prairie island, unit 2, inservice inspection summary ... · unit 2 fuel cycle 26, 05/24/2010 to...

@ 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

171 7 Wakonade Drive East Welch, Minnesota 55089-9642 Telephone: 651.388.1 121

Document Control Desk

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 05-29-201 2

Unit 2, Fuel Cycle 26: 05-26-201 0 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: /,&-- - Date: 8//7/2ul.l IS1 Pro'gram Engineer, Pratrle Island /

Tom Downing

Reviewed by: Date: '$3 -20 - l-;h

Ron Clow

Reviewed by: Date: - 20 *- ( c

Reviewed by: Tfcgrarn bngineer~ng Superv~sor, Yra~rle lsland

Date: [ 7 & b 9 V

Approved by: Date: 8*26 - W / Z

Dave Potter

NSPM INSERVICE INSPECTION PRAIRIE ISLAND UNIT 2 CYCLE 26 SUMMARY REPORT

Table of Contents

Section 1. Discussion

Number of Panes

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


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 3rd period 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 1 OCFR50.55a(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~t activities 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, 171 7 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

Reactor Vessel

Pressurizer

21 Steam Generator

-

21 RHR Heat Exchanger 1 Joseph Oats & Sons I 1817-1C ( _ _ _ 1 342

State or Province No. ---

Manufacturer of Installer Serial No. ---

Component or Appurtenance

Reactor Vessel Head

22 Steam Generator

21 Reactor Coolant Pump

22 Reactor Coolant Pump

National Board No. ---

Manufacturer or Installer

Mitsubishi Heavy Inds.

Creuot-Loire

Westinghouse

Westinghouse

Framatome ANP

Westinghouse

Westinghouse

22 RHR Heat Exchanger

21 RHR Pump

687

1191

1181

22 RHR Pump

21 Safety Injection Pump

8. Examination Dates: 05/26/2010 to 05/29/2012

1182

W510

W515

Joseph Oats & Sons

Byron Jackson

22 Safety Injection Pump

21 Accumulator Tank

22 Accumulator Tank

Unit 2 Containment

9. Inspection Period Identification: (3rd Period) 12/21 1201 1 to 1 2/20/20 1 4

MINN-200-51

---

---

Byron Jackson

Bingham

10. Inspection Interval Identification: (4th Interval) 12/21/2004 to 1 2/20/20 1 4

---

68-57

68-39

---

---

---

1817-1 D

---

Bingham

Delta Southern

Delta Southern

Chicago Bridge & Iron

68-40

---

---

---

---

---

---

---

41 037-68-1

41 037-69-1

---

343

--- ---

---

---

---

---

---

---

---

---

2575

2576

---

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


15. Abstract of Corrective Measures


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


Section 3. IS1 Examinations (13 pages attached)

The followi~lg table 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).

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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 1201 2V061 / NAD VC 520

501536 W- 2 Cap-Integral Tubesht 82.60 FP-PE-NDE- VT 12012V062 1 NAD VC 520

501 558 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- I IR Surge Nozzle 83.120 SWI NDE-UT- UT 12012U012 I NAD 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 1201 2V067 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 52 0

Class 1 Category B-G-2 ( Pressure Retaining Bolting, 2 inch and Less in Diameter)

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 51 0 FP-PE-NDE- VT 12012V036 / NAD SG 51 0

2-ISI-37A 3/22/2012 PSI

2-ISI-37A 3/23/2012 IS1

500725 6- 1 Inlet Manway Studs 67.30 FP-PE-NDE- VT 12012V034 / NAD 51 0 FP-PE-NDE- VT 12012V037 / NAD 51 0

2-181-378 3/22/2012 PSI

2-181-378 3/23/2012 IS1

501013 B- I Manway Studs 07.20 FP-PE-NDE- VT 12011V096 / NAD 51 0 FP-PE-NDE- VT/ 2012V026 / NAD 51 0

2-1S1-35 10/15/2011 PSI

2-181-35 3/8/2012 IS1

501 01 9 B- 2 Outlet Manway Studs (1 6) 07.30 FP-PE-NDE- VT 12012V035 / NAD 51 0

2-ISI-376 3/22/2012 PSI

Class I Category B-K (integral Attachments to Vessels, Piping, Pumps & Valves) 52021 9 H-3lIA Int. Attach.[Support] B1 0.20 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) 50001 9 H- 3 Support F l .I Oa FP-PE-NDE- VT 1201 2V025 1 NAD

530 2-181-29 3/7/2012 IS1

2-ISI-20A 2/25/2012 IS1

2-ISI-20A 2/25/2012 IS1

2-ISI-13E 2/25/2012 IS1

2-ISI-13A 4/4/2012 PSI

500272 H- 5 Restraint F l .I Oa FP-PE-NDE- VT 12012V009 / NAD 530

500273 H- I Restraint Fl.lOb FP-PE-NDE- VT 12012VOll 1 NAD 530

501 041 H- 2 Restraint F l .I Oa FP-PE-NDE- VT 12012V010 1 NAD 530

F l .I OC FP-PE-NDE- VT 12012V048 1 NAD 530

of 9

Unit 2 Fuel Cycle 26, 05/24/2010 to 05/29/2012 lnservice Inspection Report


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

501 099 H- 3 Restraint Fl.lOb FP-PE-NDE- W 1 2012V016 / NAD SI 530

501 101 H- 2 Restraint Fl.lOb FP-PE-NDE- W 1201 lV095 / NAD SI 530

2-ISI-5 10/14/2011 PSI

501 162 H- 5 Seismic Anchor Fl.lOb FP-PE-NDE- W 12012V014 / NAD RC 530

501174 H- 3 Spring F l .I Oc FP-PE-NDE- W 12012V049 / NAD VC 530

2-ISI-12C 3/23/2012 PSI

F l .lOc FP-PE-NDE- W 12012V038 1 NAD RH 530

2-ISI-1 OB 3/23/2012 PSI

F l . 1 0 ~ FP-PE-NDE- Vr / 2012V044 / NAD SI 530

2-ISI-22A 3/27/2012 PSI

F l . 1 0 ~ FP-PE-NDE- W 12012V041 1 NAD SI 530

2-181-228 3/24/2012 PSI

501 363 H-6A Double Snubber/Clamp F l .I OC FP-PE-NDE- VT 12012V045 1 NAD SI 530

2-151-1 1 3/27/2012 PSI

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 530

2-IS[-37C 3/8/2012 PSI

502649 H- 3 Snubber 3 F1.40 FP-PE-NDE- VT 12012V057 / NAD SG 530

2-181-370 5/11/2012 PSI

Class 1 Category R-A (Risk-Informed Piping Examinations) 501 512-Rl W- 9 Pipe to Elbow R1.20-4 FP-PE-NDE- UT 12012U024 1 NAD RC

402

501 524-Rl W- 7 45 Elbow to Reducer R l .I 6-5 FP-PE-NDE- UT 12012U023 1 NAD SI 402

of 9


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: 1212111 974 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

501 576-RI W- 8 Reducer to Valve R1 .I 6-5 FP-PE-NDE- UT 12012U021 1 NAD RC 402

Comments: Limited examination wil l rerquire Relief Request. See AR 1343795.

501 592-Rl W- 4 Pipe To Elbow R1.20-4 FP-PE-NDE- UT 12012U019 / NAD RC 402

501 627-RI W- 5 Pipe to 45 Elbow R1.20-4 FP-PE-NDE- UT 12012U039 1 NAD RC 402

501 639-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

501 680-Rl W- 6 Elbow to Pipe R1.20-4 FP-PE-NDE- UT/ 2012U027 1 NAD RC 402

501 844-Rl W- 9 Pipe To 45 Elbow R1.ll-2 FP-PE-NDE- UT 12012U031 1 NAD RC 402

501 885-Rl W-I 0 45 Elbow TO 30 Elbow R1.ll-2 FP-PE-NDE- UT / 201 2U030 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.

5021 1 1-RI W-15 Bent Pipe To Reducer R1.ll-2 FP-PE-NDE- UT 12012U020 / NAD RC 402

5021 92-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

of 9



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 1 201211017 / 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 I 2012M004 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

500374 H- 5 Pump Base (Slide)

500671 H- 4 Support

F1.20b FP-PE-NDE- VT/ 2012V027 1 NAD AF 530

F1.40 FP-PE-NDE- VT 1201 2V030 1 NAD RH 530

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

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. ID 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

501 182 H- 2 Spring Hanger F1.20~ FP-PE-NDE- W 12012V040 1 NAD RH 530

F1.20~ FP-PE-NDE- VT 12072V053 / NAD RH 530 FP-PE-NDE- W 12012V055 / NAD RH 530

2-18/42 4/28/2012 PSI

2-IS152 4/29/2012 PSI

5051 32 H- I Single Support F1.20a FP-PE-NDE- VT / 2012V020 / NAD SI 530

50541 8 H- I Restraint F1.20b FP-PE-NDE- VT / 2012V017 / NAD SI 530

515400 H-I Restraint F1.20b FP-PE-NDE- VT / 201 2V021 / 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- I Ring FW Ringfree supports NRCIN9320 FP-PE-NDE- VT 12012V043 / NAD SG

Tee 530 2-ISI-37A 3/26/2012 OWN

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

401 2-1S1-48 3/2/2012 IS1

2-ISI-48 3/2/2012 IS1

2-181-48 3/2/2012 OWN

2-181-48 3121201 2 IS1

2-181-54 3/21/2012 IS1

500296-Rl W-20A Flued Head to Pipe R1.ll-5 FP-PE-NDE- UT l2012U014 1 NAD FW 401

500634-Rl W-24 Reducer to Nozzle R1.ll-5 FP-PE-NDE- UT 12012U016 1 NAD FW 401

500635-Rl W-23 Pipe to Reducer R1.ll-5 FP-PE-NDE- UT l2012U015 1 NAD FW 401

501 595-Rl W- 6lLSD Pipe to Tee R1.20-4 FP-PE-NDE- UT 1 2012U032 1 NAD RH 402

of 9


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

501 605-Rl W-15 Elbow to Pipe

501871-Rl W-30 Pipe to Tee

502020-Rl W-16ILSUD Pipe to Elbow

502022-RI W-17lLSUD Elbow to Pipe

5021 37-Rl W- 5ILSUD Elbow to Pipe

5021 39-Rl W- 8ILSUD Pipe to Elbow

502303-Rl W- 9/LSU 45 Elbow to Pipe

502304-Rl W- 8/LSD Pipe to 45 Elbow

502351 -Rl W-14/LSD Pipe to Elbow

505047-Rl W- 4 Pipe to Elbow

505056-Rl W-12 Elbow to Pipe

505057-Rl W-I 3 Pipe to Elbow

505366-Rl W-I 3 Pipe to Elbow

505367-Rl W-14 Elbow to Pipe

R1 .I 9-5 SWI NDE-PT-1 PT 12012P002 / NAD RH

FP-PE-NDE- UT 12012U040 / NAD RH 402

R1.ll-2 FP-PE-NDE- UT 12012U038 1 NAD RH 402

R1.20-4 FP-PE-NDE- UT 12012U003 1 NAD RH 402

R1.20-4 FP-PE-NDE- UT / 2012U004 / NAD RH 402

R1.20-4 FP-PE-NDE- UT /2012U006 1 NAD RH 402

R1.20-4 FP-PE-NDE- UT / 2012U007 1 NAD RH 402

R1.20-4 FP-PE-NDE- UT / 201211034 1 NAD I GEO RH 402

R1.20-4 FP-PE-NDE- UT 1201 2U033 1 NAD / GEO RH 402

R1.ll-2 FP-PE-NDE- UT / 2012U037 1 NAD SI 402

Rt .20-4 FP-PE-NDE- UT / 2012U001/ NAD SI 402

R1.20-4 FP-PE-NDE- UT 12012U005 / NAD SI 402

R1.20-4 FP-PE-NDE- UT 12012U002 1 NAD SI 402

R1.20-4 FP-PE-NDE- UT /2012U011 1 NAD SI 402

R1.20-4 FP-PE-NDE- UT /2012U010 1 NAD SI 402

of 9


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 12012U009 1 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 51 0

2EGH- Int. Attach[GUIDE] 5005lIA

FP-PE-NDE- 510

VT 1 201 2V022 1 NAD

Category F-A (Supports) H-3 Support A-Base

Class 3 501253 FP-PE-NDE-

530 VT / 2012V031 1 NAD

VT 12012V019 1 NAD

VT 12012V032 1 NAD

VT / 201 2V008 1 NAD

VT / 2012V005 / NAD

VT / 2012V007 1 NAD

VT 12012V054 / IND

SVH- 5 RIGID FP-PE-NDE- 530

CCH-56 Spring F1.30~ FP-PE-NDE- 530

CCH-13 ROD F1.30a FP-PE-NDE- 530

2-CWH-50 Snubber F1.30~ FP-PE-NDE- 530

CCH-20 Seismic Anchor F1.30b FP-PE-NDE- 530

SVH- 1 Sway StruffClamp F1.30a

Dispositioned as acceptable AR 58774.

CWH-604 Sway Strut F1.30b

Lack of thread engagement evaluted as acceptable AR 1331746.

FP-PE-NDE- 530

ND-2-3-109 4/30/2012 PSI 512958

Comments:

515051

Comments:

ND-2-3-74 4/1/2012 PSI FP-PE-NDE- 530

VT / 2012V050 / IND

of 9


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

51 51 63 2EGH-5005 GUIDE

515172 2EGH-6021 GUIDE

51 51 87 2EGH-6025 RESTRAINT

51 5272 2EGH-6060 GUIDE

515275 2EGH-6061 SADDLE HANGER

F1.30a FP-PE-NDE- VT 12012V023 / NAD D5 530

F1.30a FP-PE-NDE- VT 1 2012V001 1 NAD D6 530

F1.30b FP-PE-NDE- VT 12012V002 / NAD D6 530

F1.30b FP-PE-NDE- VT 12012V004 1 NAD D6 530

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

ACC NO2 Cladding 2 100% 2 2 2

Required for Required for Comp to Cat. Item No. Code Case Population Interval Interval Total Sched Date.

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

100% the cladding and nozzles every third outage under GMP ACC-001. ccumulator nozzles owner elected examination.

% Cornp to Date.

B-A B1 .I 1 B-A 81.21

Notes

3 100% 3 3 0 0% RV shell circ welds. Deferral to end of interval allowed per IWB-2500-1

1 100% 1 1 0 1 0% 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 .

Total. 27 - 21 l4 . I 33Y. I

B-D B3.100 6 100% 6 6 0

B-D 83.120 5 100% 5 0 5

B-D 83.140 4 100% 4 2 2

B-D 83.160 RR-4-2 6

B-D B3.90 6 100% 6 6 0

1 I~eactor vessel Closure Head Bare Metal Examinaiton. Augmented Examiantion required every 3rd outage. Not included in count.

0%

100%

50%

0%

B-G-I B6.180

B-G-1 B6.190

RV nozzle inside radius. Deferral to end of interval allowed per IWB-2500-1

Pressurizer nozzle full pen welds.

SG tubesheet to head. One of each similar vessel. Class 1 HX full pen nozzles. W - 2 each outage per RR-4-2. Not included in count.

Vessel full pen nozzle welds. Deferral to end of interval allowed per code case.

Page 1 of 4

- --

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.

2 0 0 0

2 0 0 0 0

Deferral to end of interval allowed per IWB-2500-1. Each component is a set of 24 RCP bolts. Only required when required by B-L-2.

Flange surface only required when disassembled

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% IRV interior 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 ~er i~hera l CRDMs 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 o pressure test procedures each outage.

Total. 2 12 2

l 0 I I B-Q 616.20 2 0% 0 0 0 I 0% ISG tubing per Technical Requirements Manual

Total: 2 0 0 O 1 ° % 1

C-A C1.10 Welds a t gross structural discontinuity only. The examinations are limited to one vessel

8 50% 4 1 3 I 75% 1 among a group of vessels of similar design, size, and service.

C-A C1.20 4 50% 2 1 1 1 50% l ~ e a d circ welds. Tubesheet to shell welds.

C-B C2.21 C-B C2.22 C-B C2.31 - --

Total - 1 2 6 I - 5

C-C C3.10 4 50% 2 0 2

C-C C3.20 99 10% 10 1 9

C-C C3.30 16 10% 2 0 2

Reinforcing plates.

Vessel attachment welds. One of similar vessels. Piping weld attachments Pump weld attachments Valve weld attachments

Class 2 pressure tests completed once each period Some completed after outage.

D-A D1.10 Pressure Vessel Welded Attachments. For multiple vessels of similar design and service only

8 50% 4 0 4 1 100% ( 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 F-A F-A F-A F-A F-A

F-A F-A F-A

Class 1 pipe supports one direciton Class 1 pipe supports multidirection Class 1 pipe supports thermal movement (springs). Class 2 pipe supports one direciton Class 2 pipe supports multidirection Class 2 pipe supports thermal movement (springs). Class 3 pipe supports one direciton Class 3 pipe supports multidirection Class 3 pipe supports thermal movement (springs).

Page 3 of 4

F-A F1 40 74 37 3 38

R-A R1.ll-2

R-A R1.ll-5 R-A R1.15-2

R-A R1 .I 6-2 R-A R1 .I 6-5 R-A R1 .I 9-5 R-A R1.20-4 R-A R1.20-6

RI-IS1 Thermal fatigue high risk RI-IS1 Thermal fatigue medium risk

PWSSC high risk (pressurizer nozzle) SCC high risk

SCC medium risk ECSCC medium risk

Not subject to damage medium risk Not subject to damage low risk Not subject to damage low risk

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 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.

Page 4 of 4

-


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 (El . l l and E l -30) in scope for the second IWE period (111 0112 - 511 111 5). 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 lOCFR50.55a(b)(2)(ix)(A) to address indication of reheling cavity leakage in contact with the steel containment vessel (AR1332452).

of 1

1. Owner: Xcel Energy

2. Plant: Prairie Island Nuclear Generating Plant 3. Plant Unit: 2

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)

4. Owner Certificate of Authorization (If Req.):

5. Commercial Service Date: 12/21/1974 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 E l . l l FP-PE-NDE-540 VT 12012V074 1 NAD PC 2/231201 2 IS1

Primary 600691 Containment Bolted Connections E l . l l FP-PE-NDE-540 VT 12012V075 / NAD PC 2/23/2012 IS1

Bolting

Primary

600441 Containment Moisure Barrier

4/23/2012 PSI Moisture Barrier E l .30 FP-PE-NDE-540 VT 12012V073 1 NAD

IWE Completion Code Compliance Summary - Second Interval ISI Code Edition - 2001 Edition, 2003 Addenda

period.

Summary Percent Total Required Total Comp. Cat. Item No. No. Comp Desc. Population Required for Interval Total Sched To Date Cumm %

Moisture Barriers 100%

Notes

Moisture Barrier each period.

E-A E l . l l 600660 Primary Containment 1 3 1 2 Surface areas

Primary Containment 100% each

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 1 OCFR50.55a(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 most 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 1 R27 (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 50.5 5 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 50.5 5 a(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.


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.

The following pressure tests were conducted during Unit 2 cycle 26 and are credited to the third period. All indications were evaluated and coi~ective measures perfoinled as required by IWA-5250, IWB-3 142 and IWC-3 132.

,

Code Class Pressure Tests Unit 2 CycIe 26 Second Period

CV, RH, CS C-H SP 2168'25 A"

' 37891 1 Building Trench

Code Class Pressure Tests Unit 2 CycIe 26 Third Period

WO# 378903

38951 6

378906 .

Procedure SP 2168.1 1 Main Steam

SP 2168.14 Containment Spray

System Pressure Test SP 21 68'16

, Volume Control Svstem

System Main Steam

Containment Spray

Volume a Control

No relevant 0312511 1 ' indications

Cat. C-H

C-H

, C-H

System

Reactor Coolant

Comp Cooling

Comp Cooling

Aux Feed

Cooling Water

Comp. 09/13/10

0812011 0

1210711 1

WO#

409632

420369

41 5362

420371

417533

Indications No relevant indications

No relevant indications

No relevant , indications

Cat.

B-P

D-B

C-H

C-H

C-H

Comp.

0512611 2

0512411 2

04/23/12

In Prog.

0512411 2

Procedure

SP 2070 Reactor Coolant System

Integrity Test

SP 2168.4 Component Cooling

Class 3 SP 2168.4A

Component Cooling Class 2

SP 2168.6 Auxiliary Feedwater

SP 21 68.8 Cooling Water to FCU's.

Class 2

Indications Relevant indication

evaluated and found

acceptable for continued service AR 1332189.




Cooling Water

Residual Heat

Removal

Safety Injection

Post LOCA Hydrogen

RC, SI, VC, RH, CS, SF

D-B

C-H

C-H

C-H

B-P, C-H

SP 2168.8 Cooling Water to FCUJs.

Class 3

SP 21 68.10 RHR System

SP 21 68.13 Safety Injection System SP 2168.15 Post LOCA H2 Control

Svstem

SP 2392 Unit 2 Insulated Bolted

Connection Inspection

In Prog.


Relevant indications

evaluated and found

acceptable for continued

service ARJs 1338369, 1338370, 1338384, 132461 6, 1337667, 1338362.


Relevant indications

evaluated and found

acceptable for continued

service AR's 1328653, 13321 89.


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


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.

N S P M INSERVICE 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 wh ich ident i fy Prairie Island Unit 2 Repaid Replacement Activities during fuel cycle 26, 4t" IS1 Intewal. The gaps in i tem 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 i 1057 i I -- ........ -{. .......... 1. ............................ / 2-26-004 14041 47-01 i Replaced the mechanical seal IVC j 2 I I

1 igland plate i I i 1- 1." E-.-..-....-.-.-2..-.-...-.-------.. .-

2-26-006 1405904-01, EEC-1554 I Replaced bonnet assembly. I

12 ----..-=.-J.-.-----.==.- =-- -------=-+---.-.---.---;--.----- - ---- - - .--. -; -==, :- &.--

2-26-007 141 781 7-02 . 1 Replaced packing assemblies. 'VC 2-26-008 141 5821 -01 1 %built spare charging pump IVC

12- .-.--a--ie--&.?l,__--; --- ;- -------...------ --- .- -_.-.-- - j2

. ... I Replaced trim including the main : S

t land inner plugs. I r

--- - ---------.- r - ---il-.- - - -- - =;_---_ - ---- i !Replaced oackinq assemblies. ]VC : . C . i . . .................. . : 1 1 -..A...---.---. .

~j >..-..

12-26-01 5 i429773-01 j Replaced packing assemblies. VC 12 ; ! '̂.--.-..-....---..-I--- .--.----*f.-...- .- ....... i ....... -- ...

12-26-01 6 41 1 121 -01, EC-15389 1 ~ e ~ l a c e d mechanical seals with j 3 I

! 1 1 new cartridge type seals with icC ! i 1 1 1 integral gland plate I L I L j - 12-26-01 7 141 8558-01 /Replaced valve block. IsG i I I

l~eplaced internal trim including the (AF i 3 1 *-I,- ..~a-.-----.v-L--~ ----=x-- ------ .---" --.. - .-------- ,=-* *a=>.

i2-26-018 141 01 83-01 i I t /plug. I

i

i % _A__.. & ......._....-~.~....A.....~...-d..-.--4..._.--.....-.__..........-....--.-...-.... .-..._.-.-_-..._..--..._-_..--A...-_

12-26-020 I371 272-01 /Replaced bonnet and bonnet h ~ - 1 3 I ....... fasteners i -- ... - - 1.- - 1 1 ......-~...--...~.....l~-- .

ivc 2-26-022 ,424867-01 /Rebuilt spare charging pump 12 1 packing assemblies. i

- . -- L I 2-26-023 11 08895-01 i ~eplaced body to bonnet

iSI i 2

I i 'fasteners i -. I 2 ... i-- .-_2.

2-26-025 ] 1 1061 6-05 1 Replaced the valve and flange CL 13 I bolting i i

...... I . ... - , ........... . I . .: --,i - . .... 2-26-026 1395532-01 r ---

i Replaced disc. IAF : 12 - i . 2-26-027 ....... 141 / 8559-01 1 Replaced valve block. IS G

i," . ............ 2-.. -.

2-26-028 1443354-01 Replaced anchor bolt. ~ S I 12 I - J ;

I .

2-26-031 1446435-01 .......... [Replaced packing assemblies. I VC .......

2-26-032 I41 4266-01, EEC-1472 valves and associated /ZH 13 i

! ........ 2-26-033 '443403-01 jRebuilt spare charging pump

i IVC

L _ .-......---...-.....---.-...--...*....-..-.........,-L....-...--...-...._A r .........A................- 12 1

j I .'2-26-035 i ... 1371691-01 1

....................

j 2-26-039 i308073-0 I -. i --,_.-I_--._ !-; .-*---=;.-_

t2-26-041 / 157621-01, EC-19365, ~eplaced Valve and flange RH [2 I EC-1 9855 jfas'teners as well as the block plate 1 ,

[fasteners. j . ... -- ! Reolaced the valve disc and one IMs

I i ! ! i .... 1 .. ........ .L body to cover fastener set : .......... . .............. I i

IRH :2-26-043 14061 27-01 1 Replaced valve disc. 12 !;---A" -i- .--=- ".-;- -- --.---..,-_ ,-- ,..-*c-.---.-.;-- 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

! i !

i I

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. ....... 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 added new support. 1 --------- --------- --=---- --- ------- ---"----- Replaced several cover or flange ICC b stubs and nuts. ......... ..........

Replaced snubber bolted connection with . = pinned connection. = _ _ _ : L.- . . .- - _ _ Properly contoured the support to J C C 12 allow adequate clearance between ! pipe and support structural 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 201 0-057

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

7. Description of Work Replace desurger cap screws.

8. Tests conducted: ' ~~drostiti;tic/-!J' Pneumat ic0 Nominal Operating Pressure 0 Exempt

Component Name

23 CHG PMP DlSCH HYD DESURGER

Other 0 Pressure psi Test Temp. O F

Other: n/a

Yr Built

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.

Manufacturer Name

EATON

Corrected, Removed, or Installed

Corrected

Manufacturer Serial #

3139-7

ASME Code Stamp

0

Nat'l Bd # Other ID

262-393

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.

J/& Type Code Symbol Stamp

pn" Certificate of Aut Expiration Date

Signed , ASME Program Engineer Date 7hLo 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 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

Name 2. Plant Prairie Island ~uclear'Generating Plant

Name 1717 Wakonade Dr. E, Welch Minnesota 55089

Address 3. Work Performed by Owner

- -

Name Same

Address

Date 12/1/2010 .

Sheet

Repair organization P.O. No., Job No., etc

Type Code Symbol Stamp NIA

Authorization

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 1 2000A


.6. Identification of Components

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

Nat'l Bd # Component Name

21 BA Transfer Pump


ASME Code Stamp

0

Other ID -

245-031

Manufacturer Name

Goulds

Yr Built

1970


792A192-1


Corrected

FORM NIS-2 OWNER'S REPORT FOR REPAIR1 REPLACEMENT ACTIVITY

9. Remarks



Type Code Symbol Slarnp dl& Expiration Date

, ASME Program Engineer Date I < / / // d , 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 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 REPAIR1 REPLACEMENT ACTIVITY


Name 2. Plant Prairie Island Nuclear Generating Plant

Name 1717 Wakonade Dr. E, Welch Minnesota 55089

Address 3. Work Performed by Owner

Name Same

Sheet 1 of 2

405904-01, EEC-1554

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

Type Code Symbol Stamp N/A

s Address Expiration Date ' N/A

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


6. ldentification of Components

7. Description of Work Replaced bonnet assembly.

. 8. Tests conducted: Hydrostatic Pneumat ic0 Nominal Operating Pressure Exempt

Component Name

23 Charging Pump Suction valve

Other [ll Pressure ps i TestTernp. OF

Other: nla

Manufacttjrer Name

Grinnell

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.

ASME Code Stamp


Nat'l Bd # Other ID

2VC-6-7

Yr Built Corrected, Removed, or Installed

Corrected

ITEM 2-26-006

9. Remarks



Type Code Symbol Stamp /J/&

Expiration Date

, ASME Program Engineer Date / d< // 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 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



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

Name 1717 Wakonade Dr. E, Welch Minnesota 55089 417817-02




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


6. Identification of Components

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

Nat'l Bd # Manufacturer Serial #

691 7

Component Name

21 Charging Pump

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

Manufacturer Name

Ajax

Other ID

245-041

Yr Built

1969


Corrected

ASRIE Code Stamp

FORM NIS-2 OWNER'S REPORT FOR REPAIR1 REPLACEMENT ACTIVITY.

- .

9. Remarks



Type Code Symbol Stamp / j / , Expiration Date

, ASME Program Engineer Date / /2fid/ , , U -

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 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



Mt.id191'4 Commissions National Board, Province and Endorsements

Date

Date 5/9/2011 I. Owner Xcel Energy, NSP-M Nuclear Department




Name Same ~uthor iz i t ion NIA



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~plicable Section XI Code Cases None

6. ldentification of components

7. Description of Work Rebuilt spare charging pump packing assemblies.

8. Tests coXducied: ~ ~ d r o s t a t i c ~ ' Pneumatic0 Nominal Operating Pressure n Exempt @

Other Pressure psi- Test Temp. . O F

Other: nla

Other ID

Spares

Component Name

Spare Charging Pump Packing Assemblies

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.

Manufacturer, Serial #

Manufacturer Name

Goulds

Nat'l Bd # Yr Built Corrected, Removed, or Installed

Corrected

ASME Code Stamp

C]


ITEM 2-26-008

9. Remarks



Type Code Symbol Stamp d)# Expiration Date

, ASME Program Engineer Date d&// 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 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 . 1 4




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 de~ lacemen t Activity 'l998E / 2000A



7. Description of Work Replaced trim including the main and inner plugs.

8. Tests conducted: Hydrostatic 0: Pneumatic0 Nominal Operating Pressure Exempt

compo"ent Name

22 SG PORV

Other Pressure psi Test Tern p. O F

Other: Inservice testing will be performed in accordance with SP-21116,

Other ID

CV-31107


Manufacturer . Name

Copse Vulcan

Yr Built Manufacturer Serial #

701 0-95075-1-1


Corrected

Nat'l B.d sk ASME Code Stamp


ITEM 2-26-013

9. Remarks



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 21 APILIt 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 S P.J-I m d ~1424 -. - National Board, Province and Endorsements

Date ----

- --- -- I


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


, , 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


Addenda nla Code Cases n/a " ' .

(b) ~ppl icable Edition of Section XI Utilized for RepairlReplacement Activity 1998E 12000A~ . 1 '



- - -


8. Tests cond.ucted: . Hydrostatic . . Pneumatic0 Nominal Operating Pressure Exempt

ASME Code Stamp

Other Pressure psi Test Temp. O F

Other: nla

Component Name

22 Charging Pump

NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 I 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.

. .

Manufacturer Name

Ajax


Yr Built

1969


Corrected

Nat'l Bd # Other ID

245-042

9. Remarks



Type Code Symbol Stamp ~4 Expiration Date ,

, ASME Plograrn Engineer ' Date p?/aii% 2 Owner or Owner's Designee , Title

L--~


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 ~ n s ~ e c t d r ' w a t u r e . National Board, Province and Endorsements

097 ,b id . Date

I. Owner Xcel Energy, NSP-M Nuclear Department

Name 2. Plant Prairie Island Nuclear Generating Plant

Name 1717 Wakonade Dr. E, Welch Minnesota 55089 .

Address 3. Work performed by Owner

Name Same

ITEM 2-26-01 5

Date 1011 91201 1

Sheet 1 of 2

429773-01

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

Type Code Symbol Stamp N/A

Authorization . . N/A


4. ldentification of System VC Code Class 2



(b) Applicable Edition of Section,XI Vtilized for RepairlReplacement Activity 1998E 12000A




8. Tests conducted: Hydrostatic CJ Pneumatic0 Nominal Operating Pressure Exempt


Other: nla . .


Component Name .

23 Charging Pump

NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (I) size is 8 1 12 in. x 1 I in., (2) information in items 1 through 6 on this report is.included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.

Manufacturer Name

Ajax

ASME Code Stamp

0

Other ID

245-043

Yr Built

1969

Corrected, Removed, or Installed.

Corrected

' ITEM 2-26-015

9. Remarks

,



Type Code Symbol Stamp /J& , .

Expiration Date

, ASME Program Engineer Date / d / / P / /

Owner or Owner's Designee, Title


I, the undersigned, holding a valid commission issued by the National ~ o a r d 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 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.

(-py-cCkn .Q+ omm missions L i ? o ~ s A-J., \ C/ lnspector 's~nature National Board, Province and Endorsements

Date

NIS-2 OWNER'S REPORT FOR REPAIR1 REPLACEMENT ACTIVITY

I. Owner Xcel Energy, NSP-M Nuclear Department Date 7/23/2012


Name 1717 Wakonade Dr. E, Welch Minnesota 55089 41 1121-01, EC-I5389



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



lcompo"ent Name

22 CC pump t------ Manufacturer Name

- - -

Goulds

Manufacturer Nat'l Bd $ Serial #

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 1 I in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.

9. Remarks



Type Code Symbol Stamp dh Expiration Date

, ASME Program Engineer Date 7h3//2 ,



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


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.

m n . Q q - A om missions ietQo%s A*h\.l ~ h s 3192-4 In pector's Signature National Board, Province and ~ndorsements

Date Qu& $3 3 QifL

-,-A- - --------


- Name 2. Plant Prairie Island Nuclear Generating Plant Sheet 1 of 2

Name 1717 Wakonade Dr. E, Welch Minnesota 55089 41 8558-01




4. Identification of System SG Code Class 1



(b) Applicable Edition of Section XI Utilized for RepairIReplacement Activity 1998E 1 2000A

(c) Applicable Section XI Code Cases None . .


7. Description of Work Replaced valve block.

8. Tests c~n,ducted: Hydrostatic . Pneumatics ' Nominal Operating Pressure 0 Exempt @

ASME Code Stamp

El


Other: nla

Component Name

SG Snubber Block Valve

NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1 12 in. x. I I in., (2) information in items . 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.

Other ID

21 SIG03

Manufacturer Name

McDowell Welman

1


7221 8-000-1 8 ,

Yr Built Nat'l Bd # Corrected, Removed, or Installed

Installed

AIR/ REPLACEMENT ACTIVITY

ITEM 2-26-01 7

9. Remarks



Type Code symbol Stamp ,I.//A

Expiration Date

, ASME Program Engineer Date d%aQdZ 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 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~y of property damage or a loss of any kind arising from or connected with this inspection. . , -

~ ~ ~ ? ~ ~ ~ r e Commissions .-

J B ~he A . ~ s . I mrJ atqw . . - - - ~at iona lEard , Province and Endorsenients

Date - -.*L , %D 1% ,

-.---- ------- I

FORM NIS-2 O.WNERIS REPORT FOR. REPAIR1 REPLACEMENT ACTIVITY

1. Owner Xcel Energy, NSP-M Nuclear Department Date 61271201 2


Name 1717 Wakonade Dr. E, Welch Minnesota 55089 41 01 83-01



Address ~xpirat ion Date NIA

4. Identification of System AF Code Class 3

5. (a) Applicable Construction Code ASME Ill 1968 EditionlAddenda


(b) Applicable Edition of Section XI Utilized for RepairIReplacement Activity 1998E / 2000A



7. ~ e s c r i ~ t i o n of Work Replaced internal trim including the plug.

8. Tests conducted: ' ~ ~ d r o s t ' i t i c fJ Pneumaticu Nominal Operating Pressure Exempt

Component Name

22 TD AFW PMP MS SPLY Valve


Other: Exercise testing in accordance with the requirements of the IST program.


7620-95400-25- 12

Manufacturer Name

Copes Vulcan

NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1 12 in. x 11 in., (2) information in items I through 6 on this report is included on each sheet, and (3) each she$ is numbered and number of sheets is recorded at the top of this form.

Nat'l Bd # Other ID

CV-31999

Yr Built

1968


Corrected

ASME Code Stamp

0


ITEM 2-26-01 8

9. Remarks


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


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 M s o G i t 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

(lux11 I

CEMENT ACTIVITY


Name 2. Plant Prairie Island Nuclear Generating Plant Sheet I of 2






5. (a) Applicable Construction Code NIA ' NIA EditionlAddenda

Addenda NIA Code Cases NIA '

(b) Applicable Edition of Section $I Utilized for RepairlReplacement Activity 1998E / 2000A . '



7. Description of Work Replaced bonnet and bonnet fasteners.

. ' ~

8. Tests conducted: , . ~ydrostatic 0 'pneumatic0 Nominal Operating Pressure Exempt


Other: nfa

Other ID

259-201

Con~ponent Name

22 TD AFW PMP Turbine governor valve



Manufacturer Name

Terry Turbine


Corrected

ASME Code Stamp

9. Remarks



Type Code Symbol Stamp J 14

Certificate of Authorizati Expiration Date

Signed , ASME Program Engineer Date flh//k , 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 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 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 - t b l b % s n.u-\ MI( 21914 National Board, Province and Endorseinents

.- -

1. Owner Xcel Energy, NSP-M Nuclear Department Date 1011 81201 1


Name 1717 Wakonade Dr. E, Welch Minnesota 55089 424867-01 ,





5. (a) Applicable Construction Code nla nia EditionlAddenda

.,. Addenda nla Code Cases nla

(b) Applicable Edition of section XI Utilized for RepairlReplacement Activity. 1998E I 2000A ,

(c) ~ ~ ~ l i c a b l e Section XI Code Cases None

6, ldentification of Components

7. Description of Work Rebuilt spare charging pump packing assemblies. . .

8. Tests conducted: Hydrostatic 0 Pneumatic0 Nominal Operating Pressure q Exempt

Component Name


Other Pressure psi Test Tern p. O F

Other: nla


Corrected


ASME Code Stamp

Yr Built Manufacturer Name

Goulds


Nat'l Bd # Other ID

Spares

ITEM 2-26-022

9. Remarks

-



Type Code Symbol Stamp E/h Certificate of Authoriza Expiration Date

Signed , ASME Program Engineer Date /d/z 4 w



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'LSEP I \ to . ~qacr t 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 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 S a.A.1 .

National Board, Province and Endorsements

I. Owner Xcel Energy, NSP-M Nuclear Department Date 61261201 2

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



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


(b) Applicable Edition of Section XI.Utilized for RepairlReplacement Activity 1998E / 2000A

(c) Applicable Section XI Code Cases None .


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 ,

Yr Built

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.


Component Name

SUMP B TO 22 RHR PMP TRN B (INSIDE) MV


Corrected

Other ID

MV-32179

Manufacturer Nam'e

Crane

ASME Code Stamp

ITEM 2-26-023

9. Remarks



~~~k Code Symbol Stamp A A'%- Expiration Date

, ASME Program Engineer Date &,,2 - , 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 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

, ,

. . -


Name 2. Plant Prairie Island Nuciear Generating Plant Sheet 1 of 2

Name 1717 Wakonade Dr. E, Welch Minnesota 55089 I 10616-05


Name Same Authorization N/A


4. Identification of System CL Codeclass 3

5. (a) Applicable Construction Code B31 .I 1967 EditionIAddenda

Addenda nla Code Cases nla "

1998E 12000A (b) Applicable Edition of Section.XI ~ l t i l i i ed for RepairlReplacement Activity



7. Description of Work Replaced the valve and flange bolting.

8. Tests conducted: Hydrostatic PneumaticC] Nominal Operating Pressure [Z1 Exempt

Component Name

22 CLG WTR PMP DISCH

Other C ] . Pressure , psi Test Temp. O F

Other: nla

Nat'l Bd #

NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1 12 in. x 11 in., (2) information in items I through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.

Manufacturer Name

Pratt

Other ID

2CL-39-2


ASME Code Stamp


Installed

PRAIRIE ISLAND NUC

ITEM 2-26-025

9. Remarks



Type Code Symbol Stamp

Certificat

Date ~ / / 6 . / / 2 Signed



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 3OS€Plt 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, Sect io~ 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 1 h 5 pd-t md ~ S W Commissions ------- National Board, Province and Endorsements

-


Name 2. Plant , Prairie Island Nuclear Generating Plant Sheet 1 of 2




Address ~ x ~ i r a t i o n Date NIA


5. (a) Applicable C~nstruction Code 816.34 , nla EditionlAddenda


(b) Applicable Edition of Section XI Utilized for RepairIReplacement Activity 1998E 1 2000A '



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

Other ID

MV-32246

Component Name

22 AFW TO 21 SG MV

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


Manufacturer Name

Powell


Corrected

- ASME Code Stamp

ITEM 2-26-026

9. Remarks



Type Code Symbol Stamp &.(A Certificate of Aut Expiration Date

Signed : ASME Program Engineer Date k jq//! , 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 Insp, and Ins. Co. of Connecticut of Hartford Conn. have inspected the components described in this Owner's Report during the period ~&RwW 3@5Eell to , BIJtJuEJt'L I


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

V . D d 2 , w. . ~ummissions i \ l ~ ~Qr~fs A*l' aiq'?~ \ I spector's signathe

. . National Board, Province and Endorsements

Date " +,.?$--.-;- ccw od . Q042

. ~ . . , . . ,

.- ----------






Name Same '

Authorization NIA


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 n of Secfion XI utilized for RepairlReplacement Activity 1998E / 2000A



7. Description of Work Replaced valve block. I 8. Tests conducted: Hydrostatic . Pneumatic0 Nominal Operating Pressure Exempt


Other: nla

Other ID

22SIG03

Nat'l Bd #

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.


72218-000-1 5

I .

Component Name

SG Snubber Block Valve

Yr Bu'ilt Manufacturer Name

McDowell Welman


Installed

ASME Code Stamp

•


ITEM 2-26-027

9. Remarks VT-3 recorded in report 2012V057.


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


I Owner or Owner's Designee , Title


I I, the undersigned, holding a valid commission issued bv the National Board of Boiler and Pressure Vessel

measures described in this owner's ~ e p o r t in accordance with the requirements of the ASME Code, Section XI. I I

'

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

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

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


q. Owner Xcel Energy, NSP-M Nuclear ~epartment Date 1013112011





Address Expiration Date NIA 4. ldentification of System SI Code Class 2 I 5. (a) Applicable Construction Code AWS D l .I , nla EditionlAddenda

Addenda nla. Code Cases nla '

. , (b) Applicable Edition of Secti-on XI Utilized for RepairlReplacement Activity . 1998E 12000A



7. Description of Work . Replaced anchor bolt.

8. Tests conducted: Hydrostatic 0 Pneumaticn Nominal Operating Pressure D Exempt

Component Name ,

SI system support


Other: nla

Manufacturer Name

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.


Other ID

2-RSIHr241


Corrected

ASME Code Stamp

0

9. Remarks VT-3 exam recorded on PSI report 201 1V095

. CERTIFICATE OF COMPLIANCE


~ y p s Code symbol stamp dh Certificate of Auth

.

Expiration Date

Signed , ASME Program Engineer Date 10 /J/ /// 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 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

Date 1/4/2012 1. Owner Xcel Energy, NSP-M Nuclear Department






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




8. Tests conducted: ~ ~ d r o s t a t i c Pneumaticn Nominal Operating Pressure Exempt

Other D pressure psi Test Temp. O F

Other: nla


Corrected

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

ASME Code Stamp


6917

Component Name

21 Charging Pump

Manufacturer Name

Ajax

,Other ID

245-041

Yr Built

1969

9. Remarks



Type Code Symbol Stamp ,d/b Expiration Date I

, ASME Program Etigineer Date //.///a ,



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 c r 5 J ~ d 4 ' 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 S A . ~ J . \ rnt.fal.9*y 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 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



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


6. ldentification of Components.

7. Descriptipn of Work , Replace yalves. and associated piping.

8. Tests conducted: Hydrostaticn Pneumaticu Nominal Operating Pressure Exempt

Component Name

11 1 SWGR RM UNIT CLR'SPLY

P

11 1 SWGR RM UNIT CLR RTRN

Other C] Pressure NOP psi Test Temp. NOT O F

Other ID

2ZH-4-7

2ZH-4-8

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. . . , . , . .

Manufacturer Name

Vogt

Vogt

ASME Code Stamp

Il

0



Installed

Installed


9. Remarks VT-2 Leakage Test.recorded on report BOP-VT-12-002.



Type Code Symbol Stamp d/# Expiration Date

, ASME Program Engineer Date 2 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 Insp. and Ins. Co. of Connecticut of Hartford Conn. have inspected the components described in this Owner's Report during the period cWdclov4t to d 7 K r 3 I L I



I (?yzn.QQy ~ommissihns D 1'2085.A*tJ .1 f l iaf924 \ ector's ~ i g n a t d e 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 I 2000~' ,


ldentification of Components

7. Description of Work . Rebuilt spare charging punip packing assemblies.

8. Tests conducted: ~ ~ d r o s t a t i c 0 Pneumat icu Nominal Operating Pressure C ] Exempt

Other .Pressure psi Test Temp. O F

Other: nla

Component Name


NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size' is 8 1 12 in. x 11 in., (2) information in items' I through 6 on this report'is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.

,

Other ID

Spares

Manufacturer Name

Goulds

Yr Built Manufacturer Serial #

Edat'l Bd # Corrected, . Removed, or Installed .

Corrected

ASME Code Stamp

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 d l 4 Expiration Date

. , ASME Program Engineer Date / /d 7//2 , w


CERTIFICATE OF INSERVICE INSPECTION .

I,' the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of 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 - ~ommis$ io is 4 . m i 9192.q

pector',~ ~ i g d r e National Board, Province and Endorsements

Date % ' a q i4T ,

- ------


Date 6/1/2012 ?. Owner Xcel Energy, NSP-M Nuclear Department

Name 2. Plant Prairie island Nuclear Generating Plant Sheet . 1 2 of



Name Same Authorization NfA

Address ~xpiration Date 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



7. Description of Work Replaced disc.

Cb?mponent Name

22 AFW TO 22 SG MV

8. Tests conducted: Hydrostatic Pneumat ic0 Nominal Operating Pressure [IIJ Exempt

Other [7 Pressure psi Test Temp. O F

Manufacturer Name ,

PowellNVeir

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.


Yr Built NaYl Bd # Other ID

MV-32247


Corrected

ASME Code Stamp

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


I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the S ta t e o r Province of Minnesota and employed by HSB In'sp. and Ins. Co. of Connecticr~t of Hartford Conn. have inspected the components described in this Owner's Report during the period (64JmI'L . t o CPbJofdl'L , and s ta te that to the bes 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 any warranty, expressed o r implied, concerning the examinations and corrective .measure described in the Owner 's Repolt. Furthermore, neither the Inspector nor his employer shall b e liable in any manner for any personal injury of property d a m a g e or a loss of any 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

--- -- .- ----

Date 4/16/2012 1, Owner Xcel Energy, NSP-M Nuclear Department





Address Expiration Date N/A 4. Identification of System VC Code Class 1

, 1967 5. (a) Applicable Construction Code 831 .I EditionlAddenda

Addenda nla Code Cases nla ,




-- - -

7. ~escr ipt ion of Work Replaced spring can upper rod.

VC piping spring can support

- 6 . . . 8. Tests conducted: , ~ ~ d r o s t ' i t i c fJ ' Pneumatic0 Nominal Operating Pressure Exempt


Component Name


Other: nla

Nat'l Bd # Manufact~irer Name

Basic Engineering

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.

Other ID Yr Built

2-RCVCH- 1575


ASME ,

Code Stamp

Corrected 5

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



Expiration Date

, ASME Program Engineer Date YA? /$a . , 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 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, omm missions LB 1200s A.A.1 ma $1924

\ w p e c t o r ' s ~ i g n a t u g National Board, Province and Endorsements

Date d a ~ b , ~ a , O ' '

PRAIRIE ISLAND NUCLEAR GENERA




Name 1717 Wakonade Dr. E, Welch Minnesota 55089 157621-01, EC-19365, EC-19855




4. Identification of System RH Code Class 2

5. (a) Applicable Construction Code 831 .I 1967 EditionlAddenda

Addenda nla CodeCases, nla ' .



6. Identification of Components.

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

Ccj; vcted, Removed, or Installed

Installed

- -

NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 I I2 in. x 1 I in., (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.

Other ID

CV-31239

ASME Code Stamp

Nat'l Bd # Component Name

22 RHR HX RC OUTL valve

Yr Built ~anufaciurer Name

Fisher


D NUCLEAR GENERATING PLANT

9. Remarks



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 F€0 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. mJ 31q24 National Board, Province and Endorsements

Date

. . -.-.--- ---.- ---- 1




, Address Repair Organization P.O. No., Job No., etc 3. Work Performed by Owner Type Code Symbol Stamp 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 I 2000A



7. Description of Work R!

8. Tests conducted: Hydrostatic17 Pneumaticu Nominal Operating Pressure Exempt @

component Name

21 SG MS ISOL CV


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

ASME Code Stamp

0

Nat'l Bd # Corrected, Removed, or Installed

Corrected

Manufactuiir Name

Schutte & Koerting

Other ID

CV-31116


Yr Built

ITEM 2-26-042

9. Remarks



Type Code Symbol Stamp A / #

r / / a Expiration Date

, ASME Program Engineer Date ' k ,(<-//3


- . -,-. -- - 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 fbwGi!? to _ 05 Jur3l2 ., and state that to the best of my knowledge and belief, the 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 d6 ('2085 e * d . \ MA $(?'LC1 National Board, Province and Endorsements

Date

. . , . ,


I. Owner Xcel Energy, NSP-M Nuclear Department Date 513012012


Name 171 7 Wakonade Dr. E, Welch Minnesota 55089 4061 27-01



Expiration Date NIA Address 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 & m e n t Activity 1998E I 2000A


6, Identification of Components

Replaced valve disc. 7. Description of Work

8. Tests conducted:, Hydtostatic,a Pneumatic Nominal Operating Pressure 0 Exempt

Other Pressure psi Test Temp. F

Other: nla

~orroeied, Removed, or Installed

Corrected

Component Name

21 RHR PMP Suction Line Chk

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.

Nat'l Bd # ASME Code Stamp

Manufacturer Name

Crane

Other ID

2RH-3-2


Yr Built

ITEM 2-26-043

9. Remarks



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 . ~ Commissions d o \ ~ o % s ~ ~ d . t (ulJd~24 ector's sign& National Board, Province and Endorsements

Date -18 %it 4 1 ---

--.-



Name 1717 Wakonade Dr. E, Welch Minnesota 55089 374924-23, 37491 8-05




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 Sec t i~n XI Utilized for RepairIReplacement Activity 1998E 1 2000A



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.

Component Name' '

21 Steam Generator

22 Steam Generator

8. Tests conducted: ~ ~ d r o s t a t i c C] Pneumatics Nominal Operating Pressure Exempt @


Other: nla

Manufacturer Name

Westinghouse

Wesinghouse

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 . * . . - .

~anufacturer Serial #

1181

11 82

Nat'l Bd #

68-39

68-40

Other ID

234-01 1

234-01 2

Yr Built

1968

1968


Corrected

Corrected

ASME Code Stamp

id

9. Remarks

CERTIFICATE OF COMPLIANCE 1 . I We certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code, Section XI. I

I Type Code Symbol Stamp d / d I Expiration Date

a t e \~'/!~//.7 1 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 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 l0d.l -- MJ 2 t q ~ National Board, Province and Endorsements



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


Address ~xpiration Date , NtA 4. Identification of System SB Codeclass 2


Addenda nla Code Cases nla ' "

(b) Applicable Edition of section XI Utilized for RepairiReplacement Activity 1998E / 2000A


6. ldentification of Components .

Stamp 4 Component Name

SB system snubber

7. Description of Work Replaced anchor nuts.

8. Tests conducted: HydroStatic 0. Pneumatic0 Nominal Operating Pressure fJ Exempt

Manufacturer Name

BE

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 I 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.


Nat'l Bd # Other ID

2-RBDH-602


Corrected

9. Remarks VT-3 exam recorded under Report # BOP-VT-12-004



~ y p e code symbol Stamp

Certificate of A

Signed Date vhS/,? 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 1.7 MAQ 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.

w m . o = A y Commissions ie 1408s n.d.1 ~d a f 9 w National Board, Province and Endorsements

Date , blrl

. .


Date 511 01201 2 I. Owner Xcel Energy, NSP-M Nuclear Department


Name -1717 Wakonade Dr. E, Welch Minnesota 55089 454221-05, EC-I 9795


Name Same . Authorization NIA

~ d d r e s s Expiration Date NIA

4. Identification of System RC Code Class 1

5. (a) Applicable Construction Code ASME Ill, Class 1 1983 EditionIAddenda .\ ,


(b) Applicable Edition of Section,XI Utilized for RepairIReplacement Activity 1998E 1 2000A



RX Head Vent Orifice Bypass valve

Component Name

1 2RCT33 I ( installed 1 ° 1 Manufacturer- Name

7. ~ e s c r i ~ t i b n df ~ 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.

RCGVS Support .

8. Tests conducted: Hydrostatic Pneumat ic0 Nominal Operating Pressure Exempt


Other Pressure psi Test Temp. O F - Other: nla .

2-RCGV-1

NOTE: supplemental sheets in form of'lists, sketches, or drawings may be used, provided (1) size is 8 1 12 in. x I I in., (2) information in items 1 through 6 on this ,report is included'on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.

Nat'l Bd #

Installed

Other ID Yr Built Corrected, Removed, or Installed

ASME Code Stamp

2

ITEM 2-26-047

9. Remarks


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



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.

i@ IR2cbe-5 n . A - l rnA 4492~ Cornmissions ( lnsp$sctorls Signatur National Board, Province and Endorsements

Date

. . .





Address Repair Organization P.O. No., J o b No., etc 3. Work Performed by Owner Type Code Symbol Stamp NIA



4. Identification of System CC Code Class 3

5. (a) Applicable Construction Code ASME I l l , Class C 1968 EditionlAddenda

Addenda nla Code Cases nla ' ' '

(b) Applicable Edition of Section.XI. ~t i l ized for RepairIReplacement Activity 1998E 1 2000A



7. Description of Work

8. Tests conducted: .

Replaced several cover or flange studs and nuts.

Hydrostatic,D . .Pneumatics . Nominal Operating Pressure Exempt

Component Name

21 CC Heat Exchanger

Other Pressure psi Test Tem p. O F

Other: nla


696229-1 C

Manufacturer Name

Yuba

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 . / ' . . . .

Nat'l Bd # Other ID

235-031

ASME Code Stamp

Yr Built

1968


Corrected


9. Remarks



~ i ~ e Code Symbol Stamp /J,/a Expiration Date.

, ASME Program Engineer Date k/c7/~ , 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 Insp. and Ins. Co. of Connecticut of Hartford Conn. have inspected the components described in this Owner's Report during the period m A p R 1 2 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.


/-$sm.o$ Commissions I 0 8 5 r2 a . r J e l rd 214W I

In pector's Signature ' National Board, Province and Endorsements

Date J , dy '27 , QW'2

1. Owner Xcel Energy, NSP-M Nuclear Department Date 412812012





(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 I 2000A



7. Description of Work

8. Tests conducted:

Replaced snubber bolted connection with pinned connection.

Other ID

2-RCVCH- 1338

Nat'l Bd # ' Component Name

VC Line (2-2VC-17A) snubber

~ ~ d r o s t a t i c 0' Pneumaticn . Nominal Operating Pressure 0 Exempt


Other: n/a . . . . .

Yr Built Manufacturer Name

Basic Engineering

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 I through 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.



Corrected

ASME Code Stamp

17


ITEM 2-26-049

9. Remarks VT-3 exam recorded on report # BOP-VT-12-007



Type Code Symbol Stamp d i d Expiration Date

, ASME Program Engineer Date 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 ~erformed 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 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.

$8 1 % ~ Add, I m d192Y Commissions __ National Board, Frovince and Endorsen~ents

I








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 .


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.: sbPplemental sheets in fcim of lists, sketches, or drawings may be used, provided'(1) size is 8 1 12 in. x <:.I in., (2) information in items

. I through 6 on this report i,s included on each.sheet, and (3) each sheet is n~~rnbered a ~ d nuinber of sheets is-recorded at the top of this form.


Component Name

CC Line Support

Manufhcturer Name

Basic Engineering

Other ID

2-CCRH148

~r Built ' Corrected, Removed, or Installed

Corrected

ASME Code Stamp

C]

9. Remarks



Type Code Symbol Stamp d/# Certificate of Au Expiration Date

Signed , ASME Program Engineer Date s / Z q h T 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 . any kind arising from or connected with this inspection. ~. To%- Ins ecior's Sign - - -- \:; .P - .- missions ~atiunat I S 8oai-dl. A Pmviraca pn 1 d192.q aricl Endorsements

Date ----Ae- q3>..- -L

. . . . . . ---.---- _ .--_.-.. -;- i_-- +--.. --"- ."....- ---.-.-. -.-.-,------,-- ----.-I




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


.Addenda nla Code Cases nla

(b) ~ ~ ~ l i c a b l e Edition of Section XI Utilized for RepairlReplacement Activity 1998E / 2000A



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

8. Tests conducted: Hydrostatic .Pneumatic Nominal Operating Pressure Exempt

Component Name

21 RHR Pump

Other ' Pressure psi Test Temp. O F

Other: IST testing per H I 0.1


681N0274

Manufacturer Name

Byron Jackson

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

Nat'l Bd # Other ID

245-1 11

ASME Code Stamp

0


Corrected

ITEM 2-26-051

9. Remarks



Type Code Symbol Stamp dh i c e o f oriz ti n No. dl& @& Expiration Date

Signed , ASME Program Engineer Date d k / 2 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 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.

~omrni&ions l%CS -- A2N. t rnd 9142-4 nsp -tor's Signature .

------- National Board, Province and Endorsements

$ 0 7 QQ~. Date I ' .

. . !. . , . .

. . . . . . . , .

L. - ---- -




Address Repair Organization P.O. No., Job No., etc 3. .work Performed by Owner Type Code Symbol Stamp NIA

Name Same . Authorization 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 Ut i l i~ed for RepairlReplacement Activity 1998E / 2000A


6. ldentificatioti of Components

7. Description of Work Replaced Valve

8. Tests condiicted:' ' Hydrostatic fJ Pneumatic Nominal Operating Pressure CJ Exempt @

Component Name .

22 CLG PMP DSL ~acke i CLG FE 27321 \SOL

Other Pressure psi Test Temp. O F - Other: n/a

Yr Built

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. . .

Manufacturer Name .

Bonney Forge


Installed


ASME Code Stamp

Nat'l Bd # Other ID

2CL-89-1


9. Remarks


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


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 .


Name 2.' Plant Prairie Island Nuclear Generating Plant Sheet 1 of 2




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 SectionCXI Utilized for RepairlReplacement Activity 1998E I 2000A .



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 @

ASME Code Stamp

Other 0 . Pressure psi Test Temp. O F

Other: nla . .


Corrected

. . NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1.) size is 8 I I2 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.

Other ID

2-1 12-2CL-37 1 4-2CL-37

Nat'l Bd # Yr Built Manufacturer Serial #

Component Name

Piping Spool

Manufacturer '

Name


9. Remarks

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


Expiration Date

. , ASME Program Engineer Date ~h Oj/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 % m A ~ l r ~ , 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..

-

C. --- JB ~ ( ~ O P S P ~ & I MA !.V914 Commissions -: - \ National Board, Province and .Endorsements

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.

u / Date . Q ~ z 1 ?FA--

. .

Date 611 4/20? 2 1. Owner Xcel Energy, NSP-M Nuclear Department


Name 1717 Wakonade Dr. E, Welch Minnesota 55089 460351 -06




4. Identification of System RC Code Class 1

5. (a) Applicable Construction Code B16.34 , nla EditionlAddenda

Addenda nla Code Cases nla ,




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

Nat'l Bd #

. . 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.

ASME Code Stamp

Manufacturt?~. Serial #

Component Name

Loop A Hot Leg RTD Manifold Outlet

Corrected, .Removed, or Installed

Corrected

Other ID

2RC-1-9

~anufacturer Name

Rockwell

Yr Built

ITEM 2-26-054

9. Remarks

--



Type Code Symbol Stamp /;/A Expiration Date

, ASME Program Engineer Date


I .. ... 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 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 2q my1 2 to IEdur~t'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.

Cornmissions - JG 4'2085 Pod.' MA 01924 National.Board, Province andindorsements

Date

I I 1

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.

:

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