L-MT-07-058, 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) | |
Text
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.
&d This tter ake n new commitments or changes to any existing commitments.
e President, Monticello Nuclear Generating Plant Enclosure Management Company, LLC 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: 763.295.5151 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 Xcel Energy, LLC 700 1st Street 800 Nicollet Mall Hudson, WI 54016 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 PAGES I. Summary 4 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 PAGES A. Class 1,2, 3, Augmented, and Non-Code Examinations 19 (Sorted by Class, Category, and Item No.)
B. Reactor Vessel IVVI Examinations C. System Pressure Test Examinations D. Snubber Functional Testing E. Engineering Evaluations per Subsection IWE-3122.4 (1992 Edition with 1992 Addenda) and 10CFR50.55a(b)(2)(ix)(D)
- 1. CAP CE 01082766-03 for degraded containment nuclear coatings 28 CAP CE 01082766-03 Attachment 1 CAP CE 01082766-03 Attachment 2 CAP CE 01082766-03 Attachment 3
Nuclear Management Company Cycle 23 Summary Report Monticello Inservice Inspection 2007 Refueling Outage I. Summary 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 lStPeriod.
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 Cycle 23 Summary Report Monticello Insewice Inspection 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 (BWRVIP) guideline BWRVIP-03.
Examinations performed during Cycle 23 are listed in attached appendices. Code Case N-460, which allows a reduction of examination volume coverage 4 0 % 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 1 Inspection Examination Plan, Interval 1, Period 3, Cycle 23 examinations that 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 10CFR50.55a(b)(2)(ix)(D) as an alternative to IWE-2430. As required by 10CFR50.55a(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 1st 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 1st 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 Cycle 23 Summary Report Monticello Inservice Inspection 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 Cycle 23 Summary Report Monticello Inservice Inspection 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 Cycle 23 Summary Report Monticello Inservice Inspection 2007 Refueling Outage II. Form NIS-1 Information Page 1of 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~ementCompany. 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: 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: 04113/05 to 04/28/07 .
- 9. Inspection Interval: 05/01/03 to 0513 1/12 .
- 10. Applicable Edition of Section XI: 1995 Addenda: 1996 .
- 11. Abstract of Examinations. Include a list of examinations and a statement concerning status of work required for current interval.
See 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 Cycle 23 Summary Report Monticello Inservice Inspection 2007 Refueling Outage
- 11. Form NIS-1 Information Page 2 of 2 We certify that the statements made in this report are correct and the examinations and corrective measures taken conform to the rules of the ASME Code,Section XI.
Certification of Authorization No. (if applicable) N/A Expiration Date N/A Date JULY2b 20 67 Signed XCEL'ENERGY N M ~ 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 ~ r x / r v c ' ~ o n and employed by P L ~ I Z ) ' F ~ P On t BOIL~-R
~ BJ OP co)oYc'cncui of +1~lqfi1~&@ , cr have inspected the components described in this Owner's Report during the period
~ / I J/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, U L AUUO Y'(ILRAO Inspector's Signature National Board, State, Province, Endorsements 1 Date Y ~Y Lz(: 2 0 0 7
Nuclear Management Company Cycle 23 Summary Report Monticello Insewice Inspection 2007 Refueling Outage 111. Form NIS-2 Information Page 1 of 5 Cycle 23 NIS-2 Summary RIR ITEM WORK COMPONENT WORK DESCRIPTION NUMBER DOCUMENT(S) OR SYSTEM 2005-23-0001 WO-3 11347 P-109 (Spare Pump) Rebuilt spare RHRSW pump bowl assembly WO-507209 (PP 141066) # 12 Reclrc Pump 2005-23-0002 Replacement of stuffing box cover WO-SO6359 (P-200B)
(PP 140418) 2005-23-0004 WO-156335 TCV-4030B Replaced existing valve P-109B, #12 2005-23-0005 WO-507758 Replaced existing pump bowl assembly w/ rebuilt spare RHRSW Pump Removed welded stanchion, realigned and repaired by 2005-23-0006 WO-136399 SR-26 weld~ng Removed existing snubbers and replaced with rebuilt 2006-23-0008 WO-141353 SS-14 spares WO-141354 SS-184 WO-141355 SS-3 16 WO-141356 SS-13 WO-141357 SS-38A WO-141358 SS-17A WO-141359 SS-38B WO-141360 SS-121 WO-141361 SS-11 WO-141362 SS-12 WO-141363 SS-37 WO-141365 SS-17B WO-141366 CRD-H227
Nuclear Management Company Cycle 23 Summary Report Monticello Inservice Inspection 2007 Refueling Outage 111. Form NIS-2 Information Page 2 of 5 Cycle 23 NIS-2 Summary RIR ITEM WORK COMPONENT NUMBER DOCUMENT(S) OR SYSTEM WORK DESCRIPTION (Cont'd) (Cont'd) Removed exlstlng snubbers and replaced wrth WO-141369 SS-303 2006-23-0008 rebu~ltspares WO-141371 CRD-H232 WO-141372 SS-8AR WO-141374 SS-8BR WO-141375 SS-2AR WO-141377 SS-1BR WO-141378 SS3AR WO-141379 SS-1AR WO-141382 SS-20 WO-141383 SS-35 WO-153676 2006-23-0010 P-200B Replaced pump stuffing box (EC-806 and EC-103 17)
WO-153175 2006-23-001 1 WO-153676 P-200B Replaced 16 pump case-to-stuffing box nuts (EC-806) 2006-23-0013 WO-151841 MO-2373 Replaced valve and assoc~atedpip~ng(EC-748)
WO-285967 2006-23-0014 MO-2374 Replaced valve and assoc~atedpiplng (EC-748)
WO-285967 Removed / restored disc stem-to-nut tack weld to permlt 2006-23-0015 WO-265697 ESW-1-2 Inspection Modlfied support by welding, Integral attachment weld 2006-23-0016 WO-289152 TW(H)-12 removed (EC-775)
Mod~fiedsupport by lnstall~ngreplacement sprlng can 2006-23-0017 WO-289151 TWH-86 (EC-775)
WO-285768 Replaced 6 scram discharge volume level sw~tches 2006-23-0018 CRH WO-286583 (EC-901)
Nuclear Management Company Cycle 23 Summary Report Monticello Inservice Inspection 2007 Refueling Outage 111. Form NIS-2 Information Page 3 of 5 Cycle 23 NIS-2 Summary R/RITEM WORK COMPONENT WORK DESCRIPTION NUMBER DOCUMENT(S) OR SYSTEM 2006-23-0019 WO-140381 MO-2008 Replace bonnet WO-285273 Replaced 2 check valves (SW-16 and SW-18) wlth 2006-23-0020 WO-267425 EDG-ESW A and B manual gate valves (SW-228 and SW-229) and WO-284077 assoc~atedpiplng (EC-768) 2006-23-0021 WO-289151 SR-852 Installed new pipe restra~nt(EC-775) 2006-23-0022 WO-152929 P-111B Replaced P-1 1l B (EDG-ESW Pump 12) 2006-23-0023 WO-139591 ESW-32 Replaced valve and pup plece 2006-23-0024 WO-142128 ESW-3 1 Replaced valve and pup plece Changed out snubber w ~ t hnew spare and also replaced 2 2006-23-0025 WO-141349 SS-707 end pins 2006-23-0026 WO-280592 Snubber, s/n 529 Replaced main cyl~nder Replaced maln cylmder, plston, plston rmgs, plston rod, 2006-23-0027 WO-280592 Snubber, sln 044 plston rod nut 2006-23-0028 WO-280592 Snubber, s/n 460 Replaced valve man~fold 2006-23-0029 WO-280592 Snubber, sln 126 Replaced valve manlfold 2006-23-0030 WO-280592 Snubber, s/n 157 Replaced main cylinder, plston rlngs, plston RV-11-39B 2006-23-0031 WO-135620 (# 12 SBLC Pump Replaced nozzle and dlsc Dlsch RV) 2006-23-0032 WO-280592 Snubber, sln 131 Replaced valve manlfold 2006-23-0033 WO-280592 Snubber, s/n 487 Replaced valve manlfold 2006-23-0034 WO-280592 Snubber, s/n 466 Replaced valve manifold 2006-23-0035 WO-280592 Snubber, s/n 132 Replaced valve manifold 2006-23-0036 WO-280592 Snubber, s/n 148 Replaced valve manlfold
Nuclear Management Company Cycle 23 Summary Report Monticello Inservice Inspection 2007 Refueling Outage 111. Form NIS-2 Information Page 4 of 5 Cycle 23 NIS-2 Summary R/RITEM WORK COMPONENT WORK DESCRIPTION NUMBER DOCUMENT(S) OR SYSTEM 2006-23-0037 WO-280592 Snubber, s/n 132 Replaced maln cyl~nder 2006-23-0038 WO-280592 Snubber, s/n 102 Replaced main cyl~nder 2006-23-0039 WO-280592 Snubber, s/n 154 Replaced maln cylinder 2006-23-0040 WO-280592 Snubber, s/n 174 Replaced main cylinder 2006-23-0041 WO-280592 Snubber, sln 133 Replaced valve man~fold 2006-23-0042 WO-280592 Snubber, sln 125 Replaced valve man~fold 2006-23-0043 WO-152929 P-1 11B (Spare) Repaired small crack ~n 1st ~ntermed~ate bowl Removed 2 abandoned ~n-placewide range flux 2007-23-0044 WO-154343 RPV - WRFM monltors and replaced wlth new blank flanges and bolting (EC-7462)
Installed 64 striun gauges (2 locations on each of the 4 2007-23-0045 WO-3 14220 Main Steam steam lines In the drywell, 8 striun gages per location)
(EC-9174)
Removed and re~nstalleda section of pipe due to 2007-23-0046 WO-288806 CS Interference w ~ t hadjacent work RX Head Vent, 2007-23-0047 WO-267368 Replaced 1 stud and 2 nuts Flange #3 Removed / Reinstalled a section of p ~ p eto allow repalr 2007-23-0048 WO-3 14233 RCIC Steam work on AO-2-86D Replaced approx~mately4 ft section of SW10-18"-GF 2007-23-0049 WO-322082 RHRSW-B PiPC 2007-23-0050 WO-141889 Snubber, SIN 400 Replaced main cylinder 2007-23-005 1 WO-288859 MO- 1742 Replaced 14 bonnet studs and 28 nuts 2007-23-0052 WO-289152 MO-1987 Replaced 18 bonnet studs and 36 nuts 2007-23-0053 WO-289154 MO-2009 Replaced d ~ s c Removed / restored dlsc to nut tack weld to permit 2007-23-0054 WO-289151 MO-1750 disassembly and reassembly
Nuclear Management Company Cycle 23 Summary Report Monticello Inservice Inspection 2007 Refueling Outage 111. Form NIS-2 Information Page 5 of 5 Cycle 23 NIS-2 Summary R/R ITEM WORK COMPONENT WORK DESCRIPTION NUMBER DOCUMENT(S) OR SYSTEM 2007-23-0056 WO-322070 RV-2-7 1C Replaced main body w ~ t hrebu~ltspare 2007-23-0057 WO-322070 RV-2-71C Replaced topworks with rebuilt spare Replaced 5 bolts and 6 nuts for main body to topworks 2007-23-0058 WO-291884 RV-2-71B flange 2007-23-0059 WO-29 1592 CV-1729 Replaced valve body.
2007-23-0060 WO-267369 Drywell Head Replaced 2 bolts and 3 nuts 2007-23-0061 WO-141358 SS-17A Replaced 4 flange mounting bolts 2007-23-0062 WO-291592 CV-1729 Replaced plug Replace 12 studs and 24 nuts for main body to piping 2007-23-0063 WO-291883 RV-2-71E inlet flange Replace 12 bolts and 12 nuts for main body to topworks 2007-23-0064 WO-291885 RV-2-7 1G flange Replace 12 bolts and 12 nuts for main body to topworks 2007-23-0065 WO-322083 RV-2-71A flange Replaced 1 stud and 16 nuts, and the pressure retaining 2007-23-0066 WO-142056 MO-2035 disc Replaced approximately 4 ft section of pip~ngand 2007-23-0067 WO-141016 RHRSW removed I re-installed, by weldmg, portlon of restra~nt SR-396 2007-23-0068 WO-324116 RHRSW Replaced approximately 4 ft section of piping 2007-23-0069 WO-323428 V15-H3 (PH-28) Replaced slightly bent hanger rod Replaced approximately 6" section of pipe and adjacent 2007-23-0070 WO-325774 ESWl-4fl-HBD 90 degree elbow 2007-23-0071 WO-326373 ESW5-4"-HBD Replaced 90 degree elbow
Nuclear Management Company Cycle 23 Summary Report Monticello Inservice Inspection 2007 Refueling Outage 111. Form NIS-2 Information NIS-2 Forms (140 pages to follow)
MONTICELLO NUCLEAR GENERATING PLANT 3613 -
TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS FORM NIS-2 - Page 1 of 2 ITEM 2005-23-0001 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 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.
- 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 0311347, 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
- 4. ldentification of System RHR Service Water, Spare Pump Bowl Ass'y s/n PG-2265, Class 3
- 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 ASME Repaired, Code Name of Name of Manufacturer National Other Year Replaced or Stamped Component Manufacturer Serial No. Board No. ldentification Built Replacement YES NO Interstage Johnston unknown n/a n/a 1979 Repaired [XI Bowl. Exist. Pumx, Co 2 lnterstage Johnston unknown n/a n/a 1979 Replaced [XI Bowls Pum~ Co Interstage Johnston 275604-2 n/a 2005 Replacement [XI Bowl Pum~ Co N66807-2 Interstage Johnston 275604-3 n/a 2005 Replacement Bowl Pum~ Co N66807-3
- 7. Description of Work Refurbished spare pump, 2 new bowls installed, 1exisfing bowl weld repaired.
- 8. Tests Conducted: Hydrostatic Pneumatic [7 Nominal Operating Pressure Other Pressure n/a psi Test Temp n/a OF APPROVED (Signatures available in1 Master File)
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS FORM NIS-2 - Page 2 of 2 L
ITEM 2005-23-0001 I
- 9. Remarks (Applicable Manufacturer's Data Reports to be Attached)
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 34thStreet, 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.
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.
CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this 3?wCStR p w RWLACE~ZNT conforms to the rules on the ASME Code,Section XI. repairlreplacement Signed ' \
- S&cr(ou X I IS1 CWLO Date 1 8 , ZO6 Owner or ~ b n e r ' sdesignee, 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'~ C O J J Y C C ~ I C Y ~of M~tf'Ond,ci- have inspected the components described in this Owner's Report during the period Dc-c 3, Z J a j to TAM 1 8 , 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 ki 9 //&&3A , 2 hhr/ J + 90a x -4'G Inspector's Signature National Board, Province and Endorsements Date 3nurcnflt/ 16 2.006 APPROVED (Signatures available in Master File) d
MONTICELLO NUCLEAR GENERATlNG PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS - FORM NIS-2 Page 1 of 2 ITEM 2005-23-0002 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 i n 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 7/12/2007 Name
- 2. Plant Monticello Nuclear Generating Plant Sheet I of 2 Name 2807 W. Cnty. Rd. 75, Monticello, Minnesota 55362 WO 0506359, 0507209 (PP 140418, 141066)
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 Recirc (REC), Loop 6 , Pump # I 2 (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 ASME Repaired, Code Name of Name of Manufacturer National Other Year Replaced or Stamped Component Manufacturer Serial No. Board No. ldentification Built Replacement YES NO Stuffing Box Sulzer Pump 5122530 n/a Ht. K564 2004 replaced Cover Co.
Stuffing Box Bingham II N35-3 n/a Ht. 83852 2007 replacement Cover Willamette
- 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 APPROVED (Signatures available in Master File)
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS - FORM NIS-2 Page 2 of 2 ITEM 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.
CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this ??E~~R/RCQLACUV~W h v ~ r y conforms to the rules on the ASME Code,Section XI. repairlreplacement Signed ,- S m X I IS eocao ate I Zm7 Owner or ownets 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 IY 6 ~ O T A and employed by
/ - ( ~ l t T F o E o \Tt>hUOgL62 2e-P J F c o u ~ c - C T I C U T of CIAIZTFJ~ZAI , c T 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.
Inspector's Signature omm missions lrrg3 A , KJ , / 4 N "3 ~r o 2 8-ro National Board, Province and Endorsements Date ICY (3 , 20°7 APPROVED (Signatures available in Master File)
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS - FORM NIS-2 Page 1 of 2 ITEM 2005-23-0004 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 i n form of lists, sketches, or drawings may be used, provided (1) size is 8-112 i n x II in, (2) information i n items 1through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets i s recorded at the top of this form.
- 1. Owner Xcel Energy Company Date 7/12/2007 Name
- 2. Plant Monticello Nuclear Generating Plant Sheet 1 of 2 Name 2807 W. Cnty. Rd. 75, Monticello, Minnesota 55362 WO 156335 Address Repair Organization P.O. No., Job No, etc.
- 3. Work Performed By NMC /Xcel Energy Type Code Symbol Stamp n/a Company Name Authorization No, n/a 2807 W. Cty Rd 75, Monticello, MN 55362 Expiration Date n/a Address
- 4. Identification of System EFT Emergency Service Water (FSW), 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 ASME Repaired, Code Name of Name of Manufacturer National Other Year Replaced or Stamped Component Manufacturer Serial No. Board No. ldentification Built Replacement YES NO TCV-403OB Penn 60-07 704- 1-I n/a n/a 2002 Replaced TCV-40308 Penn 60-07 704-1-5 n/a n/a 2002 Replacement 0
- 7. Description of Work Planned 4 year replacement of valve.
- 8. Tests Conducted: Hydrostatic Pneumatic Nominal Operating Pressure Other Pressure 79.248 psi Test Temp n/a OF
) 3087 (DOCUMENT CHANGE, HOLD AND COMMENT FORM) incorporated: - - I
- 'USE@MCY .-IARM~:
FOR ADMIE5.l~TRATIVE R e s Supv: ~
3613 PRGE 1 Assoc Ref: PRGE I Doc Tvue: REF ONLY I Admin initials:
I SR: N I I
Freq:
Date:
0 vrs I APPROVED (Signatures available in Master File)
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS - FORM NIS-2 Page 2 of 2 ITEM 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.
CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this /
\R REPMWT ACTI v conforms to the rules on the ASME Code,Section XI. ' repairlreplacement Signed c -
, SECT^ C0oR.D. Date Owner or Owner's ~esignee,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 N I P M C ~ D ~ ' ~ and employed by
/ j ~ dFOKP j ST~M CP S+J el-' C L J N ~ X ~ ~ of I - I A ~ ~ ~ o P ~ I C T have inspected the components described in this Owner's Report during the period q/t / d r to 7/15107 , 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 , 1 8 3 ~ j , w I ,A& oa 9rL8-Cd Inspector's Signature National Board, Province and Endorsements Date JclLY /3 , 2~07 APPROVED (Signatures available in Master File)
MONTICELLO NUCLEAR GENERAT/NGPLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS FORM NIS-2 - Page 1 of 2 ITEM 2005-23-0005 I NOTE This form may not address all items needed for documentation of a repairlreplacementprogram, see 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 1M8/2006 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 # I 2 (P-109B), Class 3
- 5. (a) Applicable Construction Code ANSI B31. I 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 ASME Repaired, Code Name of Name of Manufacturer National Other Year Replaced or Stamped Component Manufacturer Serial No. Board No. ldentification Built Replacement YES NO Bowl Ass'y NRW-6523 n/a n/a 2003 Replaced [XI P u m Co~
Bowl Ass'y Johnston PG-2265 n/a n/a 2005 Replacement [XI P u m Co~
- 7. Description of Work Replaced pump bowl assembly with rebuilt spare
- 8. Tests Conducted: Hydrostatic C] Pneumatic Nominal Operating Pressure jXI Other Pressure 236 psi Test Temp n/a OF 1 3087 (DOCUMENT CHANGE, HOLD AND COMMENT FORM) incorporated: -- 1 FOR ADMlNlSTWTlVE Resp Supv: PRGE 1 Assoc Ref: PRGE 1 SR: N I Frea: 0 vrs 1
USE ONLY ARMS: 3613 I Doc T v ~ e : REF ONLY I Admin initials: I Date:
APPROVED (Signatures available in Master File)
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS FORM NIS-2 - Page 2 of 2 ITEM 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).
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 1S ~ T I IS~ a t J ~ r o a r1~ 8 , 2006 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 f - l r & u ~ S Q YA and employed by hdn'; h k f l S ? E ~ M BOIL^^? $ 0sF C&YL/FCP)C%~ of I-I~ETPJRY , c r have inspected the components described in this Owner's Report during the period J'D-f T- Z / L*J to TAU I % , b o d 6 , 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 Inspector's Signature Commissions A/f )lp/ 3 AM, ' 1 f i M 0 3 1/ O Lg- co National ~ o a i d Province
, and Endorsements Date ~ A ~ / L C '81 , 2@b APPROVED (Signatures available in Master File)
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS FORM NIS-2 - Page 1 of 2 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 REPAIRIREPLACEMENTPROGRAM) 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 7/12/2007 Name
- 2. Plant Monticello Nuclear Generating Plant Sheet I of 2 Name 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 ASME Repaired, Code Name of Name of Manufacturer National Other Year Replaced or Stamped Component Manufacturer Serial No. Board No. ldentification Built Replacement YES NO SR-26 n/a n/a n/a n/a 1969 Repaired SR-26 n/a n/a n/a n/a 1969 Replaced Stanchion SR-26 Dubose Stanchion National n/a n/a Ht #203524 2005 Replacement IXI
- 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 1 3087 (DOCUMENT CHANGE, HOLD AND COMMENT FORM) incorporated: I FOR AI?MINISTMTWE USE ONLY %
Resu Suuv: PRGE I Assoc Ref:
1 Doc Tvue:
PRGE REF ONLY I SR:
1 Admin initials:
N I Frw:
1 Date:
0 vrs I APPROVED (Signatures available in Master File)
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS FORM NIS-2 - Page 2 of 2 ITEM 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.
CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this REPAIR/ R E P L A C ~ E N TAm v ITY conforms to the rules on the ASME Code,Section XI. repairlreplacement Signed - I , SECTXII S ( ~
Owner or Owner's Designee, Title R D Date ~ 12,2a7 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 ~ F Q I L L ? S T ~ f Al u ~~ l t ' nI ' r Z ~f C O ~ ~ / ~ - C T IofC ~ ~ f t h ~ y f ~ r i,l 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~.
Inspector's Signature Commissions A@ 1 ~ 6 A3 , , / q j h c ~ oo Y ~ Z ~ - C O National Board, Province and Endorsements Date SQLY 13 , ZOO7 APPROVED (Signatures available in Master File)
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS FORM NIS-2 - Page 1 of 2 ITEM 2006-23-0008 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 REPAIRIREPLACEMENTPROGRAM) for further guidance.
NOTE 2: Supplemental sheets i n form of lists, sketches, o r drawings may be used, provided (1) size i s 8-112 in x 11 in, (2) information i n items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets i s recorded at the top of this form.
- 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.
- 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 (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 ASME Repaired, Code Name of Name of Manufacturer National Other Year Replaced or Stamped Component Manufacturer Serial No. Board No. Identification Built Replacement YES NO SEE ATTACH- - - - - El MENT
- 7. Description of Work Remove existing snubbers for seal life program, replaced with rebuilt spares.
- 8. Tests Conducted: Hydrostatic Pneumatic Nominal Operating Pressure Other [XI Pressure n/a psi Test Temp n/a "F APPROVED (Signatures available in Master File)
MONTICELLO NUCLEAR GENERATlNG PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS - FORM NIS-2 Page 2 of 2 ITEM 2006-23-0008 I
- 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.
CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this ~ E P L A G ~ N ~
conforms to the rules on the ASME Code,Section XI. repairlreplacement Signed ,SECX I ISL Cwm.
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 ~ L ~ J ~ ~ s o ? ~ and employed by t-lnflFsAa s r 6 h ~orccn272 o f 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 / 1 0(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 Inspector's A&
Signature Commissions //J 3 A , ~ 3AN, 0 0 YO LR- cu National Board, ~robinceand Endorsements Date JWLY (o , L@rJ7 APPROVED (Signatures available in Master File)
Monticello Nuclear Generating Plant Cycle 23 12007 Refueling Outage Snubber Changeout RepairIReplacement (RIR) Sequence Log RIR ltem Number 2006-23-0008 NIS-2 Attachment Installation R/R Item Snubber Snubber SIN of Year of S/N of Replacement Number Snubber Size ASME Replacement Removed Removed Replacement Snubber Sequence -
Location System -
A SS-14 CFW 10 1 141353 500 ISI-13142-53-A 3/29/1998 533 280592 NX-14086-32,34 H-5 B SS-184 PCT 10 2 141354 040 ISI-94966-A 3/31/1998 042 280592 NL-94712 H-4 ISI-13142-26-6 C SS-316 CSP-B 10 2 141355 035 3/31/1998 534 280592 NL-95946 H-I D SS-13 141356 NX-14086-17, 31, ISl-13142-52A CFW I0 1 171 312911998 044 280592 32 H-4 E SS-38A RCI-STM 10 2 141357 ISI-13142-19B 013 312511998 536 280592 NX-14086-75 H-I F SS-17A RHR-B 10 1 141358 530 ISI-97004-A 3/31/1998 157 280592 NL-97036-5-1 H-4 G SS-38B RCI-STM 10 2 141359 ISI-13142-19B 033 4/1/1998 535 280592 NX-14086-77 H-I H SS-121 PCT 10 2 141360 037 ISI-94966-A 312711998 007 02-02066 NX-14084-122 H-2 NX-14086-27, 28, ISI-13142-52A I SS-11 CNV 10 1 141361 047 312711998 039 280592 29 H-7 J SS-12 CFW I0 1 141362 095 ISI-13142-53A 312911998 043 280592 NX-14086-28,30 H-7 K SS-37 HPC-STM 10 2 141363 028 ISI-13142-19A 312511998 003 03-1 1522 NX-14086-74 H-I L SS-17B RHR-B 10 1 141365 054-1 ISI-97004-A 3/31/1998 012 280592 NL-97036-6-1 H-3 CRD- ISI-93268-IA M CRD-A 20 2 141366 099 1/24/2000 128 03-11522 NQ-93567-37 H227 H-14 Attachment Page 1 of 2
Monticello Nuclear Generating Plant Cycle 23 12007 Refueling Outage Snubber Changeout RepairlReplacement (RIR) Sequence Log RIR ltem Number 2006-23-0008 NIS-2 Attachment Installation R/R Item Snubber Snubber SIN of Year of SIN of Replacement Number Snubber Size ASME Replacement Removed Removed Replacement Snubber Applicable IS1 Iso Dwg, (KIPS) Class WO Snubber Snubber Snubber N SS-303 RHR-A 10 2 141369 001 1/23/2000 ISI-13142-37E 532 280592 NL-95936 H-2 CRD- ISI-93268-IA 0 CRD-A 20 2 141371 214 1/24/2000 019A 02-02066 NQ-9356742 H232 H-12 P SS-8AR REC-A 20 1 141372 307 313011998 132 ISI-97005-A 280592 NL-97033-20-1 H-8 SS-8BR REC-B 20 1 141374 152 ISI-97006-A Q 3/30/1998 126 280592 NL-97035-20-1 H-8 R SS-2AR REC-A 30 1 141375 005 41211998 154 ISI-97005-C 280592 NL-97033-13-1 H-8 S SS-1BR REC-B 30 I 141377 470 41411998 ISI-97006-C 146 280592 NL-97035-12-1 H-7 T SS-3AR REC-A 30 1 141378 145 41211998 050 ISI-97005-C 280592 NL-97033-14-1 H-9 U SS-1AR REC-A 30 1 141379 468 41411998 102 1st-97005-C 280592 NL-97033-12-1 H-7 V SS-20 RHR-A 10 1 141382 539 411311998 529 ISI-97003-B 280592 NL-97034-12-1 H-2 W SS-35 HPC-WTR 10 2 141383 540 4/1/1998 ISI-1314240A 202 03-11522 NX-14086-72,-1 H-5 Attachment Page 2 of 2
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS FORM NIS-2 - Page 1 of 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.
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 7/13/2007 Name
- 2. Plant Monticello Nuclear Generating Plant Sheet I of 2 Name 2807 W.Cnty. Rd. 75, Monticello, Minnesota 55362 WO 153676 and 153175, EC-806 and 10317 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 ASME Repaired, Code Name of Name of Manufacturer National Other Year Replaced or Stamped -
Component Manufacturer Serial No. Board No. ldentification Built Replacement YES NO Stuffing Box Bingham Pmp 260969 ,,/a n/a 1969 Replaced Willamette Stfa Bx. n/a Stuffing Box Sulzer Pmp 260969 n/a n/a 2007 Replacement
- PU~DS Stfa Bx. n/a
- 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 1 3087 (DOCUMENT CHANGE, HOLD AND COMMENT FORM) incorporated: I
- $ORADPINISTRATJVE
" USE ONLY &$a Resp Supv: PRGE ARMS: 3613 I I Assoc Ref: PRGE Doc T v ~ e : REF ONLY 1 SR:
I Admin initials:
N 1 Frecl:
I Date:
0 vrs I
APPROVED (Signatures available in Master File)
OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS FORM NIS-2 - Page 2 of 2 ITEM 2006-23-0010 I
- 9. Remarks (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/&pLhCEMENTA r n V l ~
conforms to the rules on the ASME Code,Section XI. repairlreplacement Signed - I SECT)(( IS1 b Owner or Owner's Designee, Title oao Date PO I3 m 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 Atr/e's;nir and employed by C I A Y ~ T P ~ K U5 ' l r ' ~ hO B I W ttt & F CCWIJCCTIC& T of rFoE&, C
~ ( A R r have inspected the components described in this Owner's Report during the period d k b 6 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.rrA d-~cr.~-
Inspector's Signature Commissions X/17 11 k63 AJyF h k (35 L/c/zf c u -
National Board, Province and Endorsements Date 'i'trCy LJ , Zcn>7 APPROVED (Signatures available in Master File)
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS - FORM NIS-2 Page 1 of 2 ITEM 2006-23-001 1 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.
NOTE 2: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8-112 in x 1Iin, (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 7/13/2007 Name
- 2. Plant Monticello Nuclear Generating Plant Sheet I of 2 Name 2807 W. Cnty. Rd. 75, Monticello, Minnesota 55362 WO 153676 and EC-806 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 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 ASME Repaired, Code Name of Name of Manufacturer National Other Year Replaced or Stamped Component Manufacturer Serial No. Board No. ldentification Built Replacement YES NO (16) Stuffing Bingham n/a n/a n/a 1969 Replaced Rox Nuts Willamette (16) Stuffing Nova Ht#7420672 Box Nuts Machine n/a n/a Q1405 2006 Replacement IXI
- 7. Description of Work Replaced A194 Gr 2H with A194 Gr 7 in support of EC 806 (installed 2007)
- 8. Tests Conducted: Hydrostatic Pneumatic Nominal Operating Pressure Other Pressure n/a psi Test Temp n/a "F APPROVED (Signatures available in Master File)
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS - FORM NIS-2 Page 2 of 2 ITEM 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.
CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this %ML\.\R 1 r- A
/ mJ t r y conforms to the rules on the ASME Code,Section XI. kepairlreplacement Signed &\ . SEQX) I s 1 b0Kb Owner o?owner% 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 ~ ~ w u E . s + ~ and employed by jld)zrk~ru fii?htl B J ~ L C X i f 2 d F @&M>~ICLIJ of ) ~ . ~ - Q F ~ P uC ,T 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*
Inspector's Signature Commissions ~8 [ I f 6 3 P , ~ Z~ d~~l~~r-cu I M National Board, Province and Endorsements Date ULY 2.3 2007 APPROVED (Signatures available in Master File)
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS FORM NIS-2 - Page 1 of 23 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 i n form of lists, sketches, or drawings may be used, provided (Isize ) is 8-112 i n x 11 in, (2) information i n items 1 through 6 on this report i s included on each sheet, and (3) each sheet is numbered and the number of sheets i s recorded at the top of this form.
- 1. Owner Xcel Energy Company Date 7/16/2007 Name
- 2. Plant Monticello Nuclear Generating Plant Sheet I of 3 Name 2807 W. Cnty. Rd. 75, Monticello, Minnesota 55362 EC-748 and WO 151841 Address Repair Organization P.O. No., Job No. etc.
- 3. Work Performed By NMC/Xcel Energy Co Type Code Symbol Stamp n/a Company Name Authorization No. n/a 2807 W. Cty Rd 75, Monticello, MN 55362 Expiration Date n/a Address
- 4. 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 ASME Repaired, Code Name of Name of Manufacturer National Other Year Replaced or Stamped Component Manufacturer Serial No. Board No. ldentification Built Replacement YES NO MO-2373 BW/lP E l 63A-1-1 n/a n/a 1998 replaced IXI MO-2373 Flowsenfe BC-390 n/a n/a 2007 replacement PS 15-35ED oioe unknown n/a n/a n/a 1998 replaced IXI PS 15-3"-ED oioe Dubose n/a n/a Ht # L40039 2007 replacement IXI SEE PAGE 2 FOR ADD'L ITEMS
- 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 APPROVED (Signatures available in Master File)
Monticello Nuclear Generating Plant Form NIS-2 Continuation Sheet ITEM 2006-23-0013 Repaired, ASME Code Name of Name of Manufacturer National Other Year Replaced or Stamped Component Manufacturer Serial No. Board No. Identification Built Replacement Yes No PSl5-3"-ED Unknown n/a n/a n/a 1998 replaced X Elbow PS153'LED Chicago n/a n/a Ht.# 5 8 5 0 A 2007 replacement X Elbow Tube & Iron A
1 3613 I I
MONTICELLO NUCLEAR GENERATING PLANT I OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS FORM NIS-2 -
1 Revision 4 Paae;_L&33&3 L,
ITEM 2006-23-0013 I
- 9. Remarks (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~- A w u IV conforms to the rules on the ASME Code,Section XI. repairlreplacement Signed , sea to^ XI IS\ C o e m 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 ~ U C O?A ' ~ and employed by FIAPTF*~Z@ ~ T l c f l h / j b l l b ' p~ f - ~ d ~ c O b C E ' C ~ f of C41 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 Inspector's ALLLA<$
Signature Commissions R/j / r g g 1 A , v,jl,~ L O CI ) L / ~ Z ~ - C C J National ~ o a r dProvince
, and Endorsements Date 3QLY ZL , CJD7 APPROVED (Signatures available in Master File)
MONTICELLO NUCLEAR GENERATlNG PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS - FORM NIS-2 Page 1 of 2 ITEM 2006-23-0014 I NOTE 1: 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.
- 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 151841 and 285967 Address Repair Organization P.O. No., Job No. etc.
- 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
- 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 ASME Repaired, Code Name of Name of Manufacturer National Other Year Replaced or Stamped Component Manufacturer Serial No. Board No. Identification Built Replacement YES NO MO-2374 BW/lP E l 63A-2-1 n/a n/a 1998 replaced MO-2374 Flowsen~e BC-39 I n/a n/a 2007 replacement IX]
PSl5-3"ED US Steel n/a n/a n/a 2003 replaced oioe IX]
PS 153"-ED Dubose n/a n/a Ht # L40039 2007 replacement be
- 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 APPROVED (Signatures available in Master File)
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS - FORM NIS-2 Page 2 of 2 ITEM 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.
CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this ~ Z C P ( H L / W ~ A ~ I \k~rOl vW iry conforms to the rules on the ASME Code,Section XI. repairlreplacement Signed . Srcnor X( 1st COOED Date .-+?&+I-Owner or dwnerl$ 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 MWIC/FS 074 and employed by C l n n C ~ o R l d rTt-ni21 ~ ~ I L CSRf - 1 ~ F C o k / & E c ~ l c a r o f + I A P ? F O ~ Z U , C ~ have inspected the components described in this Owner's Report during the period 'ill b to
~ ( L / dL7 , 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' l Y l ~03 Y ~ 2 8 4
" Inspector's Signature National Board, Province and Endorsements Date J ~ L Y 2 L , Lo07 APPROVED (Signatures available in Master File)
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS FORM NIS-2 - Page 1 of 2 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.
NOTE 2: Supplemental sheets i n form of lists, sketches, or drawings may be used, provided (1) size is 8-112 i n 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 i s recorded at the top of this form.
- 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 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 ASME Repaired, Code Name of Name of Manufacturer National Other Year Replaced or Stamped Component Manufacturer Serial No. Board No. ldentification Built Replacement YES NO ESW-1-2 OIC C o p Valve s/n n/a n/a 1969 Repaired 10568
- 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 1 3087 (DOCUMENT CHANGE, HOLD AND COMMENT FORM) incorporated: I FOR ADMINISTRATIVE/
2 U S E ~ F J LI ,~ .4:.'
Resp Supv: PRGE I Assoc Ref:
I Doc Tvw:
PRGE REF ONLY I SR:
I Admin initials:
N I Freq:
I Date:
0 yrs I APPROVED (Signatures available in Master File)
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS - FORM NIS-2 Page 2 of 2 ITEM 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)
Signed
--- CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this conforms to the rules on the ASME Code,Section XI.
, SECTX I [Sf COO(D Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION REPAIR /wCCM~~T repairlreplacement I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel fifftvlry Inspectors and the State or Province of ~ ~ I M ~ / F . F O T ~ and employed by C C ~ W F ~ K1U 7 0 ~~O I L ~1- 7L 1 O F C ~ Q ~ ~ C T ~ I C of U ~ h ~ ~ z i - r t ncoT, have inspected the components described in this Owner's Report during the period Y/ I ( J C 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&.! Inspector's Signature Commissions A/L) 1 ,tdrc/, 2 / / L ~ Y O O Y v ~ g - c c '
National Board, Province and Endorsements Date TQLY 20 , Lou7 APPROVED (Signatures available in Master File)
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS - FORM NIS-2 Page 1 of 2 ITEM 2006-23-0016 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 REPAIRIREPLACEMENTPROGRAM) 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 7/18/2007 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.
- 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, 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 ASME Repaired, Code Name of Name of Manufacturer National Other Year Replaced or Stamped Component Manufacturer Serial No. Board No. ldentification Built Replacement YES NO TW-12 n/a n/a n/a TWH-12 1987 Repaired
- 7. Description of Work Removed integral attachment and modified for Engineering Change (EC-775)
- 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 I
1 Assoc Ref: PRGE Doc T v ~ e : REF ONLY I SR I Admin initials:
N I Freq:
I Date.
0 vrs I
APPROVED (Signatures available in Master File)
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS FORM NIS-2 - Page 2 of 2 ITEM 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 D l . 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.
CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this R ~ A W/ U( PI R W~P~T Ac..l~~-ry conforms to the rules on the ASME Code,Section XI. repairlreplacement Signed -SECT XI Is\ (born Owner o<~wner'sDesignee, 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 Y M S OTA and employed by
?-d~firl?rrt(l~lt-nho d l ~ b $tS
~ 0 F r;~wt~ncki of ~[~rzr~ofia have 9 11/d L I
inspected he components described in this Owner's Report during the period 7 / 2 2 (77 , and state that to the best of my knowledge and belief, the Owner has performed to 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 t r b-6 3 4 , w.s\ & w d d L / u ~k-rd Inspector's Signature National Board, Province and Endorsements Date b y bL , 2-30>
APPROVED (Signatures available in Master File)
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS FORM NIS-2 - Page 1 of 2 ITEM 2006-23-0017 I NOTE This form may not address all items needed for documentation of a repairlreplacementprogram, 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 llin, (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 7/18/2007 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.
- 3. Work Performed By NMC /Xcel Energy Type Code Symbol Stamp n/a Company Name Authorization No. n/a 2807 W. Cty R d 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 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 ASME Repaired, Code Name of Name of Manufacturer National Other Year Replaced or Stamped Component Manufacturer Serial No. Board No. ldentification Built Replacement YES NO TWH-86 Bergen n/a n/a Type 1987 Replaced S ~ r i n aCan Patterson Size 7 7WH-86 Bergen Type S ~ r i n aCan Patterson n/a n/a Size 71 2007 Replacement IXI n
- 7. Description of Work Replaced the spring can on support WH-86 as required by EC-775
- 8. Tests Conducted: Hydrostatic Pneumatic 0 Nominal Operating Pressure C]
Other Pressure n/a psi Test Temp n/a "F 3087 (DOCUMENT CHANGE, HOLD AND COMMENT FORM) incorporated:
- p#&4gh& ' 12$A
/S)$l!P;,+;$ /P h/#l / RARMS:
x 4 ' 0 e s Suw:
~
3613 PRGE I Assoc Ref: PRGE I SR:
I Doc Tvpe: REF ONLY 1 Admin initials:
N I Freq:
I Date:
0 vrs I
APPROVED (Signatures available in Master File)
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS - FORM NIS-2 Page 2 of 2 ITEM 2006-23-0017 1
- 9. Remarks (Applicable Manufacturer's Data Reports to be Attached)
This repair-replacementactivity also included use of A WS D l . 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 / ~ c L r ) c e Ac*v\*y
~ n ~ ~
conforms to the rules on the ASME Code,Section XI. repairlreplacement Signed . SECTXIIS( COD^ Date Owner or owner'd 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 r w ~ TA, ~ o and employed by t ~ a r e l / msr~nm~ o t ~ t ' rhf z JPCG&~/ECTIC~~T of u.\emrnu , c 7 have inspected the components described in this Owner's Report during the peiiod 711 I w b to 7 h l /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,A L ~
Inspector's Signature Commissions u g 11((, 3 4 ,lv; s A/OP ~ ~ U Z ~ - C O National Board, Province and Endorsements Date n-4I.r 2L , 7 APPROVED (Signatures available in Master File)
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS - FORM NIS-2 Page 1 o f 2 3 ,za, ITEM 2006-23-0018 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.
NOTE 2: Supplemental sheets i n form of lists, sketches, or drawings may be used, provided (1) size is 8-112 in x 11 in, (2) information i n 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 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.
- 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
- 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 2006-23-0018 WO Nos. 285768 Repaired, ASME Code Name of Name of Manufacturer National Other Year Replaced or Stamped Component Manufacturer Serial No. Board No. Identification Built Replacement Yes No LS- 7429A 3337- 1 n/a n/a 1981 replaced X (Div I) Components LS- 7429A 7806-S n/a n/a 2007 replacement X (Div I) Components LS- 7430A 708 n/a n/a 1981 replaced X (Div I) Components L S- 7430A 7808-S n/a n/a 2007 replacement X (Div I) Components LS-7428C 872- 1 n/a n/a 1981 replaced X
( ~ j ,11) , Components LS-7428C 7804-S n/a n/a 2007 replacement X
( ~ j ,11), Components LS-7428D 873- 1 n/a n/a 1981 replaced X
(~i,,11) Components LS-7428D 78058 n/a n/a 2007 replacement X (D~V11) Components LS-74298 707 n/a n/a 1981 replaced X
(~i,,11) Components LS-74298 7810-S n/a n/a 2007 replacement X
( ~ i , 11)
, Components LS-7430B Fluid 709 n/a n/a X
( ~ i , ,11) Components L S- 7430B 7809-S n/a n/a 2007 replacement X (Div 11) Components
1 MONTICELLO NUCLEAR GENERATING PLANT 1 3613 I TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS FORM NIS-2 -
ITEM 2006-23-001 8 I
- 9. Remarks (Applicable Manufacturer's Data Reports to be Attached)
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.
CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this R E P A ~ R/REPLAY*E~T ACTI VlTy conforms to the rules on the ASME Code,Section XI. repairireplacement Signed , SE XI [SIb
~ ~ O N ~ a t e 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 , Q U . G - & ~ I A and employed by k~1ZthrbUSTt'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-Inspector's Signature Commissions b17 /1r63 4, % 3 r c ? ~00 q u L& 4u National Board, Province and Endorsements Date T ~ L Y 23 , -3 APPROVED (Signatures available in Master File)
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS FORM NIS-2 - Page 1 of 2 ITEM 2006-23-0019 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 i n 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 i s recorded at the top of this form.
- 1. Owner Xcel Energy Company Date 7/19/2007 Name
- 2. Plant Monticello Nuclear Generating Plant Sheet 1 of 2 Name 2807 W. Cnty. Rd. 75, Monticello, Minnesota 55362 WO 140381 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 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 ASME Repaired, Code Name of Name of Manufacturer National Other Year Replaced or Stamped Component Manufacturer Serial No. Board No. ldentification Built Replacement YES NO M"-20q8 Valve s/n Ht. #
Bonne Flowserve A Y260 n/a M3156 2005 Replaced IXJ Mo-2008 Valve d n Ht. #
. Bonnet Flowserve A Y260 n/a 227H096 2007 Replacement IXJ 0 0
- 7. Description of Work Replaced MO-2008 bonnet like for like (replacement built 2006, installed 2007)
- 8. Tests Conducted: Hydrostatic Pneumatic Nominal Operating Pressure Other Pressure 110 psi Test Temp n/a "F
) 3087 (DOCUMENT CHANGE, HOLD AND COMMENT FORM) incorporated: -- -- 1 F,OR ADMINIST,WTJVE uSEDNLY "
Resp Supv: PRGE I Assoc Ref: PRGE I SR:
I Doc T v ~ e : REF ONLY I Admin initials:
N I Frea:
I Date:
0 vrs I
APPROVED (Signatures available in Master File)
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS FORM NIS-2 - Page 2 of 2 ITEM 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.
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.
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
& SC~(ONX/ I Owner or Owner's Designee, Title IS\ &OW CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of h l ~ ~ ~ ~ 0 7 . t and employed by I - ( A @ F ~ R I I ~ ~ ~ ' ; C ^ / ) ~ U V / L L ~ 2$&
P 3 F C o k ~ ~ c > \ c w o f 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 - /(td3 p , .L , c z p o o y g ~ g , c o wh/(3~
Inspector's Signature National Board, Province and Endorsements Date J(4~c.fW , 2~07 APPROVED (Signatures available in Master File)
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS - FORM NIS-2 Page 1 ofa3,!*
ITEM 2006-23-0020 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.
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 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.
- 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
- 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 ASME Repaired, Code Name of Name of Manufacturer National Other Year Replaced or Stamped Component Manufacturer Serial No. Board No. ldentification Built Replacement YES NO SW-16 OIC Corp n/a n/a n/a 1969 replaced IXI w-22q (Loor, A)
Loor, A Flowserve BC-455 n/a n/a 2007 replacement SW2 1-4"-HF Tioga n/a n/a 52TA46652 2007 replacement (Loor, A) S/N 1 SEE PAGE 2 FOR LOOPB ITEMS
- 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 APPROVED (Signatures available in Master File)
Monticello Nuclear Generating Plant Form NIS-2 Continuation Sheet ITEM 2006-23-0020 WO Nos. 267425 284077 Repaired, ASME Code Name of Name of Manufacturer National Other Year Replaced or Stamped Component Manufacturer Serial No. Board No. Identification Built Replacement Yes No SW-18 OIC Corp n/a n/a n/a 1969 replaced X (Loop B)
SW-229 Flowserve BC-456 n/a n/a 2007 replacement X (Loop B)
SW21-4'LHF Tioga n/a n/a 52TA4665, 2007 replacement X (LOOPB) S/N f
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS FORM NIS-2 -
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.
CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this KEPAIL/REPUKWNT 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 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 n e u 376 fih 8 U ~ L L H i t~ JF CflWt6CiZof ,LT have inspected the components described in this Owner's Report during the period lC/ 3a /a& to 712.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/@ i f f 6 3 AJ U, J? hrC/ mYQZf-Q7 Inspector's Signature National Board, Province and Endorsements Date JOLT 23 , Zud 7 APPROVED (Signatures available in Master File)
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS - FORM NIS-2 Page 1 of 2 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.
- 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.
- 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 ASME Repaired, Code Name of Name of Manufacturer National Other Year Replaced or Stamped Component Manufacturer Serial No. Board No. ldentification Built Replacement YES NO SR-852 NMC n/a n/a n/a 2007 Replacement (new)
[XI
- 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 O F APPROVED (Signatures available in Master File)
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS FORM NIS-2 - Page 2 of 2 ITEM 2006-23-002 I I
- 9. Remarks (Applicable Manufacturer's Data Reports to be Attached)
This repair/replacement activity also included use of A WS D l . 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 I
'R~pfllp R c P U \ c f . W T Acwy conforms to the rules on the ASME Code,Section XI. rbpairlreplacement Signed CSEWONX ( IS\
C Owner or 0wnei's Designee, Title (00-CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of h l t % ~ & ~ o t & and employed by b l t T f ~ l i ? ~ ~ T#dl~t%!
~ % h I a O F C(rWErTTLCqX of HAIS~FUIZ~,CT have inspected the components described in this Owner's Report during the period 4 / r ld'L; to 71 ~ 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&
Inspector's Signature Commissions A/B / I S3 A )v; t ~,+,voo~i V~&--CCI National Board, Province and Endorsements Date 'S'GLY 2-2 , ZdoJ APPROVED (Signatures available in Master File)
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS - FORM NIS-2 Page 1 of 2 ITEM 2006-23-0022 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.
NOTE 2: Supplemental sheets i n form of lists, sketches, or drawings may be used, provided (1) size is 8-112 in x 11 in, (2) information i n items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets i s recorded at the top of this form.
- 1. Owner Xcel Energy Company Date 7/19/2007 Name
- 2. Plant Monticello Nuclear Generating Plant Sheet Name 2807 W. Cnty. Rd. 75, Monticello, Minnesota 55362 WO 152929 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. Identificationofsystem EDGEmerg. Service Water(EDG-ESW), P u m p # l 2 ( P - I I I B ) , 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 ASME Repaired, Code Name of Name of Manufacturer National Other Year Replaced or Stamped Component Manufacturer Serial No. Board No. ldentification Built Replacement YES NO P-1116 Johnston QD-6702 n/a n/a 2004 Replaced (XI P-1116 Johnston QD-6703 n/a n/a 2006 Replacement (XI 0
- 7. Description of Work Replaced EDG-ESW Pump # I 2 (P-11IB) with rebuilt spare.
- 8. Tests Conducted: Hydrostatic Pneumatic Nominal Operating Pressure Other 0 Pressure 47 psi Test Temp n/a O F APPROVED (Signatures available in Master File)
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS - FORM NIS-2 Page 2 of 2 ITEM 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 S C ~ ~ W 131 X ~c~t?.B. Date $,&J19 , 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 H w ~ 6 . so T 4 and employed by C I A P T ~ d~ rr) J 70-A N O ILCM Cf 0 F r d k ~ 6 - c lct c f l of b(fiflTfiK OJ c-i" have inspected the components described in this Owner's Report during the period ? I Ld6 to 7 ( L3 / d 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 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-Insp,ectorls Signature Commissions ,ud 11 86 3 4,wJ h/r/B dw W+C, National Board, Province and Endorsements Date ~ L Y 23 ' , Coo7 APPROVED (Signatures available in Master File)
MONTICELLO NUCLEAR GENERATlNG PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS - FORM NIS-2 Page 1 of 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.
NOTE 2: Supplemental sheets i n form of lists, sketches, o r drawings may be used, provided (1) size is 8-112 in x 11 in, (2) information in items 1through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.
- 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.
- 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 1978Addenda 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 AS ME Repaired, Code Name of Name of Manufacturer National Other Year Replaced or Stamped Component Manufacturer Serial No. Board No. ldentification Built Replacement YES NO ESW-32 Anchor El241-1-2 n/a n/a 1983 Replaced Oarlina (XI ES W-32 Flowserve AZ-899 n/a n/a 2007 Replacement C] (XI ES W1-3"-
HBD unknown n/a n/a n/a 1983 Replaced C] IXI ESW1-3"-
HBD Dubose n/a n/a HtpT L2 56 2007 Replacement 0
- 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 74.3 psi Test Temp n/a "F 1 3087 (DOCUMENT CHANGE, HOLD AND COMMENT FORM) incorporated: I Fog ADMIN1$TRATivE
%WEONLY " '"G Resp Supv: PRGE 1 Assoc Ref: PRGE I SR:
I Doc T v ~ e : REF ONLY I Admin initials:
N I Freq:
I Date:
0 yrs 1
APPROVED (Signatures available in Master File)
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS - FORM NIS-2 Page 2 of 2 ITEM 2006-23-0023 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 /ST required.
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 Signed c
+ 3 SECT)(/ 1 3 c00bZD Owner or Owner's Designee, Title ate 5 , 2007 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 k f ~ a t~n p 5l-t-9t-c
~ f i o r c t ~ L + ~ J JC O= ~ , / W F C T ~ ~ Y ~ of j-f-14/2tF O ~ Z Q , c T have inspe ted the components described in this Owner's Report during the period CF/C / d l ; 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 I I ~ 3G A, I L / , , ~ & t ~war J-cu Inspector's Signature National Board, Province and Endorsements Date J-L~LYL L , 2.337 APPROVED (Signatures available in Master File)
MONTlCELLO NUCLEAR GENERATlNG PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS - FORM NIS-2 Page 1 of 2 ITEM 2006-23-0024 I NOTE This form may not address all items needed for documentation of a repairlreplacementprogram, see 4 AWI-09.04.03 (ASME SECTION XI REPAIRIREPLACEMENT PROGRAM) for further guidance.
NOTE 2: Supplemental sheets i n 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 7/18/2007 Name
- 2. Plant Monticello Nuclear Generating Plant Sheet 1 of 2 Name 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 ~ d i t i o nof Section XI Utilized for Repairs or Replacement 2001 Edition, No Addenda
- 6. ldentification of Components Repaired or Replaced and Replacement Components ASME Repaired, Code Name of Name of Manufacturer National Other Year Replaced or Stamped Component Manufacturer Serial No. Board No. ldentification Built Replacement YES NO Anchor ES W-31 Darlina E1241-1-1 n/a n/a 1983 Replaced IXI ESW-31 Flowserve AZ-532 n/a n/a 2007 Replacement IX)
ES W5-3"- unknown n/a n/a n/a 1983 Replaced IXI HBD ES W5-3"-
HBD Dubose n/a n/a Ht Tde L22 69 2007 Replacement 0
- 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 1 3087 (DOCUMENT CHANGE, HOLD AND COMMENT FORM) incorporated:
L I
Resp S u ~ v : PRGE ARMS: 3613 1 Assoc Ref: PRGE 1 Doc Tvw: REF ONLY I Admin initials:
I SR: N 1 Freq:
I Date:
0 vrs I
APPROVED (Signatures available in Master File)
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS FORM NIS-2 - Page 2 of 2 ITEM 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.
CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this R E P ~ ~ ~ ~ / ~ V M C ~P HCETN ITV ) ~ ~
conforms to the rules on the ASME Code,Section XI. r6pairlreplacement Signed C
Owner or Owner's Designee, Title Date orL1 1s .ea7 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 - r n / d O~W ~ and employed by
/ . l r l n t - ~
- a e s7Mh B O I L ~ SS L f $ OF CoUI/677jQn of I - I ~ ~ r F u f ,cT lu have inspected the components described in this Owner's Report during the period c/ l c lo6 to 7 /~ 2 l d 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 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 ,-
Inspector's Signature Commissions )JO I/ P6 3 9,lv; b ict M 33 Y ~ z . w - ~
National Board, Province and Endorsements Date J'QW' 2L. , Zd07 APPROVED (Signatures available in Master File)
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS FORM NIS-2 - Page 1 of 2 ITEM 2006-23-0025 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.
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 i n 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 7/7/2007 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.
- 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 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 ASME Repaired, Code Name of Name of Manufacturer National Other Year Replaced or Stamped Component Manufacturer Serial No. Board No. ldentification Built Replacement YES NO SS-707 Lisega 614900/052 - MNGPdn 2001 Replaced IXI 700 SS-707 Lisega 615060/055 - MNGPS/" 2001 Replacement 701 (2) Snubber Bergen- - - - 1969 Replaced IXI End Pins Paterson (2) Snubber Bergen- - - Hf# 306610 1991 Replacement IXI End Pins Paterson
- 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 APPROVED (Signatures available in Master File)
MONTICEL~NUCLEA R G E ~ TlNG A PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS - FORM NIS-2 Page 2 of 2
- 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.
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 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 ~ 3PI-9 J and employed by
- 4 PTf4 s ?t'nh ~3u/l . ~1flyJ 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 m y Commissions bfi [/KG 3 A~ r v , ~, /cro 00 4 3 ~co~ -
Inspector's Signature National Board, Province and Endorsements Date . Scl Cy "r I 2a7 APPROVED (Signatures available in Master File)
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS FORM NIS-2 - Page 1 of 2 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.
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 7/10/2007 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.
- 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 ASME Repaired, Code Name of Name of Manufacturer National Other Year Replaced or Stamped Component Manufacturer Serial No. Board No. ldentification Built Replacement YES NO Main Bergen 529 n/a n/a un- Replaced Cvlinder Paferson [ql known Main Bergen 529 n/a n/a 2006 Replacement Cvlinder Paterson [ql
- 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 APPROVED (Signatures available in Master File)
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS FORM NIS-2 - Page 2 of 2 ITEM 2006-23-0026 I
- 9. Remarks (Applicable Manufacturer's Data Reports to be Attached)
Functionallv tested Der 0251. VT-3 pre-senlice exam to be com~letedfollowina installation under work order CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this R E & ~ R /~ Q ~ L O W ArrlV
~ ~ T 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
~ , A K . ~ - F o K P >?C'4h B o I L ~ W ZYJ o f c O & p i ' / c q ~ of l-I4XTFolw C T have inspected the components described in this Owner's ~ e ~ o r to t 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 / B I C ~ G J4 , J /'ru0 0 YO ~ g - c c ,
Inspector's Signature National Board, Province and Endorsements Date ~ U L Y r l I Zoo7 APPROVED (Signatures available in Master File)
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS - FORM NIS-2 Page 1 o f 2 3 $&,
ITEM 2006-23-002 7 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 REPAIRIREPLACEMENTPROGRAM) 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 7/10/2007 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.
- 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 ASME Repaired, Code Name of Name of Manufacturer National Other Year Replaced or Stamped Component Manufacturer Serial No. Board No. ldentification Built Replacement YES NO Main Bergen 044 n/a n/a un- Replaced Cvlinder Paterson known C]
Main Bergen 044 n/a n/a 2006 Replacement
- Cvlinder Paterson C] IX]
Piston Bergen 044 n/a n/a un- Replaced Paterson known IX]
Piston Bergen 044 n/a n/a 2006 Replacement Paterson IX]
See Page 2 for add'l items
- 7. Description of Work Replaced Main Cylinder, Piston, Piston Rings /Rod / Nut during rebuild.
- 8. Tests Conducted: Hydrostatic [7 Pneumatic Nominal Operating Pressure [7 Other Pressure psi Test Temp "F APPROVED (Signatures available in Master File)
Monticello Nuclear Generating Plant P a g e 2 of 3 Form NIS-2 Continuation Sheet ITEM 2006-23-0027 WO No. 280592 Repaired, ASME Code Name of Name of Manufacturer National Other Year Replaced or . Stamped Component Manufacturer Serial No. Board No. Identification Built Replacement Yes No Piston Rings Bergen 044 n/a n/a Un- replaced X Paferson known Piston Rings Bergen 044 n/a n/a 2006 replacement X Paterson Piston Rod Bergen 044 n/a n/a Un- replaced X Paterson known Piston Rod Bergen 044 n/a n/a 2006 replacement X Paterson Piston Nuf Bergen 044 n/a n/a Un- replaced X Paferson known Piston Nut Bergen 044 n/a n/a 2006 replacement X Paterson
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS FORM NIS-2 -
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.
-- CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this conforms to the rules on the ASME Code,Section XI.
Signed a SECT X I I S ( COO-Owner or 0wne?s Designee, Title CERTIFICATE OF INSERVICE INSPECTION
~ ~ P A I ~ / R ~ U ~ C ~ Acsr
'repairlreplacement N fly M E lv T 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 ~ V G LoT4 and employed by Hd f l 7 P d t b 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% / d 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.
7 lA ~Inspector's Signature Commissions A/alrr6J , q , ~ r ' , r r w ~ u v ~ z g - c u National Board, Province and Endorsements Date TQLY 1 1 , 2-uu7 APPROVED (Signatures available in Master File)
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS - FORM NIS-2 Page 1 of 2 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 i n x 11 in, (2) information in items 1through 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 7/10/2007 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.
- 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. Identificationof System Spare - 20 Kip Snubber
- 5. (a) Applicable Construction Code 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
- 8. Tests Conducted: Hydrostatic C] Pneumatic C] Nominal Operating Pressure Other Pressure psi Test Temp "F APPROVED (Signatures available in Master File)
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 i
REPLACEMENTS FORM NIS-2 - Page 2 of 2 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~letedfollowinu installation under CERTIFICATE OF COMPLIANCE
/
We certify that the statements made in the report are correct and this %@R~RW ~ C E M E ~ A T w~u I~
conforms to the rules on the ASME Code,Section XI. repairlreplacement Signed-
-7 SECT. 1 IS1 owner br 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 1 9 I p a ' S o t A and employed by
& I ~ ~ ~ O I ~ Y J T E U ~ ~ O I I ~OI FZ T ~ A / & F C F / C U / 'of / ~ A P ~ ~ CP rD , have inspected the components described in this Owner's Report during the period 3 / r c l /06 to 7 / I L 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 Inspector's Signature Commissions ~g r /l(- -
3 n , A/,1 IVJJ a J L/d LB c o National Board, Province and Endorsements Date JWY l i ~ , rw7 APPROVED (Signatures available in Master File)
--- - -- -- -- A&--- -
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS - FORM NIS-2 Page 1 of 2 ITEM 2006-23-0029 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.
NOTE 2: Supplemental sheets i n form of lists, sketches, or drawings may be used, provided (1) size is 8-112 in x II in, (2) information in items 1through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets i s recorded at the top of this form.
- 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.
- 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 - 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 ASME Repaired, Code Name of Name of Manufacturer National Other Year Replaced or Stamped Component Manufacturer Serial No. Board No. ldentification Built Replacement YES NO Valve Bergen 126 n/a n/a un- Replaced Manifold Paferson known Valve Bergen 126 n/a n/a 2006 Replacement Manifold Paterson IX) 0 Description of Work Replaced valve manifold during rebuild PM.
- 8. Tests Conducted: Hydrostatic Pneumatic Nominal Operating Pressure Other Pressure psi Test Temp O F 1 3087 (DOCUMENT CHANGE, HOLD AND COMMENT FORM) incorporated: I
@FOR 'ADMifilj9xwTIVE I Assoc Ref: I SR: I Freq: (
7
,.' U$$EON&+' . Resp Supv: PRGE ARMS: 3613 1 PRGE Doc T v ~ e : REF ONLY I Admin initials:
N I Date:
0 vrs APPROVED (Signatures available in Master File)
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS FORM NIS-2 - Page 2 of 2 ITEM 2006-23-0029 I
- 9. Remarks (Applicable Manufacturer's Data Reports to be Attached)
Functionallv tested m r 0251. VT-3 me-service exam to be completed followina installation under CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this REPAIR/ afWMENT Am v IT^
conforms to the rules on the ASME Code,Section XI. repairlreplacement Signed I -.sem.xl 1 S f c w ~ ~ Date Owner or ~wnelr'sDesignee, Title
. FO 11 . 2-04 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 R A K S F Q U ~ ,5 W A h BUILt S J ~ c o h ~ t ' c ) . l c r T of b13 dr F O , 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 , I Y ~ oOVu LR-Co Inspector's Signature National Board, Province and Endorsements Date Ij-uCLJ/ /z , zoo7 APPROVED (Signatures available in Master File)
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS FORM NIS-2 - Page 1 of33 ,G7 NOTE This form may not address all items needed for documentation of a repairlreplacement program, see 4 Awl-09.04.03 (ASME SECTION XI REPAIRIREPLACEMENTPROGRAM) 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 7/11/2007 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.
- 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 - 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 ASME Repaired, Code Name of Name of Manufacturer National Other Year Replaced or Stamped Component Manufacturer Serial No. Board No. ldentification Built Replacement YES NO Main Bergen un-Cvlinder Paferson 157 n/a n/a known Replaced IXI Main Bergen Cvlinder Paferson 157 n/a n/a 2006 Replacemenf IXI Bergen un-Piston Paferson 157 n/a n/a known Replaced IXI Bergen
- Pisfon Paferson 157 n/a n/a 2006 Replacement 0 -
See Page 2 for add'l items
- 7. Description of Work Replaced Main Cylinder, Piston, Piston Rings during rebuild.
- 8. Tests Conducted: Hydrostatic Pneumatic Nominal Operating Pressure Other [XI Pressure psi Test Temp "F APPROVED (Signatures available i n Master File)
Monticello Nuclear Generating Plant Form NIS-2 Continuation Sheet ITEM 2006-23-0030 Repaired, ASME Code Name of Name of Manufacturer National Other Year Replaced or Stamped Component Manufacturer Serial No. Board No. Identification Built Replacement Yes No Piston Rings Bergen 157 n/a n/a Un- replaced X Paterson known Piston Rings Bergen 157 n/a n/a 2006 replacement X Paterson
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS FORM NIS-2 -
ITEM 2006-23-0030 I
- 9. Remarks (Applicable Manufacturer's Data Reports to b e Attached)
Functional test oer 0251, VT-3 to be comoleted when installed.
CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this WEPAIR / ' R ~ ~ c E ' MT~ NA CTI v I TY conforms to the rules on the ASME Code,Section XI. repairlreplacement Signed a SECT XI Owner or Owner's besignee, Title 1s) &OD Date &, !I , 'LM7 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 i " ~ / Y ~ ' s T & and employed by b1.9~7 fg $ 0 J T ~ ' n h8 01 cc'tt ~ ' r f oC co MW.C;C CUT of F I ~ ~ ~ T F.Q QI LT K have inspected the components described in this Owner's Report during the period 9 /LI106 to 7/ 1 ~ / d 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.
74L-3A / ~ Y ( - ~ L . ,
Commissions h/P l1%63 A N~l M A / 0 UYO L& -Co Inspector's Signature National Board, Province and Endorsements Date mL4, 12- , 2uo 7 APPROVED (Signatures available in Master File)
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS FORM NIS-2 - Page 1 of 2 NOTE This form may not address all items needed for documentation of a repairlreplacement program, see 4 AWI-09.04.03 (ASME SECTION XI REPAIRIREPLACEMENTPROGRAM) 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 7/8/2007 Name
- 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.
- 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 ASME Repaired, Code Name of Name of Manufacturer National Other Year Replaced or Stamped Component Manufacturer Serial No. Board No. Identification Built Replacement YES NO RV- 11-398 Consolidated Valve d n Disc Dresser. Inc. TM 41591 n/a AOD71 2001 Replaced IXI RV- I 1-398 Consolidated Valve d n n/a S/"ADV03 2005 Replacement Disc Dresser. Inc. TM 4 1591 Ht Cd 67269 RV- I 1-398 Consolidated Valve s/n n/a ADD47 2001 Replaced Nozzle Dresser. Inc. TM 4 I 59 1 RV- 11-398 Consolidated Valve s/n n/a S/" 2005 Replacement Nozzle Dresser. Inc. TM 41591 Ht Cd 72470
- 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)
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS - FORM NIS-2 Page 2 of 2 ITEM 2006-23-0031 1
- 9. Remarks (Applicable Manufacturer's Data Reports to be Attached)
Set~ointand Leak Check wer 0255-02-18. No Dressure testinu, this is a ware returned to stock.
CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this 7? PLC)C(~-I@EN7 conforms to the rules on the ASME Code,Section XI. repairlreplacement Signed I Scr DISz La. Date Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of h ~ u u zsaJh
- and employed by
~~fihbifo ~TIc.A ~ ~~ I L CS+$X o f Cds/&~-c]~c~; of ~ I A P T ~ ~,CPTU 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 r p r o Inspector's Signature National ~ o a i dProvince
, and Endorsements Date J - ( J L ~ Ci , 2007 APPROVED (Signatures available in Master File)
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS - FORM NIS-2 Page 1 of 2 ITEM 2006-23-0032 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 i n form of lists, sketches, o r drawings may be used, provided (1) size i s 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 i s recorded at the top of this form.
- 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.
- 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 - 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 ASME Repaired, Code Name of Name of Manufacturer National Other Year Replaced or Stamped Component Manufacturer Serial No. Board No. ldentification Built Replacement YES NO Valve Bergen un-Manifold Paferson 131 n/a n/a known Replaced IXI Valve Bergen Manifold Paferson 131 n/a n/a 2006 Replacement IXI I7 I7
- 8. Tests Conducted: Hydrostatic Pneumatic Nominal Operating Pressure Other Pressure psi Test Temp "F
( 3087 (DOCUMENT CHANGE, HOLD AND COMMENT FORM) incorporated: I R e s Supv:
~ PRGE I Assoc Ref:
I Doc Tvw:
PRGE REF ONLY I SR:
I Admin initials:
N 1 Freq:
I Date:
0 vrs I
APPROVED (Signatures available in Master File)
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS FORM NIS-2 - Page 2 of 2 L
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~letedfollowinu installation under CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this T(EPI)IR IREPLPCEM ~ Wrp/Y 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 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 r 7 Y n h a dtt I 9-1 C u l ~ r TIcoi' of bIA P )Fdp O c r 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.
Inspector's Signature Commissions p / ~ 1/84 3 A , w, L - , I\ w 0 0 w 2 1 -CCJ National Board, Province and Endorsements Date T ' u L I ~r , Zod7 APPROVED (Signatures available in Master File)
MONTICELLO NUCLEAR GENERATING PLANT 361 3 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS FORM NIS-2 - Page 1 of 2 L
ITEM 2006-23-0033 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 II in, (2) information i n items 1through 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 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.
- 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. Identification of System Spare - 20 Kip Snubber
- 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. Identificationof Components Repaired or Replaced and Replacement Components ASME Repaired, Code Name of Name of Manufacturer National Other Year Replaced or Stamped Component Manufacturer Serial No. Board No. ldentification Built Replacement YES NO -
Valve Bergen Manifold Paterson 487 n/a n/a un-known Replaced (7 rn Valve Bergen 487 n/a n/a 2006 Replacement Manifold Paterson cl
- 8. Tests Conducted: Hydrostatic Pneumatic Nominal Operating Pressure Other Pressure psi Test Temp "F APPROVED (Signatures available in Master File)
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS - FORM NIS-2 Page 2 of 2
_r 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 rate work order CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this R W A IR /REPCACEMENT hVITY conforms to the rules on the ASME Code,Section XI. repairlreplacement Signed
. SECT X I IS\COORY Date pa 11 , 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 PI / U ~ J C ' J J ~ A and employed by H n d ; F J R ~-17t'4k UDILC'K ZtS o f cokwt5TlckT of l - / d ~~j u & J ) CJ- have inspected the components described in this Owner's Report during the period 1 1 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 / JCJY O Z J - C U Inspector's Signature National Board, Province and Endorsements Date TUyl l r , zoo7 APPROVED (Signatures available in Master File)
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS - FORM NIS-2 Page 1 of 2 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.
NOTE 2: Supplemental sheets i n form of lists, sketches, or drawings may be used, provided (1) size is 8-112 i n 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 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.
- 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 ASME Repaired, Code Name of Name of Manufacturer National Other Year Replaced or Stamped Component Manufacturer Serial No. Board No. ldentification Built Replacement YES NO Valve Bergen 466 n/a n/a un- Replaced Manifold C]
Paterson known Valve Bergen 466 n/a n/a 2006 Replacement Manifold C]
Paterson
- 8. Tests Conducted: Hydrostatic Pneumatic Nominal Operating Pressure Other [XI Pressure psi Test Temp O F 1 3087 (DOCUMENT CHANGE, HOLD AND COMMENT FORM) incorporated: I W
2$FqFAQ&IIINIdSBRATIVE 7 I Assoc Ref: PRGE I SR: N I Freq: 0 VIS I
4.Y9A~~uS6^FarbL~J , 1 Doc Tvw: REF ONLY 1 Admin initials: 1 Date:
APPROVED (Signatures available in Master File)
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS - FORM NIS-2 Page 2 of 2 ITEM 2006-23-0034 I
- 9. Remarks (Applicable Manufacturer's Data Reports to be Attached)
Functionallv tested per 0251. VT-3 pre-senlice exam to be com~letedfollowina installation under ork order CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this R r p p l a / ~ a p r ~ c n nh w y ln conforms to the rules on the ASME Code,Section XI. repairlreplacement Signed Owner or owndr's Designee, Title Date Fa 11 1M7 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 l u l ~ ~74d and employed by
~ / ~ \ R T F L I R Y ) ) T ~ A ~ I P O / ~ P ~ $ ~ ~ O F C O ~ & Cof' C T I L
~Q/ ~TI I T E o J Z D , C ~ have inspected the components described in this Owner's Report during the period 11 I Y /d6 to 7 / l z 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 1 1 8 ~ 3A , ,v, 1.&A/ &L/ ozr-co Inspector's Signature National Board, Province and Endorsements Date JULY (L , 2337 APPROVED (Signatures available in Master File)
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS - FORM NIS-2 Page 1 of 2 ITEM 2006-23-0035 I NOTE This form may not address all items needed for documentation of a repairlreplacementprogram, see 4 Awl-09.04.03 (ASME SECTION XI REPAIRIREPLACEMENT PROGRAM) for further guidance.
NOTE 2: Supplemental sheets i n 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 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.
- 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 ASME Repaired, Code Name of Name of Manufacturer National Other Year Replaced or Stamped Component Manufacturer Serial No. Board No. ldentification Built Replacement YES NO Valve Bergen 132 n/a n/a un- Replaced M a n r f o l d P a f e r s o n m - - -
Valve Bergen 132 n/a n/a 2006 Replacement Manifold Paterson IXj
- 8. Tests Conducted: Hydrostatic Pneumatic Nominal Operating Pressure Other Pressure psi Test Temp OF APPROVED (Signatures available in Master File)
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS - FORM NIS-2 Page 2 of 2
- 9. Remarks (Applicable Manufacturer's Data Reports to be Attached)
Funcfionallv tested per 0251. VT-3 ore-service exam to be com~letedfollowina installation under te work or& -~
CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this P&PA~P/REPLUKNT Acrr u l r l conforms to the rules on the ASME Code,Section XI. i-epairlreplacement Signed SE~T.XI ISICOD-Owner or owner'd~esignee,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 /Lc~*lvFsoTP and employed by
~ * ~ J F C W W % ~ I C CofI T E-rrlnTFaa~, C7-
~ , A @ T F ~ Js TJ , f k ~ y & ? o / ~ t j B have inspected the components described in this Owner's Report during the period C// t 9 I d 6 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-Inspector's Signature Commissions blJ / I & 3 4 , % .? ,&/J d d YOL-B-CU National Board, Province and Endorsements Date T b ~ 7 /z. I 200 7 APPROVED (Signatures available in Master File)
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 i
REPLACEMENTS - FORM NIS-2 Page 1 of 2 ITEM 2006-23-0036 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 II 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 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.
- 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 - 20 Kip Snubber
- 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 ASME Repaired, Code Name of Name of Manufacturer National Other Year Replaced or Stamped Component Manufacturer Serial No. Board No. ldentification Built Replacement YES NO Valve Bergen 148 n/a n/a un- Replaced Manifold Paterson known Valve Bergen 148 n/a n/a 2006 Replacemenf Manifold Paterson
- 8. Tests Conducted: Hydrostatic Pneumatic Nominal Operating Pressure Other Pressure psi Test Temp "F
) 3087 (DOCUMENT CHANGE, HOLD AND COMMENT FORM) incorporated: I FOR 1
%? Resp Supv: PRGE ARMS: 3613 1 Assoc Ref: PRGE 1 SR:
I Doc Tvpe: REF ONLY I Admin initials:
N I Freq:
I Date:
0 vn I APPROVED (Signatures available in Master File)
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS FORM NIS-2 - Page 2 of 2 ITEM 2006-23-0036 I
- 9. Remarks (Applicable Manufacturer's Data Reports to b e Attached)
Functionallv tested per 0251. VT-3 re-service exam to be com~letedfollowina installation under CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this RPA~(I / R @ ~ ~ E Jh T ~lv conforms to the rules on the ASME Code,Section XI. iepairlreplacement Signed .- SECr Kf Owner or 0wne.r'~Designee, Title ISICOORD 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 k l ~ f l ~ f r r ~f7c',+h d B U I Z~t J 4Jt C O U I A X ~ I C Q T of /-/qr~Fc)rSlJ, cT have inspected the components described in this Owner's Report during the period Q k c /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.
k LInspector's ~ hSignature 4 ~
- Commissions //kg3 4, fv,1' , />A/ 00 Y J 2 2 - C O National Board, Province and Endorsements Date TyLy 12 , 2u07 APPROVED (Signatures available in Master File)
I MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS FORM NIS-2 - Page 1 of 2 ITEM 2006-23-0037 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 REPAIRIREPLACEMENTPROGRAM) 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 i n 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 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.
- 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 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 ASME Repaired, Code Name of Name of Manufacturer National Other Year Replaced or Stamped Component Manufacturer Serial No. Board No. ldentification Built Replacement YES NO Main Bergen 132 n/a n/a un- Replaced C] (XI Cvlinder Paterson known Main Bergen 132 n/a n/a 2006 Replacement C]
Cvlinder Paterson
- 7. Description of Work Replaced main cylinder during rebuild PM.
- 8. Tests Conducted: Hydrostatic C] Pneumatic Nominal Operating Pressure C]
Other Pressure psi Test Temp "F APPROVED (Signatures available in Master File)
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS - FORM NIS-2 Page 2 of 2 ITEM 2006-23-0037 I
- 9. Remarks (Applicable Manufacturer's Data Reports to b e Attached)
Functionall~vtested Der 0251. VT-3 re-senlice exam to be com~letedfollowinu installation under r
CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this -14 / g ~ ~ ~ c e &Awa rvfy t
conforms to the rules on the ASME Code,Section XI. repairlreplacement Signed I *
,SECTXI IS\ COOED Owner or Owner's Designee, Title Oate %!+
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&$ o T n and employed by
~nkTfoKMf l t > ~ g o ~ ~ c ' ~ J t cok&r-cJrrur Jof of b r 4 n t p ~ K u CT have inspected the components described in this Owner's ~ e p o r t to c 7 112 / d 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.
A&& Commissions pfi i f ~ ~ _A,y /(/J' ,~b ode/ 0 2r -CO Inspector's Signature National Board, Province and Endorsements Date T Q L Y 12 , 2007 APPROVED (Signatures available in Master File)
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS - FORM NIS-2 Page 1 of 2 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.
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 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.
- 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 ASME Repaired, Code Name of Name of Manufacturer National Other Year Replaced or Stamped Component Manufacturer Serial No. Board No. ldentification Built Replacement YES NO '
Main Bergen un-Cvlinder Paterson 102 n/a n/a known Replaced C] IXI Main Bergen Cvlinder Paterson 102 n/a n/a 2006 Replacement C] IXI
- 7. Description of Work Replaced main cylinder during rebuild PM.
- 8. Tests Conducted: Hydrostatic Pneumatic Nominal Operating Pressure Other Pressure psi Test Temp "F APPROVED (Signatures available in Master File)
MONTICELLO NUCLEAR GENERATING PLANT 361 3 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS FORM NIS-2 - Page 2 of 2 ITEM 2006-23-0038 I
- 9. Remarks (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 R s ~ p/ t ~R G ~ E hM t ~v y ~
conforms to the rules on the ASME Code,Section XI. repairlreplacement Signed 4. : SEWXI IS1 COORD Date Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of / - j l h / ~ Pfor4 and employed by PlAlZT F o n u rr Z A B~ J j J dF C D U @ C - C ~ I ~ L ~of~ .,
I / . ~ / z ~ ~ % F MC 7 have inspected the components described in this Owner's Report during the period l o / L jc, 6 to 7 1 /tI d 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.
?,L+4- 1. &A'.
Inspector's Signature Commissions /J& 1/66 J A , y 2 , f ~ c u o @ ~ / u ~ ~ - t . C r National Board, Province and Endorsements Date TULY' 12. , tOd7 APPROVED (Signatures available in Master File)
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS FORM NIS-2 - Page 1 of 2 ITEM 2006-23-0039 I This form may not address all items needed for documentation of a repairlreplacementprogram, see 4 Awl-09.04.03 (ASME SECTION XI REPAIRIREPLACEMENT PROGRAM) for further guidance.
NOTE 2: Supplemental sheets i n 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 Name
- 2. Plant Monticello Nuclear Generating Plant Sheet Name 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 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 ASME Repaired, Code Name of Name of Manufacturer National Other Year Replaced or Stamped Component Manufacturer Serial No. Board No. ldentification Built Replacement YES NO Main Bergen 154 n/a n/a un- Replaced Cvlinder Paterson known Main Bergen 154 n/a n/a 2006 Replacement Cvlinder Paterson
- 7. Description of Work Replaced main cylinder during rebuild PM.
- 8. Tests Conducted: Hydrostatic Pneumatic Nominal Operating Pressure Other Pressure psi Test Temp "F APPROVED (Signatures available in Master File)
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS - FORM NIS-2 Page 2 of 2 r
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~letedfollowina installation under CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this R S P A ~ R / R R ) ~ E N TA cT\u~~
conforms to the rules on the ASME Code,Section XI. repairlreplacement Signed , S E X I~ ISI COO-Owner or Owner's Designee, Title Date fi 11 , 2007 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 o f C O W W C ' C ~ ~ C L , ~ of J - ~ ~ R T F O K,Pc have inspected the components described in this Owner's Report during the period to / 6 1 0 6 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 U t 6 3 P,N,$ . / ~ -wl so 43 ~ g - c o Inspector's Signature National Board, Province and Endorsements Date 7 t ~ y ' IZ , zdo7 APPROVED (Signatures available in Master File)
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS - FORM NIS-2 Page 1 of 2 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 REPAIRIREPLACEMENTPROGRAM) 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.
- 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.
- 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 ASME Repaired, Code Name of Name of Manufacturer National Other Year Replaced or Stamped Component Manufacturer Serial No. Board No. ldentification Built Replacement YES NO Main Bergen 174 n/a n/a un- Replaced Cvlinder Paterson known Main Bergen 174 n/a n/a 2006 Replacement Cvlinder Paterson Description of Work Replaced main cylinder during rebuild PM.
- 8. Tests Conducted: Hydrostatic Pneumatic Nominal Operating Pressure [7 Other Pressure psi Test Temp "F
( 3087 (DOCUMENT CHANGE, HOLD AND COMMENT FORM) incorporated: I APPROVED (Signatures available in Master File)
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS FORM NIS-2 - Page 2 of 2 ITEM 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 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 .S E XI ~ISI C ~ O R D Owner or owner's Designee, Title Date PJ-J ff . DO7 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 ~ ) ~ & W O T A and employed by C l ~ l z r ~ a n uS T C ' ~BOIIC-IZ
~ S ~ J Q F~ o & ~ . ~ & c r of i c ~ r N A P T F o ~ P D cj- have inspected the components described in this Owner's Report during the period 1' 1 Y /d6 to 7 / 1 2 /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--TA,,~I.JAA Inspector's Signature Commissions M5 l / b 6 3 A , )d, 2 , h w oo Vo2f-Go National Board, Province and Endorsements Date JCr L,Yr I t , 2-037 APPROVED (Signatures available in Master File)
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS FORM NIS-2 - Page 1 of 2 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 i s recorded at the top of this form.
- 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.
- 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 - 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 ASME Repaired, Code Name of Name of Manufacturer National Other Year Replaced or Stamped Component Manufacturer Serial No. Board No. ldentification Built Replacement YES NO Valve Bergen un-Manifold Paterson 133 n/a n/a known Replaced IXJ Valve Bergen 133 n/a n/a 2006 Replacement
- Manifold Paterson
- 8. Tests Conducted: Hydrostatic Pneumatic Nominal Operating Pressure Other Pressure psi Test Temp "F APPROVED (Signatures available in Master File)
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS - FORM NIS-2 Page 2 of 2 ITEM 2006-23-004 1 I
- 9. Remarks (Applicable Manufacturer's Data Reports to be Attached)
Functionally tested oer 0251. VT-3 pre-senlice exam to be comdeted followina installation under CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this REP*II/RCRPCEHEN~A C n U l n conforms to the rules on the ASME Code,Section XI. repairlreplacement Signed S E %I ~ IS\ b o a Owner or Owner's Designee, Title Date + 11 , 2007 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 I U U s~ and employed by t J d R t F o r Z O STC4ibc &?gll6% r + 3 & f C u r ~ l ~ ~ t r ( f fof
~ T ! ~ A H $ P ~ J ~ /~7 J~ have inspected the components described in this Owner's Report during the period If /LOT to 7/12.1 0 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.
7/* A &L&~,
Inspector's Signature Commissions D B t l f 6 3 rs,n/,.i', h U 30 902 b -(a National Board, Province and Endorsements Date Toby 12, , LOO7 APPROVED (Signatures available in Master File)
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS FORM NIS-2 - Page 1 of 2 ITEM 2006-23-0042 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 REPAIRIREPLACEMENTPROGRAM) 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 II 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 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.
- 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 - 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 ASME Repaired, Code Name of Name of Manufacturer National Other Year Replaced or Stamped Component Manufacturer Serial No. Board No. ldentification Built Replacement YES NO Valve Bergen 125 n/a n/a un- Replaced Manifold Paterson known Valve Bergen 125 n/a n/a 2006 Replacement Manifold (XI Paterson 0
o
- 8. Tests Conducted: Hydrostatic Pneumatic Nominal Operating Pressure Other Pressure psi Test Temp O F APPROVED (Signatures available in Master File)
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS - FORM NIS-2 Page 2 of 2 ITEM 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 work order 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
- - , ~ G c T X ( I ~ ~ ~ Q D Date If , u o 7 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 t-t I O M F J O ~ A and employed by
/ I ~ p ? f ~ g uSTt'4h (3U/L6\R J F J J F ~ ~ ~ 4 ~ t V l Cblnb?Pd-'JR~J 6f ,LT have inspec ed the components described in this Owner's Report during the period t / F 10'7 to 1
7 l l 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'. r, Commissions MI I/&& J 4 , b, / Y X / .W ~ ~ d;o - 2 8 Inspector's Signature National Board, Province and Endorsements Date zGLY iL , Lob7 APPROVED (Signatures available in Master File)
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS - FORM NIS-2 Page 1 of 2 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 i n form of lists, sketches, or drawings may be used, provided (1) size is 8-112 i n x 11 in, (2) information i n items 1 through 6 on this report i s included on each sheet, and (3) each sheet i s numbered and the number of sheets i s recorded at the top of this form.
- 1. Owner Xcel Energy Company Date 7/19/2007 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.
- 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 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 ASME Repaired, Code Name of Name of Manufacturer National Other Year Replaced or Stamped Component Manufacturer Serial No. Board No. ldentification Built Replacement YES NO Spare P-I 1 I Johnston Pump Assly n/a 2007 Repaired O D 6702 02686-7 u
0
- 7. Description of Work Repaired small crack in 1 intermediate bowl during rebuild.
- 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)
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS FORM NIS-2 - Page 2 of 2 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 'REPAIA / R P L ~ C E M ~ T A ~ ~ l u t r y conforms to the rules on the ASME Code,Section XI. repairlreplacement
, SEC~INXIIS(
C Signed Date Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of h/~x/rC t 074 and employed by
/-lqfltod/ll ~ ~ c - n r s r b v lz~tt~~ ' o f C o ~ ~ ~ C T / r c . of l[ ~I.-+L~FRCI,CT have 7/13 071.
inspected he components described in this Owner's Report during the period I/ Y/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 to 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 ,& ,.
h QI 00~ O L J - C O Inspector's Signature National Board, Province and Endorsements Date Ycl L Y 2 3 , 2607 APPROVED (Signatures available in Master File)
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS FORM NIS-2 - Page 1 ITEM 2007-23-0044 I NOTE 1: This form may not address all items needed for documentation of a repairlreplacementprogram, 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 II 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 3 Name 2807 W. Cnty. Rd. 75, Monticello, Minnesota 55362 WO 154343, EC-7462 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. Ctv Rd 75, Monticello. MN 55362 Ex~irationDate n/a 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 ASME Repaired, Code Name of Name of Manufacturer National Other Year Replaced or Stamped Component Manufacturer Serial No. Board No. ldentification Built Replacement YES NO WRFM GE Reuter Marking n/a Ht. # 1984 Replaced 12-45 Sfokes 6549798 132567 Blind Flange GE Reuter s/n 11-soare 12-45 Stokes 76748-1 n/a Hf. # 2F353 2007 Replacement IXI WRFM GE Reuter Marking Ht. #
20-05 Stokes 6549796 n/a 132567 1984 Replaced IXI Blind Flange GE Reuter s/n 12- n/a Hf. # 2F353 2007 Replacement soare7G05 Stokes 76748-1 SEE PAGE 2 FOR ADD'L ITEMS
- 7. Description of Work Removed (2) abandoned WRFM's, replaced with blind flanges including bolting
- 8. Tests Conducted: Hydrostatic Pneumatic Nominal Operating Pressure Other Pressure 1000 psi Test Temp 181.8 OF
) 3087 (DOCUMENT CHANGE, HOLD AND COMMENT FORM) incorporated: -- - - 3 FQR ADMIN,!$TRATIVE, USE ONLY '
R ~ SSLID~:
ARMS:
D 3613 PRGE I
1 Assoc Ref: PRGE Doc T v ~ e : REF ONLY I SR:
I Admin initials:
N 1 Freq:
I Date:
0 yrs -
1 APPROVED (Signatures available in Master File)
Monticello Nuclear Generating Plant P a g e 2 of 3 Form NIS-2 Continuation Sheet ITEM 2007-23-0044 WO No. 154343 Repaired, ASME Code Name of Name of Manufacturer National Other Year Replaced or Stamped Component Manufacturer Serial No. Board No. Identification Built Replacement Yes No WFRM GE Reuter n/a n/a Ht. # 85483 1984 replaced X 12-45 Stokes (4) capscrews Blind Flange GE Reuter n/a n/a Ht. # 96903 2007 replacement X spare 12-45 Stokes (4) capscrews WFRM GE Reuter n/a n/a Ht. # 85483 1984 replaced X 20-05 Stokes (4) capscrews Blind Flange GE Reuter n/a n/a Ht. # 96903 2007 replacement X spare 20-05 Stokes (4) capscrews
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS - FORM NIS-2 PageM3al:3 IW
,1,,1,,
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.
CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this T ~ F ARi'~acdv\-
~R/ dfllv try conforms to the rules on the ASME Code,Section XI. repairlreplacement Signed w, &C~OLI~/ IS\cooeo.
Owner or Owner's Designee, Title 0ate PJ2-l , m 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 AIkM s o7A and employed by
)(A AT ~ ~ p 57'c-&13 r , do/ /LC% 2 *r crF c o ~ k / b cI tC ~ Tof t-f/tpi-hBu, e 7 have inspected the components described in this Owner's Report during the period 3 1 2 3 117 to 7 / ~ 107 3 , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section 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.
742dA4SInspector's Signature Commissions h/f N X 7 A , U S 4~ o d l/az ,f--co National Board, Province and Endorsements Date JULY 23 , Zdd?
APPROVED (Signatures available in Master File)
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 .
REPLACEMENTS - FORM NIS-2 Page I of 2 ITEM 2007-23-0045 I NOTE 1: This form may not address all items needed for documentation of a repairlreplacementprogram, see 4 Awl-09.04.03 (ASME SECTION XI REPAIRIREPLACEMENT PROGRAM) for further guidance.
NOTE 2: Supplemental sheets i n form of lists, sketches, or drawings may be used, provided (1) size is 8-112 in x 11 in, (2) information in items 1through 6 on this report is included on each sheet, and (3) each sheet is numbered and 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 314220, EC-9174 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 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 ASME Repaired, Code Name of Name of Manufacturer National Other Year Replaced or Stamped Component Manufacturer Serial No. Board No. ldentification Built Replacement YES NO Strain Gage HlTEC See PSI-1 8'LED Prod~cf n/a n/a Remarks 2007 Repair 3
=in Gage HlTEC See PS2- 18"-ED Product n/a n/a Remarks 2007 Repair CI ISI Strain Gage HlTEC See PS3- 18"-ED Product n/a n/a Remarks 2007 Repair CI ISI Sfrain Gage HlTEC See PS4- 18"-ED Product n/a n/a Remarks 2007 Repair IXI
- 7. Description of Work Spot welded 64 strain gages to Main Steam Piping for EC-9174
- 8. Tests Conducted: Hydrostatic Pneumatic C] Nominal Operating Pressure Other Pressure n/a psi Test Temp n/a "F APPROVED (Signatures available in Master File)
MONTICELLO NUCLEAR GENERATlNG PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS - FORM NIS-2 Page 2 of 2 ITEM 2007-23-0045 I
- 9. Remarks (Applicable Manufacturer's Data Reports to b e 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.
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 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 l 6 ~ & 6 5b T 4 and employed by
,BA rcir~nlls ~ t ~ d.UO/LC&
h d rS 0 1 c~ a w d ' ~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 &-
Inspector's Signature Commissions #B /I $6 2 2 -
h W O O Y o L X CU National Board, Province and Endorsements Date ThLY 2-,r , 2-Ua7 APPROVED (Signatures available in Master File)
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS FORM NIS-2 - Page 1 of 2 ITEM 2007-23-0046 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.
NOTE 2: Supplemental sheets i n 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 1 of 2 Name 2807 W. Cnty. Rd. 75, Monticello, Minnesota 55362 WO 288806 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 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 ASME Repaired, Code Name of Name of Manufacturer National Other Year Replaced or Stamped Component Manufacturer Serial No. Board No. ldentification Built Replacement YES NO TW9-2 1/2"- unknown n/a n/a n/a 1969 Repaired HE
- 7. Description of Work Removed/ Reinstalled piping due to interference with adjacent work.
- 8. Tests Conducted: Hydrostatic Pneumatic Nominal Operating Pressure (XI Other Pressure 300 psi TestTemp n/a O F
) 3087 (DOCUMENT CHANGE, HOLD AND COMMENT FORM) incorporated: - - I FOR AJMINISTRATIVE
' ' ^US~ONLY ,+2 Reso S u ~ v : PRGE I Assoc Ref: PRGE I Doc Tvoe: REF ONLY I Admin initials:
I SR: N I Frea:
I Date:
0 vn I
APPROVED (Signatures available in Master File)
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS FORM NIS-2 - Page 2 of 2 ITEM 2007-23-0046 I
- 9. Remarks (Applicable Manufacturer's Data Reports to b e 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.
CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this REPA\R/ R E ~ U WA~ mT ~ 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 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 g d / i r Q " rf-J ~ F c o w l ~ p l - l c t of ri HqfiWdO,CT have inspected the components described in this Owner's Report during the period 3 /9 /u7 to 71 22 / d 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 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 ,
1 1 6 ~ 3 A /$S ~ l noo / Y O ~g - c d Inspector's Signature National Board, Province and Endorsements Date .Tl/L'f 23 , Zoo7 APPROVED (Signatures available in Master File)
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS - FORM NIS-2 Page 1 of 2 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 REPAIRIREPLACEMENTPROGRAM) 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 7/20/2007 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.
- 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
- 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 ASME Repaired, Code Name of Name of Manufacturer National Other Year Replaced or Stamped Component Manufacturer Serial No. Board No. ldentification Built Replacement YES NO Ht. #
( I ) 5/811Stud Nova n/a n/a 7404456 2005 Replaced IXI Ht. #
( I ) 518" Stud Nova n/a n/a 2301 1I 2007 Replacement IXJ Ht. #
(2) 5/8" Nuts Nova n/a n/a 887035 2005 Replaced 0 IXJ Ht. #
(2) 5/8" Nuts Nova n/a n/a 7220464 2007 Replacement IXI n
- 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 APPROVED (Signatures available in Master File)
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS FORM NIS-2 - Page 2 of 2 ITEM 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.
CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this R ~ P A \ /RR ~ ~ * - E ~ J T An\~q conforms to the rules on the ASME Code,Section XI. repairlreplacement r .
Signed ,- SECTIONXI 18 \ born. Date Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of h t r v r v ~ 73 ~ d and employed by 60izY) s76 4 h f r o l r tY r r l .IF C W M ~ T I C L I T 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- A h % -
Inspector's Signature Commissions ~8 icfi ,I A J &W &q d u - c o National Board, Province and Endorsements Date Tct~Lfti9 , 2307 APPROVED (Signatures available in Master File)
I I
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS - FORM NIS-2 Page 1 of 2 ITEM 2007-23-0048 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.
NOTE 2: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8-112 in x IIin, (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.
- 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 Reactor Core Isolation Cooling (RCIC), Steam Supply, Class 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 ASME Repaired, Code Name of Name of Manufacturer National Other Year Replaced or Stamped Component Manufacturer Serial No. Board No. ldentification Built Replacement YES NO PSl7-3"ED unknown n/a n/a n/a 2001 Repaired 17
- 7. Description of Work Removed / Reinstalled piping due to interference with adjacent work.
- 8. Tests Conducted: Hydrostatic Pneumatic Nominal Operating Pressure IXJ Other Pressure 1040 psi Test Temp n/a "F APPROVED (Signatures available in Master File)
MONTICELLO NUCLEAR GENERATlNG PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS FORM NIS-2 - Page 2 of 2
- 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-115, and SR-564.
RT performed following reinstallation of piping.
No PSI required.
System leakage test with VT-2 performed per work order PMT attachment / work plan.
CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this R E Q A ~ R ( R E P ~ A ~ E ~ EA; N c T~ r v t ~ y conforms to the rules on the ASME Code,Section XI. repairlreplacement Signed m - ,,~ECT~DN Owner or Owner's Designee, Title IS1 b w .
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 )uwfon 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 I t 1 lo7 to 7 / 2 1 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 b y O Q 2~ ~
Inspector's Signature National Board, Province and Endorsements Date Jwy 22, , 2037 APPROVED (Signatures available in Master File)
1 I MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS FORM NIS-2 - Page 1 of 2 ITEM 2007-23-0049 I NOTE 1: 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 i n 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.
- 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 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 ASME Repaired, Code Name of Name of Manufacturer National Other Year Replaced or Stamped Component Manufacturer Serial No. Board No. Identification Built Replacement YES NO SW10-18"- n/a n/a n/a n/a 1969 Replaced IX]
GF SW10-18"- Dubose n/a n/a HMA83222 2007 Replacement IX]
GF
- 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)
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS FORM NIS-2 - PageJ20f 2 wMb 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.
CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this RPAIR/R~PW~EMENT,L)c~~utry conforms to the rules on the ASME Code,Section XI. repairlreplacement Signed ,SECI-IONX~IS1 Coo-Owner or dwner's Designee, Title Date ~ 20 , 2007 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- ~ O V and employed by k h n ~ ~ s an6.m a no/~c-flJ ~ J# F W U U ~ C ? I L ~ ~ of ~MIYFOW ,u4 have inspected the components described in this Owner's Report during the period 3 / tz b 7 to 3 ( L O 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 Inspector's Signature Commissions p t J 3 ~ u o o q o t k-cd National Board, Province and Endorsements Date Tqcr 2u , L U O ~
APPROVED (Signatures available in Master File)
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS - FORM NIS-2 Page 1 of 2 ITEM 2007-23-0050 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 i n 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 7/8/2007 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.
- 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 ASME Repaired, Code Name of Name of Manufacturer National Other Year Replaced or Stamped Component Manufacturer Serial No. Board No. ldentification Built Replacement YES NO Main Bergen un-Cvlinder Paterson 400 n/a n/a known Replaced IXJ Main Bergen Cvlinder Paterson 400 n/a n/a 2007 Replacement 0 IXJ
- 7. Description of Work Replaced main cylinder during rebuild.
- 8. Tests Conducted: Hydrostatic Pneumatic Nominal Operating Pressure Other [XJ Pressure psi Test Temp "F APPROVED (Signatures available in Master File)
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS - FORM NIS-2 Page 2 of 2 ITEM 2007-23-0050 I
- 9. Remarks (Applicable Manufacturer's Data Reports to be Attached)
Functional test oer 0251. VT-3 to be com~letedwhen installed.
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 b o r n . Date Owner or 0wnei's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of h~hn/es OTA and employed by
@An 7 ~ o L D 5164fi Bolltn .2 $x o F Cuukrrrlc~ 7 of H ~ n T f a C Z A ,C 7 have inspected the components described in this Owner's Report during the period J / 23 107 to
,719107 , 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 I J 3 ~ A",/v, 5 , yl u 40 w~k-ccl Inspector's Signature National Board, Province and Endorsements Date T ~ - c L )9/ , 2007 APPROVED (Signatures available in Master File)
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS - FORM NIS-2 Page 1 of 2 ITEM 2007-23-0051 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.
- 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 288859, 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 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 ASME Repaired, Code Name of Name of Manufacturer National Other Year Replaced or Stamped Component Manufacturer Serial No. Board No. ldentification Built Replacement YES NO MO- 1742 Wm Powell Valve d n n/a n/a 1969 Replaced studs (14) Valve 58767 MO- 1742 studs (14 )
Cardinal n/a n/a 042339 2007 Replacement IXI MO- 1742 Wm Powell Valve d n nuts (28) Valve 58767 n/a n/a 1969 Replaced IXI MO- 1742 Nova n/a n/a B87035 2007 Replacement nuts (28)
- 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 Other Pressure n/a psi Test Temp n/a "F
( 3087 (DOCUMENT CHANGE, HOLD AND COMMENT FORM) incorporated: p p p p p I
F$R AD,MINISTWTlVE, Resu SUUV: PRGE USE ONLY ""* :,
I Assoc Ref: PRGE I Doc Tvpe: REF ONLY I Admin initials:
I SR: N I I
Freq:
Date:
0 vrs I
APPROVED (Signatures available in Master File)
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS - FORM NIS-2 Page 2 of 2 ITEM 2007-23-0051 I
- 9. Remarks (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.
CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this E Q A I E / R E P ~ M ~h t v ri-y conforms to the rules on the ASME Code,Section XI. repairlreplacement Signed
, -I S E ~
- Owner or owner's Designee, Title
&OW Date ~ [q ,
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 I ~ I J F 5 0 7 4 and employed by U+nrFd'JRJ sI'c'A~ /3alLEK ri$ dF cdh/k/FtTlchT of j / ~ ~ ~ F o M t f , t r have inspected the components described in this Owner's Report during the period 3 /td/u'.l to 1 1 2 3 147 , 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 v h / ( f iJ A, w,S rc-rwO ~ uzf--to Y
Inspector's Signature National Board, Province and Endorsements Date if-qcy 2.2 - , Zdu7 APPROVED (Signatures available in Master File)
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS - FORM NIS-2 Page 1 of 2 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.
NOTF 7 . --rr.-...-..--.
S~lnnlemantal -..--- ... .-.... -. .. -..---..--, -.
aheek in fnrm nf l i z k akatchaa nr rlrawinna
- I , ...
-.-.....a- mav -- ----,
" ha 1 1 a 4 nrnvirlarl J -.-" .-.
r.-..--- I1 I. 1\ ai7n ic 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 7/18/2007 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 ASME Repaired, Code Name of Name of Manufacturer National Other Year Replaced or Stamped Component Manufacturer Serial No. Board No. ldentification Built Replacement YES NO M0-1987 unknown n/a n/a n/a 1969 Replaced IXI MO-1987 Studs (12)
Nova n/a n/a Ht. #240902 2007 Replacement IXI MO-1987
. Studs (6)
Nova n/a n/a Ht. # 53410 2007 Replacement IXI M0-1987 unknown n/a n/a n/a 2007 Replaced IXI MO-1987 Nova n/a n/a Ht. 2007 Replacement tit8994826 IX]
Nuts (36)
- 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 (4
FPR PIDVINISTRATIVE , Resp Supv: PRGE
,&:USE ~ N L Y ; ~ * + ~ ARMS: 3613 1 Assoc Ref:
I Doc Tvpe:
PRGE REF ONLY I SR:
I Adrnin initials:
N I Freq:
I Date:
0 vrs I
APPROVED (Signatures available in Master File)
MONTICELLO NUCLEAR GENERATING PLANT 361 3 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS - FORM NIS-2 Page 2 of 2 ITEM 2006-23-0016 I
- 9. Remarks (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.
CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this RE+~~R/RE~W~?MFW AC ~b Uy conforms to the rules on the ASME Code,Section XI. repairlreplacement Signed .- SECTXI COORD Date , 2007 Owner dr 0wne'r'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 Islv&-so7d and employed by rlfi~ r ~ i 5 9 7 O/I/LCP ~ J~ ~ xs~ h w m c rrcur of H~~TFPK , cT B have inspected the components described in this Owner's Report during the period ,I /26/07 to
~ / Z L / 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.
L AInspector's A J Signature w~ Commissions v,a I ~ ~ L AJ ,u 2 AW LLOL&-CU National Board, Province and Endorsements Date TQLY LL , 2307 APPROVED (Signatures available in Master File)
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS FORM NIS-2 - Page 1 of 2 ITEM 2007-23-0053 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.
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.
- 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.
- 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), 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 ASME Repaired, Code Name of Name of Manufacturer National Other Year Replaced or Stamped Component Manufacturer Serial No. Board No. ldentification Built Replacement YES NO MO-2009 Anchor n/a n/a n/a 1989 Replaced Disc Darlina MO-2009 Anchor n/a n/a /-/#A34626 1989 Replacement Disc Darlina
- 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).
- 8. Tests Conducted: Hydrostatic Pneumatic Nominal Operating Pressure Other Pressure n/a psi Test Temp n/a "F APPROVED (Signatures available in Master File)
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS FORM NIS-2 - Pagesof 2 +$ ,
ITEM 2007-23-0053 I
- 9. Remarks (Applicable Manufacturer's Data Reports to b e 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.
CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this R ~ P A /REPL~-ENT
~Q k m u1 - r ~
conforms to the rules on the ASME Code,Section XI. repairlreplacement Signed p , k~ XI I SI b e g Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of ? I ILJUC^ gal2 and employed by J I A I ~ T F ~ R IJft\Ah J #@~GX ~ + C ~ W M F C T ~ C of R~ H f i C S A R D CT have inspected the components described in this Owner's Report during the period 3 / z 6 1 0 to 3 / 4 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.
f/- A ~~LL,A*
Inspector's Signature Commissions ,Up 1cr63 A , r(/,j AX/00 4 0 ~ t - t d National Board, Province and Endorsements Date TbLy W , Lo07 APPROVED (Signatures available in Master File)
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: OW'NER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS - FORM NIS-2 Page I of 2 L
ITEM 2007-23-0054 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 (I) size is 8-112 in x IIin, (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 7/18/2007 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.
- 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 ASME Repaired, Code Name of Name of Manufacturer National Other Year Replaced or Stamped Component Manufacturer Serial No. Board No. Identification Built Replacement YES NO MO- 1750 Anchor d~sc Darlina n/a n/a n/a 1969 Repair IXI
- 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)
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS FORM NIS-2 - Page 2 of 2 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.
CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this a m I R / ~ ~ ~A c rt l VW f~~
conforms to the rules on the ASME Code,Section XI. repairlreplacement Signed . S ~ c r X l1st b Owner or ~wner's'~esignee, Title o a Date p,\ 7 , 2007 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 I ~ / A J/ E3 T A and employed by ficrlhflTF0~4 g'rcdh ~~DJICPX' t c c r w w ~ c ~h/ ci of
~ ' t o~ p ~ ~ tf6&t t 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, Inspector's Signature Commissions A/(J 1~ 6% 3 A s
,/e / Y ~ V00 V O . L ~ ~ - C O National Board, Province and Endorsements Date TCcLY 2 2 , 2Jd7 APPROVED (Signatures available in Master File)
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS - FORM NIS-2 Page 1 of 2 ITEM 2007-23-0056 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.
NOTE 2: Supplemental sheets i n form of lists, sketches, or drawings may be used, provided (1) size is 8-112 in x 11 in, (2) information i n items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets i s recorded at the top of this form.
- 1. Owner Xcel Energy Company Date 7/23/2007 Name
- 2. Plant Monticello Nuclear Generating Plant Sheet 1 of 2 Name 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 ASME Repaired, Code Name of Name of Manufacturer National Other Year Replaced or Stamped Component Manufacturer Serial No. Board No. ldentification Built Replacement YES NO Mag Stage Target Rock 1458 n/a 2005 Replaced C] IXI Main Stage Target Rock 53 n/a 2007 Replacement C] IXI Bodv
- 7. Description of Work Replaced Main Stage Body for RV-2-71 C with rebuilt spare
- 8. Tests Conducted: Hydrostatic Pneumatic Nominal Operating Pressure Other C] Pressure n/a psi Test Temp n/a OF 1 3087 (DOCUMENT CHANGE, HOLD AND COMMENT FORM) incorporated: . - 3 FOR#@~NW?ATIM
"/
7 BE ONkL'fi Mm Resp Supv: PRGE I
I Assoc Ref: PRGE Doc T v ~ e : REF ONLY I SR:
I Admin initials:
N I Freq:
I Date:
0 yrs I
APPROVED (Signatures available in Master File)
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS - FORM NIS-2 Page 2 of 2 ITEM 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.
CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this rb,, :F/~~/rcrrrAP&~:~:cs I rebair~rep~acement conforms to the rules on the ASME Code,Section XI.
Signed H h
, S r c n o ~%I IS1 &ORB 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 h,w~/6~oTA and employed by k1AflrFollu C l C C 4 h Bu\u'/l 275 d F C o ~ M - c t ~ ~ c o HqdTf FoRe) , ~7 have inspected the components described in this Owner's Report during the peiod C/ / 3 h 7 to
'7/ 2 7 /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 ~h S ~0'd Yo 26-C.G
' Inspector's Signature National Board, Province and Endorsements Date Shdy 23 , Zdd 7 APPROVED (Signatures available in Master File)
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS - FORM NIS-2 Page 1 of 2 ITEM 2007-23-0057 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 i n form of lists, sketches, or drawings may be used, provided (1) size i s 8-112 i n x IIin, (2) infonnation i n 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 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 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 ASME Repaired, Code Name of Name of Manufacturer National Other Year Replaced or Stamped Component Manufacturer Serial No. Board No. ldentification Built Replacement YES NO ST Target Rock Target Rock 208 217 n/a n/a 2005 2007 Replaced Replacement aae p p IX]
- 7. Description of Work Replaced SRV Pilot Stage (Topworks) for RV-2-71 C with rebuilt spare
- 8. Tests Conducted: Hydrostatic C] Pneumatic Nominal Operating Pressure C]
Other Pressure n/a psi Test Temp n/a O F 1 3087 (DOCUMENT CHANGE, HOLD AND COMMENT FORM) incorporated: I
' FOR ADMlysTRA'fIvE$
USED~LY; -
R ~ SSupv:
D PRGE 1
1 Assoc Ref: PRGE Doc T v ~ e : REF ONLY I I SR:
Admin initials:
N 1 Freq:
1 Date:
0 vrs 1
APPROVED (Signatures available in Master File)
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS - FORM NIS-2 Page 2 of 2 ITEM 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.
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 ,SECTIONK( is1 Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of h r w ~ f s a - M and employed by
~ t91l.E.oF CVUWT)~C S T C ' ~ DO^ Y r of ~ d pFtP J c T- have inspected the components described in this Owner's Report during the period Ll 13 1 d 7 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) f i , v X & ~ / ~ Q Y J % ~ - c c )
National Board, Province and Endorsements Inspector's Signature Date J' ~1 CY 2 3 , ZCo7 APPROVED (Signatures available in Master File)
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS - FORM NIS-2 Page 1 of 2 ITEM 2007-23-0058 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.
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 7/23/2007 Name
- 2. Plant Monticello Nuclear Generating Plant Sheet 1 of 2 Name 2807 W. Cnty. Rd. 75, Monticello, Minnesota 55362 WO 291884 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-2-715, 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 AS ME Repaired, Code Name of Name of Manufacturer National Other Year Replaced or Stamped Component Manufacturer Serial No. Board No. ldentification Built Replacement YES NO (5) topworks flanae bolts Nova n/a n/a Ht ' O d e H250 2003 Replaced rn (5) topworks flanae bolts Nova n/a n/a Ht ' O d e HZ50 2007 Replacement rn (6) topworks Nova n/a n/a Ht 'Ode 2003 Replaced flanae nuts H25 1 (6) topworks flanae nuts Nova n/a n/a Ht 'Ode HZ5 1 2007 Replacement rn
- 7. Description of Work Partial 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 O F APPROVED (Signatures available in Master File)
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS FORM NIS-2 - Page 2 of 2 ITEM 2007-23-0058 I
- 9. Remarks (Applicable Manufacturer's Data Reports to be Attached)
GE SPEC 27/1\9206and 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.
CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this RWRIR / R ~ C E & W T k n ~ t - p /
conforms to the rules on the ASME Code,Section XI. repairlreplacement Signed I Q ~ Q XI 1s N 1 60- Date Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of )-l~wbfGpe and employed by H APTFo iLJ1 6-t~- l*1 or wfi ~?f3& 0u h 1 ~ - c r I c c c ~ f H&(ZT%TcB J CT have inspected t e components described in this Owner's Report during the period 3 /,f /h7 to
~ [ L Y I J J ~ , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.
By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective 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,, ,
National Board, Province and Endorsements FA/0 0 Y O 2 8 C o Inspector's Signature Date ?11~q 2 q , &d07 APPROVED (Signatures available in Master File)
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS FORM NIS-2 - Page 1 of 2 ITEM 2007-23-0059 I NOTE This form may not address all items needed for documentation of a repairlreplacementprogram, see 4 Awl-09.04.03 (ASME SECTION XI REPAIRIREPLACEMENTPROGRAM) 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 IIin, (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 7/17/2007 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.
- 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
- 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 ASME Repaired, Code Name of Name of Manufacturer National Other Year Replaced or Stamped Component Manufacturer Serial No. Board No. ldentification Built Replacement YES NO CV-1729 Valfek 47907.001.1 n/a n/a 1987 Replaced CV-1729 Valtek n/a n/a Ht. #ZFE 2007 Replacement
- 7. Description of Work Replaced CV-1729 valve body like-for-like. (built 1998, installed 2007)
- 8. Tests Conducted: Hydrostatic Pneumatic Nominal Operating Pressure Other Pressure n/a psi Test Temp n/a "F APPROVED (Signatures available in Master File)
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS FORM NIS-2 - Page 2 of 2 ITEM 2007-23-0059 I
- 9. Remarks (Applicable Manufacturer's Data Reports to be Attached)
Design Change 872015 applies.
New mechanicaljoint 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, CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this REPRIR/R~PCA~M ~~
) ~~ T I U I T ~
conforms to the rules on the ASME Code,Section XI. repairlreplacement Signed ,- SECT )(/ SI Date 7 , 2007 Owner or ~wner's'~esignee, 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 u 6 ; l o r ~ and employed by h~ rzr k118 3 T C U ~B I ~ I L C X1-1& 0 F c d ~ ~ ~ 7 1of ~ ~ 1 k Y~ n r F c r n R ,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, ~rovihceand Endorsements Date T U L L4 ~ , 2/807 APPROVED (Signatures available in Master File)
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS - FORM NIS-2 Page 1 of 2 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.
- 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 W O 267369 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 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 FOR pMINIgRATIVE,
+USEONLY ResS ~ u ~ v : PRGE I
1 Assoc Ref: PRGE Doc T v ~ e : REF ONLY I SR:
I Admin initials:
N I Freq:
I Date:
0 vrs - 1 APPROVED (Signatures available in Master File)
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS FORM NIS-2 - Page 2 of 2 ITEM 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.
CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this R~RIR/REPLACEMEW ACTIV(T~
repairlreplacement
~
conforms to the rules on the ASME Code,Section XI.
Signed 4,- ' &TION&! Is/b. Date , 2007 Owner or owner'k 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 j L l / l r / l / G s e ~ ~ and employed by j+~prForzYI5rc~r-1JI OILCW I t L O F c o ~ ~ d ~ c ) r c ~ofc ~- Nqnl Fdlt8 , C T 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 YLJL8 - 6 u Inspector's Signature National Board, Province and Endorsements Date ~ - , L . Y 20 , 2 J 32 APPROVED (Signatures available in Master File)
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS - FORM NIS-2 Page 1 of 2 L
ITEM 2007-23-0061 I NOTE This form may not address all items needed for documentation of a repairlreplacement program, see 4 AWIQ9.04.03 (ASME SECTION XI REPAIRIREPLACEMENT PROGRAM) for further guidance.
NOTE 2: Supplemental sheets i n form of lists, sketches, or drawings may be used, provided (1) size is 8-112 i n x 11 in, (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet i s numbered and the number of sheets i s recorded at the top of this form.
- 1. Owner Xcel Energy Company Date 7/3/2007 Name
- 2. Plant Monticello Nuclear Generating Plant Sheet 1 of 2 Name 2807 W. Cnty. Rd. 75, Monticello, Minnesota 55362 WO- 141358 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), 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 ASME Repaired, Code Name of Name of Manufacturer National Other Year Replaced or Stamped Component Manufacturer Serial No. Board No. ldentification Built Replacement YES NO SS- 17A Bergen 157 - 4 bolts, HI% un- replaced IX1 Patterson unknown known Ss- 7A Bergen 157 - 2007 replacement Patterson 8868492 0
- 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 1 3087 (DOCUMENT CHANGE, HOLD AND COMMENT FORM) incorporated: - - I w
R e s Suw:
~
ARMS: 3613 PRGE 1
I Assoc Ref: PRGE Doc T v ~ e : REF ONLY I SR:
1 Admin initials:
N I~ r e 1 Date:
~ 0: vrs I APPROVED (Signatures available in Master File)
) MONTICELLO NUCLEAR GENERATING PLANT 1 3613 3 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS - FORM NIS-2 Page 2 of 2 ITEM 2007-23-0061 I
- 9. Remarks (Applicable Manufacturer's Data Reports to be Attached)
Installation performed per procedure 4903.
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 ~ D W a
- 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? 1pw2s 0 7 4 and employed by NnPTFoSo ~ ~ ~ I \ ~ ~ ~ ~ L C ; ? ~ ' ~ ~ of K YF, C C ~ ~P P
~ ~ F blAPT C 7~ I C ~ P have inspe ted the components described in this Owner's Report during the period 3 / 3 0 107 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.
Inspector's Signature Commissions u g r/zJ A , A / ; / I , A ~ A / ~ Q ~ / u L B - c o National Board, Province and Endorsements Date ~ W Y
((I , ZOO]
APPROVED (Signatures available in Master File)
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS - FORM NIS-2 Page 1 of 2 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 i n items 1through 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 7/17/2007 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.
- 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
- 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 ASME Repaired, Code Name of Name of Manufacturer National Other Year Replaced or Stamped Component Manufacturer Serial No. Board No. ldentification Built Replacement YES NO CV-1729 Plua Valtek V12499 n/a n/a 1995 Replaced 0 IE3 729 Flowsen~e n/a n/a Ht-Code 2007 Replacement Plua 86966-1
- 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 APPROVED (Signatures available in Master File)
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS FORM NIS-2 - Page 2 of 2 ITEM 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 ~ = * ~ TAmvl?y conforms to the rules on the ASME Code,Section XI. repairlreplacement Signed m- ,SKTX( IS\ Coom Owner or Owner's Designee, Title Date d 7 , 2.007 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 ~ / W S J ' T A and employed by
~ ~ A R ~ F o LSk4k U D I I L ~ ? ZL \ t j OK Coy&~cTlcccr of f { , + f i ~ t = o l Z D , GY have inspected the components described in this Owner's Report during the period 3 / 3 0 / 0 7 to 7/ 1 7 / 0 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.
Yu A&!
Inspector's Signature Commissions 11k6,? A , W , $ h w National Board, Province and Endorsements 90 2 g -CU Date 34LV 49 , 20(37 APPROVED (Signatures available in Master File)
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS FORM NIS-2 - Page 1 of 2 ITEM 2007-23-0063 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.
- 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 1883 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-2-71E, 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 ASME Repaired, Code Name of Name of Manufacturer National Other Year Replaced or Stamped Component Manufacturer Serial No. Board No. Identification Built Replacement YES NO lnlet flange Nova n/a n/a n/a 1969 Replaced
-- IXI Inlet flange Nova n/a n/a Ht# 2007 Replacement studs (12) 3M41345 lnlet flange nuts (24)
Nova n/a n/a n/a 1969 Replaced IXI lnlet flange n/a Ht# 2007 Replacement Nova n/a IX]
nuts (24) M92614
- 7. Description of Work Replaced inlet flange bolting due to disassembly damage & thread pitch spec
- 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)
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS FORM NIS-2 - Page 2 of 2 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.
CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this F?XP&IR/REPLAC~-/HEWC ~ T I V I T ~
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 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 / k c i Po 4 and employed by k/4flfF6fiY ~ T < ~ ~ , R o / L 3 f~ ~Hd r c ~ l u l ~ ~ C ~ 1 ~Ft (l rAoRf s - ~ ~ ~ ) ~ , c T 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 k c +
Inspector's Signature Commissions ~6 i I ,
~ 3GA I\l, 2 A X /oo L~LILJ -CU National Board, Province and Endorsements Date JoLY '27 , LOO?
APPROVED (Signatures available in Master File)
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS FORM NIS-2 - Page 1 of 2 ITEM 2007-23-0064 I This form may not address all items needed for documentation of a repairlreplacement program, see 4 Awl-09.04.03 (ASME SECTION XI REPAIRIREPLACEMENTPROGRAM) 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 1885 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 ASME Repaired, Code Name of Name of Manufacturer National Other Year Replaced or Stamped Component Manufacturer Serial No. Board No. ldentification Built Replacement YES NO topworks flg Nova n/a n/a H250 2003 Replaced bolts (12) topworks flg Nova n/a n/a H t # 84013 2007 Replacement bolts (121 (XI topworks flg Nova n/a n/a H251 2003 Replaced nuts (12) topworksflg Nova n/a n/a Ht # 66036 2007 Replacement nuts (12) (XI
- 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 "F APPROVED (Signatures available in Master File)
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS FORM NIS-2 - Page 2 of 2 ITEM 2007-23-0064 I
- 9. Remarks (Applicable Manufacturer's Data Reports to b e 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)
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.
CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this ~ c p p/REPM~MEMT l ~ f icflu~~
conforms to the rules on the ASME Code,Section XI. repairlreplacement Signed .* S~rno~)(/ If\
Owner 6r ~wn'er'sDesignee, 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 .&/C~QC~OTA and employed by I - l n l l T F ~ d 3 S?c-4b pv~rcw i
- S d F o k k s c r \ c ~ i of f I 4 1 T F J # ~ CT I have inspected th components described in this Owner's Report during the period Y / 3 /d'l to 7 1 2 4 07 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.
7dx fi - ~ i ~ . + 4 -
Inspector's Signature Commissions jV8 //a6 2 A , .C/, /c/wod L/ ii 28-co National Board, Province and Endorsements Date 3UL.Y 2 7 , 2437 APPROVED (Signatures available in Master File)
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS - FORM NIS-2 Page 1 of 2 ITEM 2007-23-0065 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.
NOTE 2: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8-112 in x II 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 1 of 2 Name 2807 W.Cnty. Rd. 75, Monticello, Minnesota 55362 WO 322083 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-2-71A, 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 ASME Repaired, Code Name of Name of Manufacturer National Other Year Replaced or Stamped Component Manufacturer Serial No. Board No. ldentification Built Replacement YES NO topworks flg bolts (12)
Nova n/a n/a n/a various Replaced [3 IXI topworks flg bolts (12)
Nova n/a n/a H t # 84013 2007 Replacement [3 IXI topworks flg Nova n/a n/a n/a various Replaced nuts (12) topworks flg nuts (12)
Nova n/a n/a H t # 66036 2007 Replacement [3 IXJ
- 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 O F APPROVED (Signatures available in Master File)
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS FORM NIS-2 - Page 2 of 2 L
ITEM 2007-23-0065 I
- 9. Remarks (Applicable Manufacturer's Data Reports to b e 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.
CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this R m ~Pl / W W ~ T h t v l ~ y conforms to the rules on the ASME Code,Section XI. repairlreplacement
,S E ~ W O XI N &a Date Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of M I W U F ~OTA and employed by L ~ A ~ T F ~ P ~ ~ T ~ E A ~ D O I L H ~ ~ L ~ FofC O NM W~ E ~
L P. I~~ J~ J
~ ~? u , c T have inspected the components described in this Owner's Report during the period ~ / /473 to
~ / L /YJI , 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 SUL-Y 2Y , 2007 APPROVED (Signatures available in Master File)
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS FORM NIS-2 - Page 1 of 2 L
ITEM 2007-23-0066 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.
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-andthe number of sheets is recorded at the top of this form.
- 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.
- 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
- 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 ASME Repaired, Code Name of Name of Manufacturer National Other Year Replaced or Stamped Component Manufacturer Serial No. Board No. ldentification Built Replacement YES NO MO-2035 Nova/ n/a n/a n/a various Replaced stud. nuts Flowserve MO-2035 Nova/
stud, nuts Flowserve n/a n/a n/a 2007 Replacement IXI M0-2035 Ht. 'Ode Disc Flowserve S/N 2 n/a TRH-1 2000 Replaced IXI M%2035 Flowserve S/N I n/a Ht Code 2007 Replacement TRH-2 CI
- 7. Description of Work Like for like replacement of I bonnet stud and 16 nuts on valve MO-2035
- 8. Tests Conducted: Hydrostatic C] Pneumatic C] Nominal Operating Pressure Other Pressure n/a psi Test Temp n/a "F APPROVED (Signatures available in Master File)
MONTICELLO NUCLEAR GENERATlNG PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS - FORM NIS-2 Page 2 of 2 ITEM 2007-23-0066 I
- 9. Remarks (Applicable Manufacturer's Data Reports to b e Attached)
Like for like replacement of stud and nuts due to damage during removal.
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 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 LLRT 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 1s1 e o o ~ 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 & I U U F so T4 and employed by f - ~ c l ~ t r = o n s s ~ t ' ~ . g, o r ~ ~ ~J r+. ~ ~ F C ~ ~ M - C ~ I C of~ ~ H ~ R T . F O R D,ct- have inspected the components described in this Owner's Report during the period CI ( /o 7 to 71 ~2 I d 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.
%L-T- A d.t.4-1;. Commissions -
I / ~ G J A, w i t k w & a Y O L K co Inspector's Signature National Board, Province and Endorsements Date J4Ly Zc , 2dd7 APPROVED (Signatures available in Master File)
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS - FORM NIS-2 Page 1 of 2 ITEM 2007-23-0067 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.
- 1. Owner Xcel Energy Company Date 7/14/2007 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.
- 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 Senlice Water (RHRS w,Loop A, Class 3
- 5. (a) Applicable Construction Code ANSI B31.7 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. Identification of Components Repaired or Replaced and Replacement Components ASME Repaired, Code Name of Name of Manufacturer National Other Year Replaced or Stamped Component Manufacturer Serial No. Board No. ldentification Built Replacement YES NO SW9- 18"-GF n/a n/a n/a n/a 1969 Replaced (XI SW9-18"-GF Dubose n/a n/a H#A83222 2007 Replacemenf IX(
SR-396 n/a n/a n/a n/a 2007 Repaired (XI
- 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 Other Pressure 235-240 psi Test Temp n/a O F APPROVED (Signatures available in Master File)
MONTICELLO NUCLEAR GENERATING PLANT 361 3 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS FORM NIS-2 - Page-3l0f 2 ?f&ior 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.
CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this REP&IR/ RFPLACMENT AcXlvly conforms to the rules on the ASME Code,Section XI. repairlreplacement Signed . SECT)O IS/ 6 0 - Date Owner or 0wner"s Designee, Title ( I d i 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 W I L & ~ arA and employed by
/ M & ~ F
- F I Jrrf'nrs a o i ~ l t ti3 J F cY&-~t'crlcu2 of bheTt=J3&, c T have inspected the components described in this Owner's Report during the period &/!7 /d-) 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 Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report. Furthermore, neither the Inspector nor his employer SHALL be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.
~ L T,4.hLk. Commissions P V I ( k c ) A , IV, 2 h v 3 d ~ I U t-co Z
Inspector's Signature National Board, Province and Endorsements Date S l N ' L3 , 2337 APPROVED (Signatures available in Master File)
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS FORM NIS-2 - Page 1 of 2 ITEM 2007-23-0068 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 REPAIRIREPLACEMENTPROGRAM) 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 IIin, (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 7/14/2007 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.
- 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 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 ASME Repaired, Code Name of Name of Manufacturer National Other Year Replaced or Stamped Component Manufacturer Serial No. Board No. ldentification Built Replacement YES NO SW9-18"-GF n/a n/a n/a n/a 1969 Replaced IXJ SW9-18"-GF Dubose n/a n/a HHA83222 2007 Replacement
- 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 Other Pressure 235-240 psi Test Temp n/a "F APPROVED (Signatures available i n Master File)
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: I OWNER'S REPORT FOR REPAIRS OR Revision 4 I I REPLACEMENTS FORM NIS-2 -
ITEM 2007-23-0068 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 R E ? ~ & E P L ~ ~ M N T Acrhvrry conforms to the rules on the ASME Code,Section XI. repairlreplacement Signed I - SECTXI Is\ bow Owner or ~'wner'sbesignee, 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 ~ / ~ ' ~ o T n and employed by
/ j ~ g j - ~ ~ fJ?-cenn l u rlolcr2~'jJ'dPcflwc'cT~cyT of ~(ACTFU&.JJ,C~ have inspected the components described in this Owner's Report during the period Y/? I d 7 to
~ / L 107J , 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* Inspector's Signature Commissions I Y I~( 663 A ,MA- /7 M 30 % L&-CO National Board, Province and Endorsements Date ~ Q L Y 23 I ZOQ7 APPROVED (Signatures available in Master File)
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS - FORM NIS-2 Page 1 of 2 ITEM 2007-23-0069 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.
NOTE 2: Supplemental sheets i n form of lists, sketches, or drawings may be used, provided (1) size i s 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 i s 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 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 ASME Repaired, Code Name of Name of Manufacturer National Other Year Replaced or Stamped Component Manufacturer Serial No. Board No. ldentification Built Replacement YES NO Vl5-H3, umer rod Bergen Paterson n/a n/a n/a 1969 Replaced rn Vf5H3, Bergen n/a n/a Po E46743j 2007 Replacement u ~ o erod r Paterson Ln. 10
- 7. Description of Work Replaced upper hanger rod due to bend identified by IS/.
- 8. Tests Conducted: Hydrostatic Pneumatic Nominal Operating Pressure Other Pressure n/a psi Test Temp n/a O F APPROVED (Signatures available in Master File)
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS - FORM NIS-2 Page 2 of 2 ITEM 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)
CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this R E ~ A ~ R / \/cry R ~ P ~ ~
conforms to the rules on the ASME Code,Section XI. repairlreplacement Signed , Seer Xl Owner or Owner's Designee, Title ISI bog,) Date fi ic , w"T 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 P I W W S B F A and employed by IIAvlm PB ~ t r ; sb~a ~ ~ mIt& 31: COWGCTIC 4~ of F/*QP'~' ~ C J I ~ I ,J L r have inspected t e components described in this Owner's Report during the period Y /[J 107 to
-7 1 ~ ~ 1 0, and ~state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI. 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&
Inspector's Signature Commissions Plt r r 4-6 j 4, N,t h t v o o YUZ 6 - ~ 0 National Board, Province and Endorsements Date T Q L Z~C , 2-007 APPROVED (Signatures available in Master File)
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS - FORM NIS-2 Page 1 of 2 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.
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 7/14/2007 Name
- 2. Plant Monticello Nuclear Generating Plant Sheet I of 2 Name 2807 W. Cnty. Rd. 75, Monticello, Minnesota 55362 WO 325774 Address Repair Organization P.O. No., Job No. etc.
- 3. Work Performed By NMC /Xcel Energy Type Code Symbol Stamp n/a Company Name Authorization No. n/a 2807 W. Cty Rd 75, Monticello, MN 55362 Expiration Date n/a Address
- 4. 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 GENERATlNG PLANT 1 3613 3 1 TITLE: 1 OWNER'S REPORT FOR REPAIRS OR ( Revision 4 1 I I REPLACEMENTS FORM NIS-2 - Ip a g - ~ 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/ RFPWCEMENTP CS~V~
conforms to the rules on the ASME Code,Section XI. repairlreplacement Signed 2 sw$1 IS[
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 /1cv~,420 TA and employed by C ( A ~ ~ T F O K O 9rc~114QOI la J'~J' c r r t o ~ ~ ~ l i t l c r l r of ? - i ~ ~ f J l b lCe ~r, have inspected the components described in this Owner's Report during the ~ e r i o d /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 ~ O O Yap- c d Inspector's Signature National Board, Province and Endorsements Date T C c L v 'iW , Ld07
- A APPROVED (Signatures available in Master File)
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS - FORM NIS-2 Page 1 of 2 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.
- 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 326373 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 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 ASME Repaired, Code Name of Name of Manufacturer National Other Year Replaced or Stamped Component Manufacturer Serial No. Board No. ldentification Built Replacement YES NO ES W5-4"- unknown n/a n/a n/a 1981 Replaced HRD Elbow ES W5-4"- Consolidated n/a n/a Ht# 7662 2007 Replacemenf HBD Elbow Power
- 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 2007).
- 8. Tests Conducted: Hydrostatic Pneumatic Nominal Operating Pressure Other Pressure 76 psi Test Temp n/a "F APPROVED (Signatures available in Master File)
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS FORM NIS-2 - Page%oB ,,iq/q 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/ R w u w w r 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 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 N t u o b y o T A and employed by t-1.sRbFuICU J X a h BOIL@ ~'1.4' O F c - w & r n c k T of [Ia~F ,
t U K CT ~ have inspected the components described in this Owner's Report during the period ' ? / L + / U ~ to 71 L ~ I J ~ , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.
By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective 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/& / / & 6 3 4 , /1.; 5 h-c~/ d0Vo LF -C 0 Inspector's Signature National Board, Province and Endorsements Date ~ C / L Y LO I Zd3)
APPROVED (Signatures available in Master File)
Nuclear Management Company Cycle 23 Summary Report Monticello Inservice Impation 2007 Refueling Outage IV. Form NIS-1 Information Page 1of 2 Form NIS-1 Owner's Data Report for Inservice Inspections
(**Supplement to Submittal for Cycle 22,2005 RFO**)
As required by the Provisions of the ASME Code Rules
- 1. Owner: Xcel Energy. LLC / Nuclear Management Company, LLC Address: 800 Nicollet Mall. Mpls. MN 55402 / 700 1st St., Hudson WI 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 04113/05 .
- 9. Inspection Interval: 05/01/03 to 0513 1/12 .
- 10. Applicable Edition of Section XI: 1995 Addenda: 1996 .
- 11. Abstract of Examinations. Include a list of examinations and a statement concerning status of work required for current interval.
See Sections IV and V for supplemental 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 Cycle 23 Summary Report Monticello Inservice Inspection 2007 Refueling Outage IV. Form NIS-1 Information Page 2 of 2
(**Supplement to Submittal for Cycle 22,2005 RF'O**)
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 X C E L ~ E R WINNC 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 r r rb~ nu ~rchp,J ~ W I ~ =OFRC~~ UYV~SI k w i of +3wj\ F 4 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 / ~ Y W ~ - C U National Board, State, Province, Endorsements Date 741,~ 26 2007
Nuclear Management Company Cycle 23 Summary Report Monticello Inservice Inspection 2007 Refueling Outage V. Form NIS-2 Information Supplemental NIS-2 Form for Cycle 22 2005 RFO Summary Report Previously unsubmitted Form NIS-2 RIR ITEM WORK COMPONENT NUMBER DOCUMENT OR SYSTEM WORK DESCRIPTION Replaced valve plug note: replaced during 2005 RFO 2006-22-0007 WO-0307010 CV-1728 (reference CAP 01006064)
(2 pages to follow)
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS FORM NIS-2 - Page Iof 2 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.
- 1. Owner Xcel Energy Company Date 7/13/2006 Name
- 2. Plant Monticello Nuclear ~eneratingPlant Sheet 1 of 2 Name 2807 W. Cnty. Rd. 75, Monticello, Minnesota 55362 WO 0307010 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
- 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 ASME Repaired, Code Name of Name of Manufacturer National Other Year Replaced or Stamped Component Manufacturer Serial No. Board No. ldentification Built Replacement YES NO CV- 1728 Valtek 47907-001 n/a 0411236- 1987 Replaced (valve) 9970-01 jXI CV- 1728 Flowserve 47907-001 n/a O4 1236- 2005 Replacement (XI (valve) 29970-01
- 7. Description of Work Replaced plug
- 8. Tests Conducted: Hydrostatic 0 Pneumatic Nominal Operating Pressure Other Pressure n/a psi TestTemp n/a OF APPROVED (Signatures available in Master File)
MONTICELLO NUCLEAR GENERATING PLANT 3613 TITLE: OWNER'S REPORT FOR REPAIRS OR Revision 4 REPLACEMENTS FORM NIS-2 - Page 2 of 2 ITEM 2006-22-0007 I
- 9. Remarks (Applicable Manufacturer's Data Reports to be Attached)
Design Change 8720 15 is applicable to valve and Alteration 95A0 1I 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).
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 ~ L L/'/ ~ 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 M I U ~ 6l ~ ' T A and employed by H A & ~ F Q ~ PSOT L ~ ~4,o/~b12 W ; C T ~ ~ & CT
~ ~ ~ ~ F C O U ~ E t-(AZi-PaP-U, ~ have inspected the components described in this Owner's Report during the period UBc& M Lf Qg lc , Ldo3" to 3 ~ j ~l yy, 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 (//KG3 A , h/a 40 tx- co Inspector's Signature National Board, Province and Endorsements Date ~ C C L ' Pl Y , coo6 APPROVED (Signatures available in Master File)
Nuclear ~anagementCompany Cycle 23 Summary Report Monticello Inservice Inspection 2007 Refueling Outage 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 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 Owner Certificate of Authorization (If Req.): N/A Operator: Nuclear Management Company, LLC, 700 First Street, Hudson, WI 54016 Commercial Service Date: 6/30/1971 Plant: Monticello Nuclear Generating Plant, Unit 1, 2807 West County Rd #75, Monticello, MN 55362 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 B A , EXAMS PERFORMED FOR IS1 (4th Interval, Period 2 Credited Exams) and PSI 81.12 102643 VLAA-2 Long Seam PEI-02.03.15 UT 2007UT059 NRI Reactor Vessel IS1 Fig 4 3/22/2007 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 Fig 1 3/25/2007 IS1 Reactor Vessel 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 312112007 IS1 83.90 102658 N- 2B NV N- 2B Noz 1Vsl Weld PEI-02.03.15 UT 2007UT058 NRI Reactor Vessel IS1 Fig 5 3/2112007 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 Fig 5 3/22/2007 IS1 Reactor Vessel 83.90 102668 N- 2G NV N- 2G NozNsl Weld PEI-02.03.15 UT 2007UT061 NRI Reactor Vessel IS1 Fig 5 3/22/2007 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 Owner Certificate of Authorization (If Req.): N/A Operator: Nuclear Management Company, LLC, 700 First Street, Hudson, WI 54016 Commercial Service Date: 6/30/1971 Plant: Monticello Nuclear Generating Plant, Unit 1, 2807 West County Rd #75, Monticello, MN 55362 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 B3.1O0 FP-PE-NDE-UT-03 UT 2007UT101 NRI IS1 Fig 5 3/24/2007 IS1 Reactor Vessel 83.90 102684 N- 4A NV N- 4A NozNsl Weld PEI-02.03.15 UT 2007UT103 NRI Reactor Vessel IS1 Fig 5 3/24/2007 IS1 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 Fig 5 3/24/2007 IS1 Reactor Vessel 83.90 102700 N- 9 NV N- 9 VesINoz Weld PEI-02.03.15 UT 2007UT102 NRI Reactor Vessel IS1 Fig 5 3/24/2007 IS1 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 86.180 102076 8- 2 RC Pump B Studs, Nuts PEI-02.03.06 UT 2007UT125 NRI Recirculation B ISI-97006-A 3/25/2007 IS1 IS1 PEI-02.05.01 VT 2 0 0 M 0 4 4 NRI Recirculation B ISI-97006-A 3/25/2007 PSI PEI-02.05.01 VT 2 0 0 M 0 4 5 NRI Recirculation B 1st-97006-A 3/25/2007 B6.190 107184 P200-B Flange Surface PEI-02.05.01 VT 2007Vr475 NRI Recirculation B ISI-97006-A 3/25/2007 IS1 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 Owner Certificate of Authorization (If Req.): NIA Operator: Nuclear Management Company, LLC, 700 First Street, Hudson, WI 54016 Commercial Service Date: 6/30/1971 Plant: Monticello Nuclear Generating Plant, Unit 1, 2807 West County Rd #75, Monticello, MN 55362 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 B7.50 100567 B- 2 Flange Bolts @ W-14 PEI-02.05.01 VT 2007VT032 NRI Main Steam A ISI-I 3142-33-A 311912007 IS1 87.50 100568 B- 3 Flange Bolts @ W-16 PEI-02.05.01 VT 2 0 0 M 4 8 6 NRI Main Steam A ISI-13142-33-A 4/3/2007 PSI 87.70 100574 B- 9 Valve Bolts PEI-02.05.01 VT 2 0 0 M 4 8 7 NRI Main Steam A ISI-13142-33-A 4/3/2007 PSI B7.50 100622 B- 2 Flange Bolts @ W-15 PEI-02.05.01 VT 2007VT031 NRI Main Steam B ISI-13142-34-A 311912007 IS1 87.70 100626 B- 6 Valve Bolts PEI-02.05.01 VT 2 0 0 M 4 8 8 NRI Main Steam B ISI-13142-34-A 4/3/2007 PSI 87.70 100629 B- 7 Valve Bolts PEI-02.05.01 VT 2007VT459 NRI Main Steam B ISI-13142-34-A 4/1/2007 PSI B7.70 100974 B- 2 Valve Bolts PEI-02.05.01 VT 2007VT494 NRI HPCl Steam ISI-13142-42-A 4/4/2007 PSI IS1 PEI-02.05.01 VT 2007Vr495 NRI HPCl Steam ISI-13142-42-A 4/4/2007 87.50 101408 B- I Flange Bolts PEI-02.05.01 VT 2007Vr732 NRI Recirc B Drain Line ISI-74210-1A 411 112007 IS1 B7.50 101492 B- 2 Flange Bolts PEI-02.05.01 VT 2007VT477 NRI Head Vent ISI-782A-A 4/3/2007 PSI B7.70 101929 B- 2 Valve Bolts PEI-02.05.01 VT 2007Vr474 NRI RHR Return B ISI-97004-A 3/27/2007 IS1 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 Owner Certificate of Authorization (If Req.): N/A Operator: Nuclear Management Company, LLC, 700 First Street, Hudson, WI 54016 Commercial Service Date: 613011971 Plant: Monticello Nuclear Generating Plant, Unit 1, 2807 West County Rd #75, Monticello, MN 55362 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)
B12.20 102099 P200-B Pump Casing Internal Surfaces PEI-02.05.04 VT 2007VT043 NRI Recirculation B ISI-97006-A 3/25/2007 IS1 Class 1 Category B-M-2, EXAMS PERFORMED FOR IS1 (4th Interval, Period 2 Credited Exams) 812.50 100992 v- 2 Valve Int Surfaces IS1 PEI-02.05.04 VT 2007Vr493 NRI HPCl Steam ISI-13142-42-A 4/4/2007 B12.50 101938 v- 2 Valve Int Surfaces IS1 PEI-02.05.04 VT 2007M-446 NRI RHR Return B ISI-97004-A 3/27/2007 Class 1 Category 6-N-1, EXAMS PERFORMED FOR IS1 (4th Interval, Period 2 Credited Exams)
Top Guide (areas made access., fuel cell 813.1 0 102716 C-1A PEI-02.05.05 VT-3 AREVA-RPT NRI Reactor Vessel IS1 Fig 0 3/3112007 vacated) IS1 813.10 102718 C-3A Shroud Shelf 0-180 deg PEI-02.05.05 VT-3 AREVA-RPT NRI Reactor Vessel IS1 Fig 0 3/31/2007 IS1 B13.10 107690 C-3B Shrd Shlf 180-360 deg PEI-02.05.05 VT-3 AREVA-RPT NRI Reactor Vessel IS1 Fig 0 3/3112007 IS1 lncore Dry Tubes (if made accessible B13.10 107737 C-I I PEI-02.05.05 VT-3 AREVA-RPT NRI Reactor Vessel IS1 Fig 0 313 112007 during RFO) IS1 Core Plate (areas made access., fuel cell B13.10 107738 C-12A PEI-02.05.05 VT-3 AREVA-RPT NRI Reactor Vessel IS1 Fig 0 3/31/2007 vacated) IS1 Core Plate (areas made access., fuel cell 813.10 102668 N- 2G NV PEI-02.05.05 VT-3 AREVA-RPT NRI Reactor Vessel IS1 Fig 0 3/31I2007 vacated) IS1 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 Owner Certificate of Authorization (If Req.): N/A Operator: Nuclear Management Company, LLC, 700 First Street, Hudson, WI 54016 Commercial Service Date: 613011971 Plant: Monticello Nuclear Generating Plant, Unit 1, 2807 West County Rd #75, Monticello, MN 55362 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)
B13.30 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 3/3112007 IS1 B13.30 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 3/3112007 IS1 Core Plate (areas made access., fuel cell B13.40 107739 C-12B PEI-02.05.05 VT-3 AREVA-RPT NRI Reactor Vessel IS1 Fig 0 3/31/2007 vacated) IS1 Fuel Spt Cast (areas access, fuel cell B13.40 107744 C-I 7A PEI-02.05.05 VT-3 AREVA-RPT NRI Reactor Vessel IS1 Fig 0 3/3112007 vacated) IS1 107746 C-18 accessible)
Ctrl Rod Guide Tube Int (when B13.40 PEI-02.05.05 VT-3 AREVA-RPT NRI Reactor Vessel IS1 Fig 0 3/31/2007 IS1 B13.40 107747 C-3E Shroud Shelf 0-180 deg PEI-02.05.05 VT-3 AREVA-RPT NRI Reactor Vessel IS1 Fig 0 3/3112007 IS1 813.40 107748 C-3F Shroud Shelf 180-360 deg PEI-02.05.05 VT-3 AREVA-RPT NRI Reactor Vessel IS1 Fig 0 3/3112007 IS1 Class 1 Category F-A, EXAMS PERFORMED FOR IS1 (4th Interval, Period 2 Credited Exams) and PSI Fl.lOb 100582 H- 6 Snubber 1 Clamp PEI-02.05.02 VT 2 0 0 M 0 2 2 NRI Main Steam A ISI-13142-33-A 311512007 PSI IS1 PEI-02.05.02 VT 2007VT021 NRI Main Steam A ISI-13142-33-A 311512007 Fl.lOb 100682 H- 2 Snubber 1 Clamp PEI-02.05.02 VT 2 0 0 M 0 1 3 NRI Main Steam C ISI-13142-35-A 311512007 PSI Fl.lOb 100683 H- 3 Snubber IClamp PEI-02.05.02 VT 2 0 0 M 0 1 2 NRI Main Steam C ISI-I3142-35-A 311512007 PSI Fl.lOb 101198 H- 4 Snubber / Clamp PEI-02.05.02 VT 2007VT717 NRI Feedwater ISI-13142-52-A 313012007 PSI Fl.lOb 101201 H- 7 Snubber IClamp PEI-02.05.02 VT 2007Vr713 NRI Feedwater ISI-13142-52-A 3/30/2007 PSI 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 Owner Certificate of Authorization (If Req.): NIA Operator: Nuclear Management Company, LLC, 700 First Street, Hudson, WI 54016 Commercial Service Date: 613011971 Plant: Monticello Nuclear Generating Plant, Unit 1, 2807 West County Rd #75, Monticello, MN 55362 National Board Number for Unit: NIA Summary No. Comp ID Comp Desc. Category Item Procedure MethodISheetlResults System IS0 Num Exam Date Fl.lOb 101253 H- 5 Snubber IClamp PEI-02.05.02 VT 2007VT710 NRI Feedwater ISI-13142-53-A 313012007 PSI Fl.lOb 101255 H- 7 Snubber IClamp PEI-02.05.02 VT 2007VT482 NRI Feedwater ISI-13142-53-A 3/31/2007 PSI Fl.lOb 101855 H- 3 Snubber IClamp PEI-02.05.02 VT 2 0 0 M 0 1 6 NRI RHR Return A ISI-97003-A 311412007 PSI Fl.lOb 101896 H- 2 Snubber IClamp PEI-02.05.02 VT 2007VT709 NRI RHR Suction A ISI-97003-B 41512007 PSI PSI PEI-02.05.02 VT 2007VT014 NRI RHR Suction A ISI-97003-B 311412007 Fl.10~
101934 H- 2 VariablelSlidelClamp PEI-02.05.02 VT 2007VT030 NRI RHR Return B ISI-97004-A 411412007 IS1 Fl.lOb 101935 H- 3 Snubber IClamp PEI-02.05.02 VT 2007VT484 NRI RHR Return B ISI-97004-A 313012007 PSI Fl.lOb 101936 H- 4 Snubber IClamp PEI-02.05.02 VT 2 0 0 M 4 8 1 NRI RHR Return B ISI-97004-A 313012007 PSI F l .lOa 102027 H-10 Restraint PEI-02.05.02 VT 2 0 0 M 0 4 1 NRI Recirc Manifold A ISI-97005-B 312512007 IS1 --
Fl.lOa 105020 H-5A Hanger PEI-02.05.02 VT 2 0 0 M 0 2 6 NRI Head Vent ISI-782A 311812007 IS1 Fl.10~
105022 H-17 Spring IClamp PEI-02.05.02 VT 2007VT023 RI Head Vent ISI-782A 311812007 IS1 PSI PEI-02.05.02 VT 2 0 0 M 7 4 7 NRI Head Vent ISI-782A 411412007 Fl.lOa 105023 H- I Hanger PEI-02.05.02 VT 2 0 0 M 7 4 5 NRI Head Vent ISI-782A-A 411212007 PSI Fl.10~
105024 H- 2 Spring IClamp PEI-02.05.02 VT 2007W748 NRI Head Vent ISI-782A-A 411212007 PSI Fl.lOa 105025 H- 3 Hanger PEI-02.05.02 VT 2 0 0 M 7 4 6 NRI Head Vent ISI-782A-A 411212007 PSI Fl.10~
107523 H- 3 Dbl Spring 14 Lugs PEI-02.05.02 VT 2 0 0 M 0 2 9 NRI Reactor Wtr Cleanup ISI-73880-A 311812007 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 Owner Certificate of Authorization (If Req.): N/A Operator: Nuclear Management Company, LLC, 700 First Street, Hudson, WI 54016 Commercial Service Date: 6/30/1971 Plant: Monticello Nuclear Generating Plant, Unit 1, 2807 West County Rd #75, Monticello, MN 55362 National Board Number for Unit: NIA Summary No. Comp ID Comp Desc. Category Item Procedure MethodlSheetlResults System IS0 Num Exam Date Fl.lOb 107528 H- 8 Snubber / Lugs PEI-02.05.02 VT 2007VT712 NRI Recirculation A ISI-97005-A 3/31/2007 PSI PSI PEI-02.05.02 VT 2 0 0 M 0 2 0 NRI Recirculation A ISI-97005-A 311512007 IS1 PEI-02.05.02 VT 2007VT019 NRI Recirculation A ISI-97005-A 311512007 F1.40~
107534 H- I RodlClevis GriplLugslConstant-Support PEI-02.05.02 VT 2007W-034 NRI Recirc Pump A ISI-97005-C 311912007 IS1 F1.40~
107535 H- 2 RodlClevis GriplLugslConstant-Support IS1 PEI-02.05.02 VT 2007VT033 NRI Recirc Pump A ISI-97005-C 311912007 F1.40b 107540 H- 7 Snubber 1 Lugs PEI-02.05.02 VT ZOOM024 NRI Recirc Pump A ISI-97005-C 311812007 PSI F1.40b 107541 H- 8 Snubber 1 Lugs PEI-02.05.02 VT 2007VT714 NRI Recirc Pump A ISI-97005-C 4/6/2007 PSI F1.40b 107542 H- 9 Snubber 1 Lugs PEI-02.05.02 VT 2007VT715 NRI Recirc Pump A ISI-97005-C 4/6/2007 PSI Fl.lOb 107547 H- 8 Snubber 1 Lugs PEI-02.05.02 VT ZOOM480 NRI Recirculation B ISI-97006-A 3/31/2007 PSI F1.40~
107555 H- 3 RodIClevis GriplLugslConstant-Support PEI-02.05.02 VT 2007VT485 NRI Recirc Pump B ISI-97006-C 3/29/2007 PSI F1.40b 107559 H- 7 Snubber / Lugs PEI-02.05.02 VT 2 0 0 M 0 2 5 NRI Recirc Pump B ISI-97006-C 311812007 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 Owner Certificate of Authorization (If Req.): NIA Operator: Nuclear Management Company, LLC, 700 First Street, Hudson, WI 54016 Commercial Service Date: 613011971 Plant: Monticello Nuclear Generating Plant, Unit 1, 2807 West County Rd #75, Monticello, MN 55362 National Board Number for Unit: NIA Summary No. Comp ID Comp Desc. Category Item Procedure Method/Sheet/Results System I S 0 Num Exam Date Class 1 Category RA(L), EXAMS PERFORMED FOR IS1 (4th Interval, Period 2 Credited Exams), PSI, and AUGMENTED (HELB ISUPERPIPE) 100618 W-30 Pipe-to-Pipe R1'20 FP-PE-NDE-401 UT 2007UT068 NRI Main Steam A ISI-13142-33-A 311712007 AUG AUG FP-PE-NDE-401 UT 2007UT067 NRI Main Steam A ISI-13142-33-A 311712007 100619 W-31 Pipe-to-Pipe R1'20 FP-PE-NDE-401 UT 2007UT066 NRI Main Steam A ISI-13142-33-A 311712007 AUG AUG FP-PE-NDE-401 UT 2007UT065 GEO Main Steam A ISI-13142-33-A 311712007 AUG FP-PE-NDE-401 UT 2007UT064 NRI Main Steam A ISI-13142-33-A 311712007 100668 W-30 Pipe-to-Pipe R1.20 FP-PE-NDE-401 UT 2007UT005 NRI Main Steam B ISI-I 3142-34-A 311612007 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 311612007 AUG AUG FP-PE-NDE-401 UT 2007UT009 GEO Main Steam B ISI-I3142-34-A 3/16/2007 AUG FP-PE-NDE-401 UT 2007UT010 NRI Main Steam B ISI-13142-34-A 311612007 100670 W-32 Pipe-to-Pipe R1'20 FP-PE-NDE-401 UT 2007UT007 NRI Main Steam B ISI-13142-34-A 311612007 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) 1i Owner: Xcel Energy, LLC. 800 Nicollet Mall, Minneapolis. MN 55402 Owner Certificate of Authorization (If Req.): NIA
/ Operator: Nuclear Management Company, LLC, 700 First Street, Hudson, WI 54016 Commercial Service Date: 613011971 I
I Plant: Monticello Nuclear Generating Plant, Unit I , 2807 West County Rd #75, Monticello, MN 55362 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 ISI-13142-35-A 311612007 AUG Main Steam C AUG FP-PE-NDE-401 UT 2007UT031 GEO Main Steam C ISI-13142-35-A 311612007 AUG FP-PE-NDE-401 UT 2007UT032 NRI Main Steam C ISI-13142-35-A 3/16/2007 100721 W-31 Pipe-to-Pipe R1'20 FP-PE-NDE-401 UT 2007UT035 NRI ISI-13142-35-A 3/16/2007 AUG Main Steam C 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 311612007 .-
100722 W-32 Pipe-to-Pipe R1.20 FP-PE-NDE-401 UT 2007UT037 NRI AUG Main Steam C ISI-13142-35-A 311612007 AUG FP-PE-NDE-401 UT 2007UT038 NRI Main Steam C ISI-I 3142-35-A 311612007 AUG FP-PE-NDE-401 UT 2007UT036 NRI Main Steam C ISI-13142-35-A 311612007 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 311612007 AUG FP-PE-NDE-401 UT 2007UT041 NRI Main Steam C 1st-13142-35-A 311612007 100778 W-32 Pipe-to-Pipe R1.20 FP-PE-NDE-401 UT 2007UT002 GEO ISI-I3142-36-A 311612007 AUG Main Steam D 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 ISI-13142-36-A 3/16/2007 AUG Main Steam D AUG FP-PE-NDE-401 UT 2007UT025 NRI Main Steam D ISI-I 3142-36-A 311612007 AUG FP-PE-NDE-40f UT 2007UT024 NRI Main Steam D ISI-13142-36-A 311612007 100780 W-34 Pipe-to-Pipe R1.20 FP-PE-NDE-401 UT 2007UT028 GEO AUG Main Steam D ISI-I3142-36-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 Owner Certificate of Authorization (If Req.): NIA Operator: Nuclear Management Company, LLC, 700 First Street, Hudson, WI 54016 Commercial Service Date: 6/30/1971 Plant: Monticello Nuclear Generating Plant, Unit 1, 2807 West County Rd #75, Monticello, MN 55362 National Board Number for Unit: NIA Summary No. Comp ID Comp Desc. Category Item Procedure MethodISheetlResults System IS0 Num Exam Date 101056 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 R1.20 101529 W- 7 Tee-to-Pipe PEI-02.01.O1 PT 2007PT003 NRI MS Condensate Lkoff ISI-786A 4/1/2007 PSI R1.20 101530 W- 8 Valve-to-Pipe PEI-02.01.O1 PT 2007PT004 NRI MS Condensate Lkoff ISI-786A 112512007 PSI R1.20 101531 W- 9 Elbow-to-Pipe PEI-02.01.O1 PT 2007PT005 NRI MS Condensate Lkoff ISI-786A 1/25/2007 PSI R1.20 101535 W-I 3 Pipe-to-Pipe PEI-02.01.O1 PT 2007PT006 NRI MS Condensate Lkoff ISI-786A 4/4/2007 PSI R1.20 101536 W-14 Pipe-to-Valve PEI-02.01.O1 PT 2007PT007 NRI MS Condensate Lkoff ISI-786A 2/6/2007 PSI 107749 W-29~ pipe-to-pipe R1.20 FP-PE-NDE-~OI UT 2007UT082 NRI Main Steam A ISI-13142-33~ 311712007 IS1 IS1 FP-PE-NDE-401 UT 2007UT081 GEO Main Steam A ISI-13142-33-A 311712007 AUG FP-PE-NDE-401 UT 2007UT080 NRI Main Steam A ISI-I 3142-33-A 311712007 AUG FP-PE-NDE-401 UT 2007UT079 GEO Main Steam A ISI-13142-33-A 311712007 AUG FP-PE-NDE-401 UT 2007UT077 NRI Main Steam A ISI-13142-33-A 311712007 IS1 FP-PE-NDE-401 UT 2007UT078 NRI Main Steam A ISI-13142-33-A 3/17/2007 R1.20 107751 W- 7A Pipe-to-Valve PEI-02.01.O1 PT 2007PT008 NRI MS Condensate Lkoff ISI-786A 112512007 PSI R1.20 107752 W- 9A Pipe-to-Pipe PEI-02.01.O1 PT 2007PT009 NRI MS Condensate Lkoff ISI-786A 41112007 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 Owner Certificate of Authorization (If Req.): N/A Operator: Nuclear Management Company, LLC, 700 First Street, Hudson, WI 54016 Commercial Service Date: 6/30/1971 Plant: Monticello Nuclear Generating Plant, Unit 1, 2807 West County Rd #75, Monticello, MN 55362 National Board Number for Unit: NIA I Summary No. Comp ID Comp Desc.
Class 1 Category Item Procedure Method/Sheet/Results System Category RA(M), EXAMS PERFORMED FOR IS1 (4th Interval, Period 2 Credited Exams), PSI, and AUGMENTED (HELB ISUPERPIPE)
I S 0 Num Exam Date 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 AUG FP-PE-NDE-401 UT 2007UT126 NRI FP-PE-NDE-401 UT 2007UT127 GEO Core Spray B Core Spray B ISI-13142-26-A ISI-13142-26-A 3/25/2007 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 IS1 FP-PE-NDE-401 UT 2007UT137 NRI Main Steam A ISI-13142-33-A 3/27/2007 FP-PE-NDE-401 UT 2007UT133 NRI Main Steam A ISI-13142-33-A 3/27/2007 IS1 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 Owner Certificate of Authorization (If Req.): N/A Operator: Nuclear Management Company, LLC, 700 First Street, Hudson, WI 54016 Commercial Service Date: 613011971 Plant: Monticello Nuclear Generating Plant, Unit 1, 2807 West County Rd #75, Monticello, MN 55362 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 311712007 IS1 IS1 FP-PE-NDE-401 UT 2007UT022 NRI Feedwater ISI-13142-52-A 311712007 101233 W-27 Reducer-to-Pipe R1 FP-PE-NDE-401 UT 2007UT020 NRI Feedwater ISI-13142-52-A 311712007 IS1 IS1 FP-PE-NDE-401 UT 2007UT019 NRI Feedwater ISI-13142-52-A 311712007 101371 W- 6 LS U Pipe-to-Elbow R1.20 FP-PE-NDE-401 UT 2007UT088 NRI Reactor Wtr Cleanup ISI-73880-A 311812007 IS1 IS1 FP-PE-NDE-401 UT 2007UT087 NRI Reactor Wtr Cleanup ISI-73880-A 311812007 101379 W-14 LS pipe-to-pipe R1'20 FP-PE-NDE-401 UT 2007UT085 NRI Reactor Wtr Cleanup ISI-73880-A 311812007 U&D IS1 IS1 FP-PE-NDE-401 UT 2007UT086 NRI Reactor Wtr Cleanup ISI-73880-A 311812007 101380 W-15 LS U Pipe-to-Elbow R1.20 FP-PE-NDE-401 UT 2007UT084 NRI Reactor Wtr Cleanup ISI-73880-A 311812007 IS1 IS1 FP-PE-NDE-401 UT 2007UT083 NRI Reactor Wtr Cleanup ISI-73880-A 311812007 101391 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 101860 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 101997 W- LS Pipe-to-Elbow R1'20 FP-PE-NDE-402 UT 2007UT048 NRI Recirculation A ISI-97005-A 311712007 U&D IS1 IS1 FP-PE-NDE-402 UT 2007UT047 NRI RecirculationA ISI-97005-A 311712007 101998 W- LS Elbow-to-Pipe R1.20 FP-PE-NDE-402 UT 2007UT046 NRI Recirculation A ISI-97005-A 311712007 U&D IS1 IS1 FP-PE-NDE-402 UT 2007UT045 NRI Recirculation A ISI-97005-A 311712007 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 Owner Certificate of Authorization (If Req.): N/A 1 Operator: Nuclear Management Company. LLC, 700 First Street. Hudson. WI 54016 Commercial Service Date: 6/3011971 1 Plant: Monticello Nuclear Generating Plant, Unit 1, 2807 West County Rd #75, Monticello, MN 55362 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 R1'20 FP-PE-NDE-402 UT 2007UTOll NRI Recirculation A ISI-97005-A 311812007 U&D IS1 IS1 FP-PE-NDE-402 UT 2007UT012 NRI Recirculation A ISI-97005-A 311812007 R1.20 102041 W-1 I Safe End-to-Nozzle PEI-02.01.O1 PT 2007PT002 NRI Recirc Manifold A 1st-97005-B 312612007 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 II NRI Recirc Manifold B ISI-97006-B 3/22/2007 Comments: -
Limited exam less than 90% coverage Relief Request required 102211 W-14 Pipe-to-Elbow R1'20 FP-PE-NDE-401 UT 2007UT090 GEO ISI-97027-A 311812007 IS1 RHR Equalizer IS1 FP-PE-NDE-401 UT 2007UT089 GEO RHR Equalizer ISI-97027-A 311812007 IS1 FP-PE-NDE-401 UT 2007UT091 GEO RHR Equalizer ISI-97027-A 311812007 102212 W-I 5 Pipe-to-Elbow R1.20 IS1 FP-PE-NDE-401 UT 2007UT094 NRI RHR Equalizer ISI-97027-A 311812007 IS1 FP-PE-NDE-401 UT 2007UT093 GEO RHR Equalizer ISI-97027-A 311812007 IS1 FP-PE-NDE-401 UT 2007UT092 GEO RHR Equalizer 1st-97027-A 311812007 --
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 Owner Certificate of Authorization (If Req.): N/A Operator: Nuclear Management Company, LLC, 700 First Street, Hudson, WI 54016 Commercial Service Date: 6/30/1971 Plant: Monticello Nuclear Generating Plant, Unit 1, 2807 West County Rd #75, Monticello, MN 55362 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 C3.20 100815 H- 3 Strut 18 Lugs PEI-02.02.01 MT 2007MT003 NRI Containment Spray ISI-13142-37-B 313012007 IS1 C3.20 100978 H- 3 Dbl Spring 14 Lugs PEI-02.02.01 MT 2007MT002 NRI HPCI Steam ISI-13142-42-A 3/20/2007 IS1 C3.30 102753 Support' pump support PEI-02.02.01 MT 2007MT004 NRI Core Spray Pumps ISI-49 4/4/2007 Pump A IS1 C3.20 107616 H- 5 Variable I Support PEI-02.02.01 MT 2007MT001 NRI Core Spray B ISI-I3142-20-B 311812007 IS1 C3.20 107650 H- 4 Slide PEI-02.01.O1 PT 2007PT001 NRI RHR Suction B ISI-13142-17-C 4/7/2007 PSI Class 2 Category F A , EXAMS PERFORMED FOR IS1 (4th Interval, Period 2 Credited Exams) and PSI F1.20a 100098 H- I Rod 1 Clevis PEI-02.05.02 VT 2 0 0 M 0 4 0 NRI HPCl Water Side Sctn ISI-13142-17-B 3/22/2007 IS1 F1.20b 100131 H- 4 Slide PEI-02.05.02 VT 2007!ll720 NRI RHR Suction B ISI-13142-17-C 4/7/2007 PSI F1.20b 100132 H- 5 Strut I Clamp PEI-02.05.02 VT 2 0 0 M 7 2 1 NRI RHR Suction B ISI-13142-17-C 4/7/2007 PSI F1.20~
100168 H- I Spring I Clamp PEI-02.05.02 VT 2007W-750 NRI RHR Discharge B ISI-13142-18-A 3/22/2007 IS1 F1.20b 100263 H- I Snubber 1 Clamp PEI-02.05.02 VT 2 0 0 M 4 8 3 NRI HPCl Steam Disch ISI-13142-19-A 4/1/2007 PSI F1.20a 100365 H- 5 Variable I Support PEI-02.05.02 VT 2007VT027 NRI Core Spray B ISI-13142-20-B 3/18/2007 IS1 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 Owner Certificate of Authorization (If Req.): NIA Operator: Nuclear Management Company, LLC, 700 First Street, Hudson, WI 54016 Commercial Service Date: 613011971 Plant: Monticello Nuclear Generating Plant, Unit 1, 2807 West County Rd #75, Monticello, MN 55362 National Board Number for Unit: NIA Summary No. Comp ID Comp Desc. Category Item Procedure MethodISheetlResults System IS0 Num Exam Date F1.20~
100824 H- 9 Spring IClamp PEI-02.05.02 VT 2007VT456 NRI Containment Spray ISI-13142-37-B 3/29/2007 IS1 F1.20b 100879 H- 5 Snubber IClamp PEI-02.05.02 VT 2007VT749 NRI HPCl Water Side Dsch ISI-13142-40-A 4/6/2007 PSI F1.20b 100987 H-11 Snubber IClamp PEI-02.05.02 VT 2007VT015 NRI HPCl Steam ISI-13142-42-A 311612007 PSI PSI PEI-02.05.02 VT 2007VT716 NRI HPCl Steam ISI-13142-42-A 4/7/2007 F1.40a 101682 DVMX Supp DVMX pump support PEI-02.05.02 VT 2007VT008 NRI HPCl Pumps 181-8292-42A 311412007 A IS1 F1.40a 101683 DVMX DVMX pump support PEI-02.05.02 VT 2007VT005 NRI HPCl Pumps 181-8292-42A 311412007 B IS1 F1.40a 101684 DVMX Supp DVMX pump support PEI-02.05.02 VT 2007VT006 NRI HPCl Pumps ISI-8292-42A 311412007 C IS1 F1.40a 101688 DVS Supp C DVS Pump Support PEI-02.05.02 VT 2007VT007 NRI HPCl Pumps lSl-82924% 311412007 IS1 F1.40a 101689 DVS Supp D DVS Pump Support PEI-02.05.02 VT 2007VT009 NRI HPCl Pumps 181-8292-42A 311412007 IS1 F1.20b 101710 H- 9 Strut IClamp PEI-02.05.02 VT 2007VT018 NRI CRD Scram Header A ISI-93268-1A 311512007 IS1 F1.20b 101713 H-12 Snubber1 Clamp PEI-02.05.02 VT 2 0 0 M 0 1 7 NRI CRD Scram Header A ISI-93268-1A 311512007 PSI F1.20b 101715 H-14 Snubber IClamp PEI-02.05.02 VT 2007VT028 NRI CRD Scram Header A ISI-93268-1A 311912007 PSI F1.40a 102741 Pump Supp pump support PEI-02.05.02 VT 2007VT002 NRI RClC Turbine & Pump ISI-47 311412007 A IS1 F1.40a 102742 Pump Supp pump support PEI-02.05.02 VT 200NT001 NRI RClC Turbine & Pump ISI-47 311412007 B IS1 F1.40a 102743 Pump Supp pump support PEI-02.05.02 VT 2007VT004 NRI RClC Turbine & Pump ISI-47 311412007 C IS1 F1.40a 102744 Pump pump support PEI-02.05.02 VT 2007VT003 NRI RClC Turbine & Pump ISI-47 311412007 D IS1 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 Owner Certificate of Authorization (If Req.): N/A Operator: Nuclear Management Company, LLC, 700 First Street, Hudson, WI 54016 Commercial Service Date: 6/30/1971 Plant: Monticello Nuclear Generating Plant, Unit 1, 2807 West County Rd #75, Monticello, MN 55362 National Board Number for Unit: N/A Summary No. Comp ID Comp Desc. Category Item Procedure Method/Sheet/Results System IS0 Num Exam Date F1.20b Vacuum Relief & CGCS ISI-94966-A 106042 H- 2 Snubber I Clamp PEI-02.05.02 VT 2007VT708 NRI 4/6/2007 PSI Outlet Div.1 F1.20b PEI-02.05.02 VT 2007VT707 NRI Vacuum Relief & CGCS 106044 H- 4 Snubber IClamp PSI Outlet Div.I ISI-94966-A 4/6/2007 F1.20b 106810 H- I Double Snubber PEI-02.05.02 VT 2007VT719 NRI RClC Steam Discharge ISI-13142-19-B 4/5/2007 PSI PSI PEI-02.05.02 VT 2007VT718 NRI RClC Steam Discharge ISI-13142-19-8 4/5/2007 F1.20b 106820 H- I Snubber PEI-02.05.02 VT 2007VT042 NRI CORE SPRAY B ISI-13142-26-B 3/25/2007 PSI F1.20a 106825 H- 6 RESTRAINT HANGER TWH-121 PEI-02.05.02 VT 2007VT476 NRI CORE SPRAY B 181-13142-26-8 3/22/2007 IS1 F1.20a 106838 H- 9 Restraint Hanger PEI-02.05.02 VT 2007VT445 NRI Core Spray B Discharge ISI-13142-264 3/27/2007 PSI F1.20a 106881 H- 2 Restraint Hanger PEI-02.05.02 VT 2006VT001 NRI Core Spray A Discharge ISI-13142-31-D 12/19/2006 PSI F1.20a Fuel Pool Emergency 106996 H- 7 Seismic Restraint PEI-02.05.02 VT 2 0 0 M 4 7 8 NRI 181-13142-67 4/2/2007 IS1 Cooling F1.20b 107049 H- 2 Snubber PEI-02.05.02 VT 2007W711 NRI RHR A ISI-13142-37-E 4/6/2006 PSI F1.20b 107573 H- 2 Strut 18 Lugs PEI-02.05.02 VT 2007VT458 NRI Containment Spray ISI-13142-37-B 313012007 IS1 F1.20b 107574 H- 3 Strut 18 Lugs PEI-02.05.02 VT 2 0 0 M 4 5 7 NRI Containment Spray ISI-13142-37-B 313012007 IS1 F1.20~
107579 H- 3 Dbl Spring 14 Lugs PEI-02.05.02 VT 2 0 0 M 0 3 9 NRI HPCl Steam ISI-13142-42-A 312012007 IS1 F1.20a 107589 H-14 Tanksupport PEI-02.05.02 VT 2007VT010 NRI CRD Scram Header B lSl-93268-3A 311512007 IS1 F1.40a 107594 SuppOrtl pump support PEI-02.05.02 VT 2 0 0 M 6 9 9 NRI Core Spray Pumps ISI-49 4/4/2007 Pump A IS1 F1.20a 107750 H-1A SEISMIC RESTRAINT HANGER PEI-02.05.02 VT 2007W700 NRI CORE SPRAY B 181-13142-26-8 3/29/2007 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 Owner Certificate of Authorization (If Req.): N/A Operator: Nuclear Management Company, LLC, 700 First Street, Hudson, Wl 54016 Commercial Service Date: 613011971 Plant: Monticello Nuclear Generating Plant, Unit 1, 2807 West County Rd #75, Monticello, MN 55362 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 HPCl Water Side Dsch 181-1314240-8 312012007 IS1 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 IS1 FP-PE-NDE-401 UT 2007UT044 GEO HPCl Water Side Dsch ISI-13142-40-8 312012007 11 I IS1 FP-PE-NDE-401 UT 2007UT043 GEO HPCl Water Side Dsch 181-13142-40-8 312012007 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 311812007 IS1 IS1 FP-PE-NDE-401 UT 2007UT069 NRI RClC Water Suction ISI-13142-41-A 3/18/2007 Class 3 Category F A , EXAMS PERFORMED FOR IS1 (4th Interval, Period 2 Credited Exams) and PSI F1.30~
102243 SWH-304 Double Spring PEI-02.05.02 VT 2 0 0 M 4 5 5 NRI RHR Service Water nd-isi-I 02 3/29/2007 IS1 F1.30a 102244 SWH-305 Base Plate PEI-02.05.02 VT 2 0 0 M O l l NRI RHR Service Water nd-isi-I 02 311512007 IS1 F1.30a 102251 SR-396 Seismic Restraint PEI-02.05.02 VT 2007VT733 NRI RHR Service Water nd-isi-I03 411 112007 PSI F1.30b 102303 SR-385 Strut PEI-02.05.02 VT 2007Vr447 NRI RHR Service Water nd-isi-108 312812007 PSI F1.30b 102326 SR-88 Stanchion PEI-02.05.02 VT 2007VT038 NRI RHR Service Water nd-isi-111 311812007 IS1 Page 17 of 19
NIS-1 Attachment (Appendix A)
Cycle 22 Inservice Inspection Report (2007 RFO)
Owner: Xcel Energy, LLC, 800 Nicollet Mall, Minneapolis, MN 55402 Owner Certificate of Authorization (If Req.): NIA Operator: Nuclear Management Company, LLC, 700 First Street, Hudson, WI 54016 Commercial Service Date: 613011971 Plant: Monticello Nuclear Generating Plant, Unit 1, 2807 West County Rd #75, Monticello, MN 55362 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 311712007 AUG AUG FP-PE-NDE-401 UT 2007UT018 NRI RClC Feedwater NC-61-37 311712007 105010 W- 2 Pipe-to-Tee NCR95-068 FP-PE-NDE-401 UT 2007UT014 GEO RClC Feedwater NC-ISI-37 311712007 AUG AUG FP-PE-NDE-401 UT 2007UT013 NRI RClC Feedwater NC-ISI-37 311712007 10501I W- 3 ~ee-to-pipe NCR95-068 FP-PE-NDE-~OI UT 2007UT049 NRI RCIC Feedwater NC-ISI-37 311712007 AUG AUG FP-PE-NDE-401 UT 2007UT050 GEO RClC Feedwater NC-ISI-37 311712007 105012 W- 4 Tee-to-Elbow NCR95-068 FP-PE-NDE-401 UT 2007UT053 NRI RClC Feedwater NC-ISI-37 311712007 AUG AUG FP-PE-NDE-401 UT 2007UT054 GEO RClC Feedwater NC-ISI-37 311712007 105013 W-12 Pipe-to-Pipe NCR95-068 FP-PE-NDE-401 UT 2007UT055 NRI RClC Feedwater NC-ISI-37 311712007 AUG AUG FP-PE-NDE-401 UT 2007UT056 GEO RClC Feedwater NC-ISI-37 311712007 105014 W-12A Pipe-to-Tee NCR95-068 FP-PE-NDE-401 UT 2007UT052 NRI RClC Feedwater NC-ISI-37 311712007 AUG AUG FP-PE-NDE-401 UT 2007UT051 NRI RClC Feedwater NC-ISI-37 311712007 105016 W-11 Pipe-to-Tee NCR95-068 PEI-02.03.11 UT 2007UT112 NRI CRD TO RWCU NC-ISI-51 312412007 AUG I AUG AUG PEI-02.03.11 PEI-02.03.11 UT 2007UT116 NRI UT 2007UT117 GEO CRD TO RWCU CRD TO RWCU NC-ISI-51 NC-ISI-51 3/24/2007 3/24/2007 I
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 Owner Certificate of Authorization (If Req.): NIA Operator: Nuclear Management Company, LLC, 700 First Street, Hudson, WI 54016 Commercial Service Date: 6/30/1971 Plant: Monticello Nuclear Generating Plant, Unit 1, 2807 West County Rd #75, Monticello, MN 55362 National Board Number for Unit: N/A Summary No. Comp ID Comp Desc. Category Item Procedure MethodISheetlResults System IS0 Num Exam Date 105017 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 105018 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 Cycle 23 Summary Report Monticello Inservice Inspection 2007 Refueling Outage APPENDIX B Reactor Vessel I W I Examinations (7 pages to follow)
Committedto N~rcloar AREVA 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
Committedto Nuclear Core Spray Sparger - D lncore Dry Tubes Shroud Head Bolts 1 - 36
Cornmittod to Nuclear H3,V7,V8,V9, J-H1, 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,V13,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 215" 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 7001343 (DB# 14081)
> SIN 7001342 (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, PentiumTM2.4G Computer Sony DVD & WRW CD-RAN Pinnacle Graphics Card Canon MP830 Color Printer 30 G Hard Drive 110 G Hard Drive
> 2- 2 0 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.
Associated Component Indication Engineering Evaluations Steam Impingement Wear in Dryer Head in CR20000209 Areas of all Four Main Steam Nozzles Crack lndication in 325' Jacking Bolt Tack CR98000794 Weld - Unrepaired Crack lndication at the top of weld V3 90 CAP 037603 Steam Dryer Crack Indication at the top of weld VIO 90 CAP 037603 Crack Indication on Dryer Support Bracket CAP 037603 Guide weld at 215 Crack Indication at the top of weld V10 270 CAP 037603 Crack lndication in Jet Pump # I 0 vessel Side CR20000209 Tack Weld - Unrepaired Crack lndication in Jet Pump # I 4 Vessel Side SRI 94-019 Tack Weld - Repaired Crack indication in Jet Pump # I 5 Vessel Side SRI 94-01 Tack Weld - Repaired Crack indication in Jet Pump # I 8 Vessel Side SRI 94-01 Tack Weld - Repaired Crack indication in Jet Pump # I 4 Beam Bolt CR98000794 retainer Tack Weld - Unrepaired Jet Pumps Crack indication in Jet Pump #I9 Beam Bolt CR98000794 retainer Tack Weld - Unrepaired Crack lndication in Jet Pump #8 Secondary Riser Brace Lower Leaf to Block Weld in Leaf SRI-89-028 Material - Unrepaired Crack lndication in Jet Pump # I 9 Secondary Riser Brace Lower Leaf to Block Weld in Block CR20000209 Material - Unrepaired Evaluated by Small 0.25 Inch Crack lndication Extending NSP as Oxide from Arc Strike in Jet Pump #20 Diffuser Weld Layer Break DF Unrepaired (Non-Relevant)
Crack indication in 210' Shroud Support Leg Shroud Legs CR20000209 to Shroud Support Cylinder Weld - Unrepaired
Comrnttcd fo Nuclear AREVA Associated Component Indication Engineering Evaluations Crack lndication in 90' Tee Box Junction to SRI-93-006 Core Spray Header - Repaired N11A and N11B Removal of Typical Oxides from Nozzle Areas CR20000209 Nozzles Due to Steam Flashing or Other Phenomena Surveillance Sample Bent Alignment Bracket on the 30 degree CAP 038142 Holder Surveillance Sample Holder
Nuclear Management Company Cycle 23 Summary Report Monticello Inservice Inspection 2007 Refueling Outage APPENDIX C Page 1 of 2 System Pressure Test Examinations credited to Period 1 Test Number Procedure Title Date(s) Results 0255-03-IIC-1 Core Spray System Leakage Test - Loop A 12/20/05 Satisfactory 0255-03-IIC-2 Core Spray System Leakage Test - Loop B 11/16/05 Satisfactory RHR Shutdown Cooling Suction Piping System 0255-04-IE-3 5/22/06 Satisfactory Leakage Test Partial, 0255-05-IIC-1 RHR Service Water System Leakage Test - Loop A 9/9/05 Satisfactory (see note 1)
Partial, 11/3/05 Satisfactory 0255-05-IIC-2 RHR Service Water System Leakage Test - Loop B Partial, 4/21/06 Satisfactory (see note 2)
Partial, 2/26/06 Satisfactory 0255-06-IIC-1 HPCI System Leakage Test Partial 3/14/06 Satisfactory (see note 2)
Partial, 0255-1 1-1E-1 Emergency Service Water System Leakage Test - 10/5/05 Satisfactory Loop A (see note 3)
EDG-ESW System Leakage Test Loop A 0255-1 1-11C-3-1 10110105 Satisfactory Accessible Pressure Boundary Components EDG-ESW System Leakage Test Loop B 0255-11-11c-4-1 10/24/05 Satisfactory Accessible Pressure Boundary Components Note 1: Partial test, when combined with the partial test performed during Cycle 22 (3/20/2005), satisfies completion of 4thInterval, 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 Test Number Title Date(s) Results 0255-20-IIC-2 Reactor Coolant Boundary System Leakage Test 4/14/07 Satisfactory
Nuclear Management Company Cycle 23 Summary Report Monticello Inservice Inspection 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. Procedure Title Test Date Results 0 137-04 Primary Containment Purge and Vacuum Breaker, 411 1/07 SAT (0255-10-IIB-1) Pressure and Isolation Valve LLRT Test Sec XI Boundary 0137-05 Primary Containment Nitrogen Control and 313 1/07 SAT (0255-~o-IIB-~) Sampling System Valves Pressure and Local Leak Sec XI Boundary Rate Test 0137-18 Instrument Air System Isolation Valves Pressure 3/27/07 SAT (0255-17-IIB-1) And Local Leak Rate Test Sec XI Boundary 0137-19 Service Air System Isolation Valve Pressure and 3/22/07 SAT (0255-17-IIB-2) Local Leak Rate Test Sec XI Boundary 0137-22 Demineralized Water Supply to Drywell Isolation 4/10/07 SAT (0255-26-IIB- 1) Valve Pressure and Leak Rate Test Sec XI Boundary 0 137-24 Primary Containment Vent and Hard Pipe Vent 4/13/07 SAT (0255-10-IIB-3) Local Leak Rate Test Sec XI Boundary 0137-27 TIP System Isolation Valves and Local Leak Rate 3/16/07 SAT
( 0255-18-IIB-1) Test Sec XI Boundary 0137-30 Alternate N2 Supply Pressure and Local Leak Rate 3/24/07 SAT (0255-17-IIB-3) Test Sec XI Boundary 0137-3 1 RBCCW System Isolation Valve Pressure and 3/26/07 SAT (0255-13-IIB-1) Local Leak Rate Test Sec XI Boundary 0138 Drywell Personnel Airlock Pressure and Leak Test 4115/07 SAT (0255-10-IIB-4) Sec XI Boundary
Nuclear Management Company Cycle 23 Summary Report Monticello Inservice Inspection 2007 Refueling Outage APPENDIX D 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. Snubber Location Size Work Order No. Snubber Test Results Serial No.
1 SS-707 3 141349 700 Passed 2 SS-357 130 141350 400 Passed 3 CRD-H210 3 141351 538 Passed 4 SS-14 10 141353 500 Passed 5 SS-184 10 141354 040 Passed 6 SS-3 16 10 141355 035 Passed 7 SS-13 10 141356 171 Passed 8 SS-38B 10 141359 033 Passed 9 CRD-H227 20 141366 099 Passed 10 CRD-H232 20 141371 214 Passed 11 RV-25-NS2 30 141373 020 Passed 12 SS-2AR 30 141375 005 Passed 13 SS3AR 30 141378 145 Passed 14 SS-20 10 141382 539 Passed 15 RV-25A-H2A 20 153475 478 Passed 16 RV-24-H5 20 153475 016 Passed
Nuclear Management Company Cycle 23 Summary Report Monticello Inservice Inspection 2007 Refueling Outage APPENDIX E Engineering Evaluations per Subsection IWE-3122.4 (1992 Edition with 1992 Addenda) and 10CFR50.55a(b)(2)(ix)(D)
- 1. CAP CE 01082766-03 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)
4112107 and 6115107 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),
10CFR50.55a(b)(2)(ix)(D), and to satisfy the requirements of Fleet procedure FP-PA-ARP-01, CAP Action Request Process. Procedure FP-PA-ARP-01, 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 6115/07 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- 12-4621) 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:
Description of Region Thinning area Thinning depth diameter (inches) (inches)
Torus upper clean shell region 12 0.2 1 Torus lower clean shell region 13 0.23 Torus upper shell region near discontinuities 15 0.07 Torus lower shell region near discontinuities 16 0.09 Downcomer clear region 1.25 0.17 Downcomer region near discontinuities 2.5 0.08 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. 11 (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 E l .20 (VT-3 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.
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 0291852 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 0135 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 01348 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 6115/07 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 1 Upper Shell Plate 0.533" 0.579" 1 Lower Shell Plate 0.584" 0.618"/0.578"/ 0.618" I 1 I Downcomers I 0.250" 1
0.250"/0.268/ 0.254"/0.284" 2 Upper Shell Plate 0.533" 0.617" 2 Lower Shell Plate 0.584" 0.655"/0.593"/ 0.584" 2 Downcomers 0.250" 0.256"/0.251"/ 0.246"/0.277" 3 Upper Shell Plate 0.533" 0.574" 3 Lower Shell Plate 0.584" 0.633"/0.629" I 3 I Downcomers I -
0.250"-
1 0.296"/0.256"/ 0.279"/0.278" I Upper Shell Plate 1 0.533" I 4 I Lower Shell Plate I 0.584" 1 0.63 1"/0.669"/ 0.628" 4 Downcomers 0.250" 0.340"/0.256"/ 0.248"/0.267" 5 Upper Shell Plate 0.533" 0.602" I 5 I Lower Shell Plate I 0.584" I 0.606"/0.576" -
5 Downcomers 0.250" 0.285"/0.293"/ 0.3 12"/0.302" 6 Upper Shell Plate 0.533" 0.572" 1 6 ( Lower Shell Plate 1 0.584" ( 0.582"/0.632"/ 0.623"/0.592" 6 Downcomers 0.250" 0.290"/0.324"/ 0.301"/0.270" 7 Upper Shell Plate 0.533" 0.562" 7 Lower Shell Plate 0.584" 0.618"/0.596"/ 0.625"/0.640" 7 Downcomers 0.250" 0.298"/0.297"/ 0.346"/0.298" 8 Upper Shell Plate 0.533" 0.578" 8 Lower Shell Plate 0.584" 0.604"/0.606"/ 0.593"/0.619" 8 Downcomers 0.250" 0.287"/0.260"/ 0.265"/0.274" 9 Upper Shell Plate 0.533" 0.626" 9 Lower Shell Plate 0.584" 0.590"/ 0.607" 9 Downcomers 0.250" 0.258"/0.295"/ 0.292"/0.265" I 10 I Upper Shell Plate I 0.533" I 0.586" 10 Lower Shell Plate 0.584" 0.604"/0.675" 10 Downcomers 0.250" 0.26lY'/0.314"/ 0.257"/0.307" 11 Upper Shell Plate 0.533" 0.579" 11 Lower Shell Plate 0.584" 0.652"/0.681" Page 5 of 10
4/12/07 and 6/15/07 Condition Evaluation Page 6 of 10 11 Downcomers 0.250" 0.298"/0.335"/ 0.271"/0.357" 12 Upper Shell Plate 0.533" 0.554" 12 Lower Shell Plate 0.584" 0.581"/0.61 I"/ 0.709"/0.646" 12 Downcomers 0.250" 0.298"/0.330"/ 0.308"/0.256" 13 Upper Shell Plate 0.533" 0.606" 13 Lower Shell Plate 0.584" 0.638"/0.600"/ 0.622"/0.605" 13 Downcomers 0.250" O.279"/0.29Oy'/ 0.248"/0.27lY' 14 Upper Shell Plate 0.533" 0.562" 14 Lower Shell Plate 0.584" 0.7 18"/0.620"/ 0.645" 14 Downcomers 0.250" 0.285"/0.294"/ 0.269"/0.273" 15 Upper Shell Plate 0.533" 0.574" 15 Lower Shell Plate 0.584" 0.630"/0.750" 15 Downcomers 0.250" 0.273"/0.295"/ 0.257"/0.2717' 16 Upper Shell Plate 0.533" 0.589" 16 Lower Shell Plate 0.584" 0.63 1"/0.622"/ 0.601"/0.649" 16 Downcomers 0.250" 0.269"/0.288"/ 0.279"/0.245" 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 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.
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.
Page 6 of 10
4112/07 and 6/15/07 Condition Evaluation Page 7 of 10 Table 2 Inspection As-Found As-Left Coating Degraded Degraded repaired coatings (ft2) coatings (ft2) (ft2) 0 135, PRESSURE SUPPRESSION CHAMBER 365.8 88.4 277.4 PAINTED SURFACE INTERNAL INSPECTION (Note 2) 1367, PRESSURE-SUPPRESSION CHAMBER 453.76 213.49 240.27 BELOW WATER LINE PAINTED SURFACE INTERNAL INSPECTION (Note 2) 0140, DRYWELL INTERIOR SURFACE 96 61 35 INSPECTION (Note 2) 05 15, PRIMARY CONTAINMENT VISUAL Note 1 Note 1 EXAMINATION FOR STRUCTURAL PROBLEMS Totals 915.56 362.89 552.67 Note 1: Degraded coatings were documented in procedures 0 135,O140 and 1367.
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 ft2of coating chips assumed in Calculation CA-0 1- 135. 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 ft2administrative 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.
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.
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 0135, 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 ft2may 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 10CFR50.55a(b)(2)(ix)(D).
4/12/07 and 6/15/07 Condition Evaluation Page 9 of I 0 Actions:
Repairs of the suppression chamber and drywell coatings during the 2007 refueling outage were conducted under work orders 0 1348 19 and 29 1852 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 134819, REPAIR TORUS INTERNAL COATINGS.
- 6. Work Order 00291852, DRYWELL COATING REPAIR
- 7. Calculation -CA-01-156, ADD 0; IWE Recording Criteria. Approved 11113/01.
- 8. CAPS 691537,625896,634151,636491, and 819170
- 9. Calculation - AES calculation number MN02-PO17471-100; Rev. 0 Determination of Torus Pitting Acceptance Criteria. Dated 04/25/03.
- 10. Calculation - AES calculation number MN02-PO17471-200; 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, 5116/91 (Appendix 2 to 611719 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 1-135, Evaluation of Effect of Paint Chips on Debris Loading of ECCS Suction Strainers.
- 23. Calculation CA-0 1- 177, 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 S W 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 S W 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 0135 CE-01082766-03 Attachment Embedded Attachment 2 Page 1 of 8 COMMENTS Area Loose FT2 YIN BAY 1:
1 2
3 4 1 2 N 5 Ring girder at top of torus patches of rust bleed through 0.5 N 6
7 Monorail and it's supports has small patches of rust. 0.1 N Total degraded coatings: 2.6 Total loose coatings: 0 Area Loose FT2 YIN BAY 2:
1 2
3 4 1 1 . 5 .- N 5 Ring girder at top of torus patches of rust bleed through 0.5 N 6
7 Monorail and it's supports has small patches of rust. 0.1 N 8 Vent header has small patches of rust bleed through 2 N 9 Air temperature penetration heavily rusted 0.1 N Total degraded coatings: 4.2 Total loose coatings: 0
1 AS-LEFT 4-8-2007 CE-01082766-03 0135 Attachment Embedded Attachment 2 Page 2 of 8 Area Loose FT2 YIN BAY 3:
1 2
3 4 Top of torus, patches of rust bleed through. 10 N 5 Back wall center, patches of rust bleed through 3 N 6 Air temperature penetration heavily rusted. 0.1 N 7 Monorail and it's supports has small patches of rust. 0.1 N 8
Total degraded coatings: 13.2 Total loose coatings: 0 Area Loose FT2 YIN 1 BAY I 1 I 4:
I I I 4 Top of torus, patches of rust bleed through. 5 N 5 Top half of torus- peeling coating 1 Y 6 Torus manway cover and access many chipped spots 0.8 N 7 Monorail and it's suvvorts has small patches of rust. 0.1 N Total degraded coatings: 6.9 Total loose coatings: 1 1
AS-LEFT 4-8-2007 0135 CE-01082766-03 Attachment Embedded Attachment 2 Page 3 of 8 Area Loose FT2 YIN BAY 5:
1 2
3 4 Top of torus, and girders patches of rust bleed through. 5 N 5
6 Vent header has small patches of rust bleed through 0.5 N 7 Monorail and it's suw~ortshas small watches of rust. 0.1 N Total degraded coatings: 5.6 Total loose coatings: 0 Area Loose FT2 YIN BAY 6:
1 2
3 4 Top of torus, patches of rust bleed through. 1.5 N 5 Ring girders at top of torus patches of rust bleed through 0.5 N 6
7 Monorail and it's supports has small patches of rust. 0.1 N 8
9 Air temperature penetration, HPCI vent line & penetration heavily 2 N rusted 10.
11 Total degraded coatings: 4.1 Total loose coatings: 0
AS-LEFT 4-8-2007 0135 CE-0 1082766-03 Attachment Embedded Attachment 2 Page 4 of 8 Area Loose FT2 YIN BAY 7:
1 2
3 4 Top of torus, patches of rust bleed through around penetration. 6 N 5 Ring girders at top of torus patches of rust bleed through 1 N 6
7 Monorail and it's supports has small patches of rust. 0.1 N
-8 Vent header, has small patches of rust bleed through 4 N 9 Air temperature penetration, HPCI vent line & penetration heavily 2 N rusted Total degraded coatings: 13.1 Total loose coatings: 0 Area Loose FT2 YIN BAY 8:
1 2
3 Air temperature penetration heavily rusted. 0.2 N 5 Ring girders at top of torus patches of rust bleed through 0.5 N 6
7 Monorail and it's supports has small patches of rust. 0.1 N 8 Vent header, at support has small patches of loose coating 1 Y 9 Air temperature penetration heavily rusted 0.2 N 10 Total degraded coatings: 5 Total loose coatings: 1
AS-LEFT 4-8-2007 0135 CE-0 1082766-03 Attachment Embedded Attachment 2 Page5of 8 Area Loose FT2 YIN BAY 9:
1 2
3 4 Top of torus, patches of rust bleed through. 1 N 5 Ring girders at top of torus patches of rust bleed through 0.5 N 6
7 Monorail and it's supports has small patches of rust. 0.1 N 8 Vent header, at support has small patches of rust bleed through 0.2 N Total degraded coatings: 1.8 Total loose coatings: 0 Area Loose FT2 YIN BAY 10:
1 2
3 4 Top of torus, patches of rust bleed through. 1 N 5 Ring girders at top of torus patches of rust bleed through 0.5 N 6 Vent header has small patches of rust bleed through 0.1 N 7 Monorail and it's supports has small patches of rust. 0.1 N 8 Vent header, at support has small patches of rust bleed through 0.2 N 9 Air temperature penetration heavily rusted. 0.2 N Total degraded coatings: 2.1 Total loose coatings: 0
AS-LEFT 4-8-2007 0135 CE-0 1082766-03 Attachment Embedded Attachment 2 Page 6 of 8 Area Loose FT2 YIN BAY 11:
1 2
3 4 1 -1 - N 5 Ring girders has patches of rust. 0.5 N 6 Vent header supports has small patches of rust bleed through 0.1 N 7 Monorail and it's supports has small patches of rust. 0.1 N 8 Vent header, has small patches of rust bleed through 1 N 9 -
- Air temperature penetration heavily rusted. 0.2 N Total degraded coatings: 2.9 Total loose coatings: 0 Area Loose FT2 YlN BAY 12:
1 2
3
- Top of torus, patches of loose coatings.
4 2 Y 5 Tog of torus, light rusting
- 1 N 6 Vent header has small patches of rust bleed through 0.1 N 7 Monorail and it's supports has small patches of rust. 0.1 N 8
9 Toms manway cover and access many chipped spots 0.8 N 10 Total degraded coatings: 4 Total loose coatings: 2
AS-LEFT 4-8-2007 0135 CE-0 1082766-03 Attachment Embedded Attachment 2 Page 7 of 8 Area Loose FT2 YIN BAY 13:
1 2
3 4 Top of torus, patches of rust bleed through 3 N 5 Ring girders has patches of rust. 0.5 N 6 Vent header has small patches of rust bleed through 0.5 N 7 Monorail and it's supports has small patches of rust. 0.1 N 8
Total degraded coatings: 4.1 Total loose coatings: 0 Area Loose FT2 YIN BAY 14:
1 2
3 Top half of torus ring girdter has patches of rust bleed through 0.5 N 4 Top of torus, patches of rust bleed through 8 N 5 Torus spray line has patches of rust. 0.5 N 6 Vent header, has small patches of rust bleed through 0.2 N 7 Monorail and it's supports has small patches of rust. 0.1 N Total degraded coatings: 9.3 Total loose coatings: 0
AS-LEFT 4-8-2007 0135 CE-01082766-03 Attachment Embedded Attachment 2 Page 8 of 8 Area Loose FT2 YIN BAY 15:
3 4 Top of torus, patches of rust bleed through 5 N 5 Ring girders has patches of rust. 1 N 6 Vent header, has small patches of rust bleed through 0.2 N 7 Monorail and it's s u ~ ~ o rhas t s small ~atchesof rust. 0.1 N Total degraded coatings: 6.3 1 Total loose coatings: 10 Area Loose FT2 YIN BAY 16:
1 2
3 4
5 Vent header gusset at top has patches of rust. 1 N 6 Vent header, has small patches of rust bleed through 0.2 N 7 Monorail and it's supports has small patches of rust. 0.1 N 8
9 10 Air temperature penetration heavily rusted. 0.2 N Total degraded coatings: 3.5 Total loose coatings: 0 TOTALS OF ALL BAYS As-Left Bay 1 through Bay 16 Total degraded coatings: (365.8 as-found) 88.4 Bay 1 through Bay 16 Total loose coatings: (14.0 as-found) 4.0
AS-LEFT 1367 Attachment CE-0 1082766 Page 1 of 8 Embedded Attachment 3 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:
1 2
3 4
5 6
7 Downcomer-ID- 40 spots weld damaged coating inch2 + 5-ft2 15 N 8 Downcomer-OD- 6 spots of degraded coating- Totaling-1-ft2 1 N 9 Downcomer-OD- 2 spots of degraded coating- Totaling-0.4-ft2 0.4 Y 10 Total degraded coatings: 16.4 Total loose coatings: 0.4 Area Loose FT2 YIN BAY 2:
I1 I I 9 Ring Girder - 16 small rust spots -112-inch square 0.02 Y 10 Downcomer-ID- 20 spots weld damaged coating inch2+ 4-ft2 9 N 11 Downcomer-OD- 3 spots of degraded coating- Totaling-0.23-ft2 0.23 N 12 Total degraded coatings: 9.25 Total loose coatings: 0.02
AS-LEFT 1367 Attachment CE-0 1082766 Page 2 of 8 Embedded Attachment 3 Area Loose FT2 YIN BAY 3:
1 2
3 4
5 6 Downcomer-ID- 40 spots weld damaged coating inch2 + 5.5-ft2 15.5 N 7 Downcomer-OD- 5 spots of degraded coating- Totaling-1-ft2 0.23 N 8 Downcomer-OD- 1 spots of degraded coating- Totaling-0.06-ft2 0.06 Y 9
10 Total degraded coatings: 15.79 Total loose coatings: 0.06 Area Loose FT2 YIN BAY 4:
11 1 4 Downcomer-ID- 20 spots weld damaged coating inchZ+ 2-ftz 7 N 5 Downcomer-OD- 3 spots of degraded coating- Totaling- 0.13-ftz 0.13 N Total degraded coatings: 7.13 Total loose coatings: 0
AS-LEFT 1367 Attachment CE-0 1082766 Page 3 of 8 Embedded Attachment 3 Area Loose FT2 YIN BAY 5:
1 2
3 4
5 Downcomer-ID- 40 spots weld damaged coating inch2+ 12-ft2 22 N 6 Downcomer-OD- 10 spots of degraded coating- Totaling-4.45-ft2 4.45 N 7 Downcomer-OD- 3 spots of degraded coating- Totaling- 3.25-ft2 3.25 Y 8
9 10 Total degraded coatings: 29.7 Total loose coatings: 3.25 Area Loose FT2 YIN BAY 6:
8 9 Downcomer-ID- 20 spots weld damaged coating inch2 5 N 10 Downcomer-OD- 3 spots of degraded coating- Totaling-2.17-ft2 2.17 Y I I 1 Total degraded coatings:
I 1 7.17 I
I Total loose coatings: 12.17
AS-LEFT 1367 Attachment CE-0 1082766 Page 4 of 8 Embedded Attachment 3 Area Loose FT2 YIN BAY 7:
1 2
3 4
5 6
7 Downcomer-ID- 40 spots weld damaged coating inch2+4-ft2 10 N 8 Downcomer-OD- 7 spots of degraded coating- Totaling-2.34-ft2 2.34 N 9 Downcomer-OD- 2 spots of degraded coating- Totaling- 7.02-ft2 7.02 Y 10 Downcomer-ID- 5 spots of degraded coating-Totaling 1-ft2 1 Y Total degraded coatings: 20.36 Total loose coatings: 8.02 Area Loose FT2 YIN BAY 8:
1 2
3 4
5 6
7 Downcomer-ID- 20 spots weld damaged coating inch2 +2-ft2 7 N 8 Downcomer-OD- 3 spots of degraded coating- Totaling-0.067-fi2 0.07 N 9 Downcomer-OD- 4 spots of degraded coating- Totaling- 9.1 -ft2 9.1 Y 10 Downcomer-ID- 1 spots of degraded coating-Totaling 2-ft2 2 Y Total degraded coatings: 18.17 Total loose coatings: 11.1
AS-LEFT 1367 Attachment CE-0 1082766 Page 5 of 8 Embedded Attachment 3 Area Loose FT2 YIN BAY 9:
1 2
3 4
5 6
7 8
9 10 Downcomer-ID- 40 spots weld damaged coating inch2 10 N 11 Downcomer-OD- 3 spots of degraded coating- Totaling-0.095-ft2 0.1 N 12 Downcomer-OD- 4 spots of degraded coating- Totaling- 0.187-ft2 0.19 Y Total degraded coatings: 10.3 Total loose coatings: 0.19 Area Loose FT2 YlN BAY 10:
9 1 Downcomer-ID- 20 mots weld damaged coating inch2+0.5-ft2 1 5.5 IN 10 Downcomer-OD- 3 spots of degraded coating- Totaling-0.17-ft2 0.17 N 11 Downcomer-OD- 3 mots of degraded coating- Totaling- 0.077-ft2 0.08 Y Total degraded coatings: 5.75 I Total loose coatings: 1 0.08
AS-LEFT 1367 Attachment CE-01082766 Page 6 of 8 Embedded Attachment 3 Area Loose FT2 YIN BAY 11:
10 Downcomer-ID- 40 spots weld damaged coating inch2+0.2-ft2 10.2 N 11 Downcomer-OD- 6 spots of degraded coating- Totaling-0.83-ftz 0.83 N 12 Downcomer-OD- 4 spots of degraded coating- Totaling- 3.06-fY 3.06 Y I I I 1 Total degraded coatings: 1 11.85 I Total loose coatings: 1 3.06 Area Loose FT2 YIN BAY 12:
I1 I 9
10 Downcomer-ID- 20 mots weld damaged coating- 6-inch2+0.36-ftz 5.36 N 11 Downcomer-OD- 3 spots of degraded coating- Totaling-0.292-ft2 0.3 N 12 Downcomer-OD- 4 mots of demaded coating- Totaling- 10-ft2 10 Y Total degraded coatings: 15.66 I Total loose coatings: 1 10
AS-LEFT 1367 Attachment CE-0 1082766 Page 7 of 8 Embedded Attachment 3 Area Loose FT2 YIN BAY 13:
1 2
3 4
5 6
7 8
9 Downcomer-ID- 4 spots weld 0 damaged6 coating- - inchZ 10 N 10 Downcomer-OD- 8 spots of degraded coating- Totaling- 6.4-ft2 0.1 N 11 Downcomer-OD- 3 spots of degraded coating- Totaling- 0.47-ft2 0.47 Y Total degraded coatings: 10.57 Total loose coatings: 0.47 Area Loose l?T2 YIN BAY 14:
I1 I I 9
10 Downcomer-ID- 2 spots weld0 damaged6coating- - inchZ 5 N 11 Downcomer-OD- 4 spots of degraded coating- Totaling-0.165-fi2 0.17 N 12 Downcomer-OD- 4 spots of degraded coating- Totaling- 0.567-ft2 0.57 Y 13 Downcomer-ID- 1 spots of degraded coating-Totaling 3-ftz 3 Y Total degraded coatings: 8.74 Total loose coatings: 3.57
AS-LEFT 1367 Attachment CE-01082766 Page 8 of 8 Embedded Attachment 3 Area Loose FT2 YIN BAY 15:
1 2
3 4
5 6
7 8 Downcomer-ID- 40 spots weld damaged coating inch2+2-ft2 12 N 9 Downcomer-OD- 7 spots of degraded coating- Totaling-4.6-ft2 4.6 N 10 Downcomer-OD- 4 spots of degraded coating- Totaling- 3.1 5-ft2 3.15 Y Total degraded coatings: 19.75 Total loose coatings: 3.15 Area Loose FT2 YIN BAY 16:
1 2
3 9
10 Downcomer-ID- 20 spots weld damaged coating inch2 5 N 11 Downcomer-OD- 4 spots of degraded coating- Totaling-2.88-ft2 2.9 N Total degraded coatings: 7.9 Total loose coatings: 0 TOTALS OF ALL BAYS for 1367 Bay 1 through Bay 16 Total degraded coatings: 213.49 Bay 1 through Bay 16 Total loose coatings: 45.54
Nuclear Management Company Cycle 23 Summary Report Monticello Inservice Inspection 2007 Refueling Outage APPENDIX E (continued)
Engineering Evaluations per Subsection IWE-3122.4 (1992 Edition with 1992 Addenda) and 10CFR50.55a(b)(2)(ix)
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. 10CFR50.55a 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-3410-1, 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.
Arc Strikes.doc J:\Prge\MIR\ISI\Summary Reports\lS1~2007-RFO~Cycle-23\Miscellaneous\ce~0l084149~Torus 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