing top coat, no corrosion, marked AZ 149, elev 990 and 989, small spots missing top coat, no corrosion, marked SW above N4B, small spot missing top coat, no corrosion, not marked AZ 21 1, elev 985-990, shield, small area missing topcoat, no corrosion, not marked AZ 119, shield, elev 988, small spot missing topcoat, no corrosion, marked Area near X-25,6 sq in flaky, not marked AZ 85, elev 992, small area missing top coat, no corrosion, not marked.

AS-LEFT 4-8-2007 CE-01082766-03 Embedded Attachment 2 0135 Attachment Page 1 of 8 COMMENTS Area Loose FT2 YIN BAY 1: 1 2 3 4 5 6 7 Area Loose FT2 YIN BAY 2: 12 1 2 3 4 5 6 7 8 9 N 11.5 Ring girder at top of torus patches of rust bleed through Monorail and it's supports has small patches of rust. Total degraded coatings: Total loose coatings:

N -. 0.5 0.1 2.6 0 Ring girder at top of torus patches of rust bleed through Monorail and it's supports has small patches of rust. Vent header has small patches of rust bleed through Air temperature penetration heavily rusted Total degraded coatings: Total loose coatings:

N N 0.5 0.1 2 0.1 4.2 0 N N N N 1 AS-LEFT 4-8-2007 CE-01082766-03 Embedded Attachment 2 0135 Attachment Page 2 of 8 Area Loose FT2 YIN Area Loose FT2 YIN BAY 3: 1 BAY 4: I1 I I I I N N N N 1 2 3 4 5 6 7 8 4 5 6 7 Top of torus, patches of rust bleed through. Back wall center, patches of rust bleed through Air temperature penetration heavily rusted. Monorail and it's supports has small patches of rust. Total degraded coatings:

Total loose coatings:

Total degraded coatings:

Total loose coatings:

10 3 0.1 0.1 13.2 0 Top of torus, patches of rust bleed through. Top half of torus- peeling coating Torus manway cover and access many chipped spots Monorail and it's suvvorts has small patches of rust. 6.9 1 1 5 1 0.8 0.1 N Y N N AS-LEFT 4-8-2007 CE-01082766-03 Embedded Attachment 2 0135 Attachment Page 3 of 8 Area Loose FT2 YIN BAY 5: 1 2 3 4 5 6 7 Area Loose FT2 YIN Top of torus, and girders patches of rust bleed through. Total degraded coatings: Total loose coatings:

BAY 6: 5.6 0 5 N N Vent header has small patches of rust bleed through Monorail and it's suw~orts has small watches of rust. N 0.5 0.1 1 2 3 4 5 6 7 8 9 10. 11 Top of torus, patches of rust bleed through. Ring girders at top of torus patches of rust bleed through Monorail and it's supports has small patches of rust. Air temperature penetration, HPCI vent line & penetration heavily rusted Total degraded coatings: Total loose coatings:

1.5 0.5 0.1 2 4.1 0 N N N N AS-LEFT 4-8-2007 CE-0 1082766-03 Embedded Attachment 2 0135 Attachment Page 4 of 8 Area Loose FT2 YIN Area Loose FT2 YIN BAY 7: BAY 8: N N N N N 6 1 0.1 4 2 13.1 0 1 2 3 4 5 6 7 8 - 9 1 2 3 Top of torus, patches of rust bleed through around penetration.

Ring girders at top of torus patches of rust bleed through Monorail and it's supports has small patches of rust. Vent header, has small patches of rust bleed through Air temperature penetration, HPCI vent line & penetration heavily rusted Total degraded coatings:

Total loose coatings: Air temperature penetration heavily rusted.

5 6 7 8 9 10 0.2 N Total degraded coatings:

5 Total loose coatings:

1 Ring girders at top of torus patches of rust bleed through Monorail and it's supports has small patches of rust. Vent header, at support has small patches of loose coating Air temperature penetration heavily rusted 0.5 0.1 1 0.2 N N Y N AS-LEFT 4-8-2007 CE-0 1082766-03 Embedded Attachment 2 0135 Attachment Page5of 8 Area Loose FT2 YIN Area Loose FT2 YIN BAY 9: BAY 10: 1 2 3 4 5 6 7 8 1 0.5 0.1 0.2 1.8 0 Top of torus, patches of rust bleed through. Ring girders at top of torus patches of rust bleed through Monorail and it's supports has small patches of rust. Vent header, at support has small patches of rust bleed through Total degraded coatings:

Total loose coatings:

N N N N N N N N N N 1 2 3 4 5 6 7 8 9 Top of torus, patches of rust bleed through. Ring girders at top of torus patches of rust bleed through Vent header has small patches of rust bleed through Monorail and it's supports has small patches of rust. Vent header, at support has small patches of rust bleed through Air temperature penetration heavily rusted.

Total degraded coatings:

Total loose coatings:

1 0.5 0.1 0.1 0.2 0.2 2.1 0 AS-LEFT 4-8-2007 CE-0 1082766-03 Embedded Attachment 2 0135 Attachment Page 6 of 8 Area Loose FT2 YIN BAY 11: Area Loose FT2 YlN BAY 12: 1 2 3 - 5 6 7 8 9 -- 0.5 0.1 0.1 1 0.2 2.9 0 411 Ring girders has patches of rust. Vent header supports has small patches of rust bleed through Monorail and it's supports has small patches of rust. Vent header, has small patches of rust bleed through Air temperature penetration heavily rusted.

-- Total degraded coatings:

Total loose coatings:

Y N N N N N N 2 1 2 3 4 - Top of torus, patches of loose coatings.

5 - 6 7 8 9 10 Tog of torus, light rusting 1 N Vent header has small patches of rust bleed through Monorail and it's supports has small patches of rust. Toms manway cover and access many chipped spots Total degraded coatings:

Total loose coatings:

0.1 0.1 0.8 4 2 N N N AS-LEFT 4-8-2007 CE-0 1082766-03 Embedded Attachment 2 0135 Attachment Page 7 of 8 Area Loose FT2 YIN BAY 13: 1 2 3 4 5 6 7 8 Area Loose FT2 YIN BAY 14: 3 0.5 0.5 0.1 4.1 0 Top of torus, patches of rust bleed through Ring girders has patches of rust. Vent header has small patches of rust bleed through Monorail and it's supports has small patches of rust. Total degraded coatings:

Total loose coatings:

1 2 3 4 5 6 7 N N N N Top half of torus ring girdter has patches of rust bleed through Top of torus, patches of rust bleed through Torus spray line has patches of rust. Vent header, has small patches of rust bleed through Monorail and it's supports has small patches of rust. Total degraded coatings:

Total loose coatings:

0.5 8 0.5 0.2 0.1 9.3 0 N N N N N AS-LEFT 4-8-2007 CE-01082766-03 Embedded Attachment 2 0135 Attachment Page 8 of 8 Area Loose FT2 YIN BAY 15: 3 4 5 6 7 1 Total loose coatings:

10 Top of torus, patches of rust bleed through Ring girders has patches of rust. Total degraded coatings:

Vent header, has small patches of rust bleed through Monorail and it's su~~orts has small

~atches of rust. 6.3 5 1 Area Loose FT2 YIN BAY 16: 1 2 3 4 N N 0.2 0.1 - 5 6 7 8 9 10 TOTALS OF ALL BAYS Bay 1 through Bay 16 Total degraded coatings: (365.8 as-found) Bay 1 through Bay 16 Total loose coatings: (14.0 as-found)

N N As-Left 88.4 4.0 Vent header gusset at top has patches of rust. Vent header, has small patches of rust bleed through Monorail and it's supports has small patches of rust. Air temperature penetration heavily rusted. Total degraded coatings: Total loose coatings:

1 0.2 0.1 0.2 3.5 0 N N N N AS-LEFT CE-0 1082766 Embedded Attachment 3 1367 Attachment Page 1 of 8 Note: "loose" means peelinglflaking, not tightly adhering. " Not loose" means no peeling, flaking , blistering, cracking or checking, but does have bare metal or rust spots on shell. Area Loose FT2 YIN BAY 1: Area Loose FT2 YIN 1 2 3 4 5 6 7 8 9 10 BAY 2: I1 I I Downcomer-ID-40 spots weld damaged coating-6- inch2 + 5-ft2 Downcomer-OD- 6 spots of degraded coating- Totaling-1 -ft2 Downcomer-OD-2 spots of degraded coating- Totaling-0.4-ft2 Total degraded coatings:

Total loose coatings:

9 10 15 1 0.4 16.4 0.4 11 12 N N Y Ring Girder - 16 small rust spots -112-inch square Downcomer-ID-20 spots weld damaged coating-6- inch2+ 4-ft2 Total degraded coatings: Total loose coatings: Downcomer-OD- 3 spots of degraded coating- Totaling-0.23-ft2 9.25 0.02 0.02 9 Y N 0.23 N AS-LEFT CE-0 1082766 Embedded Attachment 3 1 3 67 Attachment Page 2 of 8 Area Loose FT2 YIN BAY 3: Area Loose FT2 YIN BAY 4: 11 1 N N Y 1 2 3 4 5 6 7 8 9 10 4 5 Downcomer-ID- 40 spots weld damaged coating inch2 + 5.5-ft2 Downcomer-OD- 5 spots of degraded coating-Totaling-1 -ft2 Downcomer-OD- 1 spots of degraded coating- Totaling-0.06-ft2 Total degraded coatings:

Total loose coatings:

Total degraded coatings:

Total loose coatings:

15.5 0.23 0.06 15.79 0.06 Downcomer-ID- 20 spots weld damaged coating inchZ + 2-ftz Downcomer-OD- 3 spots of degraded coating-Totaling-0.1 3-ftz 7.13 0 7 0.13 N N AS-LEFT CE-0 1082766 Embedded Attachment 3 1 3 67 Attachment Page 3 of 8 Area Loose FT2 YIN Area Loose FT2 YIN BAY 5: BAY 6: N N Y I I I 1 Total degraded coatings:

I 1 7.17 22 4.45 3.25 29.7 3.25 1 2 3 4 5 6 7 8 9 10 8 9 10 I Total loose coatings:

12.17 Downcomer-ID- 40 spots weld damaged coating inch2 + 12-ft2 Downcomer-OD- 10 spots of degraded coating- Totaling-4.45-ft2 Downcomer-OD- 3 spots of degraded coating- Totaling- 3.25-ft2 Total degraded coatings:

Total loose coatings:

Downcomer-ID- 20 spots weld damaged coating-6- inch2 Downcomer-OD- 3 spots of degraded coating- Totaling-2.1 7-ft2 5 2.17 N Y AS-LEFT CE-0 1082766 Embedded Attachment 3 1 3 67 Attachment Page 4 of 8 Area Loose FT2 YIN BAY 7: Area Loose FT2 YIN 1 2 3 4 5 6 7 8 9 10 BAY 8: Downcomer-ID- 40 spots weld damaged coating inch2 +4-ft2 Downcomer-OD-7 spots of degraded coating- Totaling-2.34-ft2 Downcomer-OD- 2 spots of degraded coating- Totaling-7.02-ft2 Downcomer-ID-5 spots of degraded coating-Totaling 1 -ft2 Total degraded coatings:

Total loose coatings:

1 2 3 4 5 6 7 8 9 10 10 2.34 7.02 1 20.36 8.02 N N Y Y N N Y Y Downcomer-ID-20 spots weld damaged coating-6- inch2 +2-ft2 Downcomer-OD- 3 spots of degraded coating- Totaling-0.067-fi2 Downcomer-OD-4 spots of degraded coating- Totaling-9.1 -ft2 Downcomer-ID- 1 spots of degraded coating-Totaling 2-ft2 Total degraded coatings: Total loose coatings:

7 0.07 9.1 2 18.17 11.1 AS-LEFT CE-0 1082766 Embedded Attachment 3 1367 Attachment Page 5 of 8 Area Loose FT2 YlN Area Loose FT2 YIN BAY 9: BAY 10: 9 1 Downcomer-ID-20 mots weld damaged coating inch2 +0.5-ft2 1 5.5 I N N N Y 1 2 3 4 5 6 7 8 9 10 1 1 12 Downcomer-ID-40 spots weld damaged coating-6- inch2 Downcomer-OD- 3 spots of degraded coating-Totaling-0.095-ft2 Downcomer-OD-4 spots of degraded coating- Totaling-0.187-ft2 Total degraded coatings: Total loose coatings:

10 11 I Total loose coatings:

1 0.08 10 0.1 0.19 10.3 0.19 Total degraded coatings: Downcomer-OD- 3 spots of degraded coating- Totaling-0.1 7-ft2 Downcomer-OD- 3 mots of degraded coating- Totaling- 0.077-ft2 5.75 0.17 0.08 N Y AS-LEFT CE-01082766 Embedded Attachment 3 1 367 Attachment Page 6 of 8 Area Loose FT2 YIN BAY 11: I I 1 Total degraded coatings:

I 1 11.85 I Total loose coatings:

1 3.06 10 11 12 Area Loose FT2 YIN BAY 12: I1 I 10.2 0.83 3.06 Downcomer-ID- 40 spots weld damaged coating inch2 +0.2-ft2 Downcomer-OD- 6 spots of degraded coating- Totaling-0.83-ftz Downcomer-OD-4 spots of degraded coating- Totaling-3.06-fY N N Y 9 10 11 12 I Total loose coatings:

1 10 Downcomer-ID-20 mots weld damaged coating- 6-inch2

+0.36-ftz Total degraded coatings: Downcomer-OD- 3 spots of degraded coating- Totaling-0.292-ft2 Downcomer-OD- 4 mots of demaded coating- Totaling-1 0-ft2 15.66 5.36 N 0.3 10 N Y AS-LEFT CE-0 1082766 Embedded Attachment 3 1 3 67 Attachment Page 7 of 8 Area Loose Area Loose FT2 YIN BAY 13: l?T2 YIN 1 2 3 4 5 6 7 8 9 10 11 Downcomer-ID-406- spots weld damaged coating-inchZ Downcomer-OD- 8 spots of degraded coating- Totaling-6.4-ft2 Downcomer-OD- 3 spots of degraded coating- Totaling- 0.47-ft2 Total degraded coatings: Total loose coatings:

BAY 14: I1 I 9 10 1 1 12 13 10 0.1 0.47 10.57 0.47 I Total degraded coatings: Total loose coatings:

N N Y Downcomer-ID-206- spots weld damaged coating-inchZ Downcomer-OD- 4 spots of degraded coating- Totaling-0.1 65-fi2 Downcomer-OD- 4 spots of degraded coating-Totaling-0.567-ft2 Downcomer-ID-1 spots of degraded coating-Totaling 3-ftz 8.74 3.57 5 0.17 0.57 3 N N Y Y AS-LEFT CE-01082766 Embedded Attachment 3 1 3 67 Attachment Page 8 of 8 Area Loose FT2 YIN BAY 15: Area Loose FT2 YIN 1 2 3 4 5 6 7 8 9 10 BAY 16: 1 2 3 Downcomer-ID- 40 spots weld damaged coating inch2 +2-ft2 Downcomer-OD-7 spots of degraded coating- Totaling-4.6-ft2 Downcomer-OD- 4 spots of degraded coating- Totaling-3.1 5-ft2 Total degraded coatings: Total loose coatings:

9 10 11 12 4.6 3.15 19.75 3.15 Total degraded coatings:

Total loose coatings:

N N Y Downcomer-ID- 20 spots weld damaged coating inch2 Downcomer-OD- 4 spots of degraded coating- Totaling-2.88-ft2 7.9 0 TOTALS OF ALL BAYS for 1367 Bay 1 through Bay 16 Total degraded coatings:

Bay 1 through Bay 16 Total loose coatings:

213.49 45.54 5 2.9 N N Nuclear Management Company Monticello Inservice Inspection APPENDIX E (continued)

Cycle 23 Summary Report 2007 Refueling Outage Engineering Evaluations per Subsection IWE-3122.4 (1992 Edition with 1992 Addenda) and lOCFR50.55a(b)(2)(ix)

2. CAP CE 01 084149-0 1 for Arc Strikes on Torus Shell Plates (2 pages to follow) 3/29/07 Condition Evaluation Page I of 2 CAP Number: 01084149 Condition Evaluation Number: 01 Description of problem: Arc strikes were noted on the torus shell during IWE examinations.

Evaluation Details: ASME Section XI, Subsection IWE requires examination of containment surfaces. Arc strikes were noted on the interior of the torus shell during base metal examination associated with the torus coating project. These arc strikes occurred during construction of the torus. The arc strikes only became visible after all coating was removed. The arc strikes are superficial as evidenced by the visual examination results(little or no removal of metal). Inspection of the containment is governed by IWE. 1 OCFR50.55a states that 50.55a(b)(2)(ix)(D) may be used in as an alternative to the requirements of IWE 2430. 50.55a(b)(2)(ix)(D) follows. (1) If the examinations reveal flaws or areas of degradation exceeding the acceptance standards of Table /WE-34 10-1, an evaluation must be performed to determine whether additional component examinations are required. For each flaw or area of degradation identified which exceeds acceptance standards, the licensee shall provide the following in the IS1 Summary Report required by IWA-6000:

(0 A description of each flaw or area, including the extent of degradation, and the conditions that led to the degradation; (i0 The acceptability of each flaw or area, and the need for additional examinations to verify that similar degradation does not exist in similar components, and; (iii) A description of necessary corrective actions. For the arc strikes noted during this examination, additional examinations are not required. The torus shell is a coated structure. Serious arc strikes would result in metal removal. Such metal removal would not meet the base metal profile requirements for coating and would have been rejected and reworked. Superficial arc strikes such as those noted during this examination would not interfere with base metal profile for coating and may not have been rejected and reworked.

The code of fabrication (ASME 111 1965, Winter 1965 and Section Vlll 1965 Winter 1965) does not specifically address arc strikes. Arc strikes are required to be addressed by ASME Section XI, Subsection IWE.

As noted above, 50.55a(b)(2)(ix)(D) allows evaluation of IWE indications by the alternate means detailed in 50.55a. An additional concern with arc strikes is the effect of rapidly heating and cooling the metal. Such rapid heating and cooling may lead to cracks. Cracks could lead to failure of the pressure boundary.

J:\Prge\MIR\ISI\Summary Reports\lS1~2007-RFO~Cycle-23\Miscellaneous\ce~0l084149~Torus Arc Strikes.doc Page 1 of 2 Condition Evaluation Page 2 of 2 Actions: Visual and pitting examinations of the torus (IWE exams and coating prep exams) have confirmed the superficial nature of the arc strikes. The thickness of the torus shell is acceptable. The base metal profile for coating is acceptable.

No further actions are required to address metal removal/profile for these superficial arc strikes.

All of the arc strikes were subjected to Section XI compliant magnetic particle examinations. The intent of these examinations was to confirm the visual examination results that no linear indications (i.e. cracks) were present in the area of the arc strikes.

The magnetic particle examinations confirmed that there were no linear indications. Additional examinations to detect arc strikes are not required. Severe arc strikes (if any) would have been rejected during initial construction either for base metal profile concerns (e.g. undercut, thinning) or for coating profile concerns.

Any superficial arc strikes remaining under the existing coating are acceptable based on the absence of linear indications from the magnetic particle examinations performed for this CAP. The torus has been subjected to (essentially) design level stress a number of times (during Type A tests and performance tests). If the superficial arc strikes had created cracks or removed metal or had created hard spots, these tests would have encouraged the growth of linear indications.

The absence of any linears in the areas subjected to magnetic particle examinations and the acceptability of the base metal thickness and profile provides strong evidence that only superficial arc strikes occurred. Additional examinations would only reveal additional superficial arc strikes (if there are additional arc strikes). A large amount of work and dose would be required to reveal these additional (if any) superficial arc strikes.

No corrective actions are required for these superficial arc strikes. Visual and magnetic particle examinations have confirmed that there is no thinninglprofile concern and that there are no linear indications (cracks). Since the initial construction codes did not require removal of arc strikes (that did not otherwise violate acceptance criteria), there is no code reconciliation or other document rework required to achieve code compliance.

A GAR has been created to verify that the evaluation results are reported per IWA-6000 (Reference AR 01084776).

Inclusion of IWE results in the IS1 summary report is unusual. The GAR will verify that this action occurs.

Preparer's Name: Jim Bridgeman Date: 3/29/2007 Complete Page two of this form to address Failure Modes for Trend Coding. This is a legacy issue.

No cause coding performed.

J:\PrgeWIIR\ISI\Summary Reports\lS1~2007-RFQ~Cycle-23\Miscellaneous\eOl084149~Torus Arc Strikesdoc Page 2 of 2

L-MT-07-058, Cycle No. 23 Lnservice Inspection Summary Report for Lnservice Inspection and ASME Section XI Repairs and Replacements

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L-MT-07-058, Cycle No. 23 Lnservice Inspection Summary Report for Lnservice Inspection and ASME Section XI Repairs and Replacements

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