L-PI-12-077, Inservice Inspection Summary Report, Interval 4, Period 3, Outage 1, Refueling Outage Dates: 02-21-2012 to 05-29-2012 U2, Fuel Cycle 26: 05-26-2010 to 05-29-2012
| ML12237A168 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 08/23/2012 |
| From: | Molden J Northern States Power Co, Xcel Energy |
| To: | Office of Nuclear Reactor Regulation, Document Control Desk |
| References | |
| L-PI-12-077 | |
| Download: ML12237A168 (109) | |
Text
{{#Wiki_filter:@ Xcel Energym L-PI-12-077 10 CFR 50.55a U S Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Prairie Island Nuclear Generating Plant Unit 2 Docket 50-306 Renewed License No. DPR-60 lnservice Inspection Summaw Report, Interval 4, Period 3, Outage 1, Refueling Outage Dates: 02-21-2012 to 05-29-2012 Unit 2, Fuel Cvcle 26: 05-26-2010 to 05-29-2012 During the 2012 Prairie Island Nuclear Generating Plant (PINGP) Unit 2 refueling outage, an inservice inspection (ISI) examination for the third period of the fourth interval was conducted. Enclosure 1 is a copy of the IS1 examination summary report for this period. The summary report is being submitted in accordance with the PINGP American Society of Mechanical Engineers (ASME) Code Section XI IS1 Program and is intended to satisfy the inspection reporting requirements contained in IWA-6230 of the ASME Boiler and Pressure Vessel Code. The report identifies components examined; the examination methods used; the examination number; and summarizes the results. All anomalies were either corrected or an engineering evaluation was performed to accept "as-is" conditions. A description of repairlreplacement activities and the corresponding work order numbers are provided in Section 8 of the enclosure. Summaw of Commitments This letter contains no new commitments and no revisions to existing commitments. James E. Molden VSite Vice President, Prairie Island Nuclear Generating Plant Northern States Power Company - Minnesota Enclosure 1717 Wakonade Drive East Welch, Minnesota 55089-9642 Telephone: 651.388.1121
Document Control Desk Page 2 cc: Administrator, Region Ill, USNRC Project Manager, PINGP, USNRC Resident Inspector, PINGP, USNRC Chief Boiler Inspector, State of Minnesota
ENCLOSURE 1 lnservice Inspection Summary Report, Interval 4, Period 3, Outage 1, Refueling Outage Dates: 02-21-2012 to 05-29-2012 Unit 2, Fuel Cycle 26: 05-26-2010 to 05-29-2012 106 Pages Follow
NSPM PRAENE ISLAND NUCLEAR GENERATING PLANT 1717 WAICONADE DRIVE EAST WELCH, MINNESOTA 55089 INSERVICE INSPECTION
SUMMARY
REPORT INTERVAL 4, PERIOD 3, OUTAGE 1 REFUELING OUTAGE DATES: 02-21-2012 TO 05-29-2012 UNIT 2, FUEL CYCLE 26: 05-26-2010 TO 05-29-2012 COMMERCIAL SERVICE DATE: DECEMBER 21,1974 d Prepared by: /,I& -- S1 Pro'gram Engineer, Pratrle Island
- Date: 8//7/2ul.l
/
Tom Downing Reviewed by: Date: $' 3 -20 - l-;h Ron Clow Reviewed by: Date: - 20 *- ( c Reviewed by: Tfcgrarn bngineer~ngSuperv~sor,Yra~rlelsland Date: [7&b9 V Approved by: Date: 8*26- W / Z Dave Potter
NSPM INSERVICE INSPECTION PRAIRIE ISLAND UNIT 2 CYCLE 26
SUMMARY
REPORT Table of Contents Number of Panes Section 1. Discussion 2 Section 2. Form NIS-1, Owner's Report for Inservice Inspection 3 Section 3. IS1 Examinations 14 Section 4. IWE Examinations Section 5. Pressure Tests Section 6. Snubber Inservice Testing and Preservice Examinations 1 Section 7. Steam Generator Eddy Current Examination Results 1 Section 8. RepairReplacement Activities for Fuel Cycle 26 74
NSPM INSERVICE INSPECTION PRAIRIE ISLAND UNIT 2 CYCLE 26
SUMMARY
REPORT Section 1. Discussion
1.0 INTRODUCTION
This summary report identifies the components examined, the examination methods used, the examination number and summarizes the results of examinations performed during the 3rdperiod of the 4th interval, unit 2 fuel cycle 26. The 4th inspection interval is based on the examination requirements of the ASME Boiler and Pressure Vessel Code Section XI, 1998 Edition with 2000 Addenda within the limitations and modifications required by Title 10 of the Code of Federal Regulation, Part 50.55a. 2.0 PERSONNEL Visual and nondestructive examinations were performed by Xcel Energy Company and Lambert Macgill & Thomas (LMT). The Hastford Steam Boiler Inspection and Insurance Company of Connecticut provided the Authorized Inspection services. Examination personnel certifications are maintained on file by Xcel Energy Company. 3.0 INSPECTION
SUMMARY
Examination results indicate that plant system's integrity has been maintained. Section 3 contains the Class 1 and 2 components examined, the examination number and summary of the examination results performed during unit 2 cycle 26. The number and percentage of scheduled examinations or tests completed are also included in this section as required by IWA-6220(f). There were no Class 1 or 2 examinations with indications requiring scope expansion or repairlreplacernent. There was one limited volumetric examination (AR 1343795) of a class 1 valve to reducer weld limited by geometry. A Relief request will be submitted for the limitation as required by 10 CFR 50.55a(g)(5)(iv). Section 4 contains the Class MC components examined, the examination number and summary of the examination results performed during unit 2 cycle 26. The second IWE interval, September 10,2008 through September 9,2018, is based on the examination requirements of the 2001 Edition with 2003 Addenda of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code Section XI with limitations and modifications as required by Title 10 of the Code of Federal Regulation, Part 50.55a. The number and percentage of examinations or tests completed are also included in this section as required by IWA-6220(f). There were no indications that required repairlreplacement or successive inspections under IWE-2420. This section includes an evaluation of inaccessible areas as required by 10CFR50.55a(b)(2)(ix)(A) to
address indication of refueling cavity leakage in contact with the steel containment vessel (AR1332452). Section 5 contains a summary of pressure tests completed or initiated during the cycle including pressure tests completed since the last 90 day summary repoi?, but before the end of the preceding period. All indications of leakage were evaluated and/or coi~ective measures perfoimed as required by IWA-5250, IWB-3 142 and IWC-3 132. Section 6 contains the Snubber inspection results. There were no visual snubber failures. All snubbers that under went functional testing had satisfactory results. Section 7 addresses the Eddy Current examination results of the 21 and 22 Steam Generators tubes. Section 8 contains 36 RepairIReplacemel~tactivities completed in the 4th Inteival unit 2 cycle 26. 4.0 EXAMINATON REPORTS, EQUIPMENT AND MATERIALS The inselvice inspection reports in Sections 3 and 4 contain references to procedures, equipment, and inaterials used to complete the specific examinations. Copies of the examination reposts, examination procedures, and equipment records are available fiom Xcel Energy Company. Sections 3 and 4 may contain several abbreviations which are identified below: CAP = Coi-rective Action Process CE = Condition Evaluation GEO = Geometry, evaluation of indication OPR = Operability Recommendation IN = Infonnation Notice IND = Indication requires further evaluation NAD = No Apparent Defects SE = Safety Evaluatioil WO = Worlc Order WR = Worlc Request
NSPM INSERVICE INSPECTION PRAIRlE ISLAND UNIT 2 CYCLE 26
SUMMARY
REPORT Section 2. NIS- 1 (2 pages attached)
NIS-I OWNER'S REPORT FOR INSERVICE INSPECTIONS (As required by the Provisions of the ASME Code Rules) I. Owner: NSPM d/b/a Xcel Enerqv, 414 Nicollet Mall, Minneapolis, Minnesota 55401 (Name and Address of Owner)
- 2. Plant Prairie Island Nuclear Generating Plant, 1717 Wakonade Drive E, Welch, Minnesota 55089 (Name and Address of Plant)
- 3. Plant Unit 2
- 4. Owner Certificate of Authorization (if required) N/A
- 5. Commercial Service Date 12/21/ I 974
- 6. National Board Number for Unit N/A
- 7. Components Inspected Component or Manufacturer or Manufacturer of State or National Board Appurtenance Installer Installer Serial No. Province No. No.
Reactor Vessel Head Mitsubishi Heavy Inds. --- --- --- Reactor Vessel Creuot-Loire 687 MINN-200-51 --- Pressurizer Westinghouse 1191 --- 68-57 21 Steam Generator Westinghouse 1181 --- 68-39 22 Steam Generator Framatome ANP 1182 --- 68-40 21 Reactor Coolant Pump Westinghouse W510 --- --- 22 Reactor Coolant Pump Westinghouse W515 --- --- 21 RHR Heat Exchanger 1 Joseph Oats & Sons I 1817-1C ( ___ 1 342 22 RHR Heat Exchanger Joseph Oats & Sons 1817-1D --- 343 21 RHR Pump Byron Jackson --- --- --- 22 RHR Pump Byron Jackson --- --- --- 21 Safety Injection Pump Bingham --- --- --- 22 Safety Injection Pump Bingham --- --- --- 21 Accumulator Tank Delta Southern 41037-68-1 --- 2575 22 Accumulator Tank Delta Southern 41037-69-1 --- 2576 Unit 2 Containment Chicago Bridge & Iron --- --- ---
- 8. Examination Dates: 05/26/2010 to 05/29/2012
- 9. Inspection Period Identification: (3rd Period) 12/2112011 to 12/20/20 14
- 10. Inspection Interval Identification: (4th Interval) 12/21/2004 to 12/20/20 14
- 11. Applicable Edition of Section XI: 1998 Edition with 2000 Addenda (2001 Edition, 2003 Addenda IWE)
- 12. DateIRevision of lnspection Plan: 4/28/12, Revision 11
- 13. Abstract of Examination and Tests. Include a list of examinations and tests and statement concerning status of work required for the lnspection Plan See Sections 3 through 7
- 14. Abstract of Results of Examinations and Tests See Sections 3 through 7
- 15. Abstract of Corrective Measures See Sections 3 through 6 We certify that a) that the statements made in this report are correct, b) the examinations and tests meet the lnspection Plan as required by the ASME Code, Section XI, and c) corrective measures taken conform to the rules of the ASME Code, Section XI.
Certificate of Authorization No. (if applicable) N/A ExpirationDate Date Signed BY Tom Downing CERTIFICATE OF INSERVICE INSPECTION I, undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or 1 provinces of
-Minnesota and employed by H a r t f o r d Steam Boiler lnspection and Insurance Company- of -Connecticut have inspected the components described in this Owner's Report during the period 05/26/2010 to 05/29/2012 , and state that to the best of my knowledge and belief, the Owner has performed examinations and tests and taken corrective measures described in this Owner's Report in accordance with the inspection plan and as required by the ASME Code, Section XI.
By signing this certificate neither the Inspector nor his employer makes and any warranty, expressed or implied, concerning the examinations, tests, and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or loss of any kind arising from or connected with this inspection. Commissions I b ~ m*l~ dl924 3 National Board, State, Province, and Endorsements Date: 20 Ao& ft
NSPM INSERVICE INSPECTION PRAIRIE ISLAND UNIT 2 CYCLE 26
SUMMARY
REPORT Section 3. IS1 Examinations (13 pages attached) The followi~lgtable suinrnarizes the IS1 inspections performed in cycle 26. hispectioas are listed by class, category and site surnnlary number. Inspections that identified indications or were limited are bold with a reference to the col-sective action process (AR) number as appropriate. There was no Class 1 or 2 examinations with indications requiring scope expansion or repairlreplacement. There was one Limited Exanliilation of a class 1 valve to reducer weld limited by geometry. A Relief request will be submitted as required by 10 CFR 50.55a(g)(5)(iv). The second table lists the number and percentage of examinations or tests completed as required by IWA-6220(f).
Page 1 of 9 Unit 2 Fuel Cycle 26, 05/24/2010 to 05/29/2012 Inservice Inspection Report Interval 4, Period 3, Outage I (2R27)
- 1. Owner: Xcel Energy 4. Owner Certificate of Authorization (If Req.):
- 2. Plant: Prairie Island Nuclear Generating Plant 5. Commercial Service Date: 12/21/1974
- 3. Plant Unit: 2 6. National Board Number for Unit: NIA Summary No. Comp. ID Comp. Desc. Item Procedure Method/ReporVResults System DwgIlSO Exam Date Scope Class 1 Category B-B (Pressure Retaining Welds in Vessels other than Reactor Vessels) 501474 W- I Vertical Shell Weld 82.12 FP-PE-NDE- UT 12012U042 1 NAD RC 406 501482 W- 1 Cap-Integral Tubesht 82.60 FP-PE-NDE- VT 12012V061 / NAD VC 520 501536 W- 2 Cap-Integral Tubesht 82.60 FP-PE-NDE- VT 12012V062 1 NAD VC 520 501558 W- 3 Bottom Head to Shell 82.11 FP-PE-NDE- UT /2012U041/ NAD RC 406 501594 W- 3 Cap-Integral Tubesht B2.60 FP-PE-NDE- VT 1 2012V063 1 NAD VC 520 Class 1 Category B-D ( Full Penetration Welds of Nozzle in Vessels) 501409 N- 2 1R Spray Nozzle B3.120 SWI NDE-UT- UT 12012U036 / NAD RC 14 505001 N- IIR Surge Nozzle 83.120 SWI NDE-UT- UT 12012U012 INAD RC 14 505024 N- 1 IR Nozzle Inner Radius B3.160 FP-PE-NDE- VT 12012V064 / NAD VC 520 505025 N- 2 1R Nozzle Inner Radius B3.160 FP-PE-NDE- VT / 2012V065 / NAD VC 520 505026 N- 3 1R Nozzle Inner Radius 83.160 FP-PE-NDE- VT 12012V066 1 NAD VC 520 505027 N - 4 1R Nozzle Inner Radius B3.160 FP-PE-NDE- VT 12012V067 1 NAD VC 520 505028 N- 5 1R Nozzle Inner Radius 83.160 FP-PE-NDE- VT 12012V068 1 NAD VC 520 505029 N- 6 1R Nozzle Inner Radius 83.160 FP-PE-NDE- VT / 2012V069 1 NAD VC 520 Class 1 Category B-G-2( Pressure Retaining Bolting, 2 inch and Less in Diameter)
Page 2 of 9 Unit 2 Fuel Cycle 26, 05/24/2010 to 05/29/2012 Inservice Inspection Report Interval 4, Period 3, Outage 1 (2R27)
- 1. Owner: Xcel Energy 4. Owner Certificate of Authorization (If Req.):
- 2. Plant: Prairie Island Nuclear Generating Plant 5. Commercial Service Date: 12/21/1974
- 3. Plant Unit: 2 6. National Board Number for Unit: N/A Summary No. Cornp. ID Cornp. Desc. Itern Procedure Method/ReportlResults System Dwg/lSO Exam Date Scope 500724 B- 1 Inlet Manway Studs 07.30 FP-PE-NDE- VT 12012V033 / NAD SG 2-ISI-37A 3/22/2012 PSI 510 FP-PE-NDE- VT 12012V036 / NAD SG 2-ISI-37A 3/23/2012 IS1 510 500725 6- 1 Inlet Manway Studs 67.30 FP-PE-NDE- VT 12012V034 / NAD 2-181-378 3/22/2012 PSI 510 FP-PE-NDE- VT 12012V037 / NAD 2-181-378 3/23/2012 IS1 510 501013 B- I Manway Studs 07.20 FP-PE-NDE- VT 12011V096 / NAD 2-1S1-35 10/15/2011 PSI 510 FP-PE-NDE- VT/ 2012V026 / NAD 2-181-35 3/8/2012 IS1 510 501019 B- 2 Outlet Manway Studs (16) 07.30 FP-PE-NDE- VT 12012V035 / NAD 2-ISI-376 3/22/2012 PSI 510 Class I Category B-K (integral Attachments to Vessels, Piping, Pumps & Valves) 520219 H-3lIA Int. Attach.[Support] B10.20 SWI NDE-PT-1 PT I2012P001 1 NAD 521730 H-I /\A Int. Attach[Base] B1O.10 SWI NDE-MT-1 MT /2012M001 1 NAD Class 1 Category B-P (All Pressure Retaining Components)
See section 5 for pressure tests. Class I Category F-A (Supports) 500019 H- 3 Support F l .I Oa FP-PE-NDE- VT 12012V025 1 NAD 2-181-29 3/7/2012 IS1 530 500272 H- 5 Restraint F l .I Oa FP-PE-NDE- VT 12012V009 / NAD 2-ISI-20A 2/25/2012 IS1 530 500273 H- I Restraint Fl.lOb FP-PE-NDE- VT 12012VOll 1 NAD 2-ISI-20A 2/25/2012 IS1 530 501041 H-2 Restraint F l .I Oa FP-PE-NDE- VT 12012V010 1 NAD 2-ISI-13E 2/25/2012 IS1 530 F l .I OC FP-PE-NDE- VT 12012V048 1NAD 2-ISI-13A 4/4/2012 PSI 530
Page 3 of 9 Unit 2 Fuel Cycle 26, 05/24/2010 to 05/29/2012 lnservice Inspection Report Interval 4, Period 3, Outage I (2R27)
- 1. Owner: Xcel Energy 4. Owner Certificate of Authorization (If Req.):
- 2. Plant: Prairie Island Nuclear Generating Plant 5. Commercial Service Date: 12/21/1974
- 3. Plant Unit: 2 6. National Board Number for Unit: NIA Summary No. Comp. ID Comp. Desc. Item Procedure MethodIReporVResults System DwgIISO Exam Date Scope F l .I OC FP-PE-NDE- W / 2012V015 / NAD RC 530 501099 H- 3 Restraint Fl.lOb FP-PE-NDE- W 1 2012V016 / NAD SI 530 501101 H- 2 Restraint Fl.lOb FP-PE-NDE- W 1201lV095 / NAD SI 2-ISI-5 10/14/2011 PSI 530 501162 H- 5 Seismic Anchor Fl.lOb FP-PE-NDE- W 12012V014 / NAD RC 530 501174 H- 3 Spring F l .IOc FP-PE-NDE- W 12012V049 / NAD VC 2-ISI-12C 3/23/2012 PSI 530 F l .lOc FP-PE-NDE- W 12012V038 1 NAD RH 2-ISI-1OB 3/23/2012 PSI 530 Fl.10~ FP-PE-NDE- Vr / 2012V044 / NAD SI 2-ISI-22A 3/27/2012 PSI 530 Fl.10~ FP-PE-NDE- W 12012V041 1 NAD SI 2-181-228 3/24/2012 PSI 530 501363 H-6A Double Snubber/Clamp F l .IOC FP-PE-NDE- VT 12012V045 1 NAD SI 2-151-1 1 3/27/2012 PSI 530 501730 H- I Base F1.40 FP-PE-NDE- W / 2012V024 / NAD RC 530 502645 H- 3 Snubber 3 F1.40 FP-PE-NDE- VT /2012V029 / NAD SG 2-IS[-37C 3/8/2012 PSI 530 502649 H- 3 Snubber 3 F1.40 FP-PE-NDE- VT 12012V057 / NAD SG 2-181-370 5/11/2012 PSI 530 Class 1 Category R-A (Risk-Informed Piping Examinations) 501512-Rl W- 9 Pipe to Elbow R1.20-4 FP-PE-NDE- UT 12012U024 1 NAD RC 402 501524-Rl W- 7 45 Elbow to Reducer R l .I 6-5 FP-PE-NDE- UT 12012U023 1 NAD SI 402
Page 4 of 9 Unit 2 Fuel Cycle 26, 05/24/2010 to 05/29/2012 Inservice Inspection Report Interval 4, Period 3, Outage 1 (2R27)
- 1. Owner: Xcel Energy 4. Owner Certificate of Authorization (If Req.):
- 2. Plant: Prairie Island Nuclear Generating Plant 5. Commercial Service Date: 1212111974
- 3. Plant Unit: 2 6. National Board Number for Unit: NIA Summary No. Comp. ID Comp. Desc. Item Procedure MethodlRepoNResults System DwgIlSO Exam Date Scope 501576-RI W- 8 Reducer to Valve R1.I 6-5 FP-PE-NDE- UT 12012U021 1 NAD RC 402 Comments: Limited examination will rerquire Relief Request. See AR 1343795.
501592-Rl W- 4 Pipe To Elbow R1.20-4 FP-PE-NDE- UT 12012U019 / NAD RC 402 501627-RI W- 5 Pipe to 45 Elbow R1.20-4 FP-PE-NDE- UT 12012U039 1 NAD RC 402 501639-Rl W- 6 Elbow To Reducer R1.20-4 FP-PE-NDE- UT 12012U018 1 NAD RC 402 501676-Rl W- 6 45 Elbow to Pipe R1.20-4 FP-PE-NDE- UT 12012U022 1 NAD RC 402 501680-Rl W- 6 Elbow to Pipe R1.20-4 FP-PE-NDE- UT/ 2012U027 1 NAD RC 402 501844-Rl W- 9 Pipe To 45 Elbow R1.ll-2 FP-PE-NDE- UT 12012U031 1 NAD RC 402 501885-Rl W-I 0 45 Elbow TO 30 Elbow R1.ll-2 FP-PE-NDE- UT / 2012U030 1 NAD RC 402 502071-Rl W-14 Bent Pipe To Bent Pipe R1.ll-2 FP-PE-NDE- UT 12012U035 1 IND RC 402 FP-PE-NDE- UT 12012U043 1 NAD RC 403 Comments: Fabrication flaw outside exam volume accepted by code of construction. Dispositioned on 201211043. 502111-RI W-15 Bent Pipe To Reducer R1.ll-2 FP-PE-NDE- UT 12012U020 / NAD RC 402 502192-Rl W- 1 Pipe to Elbow R1.20-4 FP-PE-NDE- UT l2012U026 1 NAD RC 402 502229-Rl W-I 8 Elbow to Pipe R1.20-4 FP-PE-NDE- UT 12012U025 1 NAD RC 402 502248-RI W-19 Pipe To Elbow R1.20-4 FP-PE-NDE- UT l2012U028 1 NAD RC 402
Page 5 of 9 Unit 2 Fuel Cycle 26, 05/24/2010 to 05/29/2012 Inservice Inspection Report Interval 4, Period 3, Outage I (2R27)
- 1. Owner: Xcel Energy 4. Owner Certificate of Authorization (If Req.):
- 2. Plant: Prairie Island Nuclear Generating Plant 5. Commercial Service Date: 12/21/1974
- 3. Plant Unit: 2 6. National Board Number for Unit: NIA Summary No. Comp. ID Comp. Desc. Item Procedure MethodlReportlResults System Dwg/lSO Exam Date Scope 502269-Rl W-20 Elbow to Pipe R1.20-4 FP-PE-NDE- UT 1201211029 1 NAD RC 402 Class 2 Category C-B (Pressure Retaining Nozzle Welds in Vessels) 502680 N-4 1R MS Nozzle Inner Radi C2.22 SWI NDE-UT-5 UT 1201211017 / NAD SG Class 2 Category C-C (Welded Attachments for Vessels, Piping, Pumps & Valves) 520317 H-18/IA Int. Attach[Double Spring Hanger] C3.20 SWI NDE-MT-1 MT 1 2012M003 1 NAD AF 520671 H-41IA Int. Attach[Support] C3.20 SWI NDE-MT-1 MT 12012M002 1 NAD FW 520988 H-3lIA Int. Attach[Seismic Restraint] C3.20 SWI NDE-MT-1 MT I2012M004 1 NAD MS Class 2 Category C-H (All Pressure Retaining Components)
See section 5 for pressure tests. Class 2 Category F-A (Supports) 500307 H-8 Single Support F1.20b FP-PE-NDE- VT/ 2012V027 1 NAD AF 530 500374 H- 5 Pump Base (Slide) F1.40 FP-PE-NDE- VT 12012V030 1 NAD RH 530 500671 H- 4 Support F1.20a FP-PE-NDE- VT / 2012V028 / NAD FW 530 500985 H- 2 Seismic Restraint F1.20a FP-PE-NDE- VT 12012V012 1 IND MS 2-ISI-47A 2/27/2012 IS1 530 FP-PE-NDE- VT 12012V051 1 IND MS 2-ISI-47A 4110/2012 IS1 530 Comments: 2012V012 indications previously evaluated and found acceptable (see sharepoint AR 93701). 2012V051 indications evaluated on AR 1328673. 500988 H- 3 Seismic Restraint F1.20a FP-PE-NDE- VT 12012V013 1 NAD MS 530
Page 6 of 9 Unit 2 Fuel Cycle 26, 0512412010 to 0512912012 lnservice Inspection Report Interval 4, Period 3, Outage I (2R27)
- 1. Owner: Xcel Energy 4. Owner Certificate of Authorization (If Req.):
- 2. Plant: Prairie Island Nuclear Generating Plant 5. Commercial Service Date: 1212111974
- 3. Plant Unit: 2 6. National Board Number for Unit: NIA Summary No. comp. I D Comp. Desc. Item Procedure Method/Report/Results System DwgIlSO Exam Date Scope 500990 H- 8 Double SnubberIClamp F1.20~ FP-PE-NDE- W 12012V046 1 NAD MS 2-ISI-46A 3/27/2012 PSI 530 501182 H- 2 Spring Hanger F1.20~ FP-PE-NDE- W 12012V040 1 NAD RH 530 F1.20~ FP-PE-NDE- VT 12072V053 / NAD RH 2-18/42 4/28/2012 PSI 530 FP-PE-NDE- W 12012V055 / NAD RH 2-IS152 4/29/2012 PSI 530 505132 H- I Single Support F1.20a FP-PE-NDE- VT / 2012V020 / NAD SI 530 505418 H- I Restraint F1.20b FP-PE-NDE- VT / 2012V017 / NAD SI 530 515400 H-I Restraint F1.20b FP-PE-NDE- VT / 2012V021 / NAD RH 530 515562 H-7 - Seismic Snubber F1.20~ FP-PE-NDE- W / 2012V047 1 NAD cs . 2-ISI-98A 3/29/2012 PSI 530 Class 2 Category FWTOSG (Feedwater to Steam Generators Owner Elected) 505734 N- IRing FW Ringfree supports NRCIN9320 FP-PE-NDE- VT 12012V043 / NAD SG 2-ISI-37A 3/26/2012 OWN Tee 530 Class 2 Category R-A (Risk-Informed Piping Examinations) 500295-Rl W-20 Pipe to Flued Head R1.ll-5 FP-PE-NDE- UT / 2012U013 / NAD AF 2-1S1-48 3/2/2012 IS1 401 500296-Rl W-20A Flued Head to Pipe R1.ll-5 FP-PE-NDE- UT l2012U014 1 NAD FW 2-ISI-48 3/2/2012 IS1 401 500634-Rl W-24 Reducer to Nozzle R1.ll-5 FP-PE-NDE- UT 12012U016 1 NAD FW 2-181-48 3/2/2012 OWN 401 500635-Rl W-23 Pipe to Reducer R1.ll-5 FP-PE-NDE- UT l2012U015 1 NAD FW 2-181-48 31212012 IS1 401 501595-Rl W- 6lLSD Pipe to Tee R1.20-4 FP-PE-NDE- UT 1 2012U032 1 NAD RH 2-181-54 3/21/2012 IS1 402
Page 7 of 9 Unit 2 Fuel Cycle 26, 05/24/2010 to 05/29/2012 Inservice Inspection Report Interval 4, Period 3, Outage 1 (2R27)
- 1. Owner: Xcel Energy 4. Owner Certificate of Authorization (If Req.):
- 2. Plant: Prairie Island Nuclear Generating Plant 5. Commercial Sewice Date: 12/21/1974
- 3. Plant Unit: 2 6. National Board Number for Unit: N/A Summary No. Comp. ID Comp. Desc. Item Procedure MethodlRepoNResults System Dwg/ISO Exam Date Scope 501605-Rl W-15 Elbow to Pipe R1.I 9-5 SWI NDE-PT-1 PT 12012P002 / NAD RH FP-PE-NDE- UT 12012U040 / NAD RH 402 501871-Rl W-30 Pipe to Tee R1.ll-2 FP-PE-NDE- UT 12012U038 1 NAD RH 402 502020-Rl W-16ILSUD Pipe to Elbow R1.20-4 FP-PE-NDE- UT 12012U003 1 NAD RH 402 502022-RI W-17lLSUD Elbow to Pipe R1.20-4 FP-PE-NDE- UT / 2012U004 / NAD RH 402 502137-Rl W- 5ILSUD Elbow to Pipe R1.20-4 FP-PE-NDE- UT /2012U006 1 NAD RH 402 502139-Rl W- 8ILSUD Pipe to Elbow R1.20-4 FP-PE-NDE- UT / 2012U007 1 NAD RH 402 502303-Rl W- 9/LSU 45 Elbow to Pipe R1.20-4 FP-PE-NDE- UT / 201211034 1 NAD IGEO RH 402 502304-Rl W- 8/LSD Pipe to 45 Elbow R1.20-4 FP-PE-NDE- UT 12012U033 1 NAD / GEO RH 402 502351-Rl W-14/LSD Pipe to Elbow R1.ll-2 FP-PE-NDE- UT / 2012U037 1 NAD SI 402 505047-Rl W- 4 Pipe to Elbow R t .20-4 FP-PE-NDE- UT / 2012U001/ NAD SI 402 505056-Rl W-12 Elbow to Pipe R1.20-4 FP-PE-NDE- UT 12012U005 / NAD SI 402 505057-Rl W-I 3 Pipe to Elbow R1.20-4 FP-PE-NDE- UT 12012U002 1 NAD SI 402 505366-Rl W-I 3 Pipe to Elbow R1.20-4 FP-PE-NDE- UT /2012U011 1 NAD SI 402 505367-Rl W-14 Elbow to Pipe R1.20-4 FP-PE-NDE- UT /2012U010 1 NAD SI 402
Page 8 of 9 Unit 2 Fuel Cycle 26, 05/24/2010 to 05/29/2012 lnservice Inspection Report Interval 4, Period 3, Outage 1 (2R27) I. Owner: Xcel Energy 4. Owner Certificate of Authorization (If Req.):
- 2. Plant: Prairie Island Nuclear Generating Plant 5. Commercial Service Date: 12/21/1974
- 3. Plant Unit: 2 6. National Board Number for Unit: NIA Summary No. Comp. ID Comp. Desc. l tem Procedure MethodIRepoNResults System DwgIlSO Exam Date Scope 505369-Rl W-I 6 Elbow to Pipe R1.20-4 FP-PE-NDE- UT 12012U0091 NAD SI 2-ISI-93A 2/29/2012 IS1 402 505586-Rl W- 3 Reducer to Pipe R1.20-4 FP-PE-NDE- UT I2012U008 1 NAD CS 402 Class 3 Category D-A (Welded Attachments Vessels, Piping, Pumps, & Valves) 522767 SVH-5/IA lnt. Attach[RIGID] D l .20 FP-PE-NDE- VT 12012V018 / NAD MS 510 522925 CCH-2011A Int. Attach[SEISMIC ANCHOR] D l .20 FP-PE-NDE- VT / 2012V006 1 NAD CC 510 2EGH- Int. Attach[GUIDE] FP-PE-NDE- VT 1 2012V022 1 NAD 5005lIA 510 Class 3 Category F-A (Supports) 501253 H-3 Support A-Base FP-PE-NDE- VT / 2012V031 1 NAD 530 SVH- 5 RIGID FP-PE-NDE- VT 12012V019 1 NAD 530 CCH-56 Spring F1.30~ FP-PE-NDE- VT 12012V032 1 NAD 530 CCH-13 ROD F1.30a FP-PE-NDE- VT / 2012V008 1 NAD 530 2-CWH-50 Snubber F1.30~ FP-PE-NDE- VT / 2012V005 / NAD 530 CCH-20 Seismic Anchor F1.30b FP-PE-NDE- VT / 2012V007 1 NAD 530 512958 SVH- 1 Sway StruffClamp F1.30a FP-PE-NDE- VT 12012V054 / IND ND-2-3-109 4/30/2012 PSI 530 Comments: Dispositioned as acceptable AR 58774.
515051 CWH-604 Sway Strut F1.30b FP-PE-NDE- VT / 2012V050 / IND ND-2-3-74 4/1/2012 PSI 530 Comments: Lack of thread engagement evaluted as acceptable AR 1331746.
Page 9 of 9 Unit 2 Fuel Cycle 26, 05/24/2010 to 05/29/2012 lnservice Inspection Report Interval 4, Period 3, Outage 1 (2R27)
- 1. Owner: Xcel Energy 4. Owner Certificate of Authorization (If Req.):
- 2. Plant: Prairie Island Nuclear Generating Plant 5. Commercial Service Date: 12/21/1974
- 3. Plant Unit: 2 6. National Board Number for Unit: NIA Summary No. Comp. ID Comp. Desc. Item Procedure MethodIReporVResults System DwgIlSO Exam Date Scope 515163 2EGH-5005 GUIDE F1.30a FP-PE-NDE- VT 12012V023 / NAD D5 530 515172 2EGH-6021 GUIDE F1.30a FP-PE-NDE- VT 1 2012V001 1 NAD D6 530 515187 2EGH-6025 RESTRAINT F1.30b FP-PE-NDE- VT 12012V002 / NAD D6 530 515272 2EGH-6060 GUIDE F1.30b FP-PE-NDE- VT 12012V004 1 NAD D6 530 515275 2EGH-6061 SADDLE HANGER F1.30b FP-PE-NDE- VT 12012V003 1 NAD D6 530
Prairie Island Nuclear Plant Completion Code Compliance Summary 4th Interval - IS1 Code Edition - 1998,2000 Addenda Percent Total# Total# I I Required for Required for Comp to % Cornp t o Cat. Item No. Code Case Population Interval Interval Total Sched Date. Date. Notes Accumulator nozzles owner elected examination. Based on site OE of both cladding and nozzle cracking (AR 0851206 and AR 10330354) the site performs visual and PT inspection of ACC NO2 Cladding 2 100% 2 2 2 100% the cladding and nozzles every third outage under GMP ACC-001. ccumulator nozzles owner elected examination. B-A B-A B1.I 81.21 1 3 1 100% 100% 3 1 3 1 0 0 1 0% 0% 1 RV shell circ welds. Deferral to end of interval allowed per IWB-2500-1 RV bottom head weld. Deferral to end of interval allowed per IWB-2500-1 RV shell to flange weld. Deferral to end of interval allowed per N-623 B-B B2.11 B-B 82.12 B-B 82.40 One of each similar vessel. B-B B2.60 RR-4-2 3 I lclass 1 tubesheet to head HX. VT-2 each outage per RR-4-2. Not included in count. Total: - - -- 9 5 0 . B-D B3.100 6 100% 6 6 0 0% RV nozzle inside radius. Deferral to end of interval allowed per IWB-2500-1 B-D 83.120 5 100% 5 0 5 100% Pressurizer nozzle full pen welds. B-D 83.140 4 100% 4 2 2 50% SG tubesheet to head. One of each similar vessel. B-D 83.160 RR-4-2 6 Class 1 HX full pen nozzles. W - 2 each outage per RR-4-2. Not included in count. B-D B3.90 6 100% 6 6 0 0% Vessel full pen nozzle welds. Deferral to end of interval allowed per code case. Total. 27 - 21 l4 . I1 33Y. II ~ e a c t ovessel r Closure Head Bare Metal Examinaiton. Augmented Examiantion required every 3rd outage. Not included in count. 3 100% 3 1 2 67% RV nuts. Deferral to end of interval allowed per IWB-2500-1. Each component is a set of 16. Deferral to end of interval allowed per IWB-2500-1. Each component is a set of 24 RCP bolts. B-G-I B6.180 2 0 0 0 Only required when required by B-L-2. B-G-1 B6.190 2 0 0 0 0 Flange surface only required when disassembled Page 1 of 4
3 100% 3 1 2 67% RV studs. Deferral to end of interval allowed per IWB-2500-1. Each component is a set of 16. RV ligaments. Deferral to end of interval allowed per IWB-2500-1. Each component is a set 1 100% 1 1 0 0% of48. RV washers. Deferral to end of interval allowed per IWB-2500-1. Each component is a set of 1 100% 1 0 1 100% Pressurizer studs. 4 50% 2 0 2 100% SG studs. 9 3 Flange bolting only if disassembled or bolting removed. 4 1 Pump bolting only required when required by B-L-2 Valve bolting only required when required by B-M-2 Total Percentage completed for 87.20 and 87.30. Other items NA. B-K 810.10 6 Vessel attachments only one attachment of one of multiple similar vessels. Pipe attachments. Pump casing welds limited to one pump in each group of similar pumps. Pump casing limited to one pump in each group of similar pumps. Only required when disassembled. Valve body interior limited to one valve in each group. Only required when disassembled. RV interior all accessible areas to be examined once each period. B-N-2 813.50 1 100% 1 1 RV interior attachments beltline. Deferral to end of interval allowed per IWB-2500-1 B-N-2 813.60 1 100% 1 'I 0 I 0% IRVinterior attachments not beltline. Deferral to end of interval allowed per IWB-2500-1 Total: 2 2 2 Core support structure. Deferral to end of interval allowed per IWB-2500-1 1 lContro1 rod welds. 20 ~ e r i ~ h e rCRDMs al with 2 welds each. All welds had preservice exam as part of new RV head Dkferral allowed per IWB-2412(a)3 Page 2 of 4
B-P B1 5.00 2 600% 12 2 10 1 l ~ w pressure o test procedures each outage. Total. B-Q 616.20 2 2 0% 12 0 2 0 l 0 0 I I 0% IISG tubing per Technical Requirements Manual Total: 2 0 0 O 1 ° % 1 C-A C-A C1.10 C1.20 8 4 50% 50% 4 2 1 1 3 1 I1 75% 50% 1 Welds a t gross structural discontinuity only. The examinations are limited to one vessel among a group of vessels of similar design, size, and service. l ~ e a dcirc welds. Tubesheet to shell welds. C-B C2.21 C-B C2.22 C-B C2.31
- Reinforcing plates.
Total - 12 6 I- 5 C-C C3.10 4 50% 2 0 2 Vessel attachment welds. One of similar vessels. C-C C3.20 99 10% 10 1 9 Piping weld attachments C-C C3.30 16 10% 2 0 2 Pump weld attachments Valve weld attachments Class 2 pressure tests completed once each period Some completed after outage. D-A D1.10 8 50% 4 0 4 1 100% ( Pressure Vessel Welded Attachments. For multiple vessels of similar design and service only the welds of one vessel need be selected for examination. Piping Welded Attachments Class 3 pressure tests completed once each period. Some completed after outage. F-A Class 1 pipe supports one direciton F-A Class 1 pipe supports multidirection F-A Class 1 pipe supports thermal movement (springs). F-A Class 2 pipe supports one direciton F-A Class 2 pipe supports multidirection F-A Class 2 pipe supports thermal movement (springs). F-A Class 3 pipe supports one direciton F-A Class 3 pipe supports multidirection F-A Class 3 pipe supports thermal movement (springs). Page 3 of 4
Other supportsClass 1,2,3, MC. Visual VT-3 examination of 100% of all non-exempt Supports, other than piping supporis. For multiple components, the supports of only one of the F-A F1 40 74 37 3 38 multiple components are required to be examined. A commitment was made to inspect the feedwater nozzle to pipe transition forging welds using ultrasonic examination at a frequency of one nozzle per refueling outage or both nozzles every other refueling outage. R-A R1.ll-2 RI-IS1 Thermal fatigue high risk R-A R1.ll-5 RI-IS1Thermal fatigue medium risk R-A R1.15-2 PWSSC high risk (pressurizer nozzle) R-A R1.I 6-2 SCC high risk R-A R1.I 6-5 SCC medium risk R-A R1.I 9-5 ECSCC medium risk R-A R1.20-4 Not subject to damage medium risk R-A R1.20-6 Not subject to damage low risk Not subject to damage low risk Page 4 of 4
NSPM INSERVICE INSPECTION PRAIRIE ISLAND UNIT 2 CYCLE 26
SUMMARY
REPORT Section 4. IWE Examinations (6 pages attached) The following table summarizes the IWE inspections performed in cycle 26. Inspections are listed by class, category and site summary number. The second IWE inte~val, September 10, 2008 though September 9,2018, is based on the examination requirements of the 2001 Edition with 2003 Addenda of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code Section XI with lilnitations and modifications as required by Title 10 of the Code of Federal Regulation, Past 50.55a. As such, there is only one category (E-A) and two item numbees ( E l . l l and E l -30)in scope for the second IWE period (1110112 - 5111115). There are cusrently no surfaces requiring augmented examination under category E-C. There were no relevant indications in the second period examination. The number and percentage of examinations or tests completed are included in this section as required by IWA-6220(f). This section includes an evaluation of inaccessible areas as required by 10CFR50.55a(b)(2)(ix)(A) to address indication of reheling cavity leakage in contact with the steel containment vessel (AR1332452).
Page 1 of 1 Prairie Island Nuclear Plant Unit 2 Fuel Cycle 26, 05/26/2010 to 05/29/2012 Inservice Inspection Report IWE Interval 2, Period 2, Outage 1 (2R27)
- 1. Owner: Xcel Energy 4. Owner Certificate of Authorization (If Req.):
- 2. Plant: Prairie Island Nuclear Generating Plant 5. Commercial Service Date: 12/21/1974
- 3. Plant Unit: 2 6. National Board Number for Unit: N/A Examinations Performed Fuel Cycle 26 Summary No. Comp. ID Comp. Desc. Item Procedure Method/Report/Results System DwgIISO Exam Date Scope Class IWE Category E-A 600660 Containment Primary Containment El.ll FP-PE-NDE-540 VT 12012V074 1 NAD PC 2/2312012 IS1 Primary 600691 Containment Bolted Connections El.ll FP-PE-NDE-540 VT 12012V075 / NAD PC 2/23/2012 IS1 Bolting Primary Containment 4/23/2012 PSI 600441 Moisture Barrier E l .30 FP-PE-NDE-540 VT 12012V073 1NAD Moisure Barrier IWE Completion Code Compliance Summary Second Interval -
ISI Code Edition 2001 Edition, 2003 Addenda Summary Percent Total Required Total Comp. Cat. Item No. No. Comp Desc. Population Required for Interval Total Sched To Date Cumm % Notes E-A El.ll 600660 Primary Containment 1 3 1 2 Surface areas Primary Containment 100% each period. Moisture Barriers 100% Moisture Barrier each period. Areas requiring Augmented Examination.
Inaccessible Areas Evaluation 50.55a(b)(2)(ix)(A) The Code of Federal Regulations, Title 10, Part 50.55a(b)(Z)(ix)(A) states: "For Class MC applications, the licensee shall evaluate the acceptability of inaccessible areas when conditions exist in accessible areas that could indicate the presence of or result in degradation to such inaccessible areas. For each inaccessible area identified, the licensee shall provide the following in the IS1 Summary Report as required by IWA-6000: ( I ) A description of the type and estimated extent of degradation, and the conditions that led to the degradation; (2) An evaluation of each area, and the result of the evaluation, and; (3) A description of necessary corrective actions." Refuel cavity leakage in 2R27 (cycle 26) resulted in water in contact with the containment vessel. Level instrumentation showed leakage into the containment RHR suction sump indicating refueling water in contact with the containment vessel. There was also water observed in contact with the containment vessel when concrete was excavaged in the reactor vessel sump to facilitate VT and UT examination of the containment vessel (AR 01337188). These indicaitons of leakage are considered a condition in an accessible area that could indicate the presence of or result in degradation of inaccessible areas. As such, this evaluation is included in the IS1 summary report as required by 10CFR50.55a(b)(2)(ix)(A). I . A description of the type and estimated extent of degradation, and the conditions that led to the degradation. The site believes there is no significant degradation of the steel containment vessel, the containment concrete, or steel concrete reinforcing bar. In December of 1998 Automated Engineering Services Corp (AES) performed an evaluation titled "Evaluation of the Effects of Borated Water Leaks on Concrete, Reinforcing Bars, and Carbon Steel Plate of the Containment Vessel". The evaluation concluded that the effect of borated water leaks on the structural materials in containment (concrete, reinforcing bars, and containment shell plate material) is in the worst case minimal and does not affect the capability of the structure to perform its intended function. In addition to the evaluation, a section of concrete was removed from the RHR sump in 1998 to allow direct examination of the steel containment vessel. This examination showed no indicaiton of corrosion or pitting. The 1998 evaluation was reviewed by AES in 2R24 to account for leakage experienced from 1998 to the fall of 2006. This review determined that "The basis and conclusions developed in the Reference 1 report are still valid and in my opinion the integrity of the structural components (concrete, rebar and containment shell) are not compromised." In 2R25 (fall of 2008) a section of concrete was again removed from the RHR sump to allow direct visual examination of the containment vessel and UT thickness readings of a known wetted area. The vessel showed no visual indicaiton of corrosion and all thickness readings were above the nominal plate thickness. It is believed the RHR sump location would be the most susceptible to corrosion as it has the m o s t frequent history of wetting and is in close proximity to the concrete surface allowing greater oxygen exposure. A lack of significant corrosion in the RHR sump provides a high level of confidence there is no significant corrosion in other areas of the containment vessel. In addition, approximately an 18' x 2' area of the lowest accessible containment vessel plates were UT scanned with all readings above the nominal plate thickness. In March of 2009 Dominion Engineering performed an independent evaluation titled "Evaluation of Effect of Borated Water Leaks on Concrete, Reinforcing Bars, and Carbon Steel Plate of the Containment Vessels at Prairie Island Units 1 and
Inaccessible Areas Evaluation 50.55a(b)(2)(ix)(A) 2". Consistent with the previous AES evaluation, this evaluation also concluded that degradation of the containment vessels would likely be minimal. In 1R27 (spring 201 1) and 2R27 (sring 2012) concrete was excavated from the unit 1 and unit 2 reactor vessel sumps to allow direct visual inspection and ultrasonic thickness measurement of the containment vessels. The unit 2 excavation showed wetness believed to be from leakage of the segmented seal between the refueling cavity floor and the reactor vessel. In both cases, the containment vessels showed no visual evidence of degradation with actual thickness readings above the nominal 1.5" design thickness. Based on the results of the 1998, 2006 and 2009 professional engineering evaluations indicating no detrimental effects of refuel cavity leakage on the containment vessel, and recent visual and thickness examinations of the containment vessels of both units showing no degradation, there is a high level of confidence of no significant degradation of the unit 2 containment vessel. The condition that could indicate the presence of or result in degradation is refueling cavity leakage that has resulted in borated water coming in contact with the steel containment vessel. Refueling cavity leakage into the unit 2 RHR sump was noted in 2R24 (fall of 2006), in 21325 (fall of 2008), 2R26 (spring of 2010) and 2R27 (spring 2012). In all cases there was indication of leakage entering the RHR sump through the concrete at the containment vessel near the RH suction lines. In 2R27 leakage was also observed in the concrete excavation of the reactor vessel sump (AR01337188). The 2R24, 2R25, and initial leakage rate in 2R26 was approximately 1 gallon per hour (gph). Leakage in 2R26 spontaneously reduced to 0.02 gph approximately three days after pool flood. It is believed the initial leakage in 2R26 was the result of refueling cavity sandplug cover leakage that spontaneously decreased as the weight of the refueling water seated the cover. In 2R27 no significant leakage was indicated until 17 days after initial pool flood following a drain down and refill of the pool. It is believed the leakage developed at the segmented seal between the refueling pool floor and the reactor vessel as a result of changing pool level. Leakage has been experienced in previous outages on both units with documentation dating back to at least 1998. In addition to the RHR sump, past outages have shown leakage at other locations such as the regenerative heat exchanger room, nuclear instrument electrical penetrations and the floor near the reactor coolant drain tank.
- 2. An evaluation of the area, and the result of the evaluation.
As noted above, in December of 1998 Automated Engineering Services Corp (AES) performed an evaluation titled "Evaluation of the Effects of Borated Water Leaks on Concrete, Reinforcing Bars, and Carbon Steel Plate of the Containment Vessel". Following are pertinent excerpts from that evaluation. EFFECT OF BORATED WATER LEAKS ON CONCRETE Many studies have been conducted on the effect of acid rain on concrete. Laboratory studies have been conducted [Ref. 1,2] utilizing accelerated test program for effects of sulfuric acid solutions with pH ranging from 2 to 5 for periods ranging from 30 days to 100 days. Concrete samples with strengths varying from 3000 psi to 9000 psi were studied. The studies revealed the surface deterioration of the concrete increased as the
Inaccessible Areas Evaluation 50m55a(b)(2)(ix)(A) strengths increased due to the higher cement content in stronger concrete samples. It also increased with increasing acidity of the solution. However the corrosive effect of borated water (boric acid) is less than that of sulfuric acid at the same acidity levels. Reference 3 shows that boric acid has negligible effect on concrete whereas the same reference indicates that sulfuric acid will rapidly disintegrate concrete. Discussions with Portland Cement Association (Mr. Robert Shuldes) confirmed that the effect of borateg water will have negligible effects on concrete especially since the surface is wetted only for a short time duration (about 15 days every outage). The lack of deterioration of the concrete surfaces where white deposits were seen further reinforces the observation that borated water does not have any appreciable effect on concrete. Based on the above, we can safely conclude that the internal concrete surfaces at the construction joints and in the flow paths of the leaks would not have any deterioration. There is no safety significance of the borated water leaks on the concrete surfaces since the concrete structure would not have deteroriated and should be capable of performing its intended funciton. EFFECT OF BORATED WATER LEAKS ON REINFORCING BARS Since the borated water does not affect the concrete surface, the reinforcing bars would be fully protected inside the concrete. Note that the chloride content of the leaking water is small and will have no effect on the reinforcing bars. Also there is no evidence that the concrete surfaces have cracked thereby providing a path to the seepage of acidic water directly to the reinforcing bars. The likelyhood of any corrosion of the reinforcing bars in this situation is very remote. Based on this observation, there is no reason to suspect the corrosion of the reinforcing bars. Therefore, the strength of the reinforced concrete material is not compromised by the borated water leaks. EFFECT OF BORATED WATER LEAKS ON THE CONTAINMENT SHELL PLATE MATERIAL It is known in the nuclear industry that borated water in the form of boric acid can be corrosive to components fabricated from carbon and low alloy steels [Ref. 41. However, most of the studies conducted involved reactor coolant at high concentration (I 3,000-1 5,000 PPM of boron with small amounts of lithium) and at high temperatures (>200°F). Reference 4 concludes that the maximum corrosion rates occurred where moisture can be replenished by a flowing solution, keeping a wetldry interface between the solution and the dry boric acid crystals. It was also seen that when the boric acid dries out and is not significantly re-wetted, the corrosion levels are much lower.
Iilaccessible Areas Evaluation 50.55 a(b)(2)(ix)(A) As a precaution, NSP removed a portion of the grout material adhering to the steel plate around the pipe sleeve in the Sump B. The exposed steel surface did not show any signs of corrosion or surface pitting. This provides strong evidence that the boric acid solution was weak enough and was not constantly wetted for a long enough period of time to cause any deterioration of the steel plate surface. The same argument can be extended to other plate surfaces which are not exposed and which may be in the leak paths. Based on the above, it is believed that the containment shell is not affected by the observed leaks and has the capability to perform its intended fuction. The evaluation quoted above was reviewed by Automated Engineering Services Corp in December of 2006 in response to the leakage observed in 2R24. The review determined that the basis and conclusions developed in the earlier report were still valid and the integrity of the structural components (concrete, rebar and containment shell) was not compromised. An independent evaluation was performed by Dominion Engineering in March of 2009. The Dominion evaluation was consistent with the previous AES evaluations indicating minimal degradation. Following are the conclusions of that evaluation: o Because of the buffering effect of alkalinity from the concrete, the pH of the water in continuously wetted areas between the concrete and lower dome of the steel containment vessel is expected to have been in a range that inhibited corrosion of the steel, e.g., over about pH 12.5. As a result, it is expected that, as a best estimate, the maximum amount of corrosion that has actually been experienced in the wetted areas between the concrete and the inside surface of the steel containment vessel is insignificant, no more than a few mils (e.g., < 10 mils). While it seems unlikely, the possibility cannot be completely ruled out that the pH of the water in contact with the steel containment vessel could have been at the near neutral values that have been measured in Sump B. Analysis of this case, assuming continuous wetting of an aerated neutral pH region for the full 36 years of operation, leads to an upper limit estimate of about 0.25 inch of corrosion. It needs to be understood that this estimate is conservative since it is unlikely the pH has been at such a low level, and since it is unlikely that the aerated region at the water line has remained in the same area, such that the accumulated time duration of exposure at any one elevation is much less than 36 years. 0 Thinning of the upper limit amount of 0.25 inch poses no risk of leakage under normal or accident conditions since the wall thickness is 1.5 inches.
Iilaccessible Areas Evaluation 50.55a(b)(2)(ix)(A) Preliminary evaluation of the effects of thinning at the upper limit amount of 0.25 inch is that it will not result in excessive stresses or strains under accident conditions. This is a result of the bending stresses and hoop stresses in the possibly thinned area at the lower knuckle region of the steel containment vessel being essentially eliminated by the support provided by the reinforced concrete on both the ID and OD of the steel containment vessel in the knuckle region. Support for this conclusion is provided by limit load analyses of steel containment vessels that have shown that, even for steel containment vessels with 65% of wall loss for significant parts of their circumference (about 13 feet), the failure pressure is still over four times the accident design pressure (Table 2 in [22]). However, it needs to be understood that any actually detected thinned areas would need to be formally reviewed and accepted per Section XI of the ASME Code, and not per the above preliminary evaluation.
- 3. A description of necessary corrective actions.
The site has taken several actions to prevent leakage since 1998 including caulking refuel cavity leakage points prior to pool flood and the use of a spray-on strippable liner. In addition, a section of concrete was removed from the RHR sump the fall 2008 2R25 outage (W000327768) to allow direct visual inspeciton of the steel containment vessel to assure no significant degradation. In recent outages the site has seal welded suspected leakage points at the internals stands and Rod Control Cluster Change Fixtures of both units. The site has also excavated the reactor sumps of both units to allow direct examinaiton of the containment vessels and has extracted core samples of the refueling cavity floor of both units. The welded repairs have significantly reduced leakage on both units. The site continues to pursue complete leakage mitigation and continues to inspect for degradation. The site has made several commitments to mitigate leakage and monitor for degradation in conjunciton with the License Renewal process as listed in AR 01 16372. In summary, the site has a high level of confidence there is no significant degradation of the containment vessel or associated structures based on evaluation and examinaitons. The site continues to take actions to prevent future leakage and continues to perform examinations of the containment vessel to assure no significnat degradation.
NSPM INSERVICE INSPECTION PRAIRIE ISLAND UNIT 2 CYCLE 26
SUMMARY
REPORT Section 5. Pressure Tests 2 pages The following pressure tests were conducted during Unit 2 cycle 26 and credited to the second period. All indications were evaluated and corrective measures perfoimed as required by IWA-5250, IWB-3 142 and IWC-3 132. Code Class Pressure Tests Unit 2 CycIe 26 Second Period System Cat. Procedure WO# Comp. Indications No relevant Main Steam C-H SP 2168.11 Main Steam 378903 09/13/10 indications SP 2168.14 Containment No relevant C-H Containment Spray 389516 08120110 Spray indications System Pressure Test Volume SP 2168'16 No relevant C-H 12107111 a Control , , Volume Control Svstem . 378906 , indications , SP 2168'25 A" No relevant CV, RH, CS C-H ' 378911 Building Trench 03125111 ' indications The following pressure tests were conducted during Unit 2 cycle 26 and are credited to the third period. All indications were evaluated and coi~ectivemeasures perfoinled as required by IWA-5250, IWB-3 142 and IWC-3 132. Code Class Pressure Tests Unit 2 CycIe 26 Third Period System Cat. Procedure WO# Comp. Indications Relevant indication SP 2070 Reactor evaluated and Reactor found B-P Coolant System 409632 05126112 acceptable for Coolant Integrity Test continued service AR 1332189. SP 2168.4 Comp No relevant D-B Component Cooling 420369 05124112 Cooling indications Class 3 SP 2168.4A Comp No relevant C-H Component Cooling 415362 04/23/12 Cooling indications Class 2 SP 2168.6 Auxiliary Aux Feed C-H 420371 In Prog. Feedwater Cooling SP 2168.8 Cooling No relevant Water C-H Water to FCU's. 417533 05124112 indications Class 2
Cooling SP 2168.8 Cooling No relevant Water D-B Water to FCUJs. indications Class 3 Relevant indications evaluated and found acceptable for continued Residual SP 2168.10 RHR service ARJs Heat C-H 1338369, System Removal 1338370, 1338384, 1324616, 1337667, 1338362. Safety SP 2168.13 Safety In Prog. C-H Injection Injection System SP 2168.15 Post No relevant Post LOCA LOCA H2 Control C-H indications Hydrogen Svstem Relevant indications evaluated and SP 2392 Unit 2 found RC, SI, VC, Insulated Bolted acceptable for B-P, C-H continued RH, CS, SF Connection Inspection service AR's 1328653, 1332189.
NSPM INSERVICE INSPECTION PRAIRIE ISLAND UNIT 2 CYCLE 26
SUMMARY
REPORT Section 6. Snubber Inselvice Testing and Preservice Examinations 1 page There were a total of 21 snubbers functionally tested in 2R27. All testing was completed satisfactorily. Seventeen of the twenty-one were Basic-PSA hydraulic snubbers, these snubbers had spares rebuilt and tested SAT prior to installation. The Basic-PSA snubbers that were renloved were tested in the as found coildition and all were also SAT. There was one ITT Grinnel snubber that was tested SAT and re-installed. One Paul Monroe snubber was functionally tested SAT and re-installed. Finally two steam generator valve bloclcs were replaced wit11 re-built spares, all pre-install testing of the rebuilt and the as found testing of removed valve blocks was SAT. There was no scope expansion due to failed testing of the sainple population during 2R27. Some of the testing was perfoimed by a Basic-PSA field represeiltative, with most tests performed by in-house maintenance after Basic-PSA field rep depai-ture (due to outage expansion). The visual inspections for SP 2171 and TP 2535 were performed by LMT. There was no scope expaiisions due to conditions found on these inspections. The snubbers that were inaccessible were not inspected. All cylinders had hydraulic fluid and any deficiei~cies noted during the visual inspections were inspected by the Snubber Engineer. Six Action Requests were initiated as a result of visual inspection deficiencies and those action requests were resolved prior to leaving Mode 4. Any leakage identified was attiibuted to fluid from overfull reservoirs and thernlal movement. Those snubbers identified during the inspections with no move~l~ent or rotation, were inspected by the snubber engineer and those that were accessible, rotation and movement was evaluated and no snubbers were found to be loclted up. CAP 01326232 CAP 01328722 CAP 01330802 CAP 01331002 CAP 01331520 CAP 01334088
NSPM INSERVICE INSPECTION PRAIRIE ISLAND UNIT 2 CYCLE 26
SUMMARY
REPORT Section 7. Steain Generator Eddy Cui-rent Examination Results. Exaniination Category B-Q, Steain Generator Tubing, is reported separately per the requirements of the Plant Technical Specifications.
NSPM I N S E R V I C E INSPECTION PRAIRIE: ISLAND UNIT 2 CYCLE 26
SUMMARY
REPORT Section 8. RepairIReplacement Activities for Cycle 26 (72 pages attached) 36 NIS-2 forms are attached w h i c h identify Prairie Island Unit 2 R e p a i d Replacement Activities during fuel cycle 26, 4t" I S 1 Intewal. The gaps in i t e m number sequence are due to cancelled or unfinished R/R activities. Item # ( WO, EEC, MOD #s / Description of Work Completed ( SYSTEM 1 Code Class 12-26-002 405456-01, IEE 2010- !Replace desurger cap screws. /VC j2 I--
/ 2-26-004 1404147-01 1057 ..
i
-{. ..........
i Replaced the mechanical seal i 1. IVC i j2 I I 2-26-006 1405904-01, EEC-1554 1 igland plate I Replaced bonnet assembly. 1 - 1." i E-.-..-....-.-.-2..-.-...-.-------.. i I
.- I
----..-=.-J.-.-----.==.- =-- -------=-+---.-.---.---;--.----- - ---- - - .--. 12 - ;: -==, &.-- -
2-26-007 1417817-02 .
--- 1 Replaced packing -------...------
assemblies. 'VC -- .- -_.-.-- - 1 IVC
- --__,l?.&--ei--a--.-. ; -
2-26-008 1415821-01 %built spare charging pump j2 I Replaced trim including the main : S r
---- land ---------.- inner plugs. r - --- il- . - - - -- t - =;_---_ - ---- i I
C .i . .........
!Replaced 1 oackinq 1 assemblies.
A
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12-26-015 i429773-01 j 1 Replaced
^'.--.-..-....---..-I---
packing assemblies. .--.----*f.-...- ~j VC . . - i 12 ....... -- ... I 1 12-26-016 41 1121-01, EC-15389 ~ e ~ l a c mechanical i 1 new cartridge type seals with ed seals with icC j3 1 1L 1 I integral gland plate LIsG Ij-I 12-26-017 1418558-01 *-I,- /Replaced valve block.------ .---" --.. -.-------- i I 1 i2-26-018 1410183-01 t
~a v-L-
~
l ~ e p l a c e dinternal trim including the (AF
----=x--
i ii 3
,=-* *a=>.
I
/plug.
i 12-26-020 I371272-01 I
% _A__.. &......._....-~.~....A.....~...-d..-.--4..._.--.....-.__..........-....--.-...-....
/Replaced bonnet and bonnet h~- 1
.-..._.-.-_-..._..--..._-_..--A...-_
3 2-26-022 ,424867-01 I ... - - .. 1.- fasteners -
/Rebuilt spare charging pump 1 1 ivc
......-~...--...~.....l~--
12
. i
- . 1 packing assemblies. -- L i I 2-26-023 1108895-01 2-26-025 ] 110616-05
-. I i~ e p l a c e d I'fasteners2 1 bolting Replaced the valve and flange body to bonnet iSI
.. i--
i CL
.-_2.
i2 i i 13 i 2-26-026 1395532-01 I I ... - ......
, .I ri Replaced disc. . --- :. --,i IAF-
- 12 1 Replaced valve block. i," . i 2-26-027....... 141 / 8559-01 . ............ IS G 2-.. -. I 2-26-028 I1443354-01 -.
2-26-031 1446435-01 .... J Replaced anchor bolt. [Replaced packing assemblies.
~SI IVC....
12 2-26-032 I414266-01, EEC-1472 valves and associated /ZH 13 i
........ ! L _ .-......---...-.....---.-...--...*....-..-.........,-L....-...--...-...._A i -.
.r
.A 2-26-033 '443403-01 jRebuilt spare charging pump IVC 12 1 j I
.'2-26-035 i ... 1371691-01 1
j 2-26-039 !-; i--,_.-I_--._ i308073-0
.-*---=;.-_
I-. t2-26-041 / 157621-01, EC-19365, ~ e p l a c e dValve and flange RH [2 I EC-19855 jfas'teners as well as the block plate , 1 j [fasteners. . ...-- i Reolaced the valve disc and one IMs
!i.. 1I I
. .... .L body to cover fastener set: .......... i. .
- 2-26-043 1406127-01
!;-A" -i- .--=- ".-;- --1 Replaced valve disc.
--.---..,-_ , IRH ,..-*c-.- - --.-.;-- -
1 2 LC----.-" --=---=-_-.
Item # I WO, EEC, MOD #s 1 Description of Work Completed SYSTEM 1 Code Class 2-26-044 /374924-23, 374918-05 /Replace fasteners sets for primary SG I hot leg stud holes 4, 6, 7, and 14 -
! on the 21 SG and the fastener sets i
iI for stud holes 3 (cold leg) and 9 (hot leg) on the 22 SG. .. Replaced anchor nuts. 1 Install high point vent to remove non-condensable gases from the RCS. Increased the line and valve / size to 1" and
--------- --------- --=----
1 added new support. --- ------- ---"----- Replaced several cover or flange ICC b stubs and nuts. ......... .. Replaced snubber bolted connection with . pinned connection.
= = _ _ _ : L.- .. .- - _ _
Properly contoured the support to allow adequate clearance between pipe and support structural JCC 12 1 i member. . 1 Replaced the pump cover and I ................
- 1. Owner Xcel Energy, NSP-M Nuclear Department Date 7/1/2010 Name ' ,
'2. Plant Prairie Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 405456-01, IEE 2010-057 Address Repair Organization P.O. No., Job No., etc
- 3. Work Performed by Owner Type Code Symbol Stamp NIA Name Same Authorization NIA Address Expiration Date NIA
- 4. Identification of System VC Code Class 2
- 5. (a) Applicable Construction Code 818.3 1969 EditionlAddenda Addenda n/a Code Cases nla (b) Applicable Edition of Section XI Utilized for RepairlReplacement Activity 1998E 12000A (c) Applicable Section XI Code Cases None 61 ldentification of Components Component Name Manufacturer Manufacturer Nat'l Bd # Other ID Yr Built Corrected, ASME Name Serial # Removed, or Code Installed Stamp 23 CHG PMP DlSCH HYD EATON 3139-7 262-393 Corrected 0 DESURGER
- 7. Description of Work Replace desurger cap screws.
- 8. Tests conducted: ' ~~drostiti;tic/-!J' Pneumatic0 Nominal Operating Pressure 0 Exempt Other 0 Pressure psi Test Temp. O F Other: n/a NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1 12 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.
FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY
- 9. Remarks CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code, Section XI.
Type Code Symbol Stamp J/& Signed pn" Certificate of Aut Expiration Date
, ASME Program Engineer Owner or Owner's Designee , Title Date 7hLo CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minnesota and employed by HSB Insp, and Ins. Co. of Connecticut of Hartford Conn. have inspected the components described in this Owner's Report during the period 2qMAr?18 t o . ICZJULLQ I and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section XI.
By signing this certificate .neither the 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 vnd J17Qq National Board, Province and Endorsements
S-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY I. Owner Xcel Energy, NSP-M Nuclear Department Date 12/1/2010 . Name
- 2. Plant Prairie Island ~uclear'GeneratingPlant Sheet Name 1717 Wakonade Dr. E, Welch Minnesota 55089 Address Repair organization P.O. No., Job No., etc
- 3. Work Performed by Owner Type Code Symbol Stamp NIA Name Same Authorization Address Expiration Date
- 4. Identification of System VC Codeclass 2
- 5. (a) Applicable Construction Code nla , nla EditionlAddenda Addenda nla Code Cases nla (b)Applicable Edition of Section XI Utilized for RepairlReplacement Activity 1998E 12000A (c) Applicable Section XI Code Cases None
.6. Identification of Components Component Name Manufacturer Manufacturer Nat'l B d # Other ID - Yr Built Corrected, ASME Name Serial # Removed, or Code Installed Stamp 21 BA Transfer Pump Goulds 792A192-1 245-031 1970 Corrected 0
- 7. Description of Work Replaced the mechanical seal gland plate.
- 8. Tests conducted: Hydrostatic 0 Pneumatic0 Nominal Operating Pressure Exempt Other [Z1 Pressure psi Tesf Temp. .F Other: nla NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1 12 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.
FORM NIS-2 OWNER'S REPORT FOR REPAIR1 REPLACEMENT ACTIVITY
- 9. Remarks CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code, Section XI.
Type Code Symbol Slarnp dl& Expiration Date
, ASME Program Engineer Date I<// // d ,
Owner or Owner's Designee , Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minnesota and employed by HSB lnsp. and Ins. Co. of Connecticut of Hartford Conn. . have inspected the components described in this Owner's Report during the period \TAU&IcD to cb\'tsc~rn , and state that to the best of my knowledge and belief, the 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. rnd &\say National Board, Province and Endorsements
PORT FOR REPAIR1REPLACEMENT ACTIVITY
- 1. Owner Xcel Energy, NSP-M Nuclear Department Date 1/24/2011 Name
- 2. Plant Prairie Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 405904-01, EEC-1554 Address Repair Organization P.O. No., Job No., etc
- 3. Work Performed b y Owner Type Code Symbol Stamp N/A Name Same Expiration Date ' N/A s Address
- 4. Identification of System VG Code Class 2
- 5. (a) Applicable Consfruction Code B16.34 , nla EditionlAddenda Addenda nla Code Cases nia (b) Applicable Edition o f Section XILJtilized for RepairiReplacement Activity 1998E / 2000A (c) Applicable Section XI Code Cases None
- 6. ldentification of Components Component Name Manufacttjrer Manufacturer Nat'l B d # Other ID Yr Built Corrected, ASME Name Serial # Removed, or Code Installed Stamp 23 Charging Pump Suction valve Grinnell 2VC-6-7 Corrected
- 7. Description of Work Replaced bonnet assembly.
. 8. Tests conducted: Hydrostatic Pneumatic0 Nominal Operating Pressure Exempt Other [ll Pressure psi TestTernp. OF Other: nla NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1 12 in. x 11 in., (2) information in items
, 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.
ITEM 2-26-006 9.Remarks CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code, Section XI. Type Code Symbol Stamp /J/& Expiration Date
, ASME Program Engineer Date / d< //
Owner or Owner's Designee , Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minnesota and employed by HSB ins^. and Ins. Co. of Connecticut of Hartford Conn. have inspected the components described in this Owner's Report during the period 2lSEP1@ to 25JAl\l?l , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section XI. By signing this certificate neither. the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations a n d 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 md Q191Y National Board, Province and Endorsements Date , 2011
FORM NIS-2 OWNER'S REPORT FOR REPAIR1 REPLACEMENT ACTIVITY
- 1. Owner Xcel Energy, NSP-M Nuclear Department Date 1/25/2011 Name
- 2. Plant Prairie Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 417817-02 Address Repair Organization P.O. No., Job No., etc
- 3. Work Performed by Owner Type Code Symbol Stamp NIA Name Same Authorization NIA Address Expiration Date NIA
- 4. Identification of System VC Code Class 2
- 5. (a) Applicable Construction Code nla , n/a EditionlAddenda Addenda nla ' Code Cases n/a '
(b) Applicable Edition of Section.XI Utilized for RepairIReplacernent Activity 1998E 1 2000A (c) Applicable Section XI Code Cases None
- 6. Identification of Components Component Name Manufacturer Manufacturer Nat'l B d # Other ID Yr Built Corrected, ASRIE Name Serial # Removed, or Code Installed Stamp 21 Charging Pump Ajax 6917 245-041 1969 Corrected
- 7. Description of Work Replaced packing assemblies.
- 8. Tests conducted: Hydrostatic Pneumatic0 Nominal Operating Pressure C] Exempt Other . Pressure . psi Test Temp. O F Other: ' nla NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (I) size is 8 112 in, x 11 in., (2) information jn items Ithrough 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.
FORM NIS-2 OWNER'S REPORT FOR REPAIR1 REPLACEMENT ACTIVITY.
- 9. Remarks CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code, Section XI.
Type Code Symbol Stamp /j/, Expiration Date
, ASME Program Engineer Date / /2fid/,,
U - Owner or Owner's Designee , Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minnesota and employed by HSB Insp. and Ins. Co. of Connecticut of Hartford Conn. have inspected the components described in this Owner's Report during the period dL(~s~lcb to d 7 , f ~ d 14 I and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section XI. By signing this certificate neither the 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 Mt.id191'4 National Board, Province and Endorsements Date
I. Owner Xcel Energy, NSP-M Nuclear Department Date 5/9/2011 Name
- 2. Plant Prairie Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 415821-01 Address Repair Organization P.O. No., Job No., etc
- 3. Work Performed by Owner Type Code Symbol Stamp NIA Name Same ~uthorizition NIA Address Expiration Date NIA
- 4. Identification of System VC Code Class 2
- 5. (a) Applicable construction Code nla , nla EditionlAddenda Addenda n/a Code Cases nla -.'
(b) Applicable Edition of Section XI Utilized for RepairIReplacement Activity 1998E 12000A , (c) A~plicableSection XI Code Cases None
- 6. ldentification of components Component Name Manufacturer Manufacturer, Nat'l Bd # Other ID Yr Built Corrected, ASME Name Serial # Removed, or Code Installed Stamp Spare Charging Pump Packing Goulds Spares Corrected C]
Assemblies
- 7. Description of Work Rebuilt spare charging pump packing assemblies.
- 8. Tests coXducied: ~ ~ d r o s t a t 'i cPneumatic0
~ Nominal Operating Pressure n Exempt @
Other Pressure psi- Test Temp. . O F Other: nla NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1 I2 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.
FORM NIS-2 OWNER'S REPORT FOR REPAIR1 REPLACEMENT ACTIVITY ITEM 2-26-008
- 9. Remarks CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code, Section XI.
Type Code Symbol Stamp d)# Expiration Date
, ASME Program Engineer Date d&//
Owner or Owner's Designee , Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minnesota and employed by HSB Insp. and Ins. Co. of Connecticut of Hartford Conn. have inspected the components described in this Owner's Report during the period 17 bEclcb to iIMA\)It , and state that to the best of my knowledge and belief, the 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. omm missions de A,~,I. National Board, Province and Endorsements Date , b.14
- 1. Owner Xcel Energy, NSP-M Nuclear Department Date 5/7/2012 Name
- 2. Plant Prairie Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 434447-01 Address Repair Organization P.O. No., Job No., etc
- 3. Work Performed by Owner Type Code Symbol Stamp N/A Name
.,, Same Authorization N/A Address Expiration Date N/A
- 4. ldentification of sys'tem MS Code Class 2
- 5. (a) Applicable Construction Code 616.34 , n/a EditionIAddenda
'Addenda nla Code Cases n/a .
(b) Applicable Edition of Section XI Utilized for ~ e ~ a i r l d e ~ l a c e mActivity ent 'l998E / 2000A (c) Applicable Section XI Code Cases None
- 6. Identification of Components compo"ent Name Manufacturer . Manufacturer Nat'l B.d sk Other ID Yr Built Corrected, ASME Name Serial # Removed, or Code Installed Stamp 22 SG PORV Copse Vulcan 7010-95075-1-1 CV-31107 Corrected
- 7. Description of Work Replaced trim including the main and inner plugs.
- 8. Tests conducted: Hydrostatic 0:Pneumatic0 Nominal Operating Pressure Exempt Other Pressure psi Test Tern p. O F Other: Inservice testing will be performed in accordance with SP-21116, NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1 12 in. x 71 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.
FORM NIS-2 OWNER'S REPORT FOR REPAIR1 REPLACEMENT ACTIVITY ITEM 2-26-013
- 9. Remarks CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code, Section XI.
Type Code Symbol Stamp d/& Certificat Signed Date 6-/7 /$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 Minnesota and employed by HSB Insp. and Ins. Co. of Connecticut of Hartford Conn. have inspected the components described in this Owner's Report during the period 21APILIt to - - ISMkY12. , and state that to the best of my knowledge and belief, the 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,.Ownerls 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. , . - omm missions -.JB I ~ B P.J-I S m d ~1424 -. National Board, Province and Endorsements Date ---- - --- - I
- 1. Owner Xcel Energy, NSP-M Nuclear Department Date 2/25/2012 Name
- 2. Plant . Prairie Island Nuclear Generating Plant Sheet 1 of . 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 431417-01 Address Repair Organization P.O. No., Job No., etc
- 3. Work Performed by Owner Type Code Symbol Stamp NIA Name Same ~uthorizakon NIA Address
. Expiration Date NIA
- 4. Identification of system . VC Code Class 2
- 5. (a) Applicable Construction Code nla , nla EditionlAddenda Addenda nla Code Cases n/a " ' .
(b)~ p p l i c a b l eEdition of Section XI Utilized for RepairlReplacement Activity 1998E 12000A~ . 1 ' (c) Applicable Section XI Code Cases None
- 6. ldentification of Components Component Name Manufacturer Manufacturer Nat'l B d # Other ID Yr Built Corrected, ASME Name Serial # Removed, or Code Installed Stamp 22 Charging Pump Ajax 245-042 1969 Corrected
- 7. Description of Work Replaced packing assemblies.
- 8. Tests cond.ucted: . Hydrostatic . . Pneumatic0 Nominal Operating Pressure Exempt Other Pressure psi Test Temp. O F Other: nla NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 II2 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet;and (3) each sheet is numbered and number of sheets is recorded at the top of this form.
- 9. Remarks CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code, Section XI.
Type Code Symbol Stamp ~4 Expiration Date ,
, ASME Plograrn Engineer ' Date p?/aii% 2 Owner or Owner's Designee , Title L--~
CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and .the State or Province 'of Minnesota and employed by, HSB ins^. and Ins. Co. of Connecticut of Hartford Conn. have inspected the components described in this Owner's Report during the period a8JQLit to 27FU312 , and state that to the best of my knowledge and belief, the 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.
,~)~Z&QO> omm missions $ t%es i l ~ F I r 1 mtL/W
~ns~ectdr'wature . National Board, Province and Endorsements Date 097 ,bid.
ITEM 2-26-01 5 I. Owner Xcel Energy, NSP-M Nuclear Department Date 1011912011 Name
- 2. Plant Prairie Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 . 429773-01 Address Repair Organization P.O. No., Job No., etc
- 3. Work performed by Owner Type Code Symbol Stamp N/A Name Same Authorization .. N/A Address Expiration Date NIA
- 4. ldentification of System VC Code Class 2
- 5. (a) Applicable Construction Code nla , nla EditionlAddenda Addenda nla Code Cases nla (b) Applicable Edition of Section,XI Vtilized for RepairlReplacement Activity 1998E 12000A (c) Applicable Section XI Code Cases None
- 6. ldentification of Components Component Name . Manufacturer Manufacturer Nat'l Bd # Other ID Yr Built Corrected, ASME Name Serial # Removed, or Code Installed. Stamp 23 Charging Pump Ajax 245-043 1969 Corrected 0
- 7. Description of Work Replaced packing assemblies.
- 8. Tests conducted: Hydrostatic CJ Pneumatic0 Nominal Operating Pressure Exempt Other 5 Pressure psi Test Temp. O F Other: nla ..
NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (I) size is 8 1 12 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 number of sheets is recorded at the top of this form.
' ITEM 2-26-015
- 9. Remarks CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code, Section XI.
Type Code Symbol Stamp /J& , . Expiration Date
, ASME Program Engineer Date /d//P//
Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National ~ o a r dof Boiler and Pressure Vessel . Inspectors and the State or Province of Minnesota and employed by HSB Insp. and Ins. Co. of Connecticut of Hartford Conn. have inspected the components described in this Owner's Report during the period I I J ~ ~ ~ Z to 2 W c T 12 , and state that to the best of my knowledge and belief, the 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. (
\
-p C/
y - c C .Q+ k n lnspector's~nature omm missions L i?o~s A-J., National Board, Province and Endorsements Date
NIS-2OWNER'S REPORT FOR REPAIR1 REPLACEMENT ACTIVITY I. Owner Xcel Energy, NSP-M Nuclear Department Date 7/23/2012 Name
- 2. Plant Prairie Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 41 1121-01, EC-I5389 Address Repair Organization P.O. No., Job No., etc
- 3. Work Performed by Owner Type Code Symbol Stamp NIA Name Same Authorization NIA Address Expiration Date NIA
- 4. ldentification of System CC Code Class 3
- 5. (a) Applicable Construction Code nla , n/a EditionlAddenda Addenda nla Code Cases n/a '
(b) Applicable Edition of Section XI Utilized for RepairlReplacement Activity 1998E / 2000A (c) Applicable Section XI Code Cases None
- 6. ldentification of Components lcompo"ent Name Manufacturer Manufacturer Nat'l Bd $
t--- Name Serial # 22 CC pump Goulds 245-1 22 Corrected
- 7. Description of Work Replaced mechanical seals with new cartridge type seals with integral gfand plate.
- 8. Tests conducted:. Hydrostatic 5 Pneumatic Nominal Operating Pressure Exempt Other a Pressure psi Test Temp. O F Other: nla NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1 /2 in. x 1Iin., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.
- 9. Remarks CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code, Section XI.
Type Code Symbol Stamp dh Expiration Date
, ASME Program Engineer Date 7h3//2 ,
Owner or Owner's Designee , Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by .the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minnesota and employed by HSB ins^. and Ins. Co, of Connecticut of Hartford Conn. . have inspected the components described in this Owner's Report during the period L l J o ~ t t to UJULIL I and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section XI. By signing this certificate neither the lnspector nor his employer makes any warranty, expressad 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. - mn.Qq A om missions ietQo%s A*h\.l ~ h 3192-4 s In pector's Signature National Board, Province and ~ndorsements Date & uQ $3 3 QifL
-A- - --------
- 1. Owner Xcel Energy, NSP-M Nuclear Department Date 5/29/2012
- Name
- 2. Plant Prairie Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 418558-01 Address Repair Organization P.O. No., Job No., etc
- 3. Work Performed by Owner Type Code Symbol Stamp NIA Name Same Authorization NIA Address Expiration Date NIA
- 4. Identification of System SG Code Class 1
- 5. (a) Applicable Construction Code 631.1 1967 EditionlAddenda Addenda nla Code Cases nla (b) Applicable Edition of Section XI Utilized for RepairIReplacementActivity 1998E 1 2000A (c) Applicable Section XI Code Cases None ..
- 6. ldentification of Components 1
Component Name Manufacturer Manufacturer Nat'l B d # Other ID Yr Built Corrected, ASME Name Serial # Removed, or Code Installed Stamp SG Snubber Block Valve McDowell Welman 72218-000-18 , 21SIG03 Installed El
- 7. Description of Work Replaced valve block.
- 8. Tests c~n,ducted: Hydrostatic . Pneumatics ' Nominal Operating Pressure 0 Exempt @
Other Pressure psi Test Temp. O F Other: nla NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1 12 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 number of sheets is recorded at the top of this form.
AIR/ REPLACEMENT ACTIVITY ITEM 2-26-017
- 9. Remarks CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code, Section XI.
Type Code symbol Stamp ,I.//A Expiration Date
, ASME Program Engineer Date d%aQdZ Owner or Owner's Designee , Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minnesota and employed by HSB Insw. and Ins. Co. of Connecticut of Hartford Conn. . have inspected the components described in this Owner's Report during the period Cb3oC7 I\ to . 2Sffl~'f12' ,
and state that to the best of my knowledge and belief, the 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 inju~yof property damage or a loss of any kind arising from or connected with this inspection. J B ~he A . ~ sI . mrJ atqw I
~ ~ ~ ? Commissions~ .-~ a t i o n~a l E a r d Province
, ~ and Endorsenients r e Date - L* . - , %D 1% ,
FORM NIS-2 O.WNERIS REPORT FOR.REPAIR1 REPLACEMENT ACTIVITY
- 1. Owner Xcel Energy, NSP-M Nuclear Department Date 612712012 Name
- 2. Plant Prairie Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 410183-01 Address Repair Organization P.O. No., Job No., etc
- 3. Work Performed by Owner Type Code Symbol Stamp NIA Name Authorization NIA Same Address ~ x p i r a t i o nDate NIA
- 4. Identification of System AF Code Class 3
- 5. (a) Applicable Construction Code ASME Ill 1968 EditionlAddenda Addenda nla Code Cases nla (b) Applicable Edition of Section XI Utilized for RepairIReplacement Activity 1998E / 2000A (c) Applicable Section XI Code Cases None
- 6. ldentification of Components Component Name Manufacturer Manufacturer Nat'l Bd # Other ID Yr Built Corrected, ASME Name Serial # Removed, or Code Installed Stamp 22 TD AFW PMP MS SPLY Valve Copes Vulcan 7620-95400 CV-31999 1968 Corrected 0 12
- 7. ~ e s c r i ~ t i oofnWork Replaced internal trim including the plug.
- 8. Tests conducted: ' ~~drost'iticfJ Pneumaticu Nominal Operating Pressure Exempt Other 0 Pressure psi Test Temp. O F Other: Exercise testing in accordance with the requirements of the IST program.
NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1 12 in. x 11 in., (2) information in items Ithrough 6 on this report is included on each sheet, and (3) each she$ is numbered and number of sheets is recorded at the top of this form.
FORM NIS-2 OWNER'S REPORT FOR REPAIR1 REPLACEMENT ACTIVITY ITEM 2-26-018
- 9. Remarks CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code, Section XI:
Type Code Symbol Stamp //h (d'/a Expiration Date
, ASME Program Engineer Date d/'7h.
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 p and employed by HSB Ins?. and Ins. Co. of Connecticut of Hartford Conn. have inspected the components described in this Owner's Report during the period MsoGit to 12JULfZ. , and state that to the best of my knowledge and belief, the 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 \POBS ~ . l * . l cJ df99'i National Board, Province and Endorsements I (lux11
CEMENT ACTIVITY
- 1. Owner Xcel Energy, NSP-M Nuclear Department Date 5/31/2012 Name
- 2. Plant Prairie Island Nuclear Generating Plant Sheet I of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 371272-01 Address Repair Organization P.O. No., Job No., etc
- 3. Work Performed by Owner Type Code Symbol Stamp N/A Name Same Authorization NIA Address Expiration Date NIA
- 4. Identification of System AF Code Class 3
- 5. (a) Applicable Construction Code NIA ' NIA EditionlAddenda Addenda NIA Code Cases NIA '
(b)Applicable Edition of Section $IUtilized for RepairlReplacement Activity 1998E / 2000A . ' (c) Applicable Section XI Code Cases None
- 6. Identification of Components Con~ponentName Manufacturer Manufacturer Nat'l Bd # Other ID Yr Built Corrected, ASME Name Serial # Removed, or Code Installed Stamp 22 TD AFW PMP Turbine Terry Turbine 259-201 Corrected governor valve
- 7. Description of Work Replaced bonnet and bonnet fasteners.
.' ~
- 8. Tests conducted: , . ~ydrostatic 0 'pneumatic0 Nominal Operating Pressure Exempt Other Pressure psi Test Temp. O F Other: nfa NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1 12 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.
- 9. Remarks CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code, Section XI.
Type Code Symbol Stamp J 14 Certificate of Authorizati Expiration Date Signed , ASME Program Engineer Date flh//k , Owner or Owner's Designee , Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel inspectors and the State or Province of Minnesota and employed by HSB ins^. and Ins. Co. of Connecticut of Hartford Conn. have inspected the components described in this Owner's Report during the period cd,36P14 to c?~l&d12, , and state that to the best of my knowledge and belief, the 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 in~plied, concerning the examinations a n d 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 -t b l b % s n . u - \ MI( 21914 National Board, Province and Endorseinents
- 1. Owner Xcel Energy, NSP-M Nuclear Department Date 1011812011 Name
- 2. Plant Prairie Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 424867-01 ,
Address Repair Organization P.O. No., Job No., etc
- 3. Work Performed by Owner Type Code Symbol Stamp N/A Name Same Authorization NIA Address Expiration Date NIA
- 4. Identification of System VC Code Class 2
- 5. (a) Applicable Construction Code nla nia EditionlAddenda
.,. Addenda nla Code Cases nla (b) Applicable Edition of section XI Utilized for RepairlReplacement Activity. 1998E I2000A ,
(c) ~ ~ ~ l i c aSection b l e XI Code Cases None 6, ldentification of Components Component Name Manufacturer Manufacturer Nat'l B d # Other ID Yr Built Corrected, ASME Name Serial # Removed, or Code Installed Stamp Spare Charging Pump Packing Goulds Spares Corrected Assemblies
- 7. Description of Work Rebuilt spare charging pump packing assemblies.
- 8. Tests conducted: Hydrostatic 0 Pneumatic0 Nominal Operating Pressure q Exempt Other Pressure psi Test Tern p. O F Other: nla NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1 12 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.
ITEM 2-26-022
- 9. Remarks CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code, Section XI.
Type Code Symbol Stamp E/h Certificate of Authoriza Expiration Date Signed , ASME Program Engineer Date /d/z 4 w Owner or Owner's Designee , Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minnesota and employed by HSB Insw. and Ins. Co. of Connecticut of Hartford Conn. have inspected the components described in this Owner's Report during the period .I'LSEPI\ to . ~qacrtl , and state that to the best of my knowledge and belief, the 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 $ M ~ B Sa.A.1 . National Board, Province and Endorsements
I. Owner Xcel Energy, NSP-M Nuclear Department Date 612612012 Name
- 2. . Plant Prairie Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 108895-01 Address Repair Organization P.O. No., Job No., etc
- 3. Work Performed by Owner Type Code Symbol Stamp NIA Name Same ~uthorization NIA Address Expiration Date NIA
- 4. ldentification of System SI Code Class 2
- 5. (a) Applicable Construction Code 616.34 , nla EditionIAddenda Addenda nla Code Cases nla (b) Applicable Edition of Section XI.Utilized for RepairlReplacement Activity 1998E / 2000A (c) Applicable Section XI Code Cases None .
- 6. Identification of Components Component Name Manufacturer Manufacturer Nat'l B d # Other ID Yr Built Corrected, ASME Nam'e Serial # Removed, or Code Installed Stamp SUMP B TO 22 RHR PMP TRN Crane MV-32179 Corrected B (INSIDE) MV
- 7. Description of Work Replaced body to bonnet fasteners.
- 8. Tests conducted: Hydrostatic Pneumatic Nominal Operating Pressure Exempt Other Pressure -psi Test Temp. O F Other: nla ,
NOTE: Supplemental sheets in form of lists, ske'tches, or drawings may be used, provided (1) size is 8 1 12 in. x 11 in., (2) information in items 1 through 6 on this rep,ort is included on each.sheet, and (3) each sheet is numbered and nurnber of sheets is recorded at the top of this form.
ITEM 2-26-023
- 9. Remarks CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code, Section XI.
~~~kCode Symbol Stamp A A'%- Expiration Date
, ASME Program Engineer Date &,,2 - ,
Owner or Owner's Designee , Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors. and the State or Province of p and employed by HSB ins^. and Ins. Co. of Connecticut of Hartford Conn. have inspected the components described in this Owner's Report during the period +S.SEPt4t 155EPll to 2bJutJIL , and state that to the best of my knowledge and belief, the 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 propertv damage or a loss of any kind arising from or connected with this inspection. Commissions l h ~ & l . MJ dlPaY National Board, Province and Endorsements Date
- 1. Owner Xcel Energy, NSP-M Nuclear Department Date 4/16/2012 Name
- 2. Plant Prairie Island Nuciear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 I10616-05 Address Repair Organization P.O. No., Job No., etc
- 3. Work Performed by Owner Type Code Symbol Stamp NIA Name Same Authorization N/A Expiration Date N/A Address
- 4. Identification of System CL Codeclass 3
- 5. (a) Applicable Construction Code B31.I 1967 EditionIAddenda Addenda nla Code Cases nla "
(b) Applicable Edition of Section.XI ~ l t i l i i e for d RepairlReplacement Activity 1998E 12000A (c) Applicable Section XI Code Cases None
- 6. ldentification of Components Component Name Manufacturer Manufacturer Nat'l B d # Other ID Yr Built Corrected, ASME Name Serial # Removed, or Code Installed Stamp 22 CLG WTR PMP DISCH Pratt 2CL-39-2 Installed
- 7. Description of Work Replaced the valve and flange bolting.
- 8. Tests conducted: Hydrostatic PneumaticC] Nominal Operating Pressure [Z1 Exempt Other C ] . Pressure , psi Test Temp. O F Other: nla NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1 12 in. x 11 in., (2) information in items Ithrough 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.
PRAIRIE ISLAND NUC ITEM 2-26-025
- 9. Remarks CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code, Section XI.
Type Code Symbol Stamp Certificat Signed Date ~//6.//2 Owner or Owner's Designee , Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minnesota and employed by HSB Ins?. and Ins. Co, of Connecticut of Hartford Conn. have inspected the components described in this Owner's Report during the period 3OSPlt to - I b W I and state that to the best of my knowledge and belief, the Owner has performed examinations and taken :orrecti& measures described in this Owner's Report in accordance with the requirements of the ASME Code, Sectio~XI. By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report: Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection. Commissions rle 1 h 5 pd-t - md
-- ~- S-- W-National Board, Province and Endorsements
- 1. Owner Xcel Energy, NSP-M Nuclear Department Date 6/4/2012 Name
- 2. Plant , Prairie Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 395532-01 Address Repair Organization P.O. No., Job No., etc
- 3. Work Performed by Owner Type Code Symbol Stamp NIA Name Same Authorization NIA Address ~ x ~ i r a t i oDate n NIA
- 4. Identification of System AF Code Class 2
- 5. (a) Applicable C~nstructionCode 816.34 , nla EditionlAddenda Addenda nla Code Cases nla (b) Applicable Edition of Section XI Utilized for RepairIReplacement Activity 1998E 12000A '
(c) Applicable Section XI Code Cases None
- 6. ldentification of Components Component Name Manufacturer Manufacturer Nat'l B d # Other ID Yr Built Corrected, ASME Name Serial # Removed, or Code Installed Stamp 22 AFW TO 21 SG MV Powell MV-32246 Corrected
- 7. Description of Work Replaced disc.
- 8. Tests conducted: Hydrostatic.Q Pneumatic a Nominal Operating Pressure [7 Exempt @
Other [7 Pressure psi' Test Temp. O F Other: nla NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided ( 1 ) size is 8 1 /2 in. x 11 in., (2) information in items Ithrough 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.
ITEM 2-26-026
- 9. Remarks CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code, Section XI.
Type Code Symbol Stamp &.(A Certificate of Aut Expiration Date Signed : ASME Program Engineer Owner or Owner's Designee , Title Date k jq//! , CERTIFICATE OF INSERVICE INSPECTION . I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minnesota and employed by HSB Insp, and Ins. Co. of Connecticut of Hartford Conn. have inspected the components described in this Owner's Report during the period ~&RwW 3@5Eellto , BIJtJuEJt'L I and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section XI. By'signing this certificate neither the 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\l~~Qr~fs Vw . D . d 2 , . ~ummissions A*l' aiq'?~
\ I spector's signathe . . National Board, Province and Endorsements Date +,.?$--.-;- ccw od . Q042
.. . ~
FORM NIS-2 OWNER'S REPORT FOR REPAIR1 REPLACEMENT ACTIVITY
- 1. Owner Xcel Energy, NSP-M Nuclear Department Date 5/21/2012 Name
- 2. Plant Prairie Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 418559-01 Address Repair Organization P.O. No., Job No., etc
- 3. Work Performed by Owner Type Code Symbol Stamp N/A Name Same '
Authorization NIA Expiration Date NIA Address
- 4. ldentification of System SG Code Class 1
- 5. (a) Applicable Construction Code 631.I 1967 EditionlAddenda Addenda nla Code cases nla . .
(b) Applicable ~ d i t i d nof Secfion XI utilized for RepairlReplacement Activity 1998E / 2000A (c) Applicable Section XI Code Cases None
- 6. ldentification of Components I .
Component Name Manufacturer Manufacturer Nat'l Bd # Other ID Yr Bu'ilt Corrected, ASME Name Serial # Removed, or Code Installed Stamp SG Snubber Block Valve McDowell Welman 72218-000-15 22SIG03 Installed
- 7.
8. Description of Work Tests conducted: Replaced valve block. Hydrostatic . Pneumatic0 Nominal Operating Pressure Exempt I Other Pressure psi Test Temp. O F Other: nla NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1 12 in, x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.
FORM NIS-2 OWNER'S REPORT FOR REPAIR1 REPLACEMENT ACTIVITY ITEM 2-26-027 9.Remarks VT-3 recorded in report 2012V057. CERTIFICATE OF COMPLIANCE We certify that the statements the report are correct and this conforms to the requirements of the ASME Code, Section XI. Type Code Symbol Stamp I Owner or Owner's Designee , Title CERTIFICATE OF INSERVICE INSPECTION I I, the undersigned, holding a valid commission issued bv the National Board of Boiler and Pressure Vessel inspectors and the state or Province of Minnesota and employed by HSB ins^. and Ins. Co. of Connecticut of Hartford Conn. have inspected the components described in this Owner's Report during the period @-!or3 I f to 23mA\/t/L and state that to the best of my knowledge and belief, the Owner has performed examinations and taken correctid I measures described in this owner's ~ e p o rin t 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, I 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 Aii C U ~ ~ P , A . I ]MA $ 1 9 2 ~ National Board, Province and Endorsements
FORM NIS-2 OWNER'S REPORT FOR REPAIR1 REPLACEMENT ACTIVITY
- q. Owner Xcel Energy, NSP-M Nuclear ~epartment Date 1013112011 Name
- 2. Plant Prairie Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 443354-01 Address Repair Organization P.O.No., Job No., etc
- 3. Work Performed by Owner Type Code Symbol Stamp NIA Name Same Authorization NIA Address Expiration Date NIA 4.
5. ldentification of System (a) Applicable Construction Code SI AWS D l .I , Code Class nla 2 EditionlAddenda I Addenda nla. Code Cases nla ' (b) Applicable Edition of Secti-on XI Utilized for RepairlReplacement Activity . 1998E 12000A (c) Applicable Section XI Code Cases None
- 6. Identification of Components Component Name , Manufacturer Manufacturer Nat'l Bd # Other ID Yr Built Corrected, ASME Name Serial # Removed, or Code Installed Stamp SI system support 2-RSIHr241 Corrected 0
- 7. Description of Work . Replaced anchor bolt.
- 8. Tests conducted: Hydrostatic 0 Pneumaticn Nominal Operating Pressure D Exempt Other Pressure psi Test Temp. O F Other: nla NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1 I2 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.
- 9. Remarks VT-3 exam recorded on PSI report 2011V095
. CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code, Section XI.
~ y p Code s symbol stamp dh Certificate of Auth Expiration Date Signed . , ASME Program Engineer Date 10 /J/ ///
Owner or Owner's Designee , Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minnesota and employed by HSB ins^. and Ins. Co. of Connecticut of Hartford Conn. have inspected the components described in this Owner's Report during the period i2ocr1.1 to . 310c7tI , and state that to the best of my knowledge and belief, the 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. (~~QJ?.QQ, ~ommissions t.I& 1C)ohs A.J. 1 National Board, Province and Endorsements Date h8vr 31 , 20ll
- 1. Owner Xcel Energy, NSP-M Nuclear Department Date 1/4/2012 Name
- 2. Plant Prairie Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 446435-01 Address Repair Organization P.O. No., Job No., etc
- 3. Work Performed by Owner Type Code Symbol Stamp NIA Name Same Authorization NIA Address Expiration Date NIA
- 4. ldentification of System ' VC Code Class 2 ,
- 5. (a) Applicable Construction code n/a , nla EditionlAddenda
' .\'
'Addenda nla Code Cases nla '
(b) Applicable Edition of Section XI Utilized for RepairlReplacement Activity 1998E 12000A (c) Applicable Section XI Code Cases None
- 6. Identification of Components Component Name Manufacturer Manufacturer Nat'l Bd # ,Other ID Yr Built Corrected, ASME Name Serial # Removed, or Code Installed Stamp 21 Charging Pump Ajax 6917 245-041 1969 Corrected
- 7. Description of Work Replaced packing assemblies.
- 8. Tests conducted: ~~drostatic Pneumaticn Nominal Operating Pressure Exempt Other D pressure psi Test Temp. O F Other: nla NOTE: Supplemental sheets in form of lists, sketches, ordrawings may be used, provided (1) size is 8 1 12 in. x 11 in., (2) information in items Ithrough 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.
- 9. Remarks CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code, Section XI.
Type Code Symbol Stamp ,d/b Expiration Date I
, ASME Program Etigineer Date //.///a ,
Owner or Owner's Designee , Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board ,of Boiler and Pressure Vessel Inspectors and the State or Province of Minnesota and employed by HSB Insw. and Ins. Co. of Connecticut of Hartford Conn. have inspected the components described in this Owner's Report during the period J3d0d I 4 t o cr5J~d4'L , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accord.ance 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 L ~ ~ ~ O C I B Srnt.fal.9*y A.~J.\ ector's ~ i g n d r e National Board, Province and Endorsements Date
- 1. Owner Xcel Energy, NSP-M Nuclear Department Date 2/21/2012'. '
Name
- 2. Plant Prairie Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 4lq266-01, EEC-1472 Address Repair Organization P.O. No., Job No., etc
- 3. WorkPerformedby Owner Type Code Symbol Stamp . NIA Name Same Authorization NIA Address Expiration Date N/A
- 4. Identification of System ZH Code Class 3
- 5. (a) Applicable Construction Code B31.I 1967 EditionlAddenda Addenda nla Code cakes n/a (b) Applicable Edition of Sectioo XI Utilized fo; RepairlReplacement Activity 1998E 12000A (c) Applicable Section XI Code Cases None
- 6. ldentification of Components.
Component Name Manufacturer Manufacturer Nat'l Bd # Other ID Yr Built Corrected, ASME Name Serial # Removed, or Code Installed Stamp 111 SWGR RM UNIT CLR'SPLY Vogt 2ZH-4-7 Installed Il P 111 SWGR RM UNIT CLR RTRN Vogt 2ZH-4-8 Installed 0
- 7. Descriptipn of Work , Replaceyalves. and associated piping.
- 8. Tests conducted: Hydrostaticn Pneumaticu Nominal Operating Pressure Exempt Other C] Pressure NOP psi Test Temp. NOT O F NOTE: Supplemental sheets in'form of lists,' sketches, or drawings may be used, provided (1) size is 8 1 l2 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of thrs form.
- .; s. . . , . , ..
FORM NIS-2 OWNER'S REPORT FOR REPAIR1 REPLACEMENT ACTIVITY
- 9. Remarks VT-2 Leakage Test.recorded on report BOP-VT-12-002.
CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code, Section XI. Type Code Symbol Stamp d/# Expiration Date
, ASME Program Engineer Date 2 Owner or Owner's Designee , Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minnesota and employed by HSB Insp. and Ins. Co. of Connecticut of Hartford Conn. have inspected the components described in this Owner's Report during the period cWdclov4t to d7Kr3IL I and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section XI.
By signing this certificate neither the 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. (?yzn.QQy
\ ector's ~ i g n a t d e
~ommissihns ID 1'2085.A*tJ.1 fliaf924 National Board, Province and Endorsements Date
FORM NIS-2 OWNER'S REPORT FOR REPAIR!, REPLACEMENT ACTIVITY Owner Xcel Energy, NSP-M Nuclear Department Date I12712012 Name Plant Prairie 1sland'Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 443403-01 .
' Address Repair Organization P.O. No., Job No., etc Work Performed by Owner Type Code Symbol Stamp NIA Name Same. Authorization NJA Address Expiration Date NIA Identification of System VC Code Class 2 ,
I (a) Applicable Construction Code n/a n/a EditionlAddenda Addenda . nla Code Cases nldi ' ' (b) Applicable Edition of Secfiori XI,Utilized for RepairlReplacement Activity 1998E I2 0 0 0 ~ ' , (c) Applicable Section XI Code Cases None ldentification of Components Component Name Manufacturer Manufacturer Edat'l Bd # Other ID Yr Built Corrected, . ASME Name Serial # Removed, or Code Installed . Stamp Spare Charging Pump Packing Goulds Spares Corrected Assemblies
- 7. Description of Work . Rebuilt spare charging punip packing assemblies.
- 8. Tests conducted: ~~drostatic 0 Pneumaticu Nominal Operating Pressure C] Exempt Other .Pressure psi Test Temp. O F Other: nla NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size' is 8 1 12 in. x 11 in., (2) information in items' Ithrough 6 on this report'is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form. ,
- 9. Remarks CERTIFICATE OF COMPLIANCE .
We certify that the statements made in the rebort are correct and this conforms to the requirements of the ASME Code, Section XI. Type Code Symbol Stamp dl4 Expiration Date w
. , ASME Program Engineer Date / /d 7//2 ,
Owner or Owner's Designee , Title CERTIFICATE OF INSERVICE INSPECTION . I,'the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minnesota and employed by HSB Insp. and Ins. Co. of Connecticut of Hartford Conn. have inspected the components described in this Owner's Report during the period IJ DEcll to zudn~~/L' , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Reporkin accordance with the requirements of the ASME Code, Section XI. By signing this certificate neither the Inspectoi- 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.?!m - . a
~ommis$iois 4 m i 9192.q pector',~~ i g d r e National Board, Province and Endorsements Date %' qi4T ,
FORM NIS-2 OWNER'S REPORT FOR REPAIR1 REPLACEMENT ACTIVITY ?. Owner Xcel Energy, NSP-M Nuclear Department Date 6/1/2012 Name
- 2. Plant Prairie island Nuclear Generating Plant Sheet . 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 371691-01 Address Repair Organization P.O. No., Job No., etc
- 3. Work Performed by Owner Type Code Symbol Stamp NIA Name Same Authorization NfA Address ~xpirationDate N/A
- 4. Identification of System AF Code Class 2
- 5. (a) Applicable Construction Code 616.34 n/a EditionlAddenda Addenda n/a Code Cases nla (b)Applicable Edition of Section XI Utilized for RepairlReplacement Activity 1998E / 2000A (c) Applicable Section XI Code Cases None
- 6. ldentification of Components Cb?mponent Name Manufacturer Manufacturer NaYl Bd # Other ID Yr Built Corrected, ASME Name , Serial # Removed, or Code Installed Stamp 22 AFW TO 22 SG MV PowellNVeir MV-32247 Corrected
- 7. Description of Work Replaced disc.
- 8. Tests conducted: Hydrostatic Pneumatic0 Nominal Operating Pressure [IIJ Exempt Other [7 Pressure psi Test Temp. O F Other: nla NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1 I2 in. x 11 in., (2) information in items 1 through 6 on this report is,included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.
ITEM 2-26-035
- 9. Remarks i
CERTIFICATE O F COMPLIANCE We certify.that the statements made in the report are correct and this conforms to the requirements of the ASME Code, Section XI. Type Code Symbol Stamp rJ/R Certificate of Authorization No. /J/A Expiration Date Signed , ASME Program Engineer Date A// // 4 Owner or Owner's Designee , Title CERTIFICATEOF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler a n d Pressure Vessel Inspectors a n d the S t a t e o r Province of Minnesota and employed by HSB In'sp. a n d Ins. Co. of Connecticr~t of Hartford Conn. have inspected t h e components described in this Owner's Report during the period (64JmI'L . t o CPbJofdl'L , a n d state that to the b e s t of my knowledge and belief, the Owner h a s 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 m a k e s a n y warranty, expressed o r implied, concerning the examinations a n d corrective .measure described in the Owner's Repolt. Furthermore, neither the Inspector nor his employer shall b e liable in a n y m a n n e r for any personal injury of property d a m a g e or a loss of a n y kind arising from o r connected with this inspection.
. Commissions LB @o%s A + L I mr(--34 9 4 National Board, Province and Endorsements Date
1, Owner Xcel Energy, NSP-M Nuclear Department Date 4/16/2012 Name
- 2. Plant Prairie Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 308073-01 Address Repair Organization P.O.No., Job No., etc
- 3. Work Performed by Owner Type Code Symbol Stamp NIA Name Same Authorization NIA Address Expiration Date N/A
- 4. Identification of System VC Code Class 1
- 5. (a) Applicable Construction Code 831.I , 1967 EditionlAddenda Addenda nla Code Cases nla ,
(b) Applicable Edition of Section XI Utilized for RepairlReplacement Activity 1998E 12000A (c) Applicable Section XI Code Cases None
- 6. Identification of Components Component Name Manufact~irer Manufacturer Nat'l B d # Other ID Yr Built Corrected, ASME ,
Name Serial # Removed, or Code Installed Stamp VC piping spring can support Basic Engineering 2-RCVCH- Corrected 5 1575
- 7. ~ e s c r i p t i o nof Work Replaced spring can upper rod.
- 6 .. .
- 8. Tests conducted: , ~~drost'itic fJ ' Pneumatic0 Nominal Operating Pressure Exempt Other Pressure psi Test Temp. O F Other: nla NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1.I2 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.
FORM NIS-2 OWNER'S REPORT FOR REPAIR/'REPLACEMENT ACTIVITY ITEM 2-26-039
- 9. Remarks VT-3 recorded on report # 2012V049.
CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code, Section XI. Type Code Symbol Stamp Expiration Date
, ASME Program Engineer Date YA?/$a . ,
Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I,the undersigned, holding a valid commission issued by the National Board of Boiler and .Pressure Vessel Inspectors and the State or Province of Minnesota and employed by HSB Insw, and Ins. Co. of Connecticut of Hartford Conn. have inspected the components described in this Owner's Report during the period 23J~d t2 to , jbinA\l42 , and state that to the best of my knowledge and belief, the 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. m.QeQ,
\ wpector's ~ignatug omm missions LB 1200s A.A.1 ma $1924 National Board, Province and Endorsements Date d a ~ b , ~ a , O ' '
PRAIRIE ISLAND NUCLEAR GENERA FORM NIS-2 OWNER'S REPORT FOR REPAIR1 REPLACEMENT ACTIVITY I. Owner Xcel Energy, NSP-M Nuclear Department Date 5/25/2012 Name
- 2. Plant Prairie Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 157621-01, EC-19365, EC-19855 Address Repair Organization P.O. No., Job No., etc
- 3. Work Performed by Owner Type Code Symbol Stamp N/A Name Same Authorization NIA Address Expiration Date NIA
- 4. Identification of System RH Code Class 2
- 5. (a) Applicable Construction Code 831.I 1967 EditionlAddenda Addenda nla CodeCases, nla ' .
(b) Applicable Edition of Section XI Utilized for RepairlReplacement Activity 1998E 12000A (c) Applicable Section XI Code Cases None
- 6. Identification of Components.
Component Name ~anufaciurer Manufacturer Nat'l B d # Other ID Yr Built Ccj; vcted, ASME Name Serial # Removed, or Code Installed Stamp 22 RHR HX RC OUTL valve Fisher CV-31239 Installed
- 7. Description of Work Replaced Valve and flange fasteners as well as the block plate fasteners.
8, Tests condhcted: Hydrostatic [ZI . Pneumatic lI] Nominal Operating Pressure Exempt Other Pressure psi Test Temp. "F Other: nla NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 II2 in. x 1Iin., (2) information in items 2 through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.
D NUCLEAR GENERATING PLANT
- 9. Remarks CERTIFICATE O F COMPLIANCE We certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code, Section XI.
Type Code Symbol Stamp 14 Certificate o Expiration Date . . Signed , ASME Program Engineer Date 6d6d2 Owner or Owner's Designee , Title CER1-IFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minnesota and employed by HSB Insp. and Ins. Co. of Connecticut of Hartford Conn. . have inspected the components described in this Owner's Report during the period F0 to dSJurJ1 and state that to the best of my knowledge and belief, the Owner has p$ormA: examin$ons and takerkorrectivb 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 ti loss OF any kind arising from or connected with this inspection. .. omm missions tlnrQm5 a+*.l. m J 31q24 National Board, Province and Endorsements Date
-.-- . . ---.- -- 1
- 1. Owner Xcel Energy, NSP-M Nuclear Department Date 61512012 Name
- 2. Plant Prairie Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 41 1469-01
, Address Repair Organization P.O. No., Job No., etc
- 3. Work Performed by Owner Type Code Symbol Stamp NIA Name Same Authorization NIA Address Expiration Date NIA
- 4. Identification of System MS Codeclass 2
- 5. (a) Applicable Construction Code B16.34 , nla EditionIAddenda Addenda nla Codecases nla '
(b) Applicable Edition of Secti0.n XI Utilized for RepairIReplacement Activity 1998E I2000A (c) Applicable Section XI Code Cases None
- 6. Identification of Components component Name Manufactuiir Manufacturer Nat'l B d # Other ID Yr Built Corrected, ASME Name Serial # Removed, or Code Installed Stamp 21 SG MS ISOL CV Schutte & Koerting CV-31116 Corrected 0
- 7. Description of Work R
- 8. Tests conducted: Hydrostatic17 Pneumaticu Nominal Operating Pressure Exempt @
Other Pressure psi Test Temp. O F Other: nla NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1 12 in. x 1.1 in., (2) information in items Ithrough 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.
ITEM 2-26-042
- 9. Remarks CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code, Section XI.
Type Code Symbol Stamp A/ # r//a Expiration Date
, ASME Program Engineer Date ' k ,(<-//3 Owner or Owner's Designee , Title
- CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State 'or Province of Minnesota and employed by HSB Insp. and Ins. Co. of Connecticut the components described in this Owner's Report during the period of Hartford Conn.
fbwGi!? and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective to _ have 05 Jur3l2 inspected 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 d6 ('2085 e
- d . \ MA $(?'LC1 National Board, Province and Endorsements Date
FORM NIS-2 OWNER'S REPORT FOR REPAIR1 REPLACEMENT ACTIVITY I. Owner Xcel Energy, NSP-M Nuclear Department Date 513012012 Name
- 2. Plant Prairie Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 406127-01 Address Repair Organization P.O. No., Job No., etc
- 3. Work Performed by Owner Type Code Symbol Stamp NIA Name Same Authorization NIA Address Expiration Date NIA
- 4. Identification of System RH Code Class 2
- 5. (a) Applicable Construction Code B16.34 , nla EditionIAddenda Addenda nla Code Cases n/a' " '
(b) Applicable Edition of ~ec'tion. Xi Utilized for ~ e ~ a i r l ~ e ~ l a c &Activity ment 1998E I2000A (c) Applicable Section XI Code Cases None 6, Identification of Components Component Name Manufacturer Manufacturer Nat'l B d # Other ID Yr Built ~orroeied, ASME Name Serial # Removed, or Code Installed Stamp 21 RHR PMP Suction Line Chk Crane 2RH-3-2 Corrected
- 7. Description of Work Replaced valve disc.
- 8. Tests conducted:, Hydtostatic,a Pneumatic Nominal Operating Pressure 0 Exempt Other Pressure psi Test Temp. F Other: nla NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (I) size is 8 1 I2 in. x 1.1 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.
ITEM 2-26-043
- 9. Remarks CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code, Section XI.
Type Code Symbol Stamp A//~P Certificate of Auth Signed a 6/3dLz Owner or Owner's Designee , Titie CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minnesota and employed by HSB Insp. and Ins. Co. of Connecticut of Hartford Conn. have inspected the components described in this Owner's Report during the period 1cirnnCL~'L to . 18Jod12 , and state that to the best of my knowledge and belief, the 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. ( T ' y s d n . ~ ector's sign& Commissions d o \ ~ o % s ~ ~ d(ulJd~24
.t National Board, Province and Endorsements Date 4 -18 1 -% i t
- 1. Owner Xcel Energy, NSP-M Nuclear Department Date 512912012 Name
- 2. Plant Prairie Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 374924-23, 374918-05 Address Repair Organization P.O. No., Job No., etc
- 3. Work Performed by Owner Type Code Symbol Stamp NIA Name Same Authorization N/A Address Expiration Date NIA
- 4. ldentification of System SG Code Class 1
- 5. (a) Applicable Construction Code ASME Ill 1965
'. . EditionlAddenda Addenda Winter 66 Code Cases nla '
(b) Applicable Edition of S e c t i ~ nXI Utilized for RepairIReplacement Activity 1998E 1 2000A (c) Applicable Section XI Code Cases None
- 6. Identification of Components Component Name' '
Manufacturer ~anufacturer Nat'l B d # Other ID Yr Built Corrected, ASME Name Serial # Removed, or Code Installed Stamp 21 Steam Generator Westinghouse 1181 68-39 234-011 1968 Corrected 22 Steam Generator Wesinghouse 1182 68-40 234-012 1968 Corrected id
- 7. Description,of Work Replace fasteners sets for primary hot leg stud holes 4, 6, 7, and 14 on the 21 SG and the fastener sets for stud holes 3 (cold leg) and 9 (hot leg) on the 22 SG.
- 8. Tests conducted: ~ ~ d r o s t a tC]
ic Pneumatics Nominal Operating Pressure Exempt @ Other 0 Pressure psi Test Temp. O F Other: nla NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided ( I ) size is 8 1 12 in. x 11 in., (2) information in items 1 through 6 on this reporf is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form. 9 .
- 9. Remarks
. I CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code, Section XI. 1I I Type Code Symbol Stamp d/d I Expiration Date ate \~'/!~//.7 1 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 sots and employed by HSB Insp. and Ins. Co. of Connecticut of' Hartford Conn. have inspected the components described in this Owner's Report during the period 22MA1212 to 14JuA12 , and state that to the best of my knowledge and belief, the 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. rle 19685 i l 0-d . l MJ 2 t q ~ National Board, Province and Endorsements
FORM NIS-2 OWNER'S REPORT FOR REPAIR1 REPLACEMENT ACTIVITY
- 1. Owner Xcel Energy, NSP-M Nuclear Department Date 411912012 Name
- 2. Plant prairie Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 . 418544-01 Address Repair Organization P.O. No., Job No., etc
- 3. Work Performed by Owner Type Code Symbol Stamp NtA Name Same Authorization N/A Address ~xpirationDate , NtA
- 4. Identification of System SB Codeclass 2
- 5. (a) Applicable Construction Code 831.1 1967 EditionlAddenda Addenda nla Code Cases nla ' "
(b) Applicable Edition of section XI Utilized for RepairiReplacement Activity 1998E / 2000A (c) Applicable Section XI Code Cases None
- 6. ldentification of Components .
4 Component Name Manufacturer Manufacturer Nat'l Bd # Other ID Yr Built Corrected, Name Serial # Removed, or Installed Stamp SB system snubber BE 2-RBDH-602 Corrected
- 7. Description of Work Replaced anchor nuts.
- 8. Tests conducted: HydroStatic 0.Pneumatic0 Nominal Operating Pressure fJ Exempt Other 0. Pressure ' psi Test Temp. O F Other: nla NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, ~rbvided(I) size is 8 I12 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.
- 9. Remarks VT-3 exam recorded under Report # BOP-VT-12-004 CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code, Section XI.
~ y p ceo d e symbol Stamp Certificate of A Signed Date vhS/,?
Owner or Owner's Designee , Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minnesota and employed by HSB ins^. and Ins. Co. of Connecticut of Hartford Conn. have inspected the components described in this Owner's Report during the period 1.7MAQ to 2ml.@Z12' , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corre'ctive 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. m . w o = A y Commissions ie 1408s n.d.1 ~d a f 9 w National Board, Province and Endorsements Date , blrl
FORM NIS-2 OWNER'S REPORT FOR REPAIR1 REPLACEMENT ACTIVITY I. Owner Xcel Energy, NSP-M Nuclear Department Date 511012012 Name
- 2. Plant Prairie Island Nuclear Generating Plant Sheet 1 of 2 Name
-1717 Wakonade Dr. E, Welch Minnesota 55089 454221-05, EC-I 9795 Address Repair Organization P.O. No., Job No., etc
- 3. Work Performed by Owner Type Code Symbol Stamp NIA Name Same . Authorization NIA
~ddress Expiration Date NIA
- 4. Identification of System RC Code Class 1
- 5. (a) Applicable Construction Code ASME Ill, Class 1 1983 EditionIAddenda
.\ ,
Addenda nla Code Cases nla (b) Applicable Edition of Section,XI Utilized for RepairIReplacement Activity 1998E 12000A (c) Applicable Section XI Code Cases None
- 6. Identification of Components Component Name Manufacturer- Manufacturer Nat'l Bd # Other ID Yr Built Corrected, ASME Name Serial # Removed, or Code RX Head Vent Orifice Bypass valve 1 2RCT33 I (
Installed installed Stamp 1°1 2 RCGVS Support . 2-RCGV-1 Installed
- 7. ~escri~tib dfn~ d r k Install high point vent to remove non-condensable gases from the RCS. Increased the line and valve size to 1" and added new support.
- 8. Tests conducted: Hydrostatic Pneumatic0 Nominal Operating Pressure Exempt Other Pressure psi Test Temp. O F Other: nla .
NOTE: supplemental sheets in form of'lists, sketches, or drawings may be used, provided (1) size is 8 1 12 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 number of sheets is recorded at the top of this form.
ITEM 2-26-047
- 9. Remarks CERTIFICATE OF COMPLIANCE I We certify that the statements made in fhe report are correct and this confotrns'to the requirements of the ASME Code, Section XI. I 1 Type Code Symbol tamp dh I Certificat Signed Owner or Owner's Designee , Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minnesota and employed
. by HSB Insp. and Ins. Co. of Connecticut -of Hartford Conn. have inspected the components described .in this Owner's Report during the period (bSAPR I'L to I4lYI~ji2 ,
and state that to the best of my knowledge and belief, the 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. Cornmissions i@ IR2cbe-5 n . A - l rnA 4492~ ( lnsp$sctorls Signatur National Board, Province and Endorsements Date
FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY
- 1. Owner Xcel Energy, NSP-M Nuclear Department Date 612612012 Name
- 2. Plant Prairie Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 367903-01 Address Repair Organization P.O. No., J o b No., etc
- 3. Work Performed by Owner Type Code Symbol Stamp NIA Name Same Authorization NIA Address Expiration Date NIA
- 4. Identification of System CC Code Class 3
- 5. (a) Applicable Construction Code ASME Ill, Class C 1968 EditionlAddenda Addenda nla Code Cases nla '
(b) Applicable Edition of Section.XI. ~tilizedfor RepairIReplacement Activity 1998E 1 2000A (c)Applicable Section XI Code Cases None
- 6. ldentification of Components Component Name Manufacturer Manufacturer Nat'l Bd # Other ID Yr Built Corrected, ASME Name Serial # Removed, or Code Installed Stamp 21 CC Heat Exchanger Yuba 696229-1 C 235-031 1968 Corrected
- 7. Description of Work Replaced several cover or flange studs and nuts.
- 8. Tests conducted: . Hydrostatic,D . .Pneumatics . Nominal Operating Pressure Exempt Other Pressure psi Test Tem p. O F Other: nla NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1 I2 in. x I1 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.
I . / '
FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY
- 9. Remarks CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code, Section XI.
~ i Code~ Symbol e Stamp /J,/a Expiration Date.
, ASME Program Engineer Date k/c7/~ ,
Owner or Owner's Designee, Title . CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel . Inspectors and the State or Province of Minnesota and employed by HSB Insp. and Ins. Co. of Connecticut of Hartford Conn. have inspected the components described in this Owner's Report during the period mApR12 to d73oAVL , and state that to the best of my knowledge and belief, the 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.
/-$sm.o$ r2 rd Date I
J , dy In pector's Signature '
'27 Commissions
, QW'2 I085 a.rJel 214W National Board, Province and Endorsements
- 1. Owner Xcel Energy, NSP-M Nuclear Department Date 412812012 Name
- 2. Plant Prairie Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 418547-01 Address Repair Organization P.O. No., Job No., etc
- 3. Work Performed by Owner Type Code Symbol Stamp NIA Name Same Authorization NIA (I . Address Expiration Date NIA 4, Identification of System VC Code Class 2
- 5. (a) Applicable Construction Code B31.1 1967 EditionIAddenda Addenda nla Code Cases nla '
(b) Applicable Edition of S.ection XI Utilized for RepairIReplacement Activity 1998E I2000A (c) Applicable Section XI Code Cases None
- 6. Identification of Components Component Name Manufacturer Manufacturer Nat'l Bd # ' Other ID Yr Built Corrected, ASME Name Serial # Removed, or Code Installed Stamp VC Line (2-2VC-17A) snubber Basic Engineering 2-RCVCH- Corrected 17 1338
- 7. Description of Work Replaced snubber bolted connection with pinned connection.
- 8. Tests conducted: ~~drostatic0'Pneumaticn . Nominal Operating Pressure 0 Exempt Other Pressure psi Test Temp. O F Other: n/a NOTE: Supplemental sheets in fork of lists, sketches, or drawings may be used, provided (1) size is 8 1 12 in. x .I1 in., (2) information in items Ithrough G on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.
FORM NIS-2 OWNER'S REPORT FOR REPAIR1 REPLACEMENT ACTIVITY ITEM 2-26-049
- 9. Remarks VT-3 exam recorded on report # BOP-VT-12-007 CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code, Section XI.
Type Code Symbol Stamp did Expiration Date
, ASME Program Engineer D a t e 3//af/7 ,
Owner or Owner's Designee , Title I I CERTIFICATE OF INSERVICE INSPECTION
- 7 I I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minnesota and employed by HSB Insp. and Ins. Co. of Connecticut of Hartford Conn. have inspected the components described in this Owner's Report during the period lCI>Af@f'L to 0tmA.l 17, ,
and state that to the best of my knowledge and belief, the Owner has ~erformedexaminations 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 neithe; the I~:specior nor his employer makes any warranty, expressed or implied, concerning the exciminations and corrective measure described in the Owner's Report. Furtherm'ore, 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 $8 1 % ~ Add, I m d192Y __ National Board, Frovince and Endorsen~ents I
FORM NIS-2 OWNER'S REPORT FOR REPAIR1 REPLACEMENT ACTIVITY I. Owner Xcel Energy, NSP-M Nuclear Department Date 5/24/2012 Name
- 2. Plant Prairie Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E,Welch Minnesota 55089 455253-01 Address Repair Organization P.O. No., Job No., etc
- 3. Work Performed by Owner Type Code Symbol Stamp NIA Name Same Authorization NIA Address Expiration Date N/A
- 4. Identification of System CC Code Class 2
- 5. (a) Applicable Constiruction Code AWS D l .I , n/a EditionlAddenda
- Addenda nla Code Cases nla '
(b) Applicable Edition of Section XI utilized for RepairIReplacement Activity 1998E 1 2000A (c) Applicable Section XI Code Cases None .
- 6. ldentification of Components Component Name Manufhcturer Manufacturer Nat'l B d # Other ID ~r Built ' Corrected, ASME Name Serial # Removed, or Code Installed Stamp CC Line Support Basic Engineering 2-CCRH148 Corrected C]
- 7. Description of Work Properly contoured the support to allow adequate clearance between pipeand support structural member.
- 8. Tests conducted: Hydiostatic a . Pneumaticn Nominal Operating Pressure Exempt Other Pressure psi Test Temp. O F Other: nla NOTE.: sbPplementalsheets in fcim of lists, sketches, or drawings may be used, provided'(1) size is 8 1 12 in. x <:.Iin., (2) information in items
. Ithrough 6 on this report i,s included on each.sheet, and (3) each sheet is n~~rnbered a ~ nuinber d of sheets is-recordedat the top of this form.
- 9. Remarks CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code, Section XI.
Type Code Symbol Stamp d/# Certificate of Au Expiration Date Signed , ASME Program Engineer Date s/ZqhT 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 nesota and employed by HSB Insp: and Ins. Co, of Connecticut of Hartford C0t1i-r. have inspected the components described in this Owner's Report during the period 2OPPR 12- ' to 2LSIu)AVtL I and state that to the best of my knowledge and belief, the Owner has periornied examinations and taken corrective measures described in this Owner's Report in accordance with ,the recjuirements 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 ineasure described in tha O?rvner's Report: Furthermore, neither the lnspector nor his employer shall be liable in any manner fortany personal injury of property damage or a lass o f . Date To%- any kind arising from or connected with this inspection. Ins ecior's Sign
----Ae- q3>..-
- - -- \:;.P - .- missions ~atiunat
-L I 8oai-dl.
SA Pmviraca 1 pn d192.q
~.
aricl Endorsements
---.---- _.--_.-.. -;- i _ - - +--.. --"- ."....----.-.-.-.-.-,------,-- ----.-I
- 1. Owner Xcel Energy, NSP-M Nuclear Department Date 6/25/2012 Name
- 2. Plant Prairie Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 419873-04 Address Repair Organization P.O.No., Job No., etc ,
- 3. Work Performed by Owner Type Code Symbol Stamp NIA Name Same . Authorization NIA Address Expiration Date NIA
- 4. Identification of System RH Code Class 2
- 5. (a) Applicable Construction Code nla , nla EditionlAddenda
.Addenda nla Code Cases nla (b) ~ ~ ~ l i c aEdition b l e of Section XI Utilized for RepairlReplacement Activity 1998E / 2000A (c) Applicable Section XI Code Cases None
- 6. Identification of Components Component Name Manufacturer Manufacturer Nat'l Bd # Other ID Yr Built Corrected, ASME Name Serial # Removed, or Code Installed Stamp 21 RHR Pump Byron Jackson 681N0274 245-1 11 Corrected 0
- 7. Description of Work Replaced the pump cover and mechanical seal gland plate
- 8. Tests conducted: Hydrostatic .Pneumatic Nominal Operating Pressure Exempt Other ' Pressure psi Test Temp. O F Other: IST testing per H I 0.1 NOTE: Supplemental sheets in forrn'of lists, sketches, or drawings may be used, provided (1) size is 8 1'12 in. x in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form. i
ITEM 2-26-051
- 9. Remarks CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code, Section XI.
Type Code Symbol Stamp dh oriz ti n No. dl& i c eo f Expiration Date Signed , ASME Program Engineer Date dk/2 Owner or Owner's Designee , Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minnesota and employed by HSB Insp. and Ins. Co. of Connecticut of Hartford Conn. have inspected the components described in this Owner's Report during the period 33AP1212 to dsJudi2 , and state that to the best of my knowledge and belief, the 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. nsp -tor's Signature .
~omrni&ions l%CS -- A2N.t rnd 9142-4 National Board, Province and Endorsements Date $ 0 7 I QQ~. '.
L. - ---- -
- 1. Owner Xcel Energy, NSP-M Nuclear Department Date 6/25/2012 Name
- 2. Plant Prairie Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 446217-01 Address Repair Organization P.O. No., Job No., etc
- 3. .work Performed by Owner Type Code Symbol Stamp NIA Name Same . Authorization NIA Address Expiration Date NIA
- 4. Identification of System CL Code Class 3
- 5. (a) Applicable Construction Code B16.34 nla EditionIAddenda Addenda nla Code Cases nla " ..
(b) Applicable Edition of Section.XI U t i l i ~ e d for RepairlReplacement Activity 1998E / 2000A (c) Applicable Section XI Code Cases None
- 6. ldentificatioti of Components Component Name . Manufacturer Manufacturer Nat'l Bd # Other ID Yr Built Corrected, ASME Name . Serial # Removed, or Code Installed Stamp 22 CLG PMP DSL ~ a c k eCLG i Bonney Forge 2CL-89-1 Installed FE 27321 \SOL
- 7. Description of Work ReplacedValve
- 8. Tests condiicted:' ' Hydrostatic fJ Pneumatic Nominal Operating Pressure CJ Exempt @
Other Pressure psi Test Temp. O F Other: n/a NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1 12 in. x 11 in., (2) information in items . 1.through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.
FORM NIS-2 OWNER'S REPORT FOR REPAIR1 REPLACEMENT ACTIVITY 9.Remarks CERTIFICATE OF COMPLIANCE We certify that the statements made in the report.are correct and this conforms to the requirements of the ASME Code, Section'XI. Type Code Symbol Stamp d ) ~ Expiration Date
, ASME Program Engineer Date k/aJ//'
Owner or Owner's Designee , Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minnesota and employed by HSB Insw. and Ins. Co. of Connecticut . of Hartford Conn. have inspected the components described in this Owner's Report during the period m M A y I t to a3Ju~tCL , and state that to the best of my knowledge and belief, the 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 tile 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 LI--s~B~>.QQ - -- Commissions \%%S A,= MQ dl924 klfispec)tor's Signature .National Board, Province and Endorsements w Date .
- 1. Owner Xcel Energy, NSP-M Nuclear Department Date 5/30/2012 Name 2.' Plant Prairie Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 460147-01 Address Repair Organization P.O. No., Job No., etc
- 3. Work Performed by Owner Type Code Symbol Stamp NIA Name Same Authorization NIA Address Expiration Date NIA
- 4. Identification of System CL Code Class 2
, 5. (a) Applicable Construction Code B31.I 1967 EditionlAddenda Addenda nla Code Cases nla ' (b) Applicable Edition of SectionCXIUtilized for RepairlReplacement Activity 1998E I2000A . (c) Applicable Section XI Code Cases None
- 6. ldentification of Components Component Name Manufacturer ' Manufacturer Nat'l Bd # Other ID Yr Built Corrected, ASME Name Serial # Removed, or Code Installed Stamp Piping Spool 2-112-2CL-37 Corrected 14-2CL-37
- 7. Description of Work Replaced flange fasteners.
- 8. Tests dondhcted: ~ ~ d r o s t a t i c' 'Pneumaticn
~ Nominal Operating Pressure q Exempt @
Other 0 . Pressure psi Test Temp. O F Other: nla . . NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1.) size is 8 II 2 in. x I 1 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.
FORM NIS-2 OWNER'S REPORT FOR REPAIR1 REPLACEMENT ACTIVITY
- 9. Remarks CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code, Section XI.
I Type Code Symbol Stamp Expiration Date
. , ASME Program Engineer Date ~hO j / Z Owner or Owner's Designee , Title I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minnesota and employed by HSB ins^. and Ins. Co. of Connecticut of Hartford Conn. have inspected the components described in this Owner's Report during the period 22MAYiCL to %mA~lr~ ,
and state that to the best of my knowledge and belief, the Owner has performid 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 einployer 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. C. --- Commissions JB ~ ( ~ O PPS ~ & I MA !.V914 - /
\ National Board, Province and .Endorsements u
Date .
?FA-- Q ~ z1
- 1. Owner Xcel Energy, NSP-M Nuclear Department Date 6114/20?2 Name
- 2. Plant Prairie Island Nuclear Generating Plant Sheet 3 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 460351-06 Address Repair Organization P.O. No., Job No., etc
- 3. Work Performed by Owner Type Code Symbol Stamp NIA Name Same Authorization N/A Expiration Date NIA Address
- 4. Identification of System RC Code Class 1
- 5. (a) Applicable Construction Code B16.34 , nla EditionlAddenda Addenda nla Code Cases nla ,
(b) Applicable Edition of Section XI Utilized for RepairlReplacement Activity 1998E 1 2000A (c) Applicable Section XI Code Cases None
- 6. Identification of Components Component Name ~anufacturer Manufacturt?~. Nat'l B d # Other ID Yr Built Corrected, ASME Name Serial # .Removed, or Code Installed Stamp Loop A Hot Leg RTD Manifold Rockwell 2RC-1-9 Corrected Outlet
- 7. Description of Work Ct out and rewelded canopy seal on valve to facilitate internal inspection and trim replacement.
- 8. Tests conducted: ~ydrostatic Pneumatic0 Nominal Operating Pressure [Zl Exempt @
Other 0 Pressure psi Test Temp. F Other: nla NOTE: ~u~~Ie,rgental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1 12 in. x I 1 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.
ITEM 2-26-054
- 9. Remarks CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code, Section XI.
Type Code Symbol Stamp /;/A Expiration Date
, ASME Program Engineer Date Owner or Owner's Designee , Title r.. ..
CERTIFICATE OF I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of by HSB Insw. and Ins. Co. of Connecticut the components described in this Owner's Report during the period Minnesota of Hartford Conn. 2q my12 and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective to and employed have inspected IEdur~t'L , I 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. Furthbrmore, neithar 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 - JG4'2085 Pod.' MA 01924 National.Board, Province andindorsements Date I I 1}}