Text

Submittal of Inservice Inspection Examination Summary Report, Interval 4, Period 2, Outage 1, Refueling Outage, Dates: 09-19-2008 to 11-01-2008 Unit 2, Fuel Cycle 24:12-15-2006 to 11-01-2008
	ML090330172
Person / Time
Site:	Prairie Island
Issue date:	01/28/2009
From:	Wadley M; Northern States Power Co, Xcel Energy
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	L-PI-09-015
	Download: ML090330172 (162)
	v • d • e

XcelEnergys JAH 2 8 2009 L-PI-09-015 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 License No. DPR-60 Inservice Inspection Summary Report, Interval 4, Period 2, Outage 1, Refuelincq Outagqe Dates: 09-19-2008 to 11-01-2008 Unit 2, Fuel Cycle 24:12-15-2006 to 11-01-2008 During the 2008 Prairie Island Nuclear Generating Plant (PINGP) Unit 2 refueling outage, an inservice inspection (ISI) examination for the second period of the fourth interval was conducted. Enclosure 1 is a copy of the ISI 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 Xl ISI 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 the components examined, the examination methods used, the examination number, and summarizes the results of the above ISI examination. All anomalies were either corrected or an engineering evaluation was performed to accept "as-is" conditions. A description of the corrective work and the corresponding work request numbers are provided in the ASME Section Xl Repair/Replacement portion of the report.

Summary of Commitments This letter contains no new commitments and no revisions to existing commitments.

che .Wadley '

Site Vice President, Prairie Island Nuclear Generating Plant Northern States Power Company-Minnesota 1717 Wakonade Drive East

Welch, Minnesota 55089-9642 Telephone: 651.388.1121

Document Control Desk Page 2 Enclosure cc: Administrator, Region Ill, USNRC Project Manager, Prairie Island, USNRC Resident Inspector, Prairie Island, USNRC Chief Boiler Inspector, State of Minnesota Ij

ENCLOSURE 1 Inservice Inspection Summary Report, Interval 4, Period 2, Outage 1, Refueling Outage Dates: 09-19-2008 to 11-01-2008 Unit 2, Fuel Cycle 24: 12-15-2006 to 11-01-2008

NSPM PRAIRIE ISLAND .NUCLEAR GENERATING PLANT 171.7 WAKONADE DRIVE EAST WELCH, MINNESOTA 55089 INSERVICE INSPECTION

SUMMARY

REPORT INTERVAL 4, PERIOD 2, OUTAGE 1 REFUELING OUTAGE DATES: 09-19-2008 TO 11-01-2008 UNIT 2, FUEL CYCLE 24: 12-15-2006 TO 11-01-2008 COMMERCIAL SERVICE DATE: DECEMBER 21, 1974 Prepared by: C"(A' ' 1 I Date: 1/i/ 2Co)C) l31 Program Engincer, Prare Island

'ror Reviewed by: "ro_ _ _ _ Date: I ?,q /0 "

Repair/Replacement Program Engineer, Prairie Island Ron Clow Reviewed by: <es: Date: I- Z3-c

-- U e~ I 1 rare Ts a-n-Reviewed bylý__* Date: /221b9 Program Engineering u St r aresa RoAgra ,

Approved by: Date:

Steve Skoyen

NSPM INSERVICE INSPECTION PRAIRIE ISLAND UNIT 2 CYCLE 24

SUMMARY

REPORT Table of Contents Number of Pages Section 1. Discussion 2 Section 2. Form NIS-1, Owner's Report for Inservice Inspection 3 Section 3. ISI Examinations 18 Section 4. IWE Examinations 7 Section 5. Pressure Tests 3 Section 6. Snubber Inservice Testing and Preservice Examinations 13 Section 7. Steam Generator Eddy Current Examination Results Section 8. Repair/Replacement Activities for Fuel Cycle 24 110

NSPM INSERVICE INSPECTION PRAIRIE ISLAND UNIT 2 CYCLE 24

SUMMARY

REPORT Section 1. Discussion

1.0 INTRODUCTION

This summary report identifies the components examined, the examination methods used, the examination number and summarizes the results of examinations performed during the 2nd period of the 4th interval, unit 2 fuel cycle 24. 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.

2.0 PERSONNEL Visual and nondestructive examinations were performed by Xcel Energy Company and Lambert Macgill & Thomas (LMT). The Hartford 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 24. The number and percentage of 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 repair/replacement. There were no "Limited Examinations" credited during the cycle.

Section 4 contains the Class MC components examined, the examination number and summary of the examination results performed during unit 2 cycle 24. 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 additional examinations under IWE-2430 or the alternative evaluations as allowed by 10CFR50.55a (b)(2)(ix)(D) during unit 2 cycle 24. In addition, this section includes an evaluation of inaccessible areas as required by 10CFR50.55a (b)(2)(ix)(A). The first interval, September 9, 1996 to September 9, 2009 is based on. the examination requirements of ASME Section XI 1992 Edition and 1992 Addenda, and 10 CFR50.55a. The interval was extended one year as allowed by 1992 ASME Section XI paragraph IWA-2430(d).

Section 5 contains the pressure test results. All indications of leakage were evaluated and corrective measures performed as required by IWB-3142, IWC-3132 and IWA-5250.

Pressure tests that have not yet been completed, but will be completed prior to the end of the period, will be documented in the 4 1h interval, 2 nd period, 2nd outage 90 day summary report.

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 54 Repair/Replacement activities completed under the 4th Interval during the unit 2 cycle 24.

4.0 EXAMINATON REPORTS, EQUIPMENT AND MATERIALS The inservice inspection reports in Sections 3 and 4 contain references to procedures, equipment, and materials used to complete the specific examinations. Copies of the examination reports, examination procedures, and equipment records are available from Xcel Energy Company.

Sections 3 and 4 contain several abbreviations which are identified below:

CAP = Corrective Action Process CE = Condition Evaluation GEO = Geometry, evaluation of indication OPR = Operability Recommendation IN = Information Notice IND = Indication requires further evaluation NAD = No Apparent Defects SE = Safety Evaluation WO = Work Order

NSPM INSERVICE INSPECTION PRAIRIE ISLAND UNIT 2 CYCLE 24

SUMMARY

REPORT Section 2. NIS-1 (3 pages)

NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS (As required.by the Provisions of the ASME Code Rules)

I. Owner: NSPM/XceI Energy, 414 Nicollet Mall, Minneapolis, Minnesota 55401 (Name and Address of Owner)

2. Plant Prairie Island Nuclear Generating Plant, 1717 Wakonade Drive E, Welch, Minnesota 55089 (Name and Address of Plant)

3. Plant Unit 2

4. Owner Certificate of Authorization (if required) N/A

5. Commercial Service Date 12/21/1974

6. National Board Number for Unit N/A

7. Components Inspected Component or Manufacturer or Manufacturer of State or National Board Appurtenance Installer Installer Serial No. Province No. No.

Reactor Vessel Head Mitsubishi Heavy Inds. - .....

Reactor Vessel Creuot-Loire 687 MINN-200-51 ---

Pressurizer Westinghouse 1191 --- 68-57 21 Steam Generator Westinghouse 1181 --- 68-39 22 Steam Generator Framatome ANP 1182 --- 68-40 21 Reactor Coolant Pump Westinghouse W510 ---

22 Reactor Coolant Pump Westinghouse W515 ---

21 RHR Heat Exchanger Joseph Oats & Sons 1817-1C --- 342 22 RHR Heat Exchanger Joseph Oats & Sons 1817-1D --- 343 21 RHR Pump Byron Jackson ---

22 RHR Pump Byron Jackson .........

21 Safety Injection Pump Bingham ---...

22 Safety Injection Pump Bingham ---......

21 Accumulator Tank Delta Southern 41037-68-1 ---.. 2575 22 Accumulator Tank Delta Southern 41037-69-1 --- 2576 21 Boric Acid Tank NAVCO

8. Examination Dates: 12/15/2006 to :,.... 11/0"12008

9. Inspection Period Identification: (2nd Period) 2/7/2008 to 12/20/2011

10. Inspection Interval Identification: (4th Interval) 12/21/2004 to 12/20/2014

11. Applicable Edition of Section XI 1998 Edition with-2000 Addenda

12. Date/Revision of Inspection Plan: 8/29/08, Revision 4

13. Abstract of Examination and Tests. Include a list of examinations and tests and statement concerning status of work required for the Inspection Plan See Sections 3 through 7

14. Abstract of Results of Examinations and Tests See Sections 3 through 7

15. Abstract of Corrective Measures See Sections 3 through 6 We certify that a) that the statements made in this report are correct, b) the examinations and tests meet the Inspection Plan as required by the ASME Code, Section Xl, 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 I /R / Zoo00 Signed Owner 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 provinces of

-Minnesota and employed by _Hartford Steam Boiler Inspection and Insurance Company- of

_Connecticut have inspected the components described in this Owner's Report during the period 12/15/2006 to 11/01/2008 ,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 rfV4 in' (t Ins ctor's Na e National Board, State, Province, and Endorsements Dat;

NSPM rNSERVICF, INSPECTION PRAIRIE ISLAND UNVI 2 CYCLE 24

SUMMARY

REPORT Section 3. ISI Examinations (18 pages)

The following table summarizes the IS inspections performed in cycle 24. Inspections are listed by class, category and site summary number. Inspections that identified indications are shaded with a brief summary of the indication, corrective actions, corrective action process (CAP) number and work order/work request numbers as appropriate. There were no Class 1 or 2 examinations with indications requiring scope expansion or repair/replacement. There were no "Limited Examinations" credited during the cycle. The second table lists the number and percentage of examinations or tests completed as required by IWA-6220(f).

Page 1 ot 12 Unit 2 Fuel Cycle 24, 12115/2006 to 11/01/2008 Inservice Inspection Report Interval 4, Period 2, Outage I (2R25)

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. Comp. ID Comp. Desc. Item Procedure Method/Report/Results System Dwg/ISO E'xam Date Scope Class I Category BACC 570032 BMV on Perform Bare Metal Visual on Bottom of RV GL88-05 FP-PE-NDE- VT I 2008V200 / NAD RV 10/17/2008 AUG Bottom Head Vessel 520 Class 1 Category B-B 501482 W- 1 Cap-Integral Tubesht B2.60 FP-PE-NDE- VT / 2008V205 / NAD VC 2-ISI-34 10/29/2008 ISI 520 501536 W- 2 Cap-Integral Tubesht B2.60 FP-PE-NDE- VT 12008V206 1 NAD vC 24ISI-34 10129J2008 ISl 520 501594 W- 3 Cap-Integral Tubesht B2.60 FP-PE-NDE- VT / 2008V207 /NAD - Vo 2-4S1-34 10/29/2008 ISI 520 502617 W-A Tube Sheet to Head 82.40 FP-PE-NDE- UT / 2008U023 (Page 1) I NAD SG 2-ISI-37A 9/23/2008 ISl 406 FP-PE-NDE- UT I 2008U023 (Page 2) 1 NAD SG 2-1St-37A 9g26r/208 ISI 406 Class 1 Category B-D 505006 N- 5 IR Nozzle Inner Radius (3.140 SWI NDE-UT-5 UT / 2008U055/ NAD SG 24lSI-37A 10/9/2008 ISI 505024 N- 1 IR Nozzle Inner Radius B3.160 FP-PE-NDE- VT / 2008V208 / NAD VC 2-ISI-34 10/29/2008 ISI 520 505025 N- 2 IR Nozzle Inner Radius B3.160 FP-PE-NDE- VT I 2008V209 1NAD VC 2-ISI-34 10/29/2008 ISl 520 505026 N- 3 IR Nozzle Inner Radius 83.160 FP-PE-NDE- VT I 2008V210 / NAD VC 2-ISI-34 10/29/2008 IS' 520 B3.160 FP-PE-NDE- VT / 2008V211 I NAD VC 24SI1-34 10/29008 ISI 505027 N- 4 IR Nozzle Inner Radius 520 B3.160 FP-PE-NDE- VTI / 2008V212 / NAD VC 2-ISI-34 10/29/2007 ISl 505028 N- 5 IR Nozzle Inner Radius 520 B3.160 FP-PE-NDE- VT / 2008V213 / NAD VC 24ISI-34 10/29/2008 ISI 505029 N- 6 IR Nozzle Inner Radius 520 Class 1 Category B-G-2

Page 2 of 12 Unit 2 Fuel Cycle 24,12115/2006 to 11/01/2008 Inservice Inspection Report Interval 4, Period 2, Outage 1 (2R25)

1. Owner: Xcel Energy 4. Owner Certificate of Authorization (If Req.):

2. Plant: Prairie Island Nuclear Generating Plant 5. Commercial Service Date: 12121/1974

3. Plant Unit: 2 6. National Board Number for Unit: N/A Summary No. Comp. ID Comp. Desc. Item Procedure Method/Report/Results System Dwg/ISO Exam Date Scope 500137 B- 1 Valve Bolting B7.70 FP-PE-NDE- VT / 2008V1 58 / NAD RC 2-1SI-5 9/25/2008 PSI 510 500138 B- 1 Valve Bolting B7.70 FP-PE-NDE- VT / 2008V1 59 / NAD RC 2-1S-23 9/2512008 PSI 510

-. 4 -FP,*E-Nb ý W426008V1869tIND RC 2-1S-23 10/11/2008" ISI

.a 510 Comments! Threads damaged duning stud removal for internals replacement. Not service induced. Studs and nuts replaced under W093081. No CAP.

500139 B- 1 Valve Bolting B7.70 FP-PE-NDE- VT I 2008V162 I NAD. SI 24SI-29 9127/2008 PSI 510 500141 B- 1 Valve Bolting B7.70 FP-PE-NDE- VT I 2008V160 / NAD SI 24S--28 9/25/2008 PSI 510

- - . FPPE.NDE- -- VTn2008V-188IINDr-. S-b . ... 2-IS-28 - 10/12008- "I "

510 Comments: ,Threads damaged during stud removal for internals replacement. Not service induced. Studs and nuts replaced on W093081. No CAP written 500144 B- 2 Valve Bolting B7.70 FP-PE-NDE- VT / 2008V163 / NAD RC 24SI-29 9/27/2008 PSI 510 500146 B-2 Valve Bolting B7.70 FP-PE-NDE- VT / 2008V161 I NAD SI 24St-28 9/25/2008 PSI 510 500376 B- 4 Upper Seal House B7.60 FP-PE-NDE- VT / 2008V164 / NAD RC 24SI-43C 9128/2008 PSI 510 500377 B-4 Upper Seal House B7.60 FP-PE-NDE- VT / 2008V1 89 / NAD RC 2-ISt-43C 10/5/2008 PSI 510 500378 B- 3 Lower Seal House (12 bolts) B7.60 FP-PE-NDE- VT / 2008V190 / NAD RC 2-ISI--43C 10/6/2008 PSI 510 Class 1 Category B-K 521040 H-1/lA Int. Attach.[Double Spring] B10.20 SWI NDE-PT-1 PT/ 2008P004 / NAD VC 24SI-13E 9/2312008 IS1 Class 1 Category B-M-2 500142 V- 1 Valve int Surfaces B12.50 FP-PE-NDE- VT 12008V187 / NAD SI 2-1SI-28 10/1)2008 ISI 530

Page 3 of 12 Unit 2 Fuel Cycle 24, 12115/2006 to 11/01/2008 Inservice Inspection Report Interval 4, Period 2, Outage I (2R25)

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 Summa*y No. Comp. ID Comp. Desc. Item Procedure Method/Report/Results System Dwg/ISO E: xam Date Sco pe 502685 V- 1 Valve Int Surfaces B12.50 FP-PE-NDE- VT I 2008V180 / NAD RC 2-1SI-23 10/2/2008 PSI 530 FP-PE-NDE- VT / 2008V185 / NAD RC 2-1SI-23 10)/1/2008 ISI 530 Class 1 Category B-P 570025 SP 2070 Reactor Coolant System Integrity Test 815.00 FP-PE-NDE- See section 5 Pressure Tests RC reference SP 10/29/2008 ISI 520 2070 B15.00 FP-PE-NDE- See section 5 Pressure Tests RC, SI, VC, RH reference SP 10/312008 IS[

570026 SP 2392 Unit 2 RCS Bolting Inspection 520 2392 Class i Category F-A 500006 H- 2 Restraint F1.10b FP-PE-NDE- VT / 2008V137 / NAD SI 24IS4-228 9122r2008 530 ISI VC 2-ISI-1 38 9122r2088 500024 H- 2 Support F1.10a FP-PE-NDE- VT / 2008V140 / NAD 530 RC 24ISI-14 9122r0888 ISI 500055 H- 4 Support F1.10b FP-PE-NDE- VT 12008V1451 NAD 530 24ISI-12A 9W2312008 is, 501033 H- 6 Restraint F1.10a FP-PE-NDE- VT / 2008V146 / NAD VC 530 H-'* DoubleSp "- 'g F1 10c'- "*"4*-"FPP:E NDE-V'- F 2008V1-35 1IND ISI 501l040 530 CAP 1152070M

(-Commrentsý in;tial indicaiton that springs of double spring can hanger were binding. Determined to be functional and acceptable as is.

VC 24St-13B ISI 501051 H- I Rigid Restraint Fl.10b FP-PE-NDE- VT /2008V1481 NAD 530 9122/208£ IS' RC" 24SI-46 501861 H-6 oulSpring Fil10c FPý-PE-NDE- VT I 2008V1 38 IIND 530 Commentts:ý Load indicator more than 10% out of tolerance. Acceptable as is CAP 1152093.

VT / 2008V141 / NAD RC 24SI-7A 9/22/2008 ISI 501161 H- 6 Double Rigid F1.10b FP-PE-NDE-530

Page 4 of 12 Unit 2 Fuel Cycle 24, 12/15/2006 to 11/01/2008 Inservice Inspection Report Interval 4, Period 2, Outage 1 (2R25)

1. Owner: Xcel Energy

2. Plant: Prairie Island Nuclear Generating Plant 4. Owner Certificate of Authorization (If Req.):

3. Plant Unit: 2 5. Commercial Service Date: 12/21/1974

6. National Board Number for Unit: N/A Summary No. Comp. ID Comp. Desc. Item Procedure Method/Report/Results System Dwg/ISO E) cam Date Scope 501267 H- 4 Double Rod Hanger F1.10a FP-PE-NDE- VT / 2008V142 / NAD Sl 2-1S-21 91/ 22/2008 ISI 530 591412 H-1 Loop B hotleg support F1.40 FP-PE-NDE- VT / 2008V1 95 / NAD RV 2-1SI-40 10/16/2008 ISI 530 591413 H-2 Loop B coldleg support F1.40 FP-PE-NDE- VT / 2008V1 94 / NAD RV 2-1I1-40 10/16/2008 ISI 530 591414 H-3 Loop A hotleg support F1.40 FP-PE-NDE- VT I 2008V193 1NAD RV 2-1SI-40 10/16r2008 is[

530 591415 H-4 Loop A coldleg support F1.40 FP-PE-NDE- VT / 2008V1 97 / NAD RV 24St-40 IC V17/2008 ISI 530 591416 H-5 RV Support Lug @ 270 F1.40. FP-PE-NDE-: VI / 2008VI 96 / NAD RV 2-ISI-40 1CV172008 ISI 530 591417 H-6 RV Support Lug @ 90 F1.40 FP-PE-NDE- VT / 2008VI92 / NAD RV 24SI-40 1iIf16r2008 ISI 530 Class 1 Category R-A 501506-RI W- 9 Elbow to Pipe R1.20-4 FP-PE-NDE- UT / 2008U024 (Page 1) / NAD SI 24ISI-21 9/23r2008 ISl 402 FP-PE-NDE- UT / 2008U024 (Page 2) / NAD SI 9/25/2008 2-151-21 ISI 402 501517-RI W-1 0 Elbow to Pipe R1.20-4 FP-PE-NDE- UT 1 2008U051 (Page 1) / NAD RC 24SI-11 9/2312008 Is' 402 FP-PE-NDE- UT/ 2008U051 (Page 2) I NAD RC 24ISI-1 1 912912008 ISl 402 501523-RI W- 8 Elbow to Pipe R1.11-2 FP-PE-NDE- UT 2008U018 (Page 1) / NAD RC 2-ISI-22B 9r23/2008 ISl 402 FP-PE-NDE- UT I 2008U018 (Page 2) / NAD RC 2-ISt-228 9W2312008 Isl 402 501535-RI W-. 3 45 Elbow to Pipe R1.20-4 FP-PE-NDE- UT / 2008U050 (Page 1) 1 NAD 9/23/2008 RC 2-ISt-30A ISI 402 FP-PE-NDE- UT / 2008U050 (Page 2) / NAD RC 2-ISI-30.A 9n28/2008 ISl 402

Page 5 of 12 Unit 2 Fuel Cycle 24, 12/15/2006 to 11/01/2008 Inservice Inspection Report Interval 4, Period 2, Outage 1 (2R25)

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: N/A Summary No. Comp. ID Comp. Desc. Item Procedure Method/Report/Results System Dwg/ISO E:xam Date Scope 501578-RI W- 8 Pipe to Elbow R1.20-4 FP-PE-NDE- UT / 2008U025 (Page 1) / NAD SI 2-ISI-21 9/ 23/2008 ISI 402 FP-PE-NDE- UT / 2008U025 (Page 2) / NAD SI 2-1SI-21 9/:25/2008 ISI 402 501615-RI W- 6, 0bow I o Valve R~1.16-2 FP-PE-N4DE- UT 2OO8UO20 (Page 1) / NADb Si 2-*11-22B" 91t23008 ISI UT / 2008U020 (Page 2) / NAD SI 2-ISI-22B 9/23/2008 ISI 402 FP-PE-NDE-UT / 2008U020 (Page 3)I/MAD SI 2-1SI-22B 9/23/2008 IS[

402 Commen[ts: Iimit.ed with < 90% coverage. Summary No. 501683-RI (W-5) from the same segment was selected as an alternate and scheduled for 2R26.

Exam was 501668-RI W- 6 Pipe To Elbow R1.11-2 FP-PE-NDE- UTT/2008U021 (Page 1) / NAD RC 2-ISt-10A 9123/2008 IS1 402 9/25/2008 Is]

FP-PE-NDE- UT / 2008U021 (Page 2) / NAD RC 24ISI-10A 402 9r23/2008 Pipe To Elbow R1.11-2 FP-PE-NDE- UT / 2008U037 (Page 1) 1 NAD RC 24ISI-2 ISI 501737-RI W- 7 402 FP-PE-NDE- UT / 2008U037 (Page 2) I NAD RC 2-ISt-2 ISl 402 9128r2008 ISI FP-PE-NDE- UT / 2008U037 (Page 3) 1 NAD RC 2-151-2 402 9/23/2008 ISI 501742-RI W- 7 Elbow To Pipe R1.11-2 FP-PE-NDE- UT/2008UO22(Page 1)/NAD RC 2-IS1-1 OA 402 9/25/208o ISI FP-PE-NDE- UT / 2008U022 (Page 2) 1NAD RC 24SI-10A 402 9/23/2008 501753-RI W- 7 Pipe to Elbow R1 20-4 FP-PE-NDE- UT / 2008U036 (Page 1) / NAD RC 2-ISt-16 ISI 402 9rz/271o08 FP-PE-NDE- UT / 2008U036 (Page 2) / NAD RC 2-ISI-16 ISl 402 9r2712008 FP-PE-NDE- UT / 2008U036 (Page 3) / NAD RC 2-151-16 ISl 402 9/23/2008 501797-RI W- 8 Elbow to Pipe R1.11-2 FP-PE-NDE- UT / 2008U038 (Page 1) / NAD RC 2-ISt-2 402 W8= ISI FP-PE-NDE- UT / 2008U038 (Page 2) / NAD RC 2-151-2 402 9/28/2008 FP-PE-NDE- UT / 2008U038 (Page 3) 1 NAD RC 2-ISI-2 402

Page 6 of 12 Unit 2 Fuel Cycle 24, 1211512006 to 11/01/2008 Inservice Inspection Report Interval 4, Period 2, Outage 1 (2R25)

1. Owner: Xcel Energy

2. Plant: Prairie Island Nuclear Generating Plant 4. Owner Certificate of Authorization (if Req.):

3. Plant Unit: 2 5. Commercial Service Date: 12/21/1974

6. National Board Number for Unit: NIA Summary No. Comp. ID Comp. Desc. Item Procedure Method/Rep,oft/Results System Dwg/ISO E)xam Date Scope 501814-RI W- 8 Elbow to Pipe R1.20-4 FP-PE-NDE- UT / 2008U030 (Page 1) / NAD RC 2-ISI-16 9/23/2008 ISl 402 FP-PE-NDE- UT / 2008U030 (Page 2) / NAD RC ISl 2-ISI-16 9/27/2008 402 FP-PE-NDE- UT / 2008U030 (Page 3) / NAD RC Ill 2-ISI-16 9/27/2008 402 501854-RI W- 4 Elbow to Pipe R1.20-4 FP-PE-NDE- UT / 2008U033 (Page 1) / NAD SI 2-ISI-11I 9/23/2008 ISl 402 FP-PE-NDE- UT / 2008U033 (Page 2) / NAD SI ISl 2-ISI-11 9/25/2008 402 501892-RI W-10 Elbow To Pipe R1.11-2 ISI FP-PE-NDE- LUT/ 2008U039 (Page 1) 1GEO RC 2-151-2 9/23/2008 402 FP-PE-NDE- UT / 2008U039 (Page 2) / NAD RO 9fl8/2008 ISI 24ISI-2 402 RC 9/28/2008 FP-PE-NDE- UT / 2008U039 (Page 3) / NAD ISI 2-4SI-2 402 501896-RI RC VC W-14 Tee to Reducer R1.20-4 FP-PE-NDE- UT / 2008U045 (Page 1) / NAD 24ISI-12C 9/23/2008 ISI 402 vc FP-PE-NDE- UT / 2008U045 (Page 2) / NAD 24ISI-12C 9/30/2008 1St 402 FP-PE-NDE- UT / 2008U045 (Page 3) / NAD ISl vc VC 24ISI-12C 9/30/2008 402 501955-RI W-1 3 Reducer to Tee R1.20-4 FP-PE-NDE- ISI UT / 2008U052 (Page 1) / NAD vc 2-ISt-12C 9/23/2008 402 ISi FP-PE-NDE- UT / 2008U052 (Page 2) / NAD vc 24ISI-12C 9r3012008 402 ISl FP-PE-NDE- UT / 2008U052 (Page 3) / NAD VC 24ISI-12C 9/30/2008 402 501997-RI W-12 Pipe to Reducer R1.20-4 FP-PE-NDE- UT 12008U053 (Page 1) / NAD VC 24lSI-12C 9/23/2008 ISl 402 FP-PE-NDE- UT / 2008U053 (Page 2) / NAD VC 24S-1St2C 9130/2008 ISl 402 502002-RI W-li Elbow to Pipe R1.20-4 FP-PE-NDE- UT/ 2008U034 (Page 1) / NAD RC 24SI1-24 9/23/2008 IS' 402 FP-PE-NDE- UT / 2008U034 (Page 2) / NAD RC 2-151-24 97/2008 ISl 402

Page 7 of 12 Unit 2 Fuel Cycle 24, 12/15/2006 to 11/01/2008 Inservice Inspection Report Interval 4, Period 2, Outage 1 (2R25)

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. Comp. ID Comp. Desc.. Item Procedure Method/Report/Results System Dwg/ISO E (am Date Scope FP-PE-NDE- UT / 2008U034 (Page 3) / NAD RC 2-ISI-24 9/22712008 I11 402 502075-RI W-14 Elbow to Pipe R1.20-4 FP-PE-NDE- UT / 2008U041 (Page 1) / NAD RC 2-ISI-7A 9/23/2008 SIi 402 FP-PE-NDE- UT / 2008Uo41 (Page 2) / NAD RC 2-ISI-7A 10/1/2008 151 402 FP-PE-NDE- UT / 2008U041 (Page 3) / NAD RC 2-ISI-7A 10/1/2008 151 402 502115-RI W-15 Pipe to Elbow R1.20-4 FP-PE-NDE- UT / 2008U044 (Page 1) / NAD RC 2-ISI-7A 9/23/2008 151 402 FP-PE-NDE- UT / 2008U044 (Page 2) / NAD RC 2-ISt-7A 1011/2008 'SI 402 FP-PE-NDE- UT / 2008U044 (Page 3) / NAD RC 2-ISI-7A 101112008 IS' 402 502150-RI W-16 Reducer To Safe End R1.11-2 UT-Vendor UT 12008VE002 I NAD RC 2-ISI-31 100812008 PSI 502154-RI W-1 6 Elbow to Pipe R1.20-4 FP-PE-NDE- UT / 2008U043 (Page 1) NAD RC 2-ISI-7A 9/23/2008 ISI 402 RC 10/11/2008 'Il FP-PE-NDE- UT / 2008U043 (Page 2) / NAD 2-ISI-7A 402 FP-PE-NDE- UT / 2008U043 (Page 3)I NAD RC 2-ISI-7A 1011/2008 ISl 402 502164-RI W-12 Pipe to Elbow R1.20-4 FP-PE-NDE- UT / 2008U029 (Page 1) / NAD RC 2-ISI-16 912312008 IS1 402 FP-PE-NDE- UT 12008U029 (Page 2) I NAD RC 2-ISI-16 9%27/2008 ISI 402 FP-PE-NDE- UT / 2008U029 (Page 3) / NAD RC 2-l51-16 IS]

402 1ri7/2008 502165-RI W-17 Safe End To Nozzle R1.15-2 UT-Vendor UT / 2008VE001 / NAD RC 2-ISI-31 PSI 502249-RI W- 5 Pipe to Elbow R1.20-4 FP-PE-NDE- UT / 2008U042 (Page 1) 1 NAD RC 2-ISI-7B3 9123r1208 ISI 402 FP-PE-NDE- UT / 2008U042 (Page 2) / NAD RC 2-1S1-78 10/1/2008 ISI 402 FP-PE-NDE- UT / 2008U042 (Page 3) / NAD RC 2-ISI-713 1011/2008 ISI 402

Page 8 of 12 Unit 2 Fuel Cycle 24, 1211512006 to 11/01/2008 Inservice Inspection Report Interval 4, Period 2, Outage I (2R25)

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. Comp. ID Comp. Desc. Item Procedure Method/Report/Results System Dwg/ISO E:xam Date Scope 502366-RI W-19 Elbow To Pipe R1.20-4 FP-PE-NDE- UT / 2008U031 (Page 1) / NAD RC 2-1SI-4 9,23/2008 IS[

402 FP-PE-NDE- UT 12008U031 (Page 2) / NAD RC 2-ISI-4 9r24/2008 ISI 402 FP-PE-NDE- UT / 2008U031 (Page 3) / NAD RC 2-1SI-4 9V2412008 IS1 402 502379-RI W-1 8 Pipe To Elbow R1.20-4 FP-PE-NDE- UT / 2008U032 (Page 1) 1NAD RC 2-1SI-4 9)23/2008 ISI 402 FP-PE-NDE- -LUTI 2008U032 (Page 2) I NAD RC 2-I1S-4 9) 2412008 ISl 402 FP-PE-NDE- UT / 2008U032 (Page 3) / NAD /24)2008 ISI RC 2-1SI-4 91 402 502706-RI W- 3 Pipe to Reducer R1.20-4 FP-PE-NDE- UT / 2008U054 (Page 1)1 NAD RC 2-4S1-19 ISI f23/2008 402 FP-PE-NDE- UT / 2008U054 (Page 2) / NAD RC 24S1-19 I 018r2008 0s' 402 Class 2 Category C-C 525605 H-3/IA Int. Attach[Double Spring Hanger] C3.20 SWI NDE-PT-1 PT / 2008P005 / NAD RH 2-ISI-52A 101412008 ISI C3.20 SWI NDE-PT-1 PT / 2008P006 I NAD RH 2-151-52 1014r2008 ISI 525614 H-6/IA Int. Attach[Seismic Restraint]

Class 2 Category C-H C7.00 FP-PE-NDE- See section 5 Pressure Tests RH 102212008 IS' 570010 SP 2168.10 RHR System Pressure Test 520 C7.00 FP-PE-NDE- See section 5 Pressure Tests MS 115/2007 IS' 570011 SP 2168.11 Main Steam Pressure Test 520 C7.00 FP-PE-NDE- See section 5 Pressure Tests SI 10113/2008 IS' 570013 SP 2168.13 Safety Injection System Pressure Test 520 C7.00 FP-PE-NDE- See section 5 Pressure Tests CS 5)102007 ISI 570014 SP 2168.14 Containment Spray System Pressure Test 520 Class 2 Category F-A 500311 H-12 Single Support Assembly F1.20b FP-PE-NDE- VT / 2008V147 / NAD AF 2-ISI-48A 9/2352008 ISI 530 AF 9/'25/'20O8 'It 500317 H-1 8 Double Spring Hanger F1.20c FP-PE-NDE- VT / 2008V150 / NAD 2-ISI-48A 530

Page 9 of 12 Unit 2 Fuel Cycle 24, 12115/2006 to 11/01/2008 Inservice Inspection Report Interval 4, Period 2, Outage I (2R25)

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. Comp. ID Comp. Desc. Item Procedure Method/Report/Results System Dwg/ISO Exam Date Scope 500410 H- 9 Girder F1.40 FP-PE-NDE- V-/ 2008V151 1NAD SG 2-1IS-37C 9/26f2008 IS]

530 562 ** **ii* j F,.*20b .FP-PE

J E V 208 V. 9 IND .;N" .. 2lsi-48'- 9/52008 - ISI CGomrT~ents:, :k;*Bolt~to nut lack-of fuHl thread engagement. Bolt one, thread below flush.. CAP .1152402 Acceptable as is.

500664 H- 1 Rupture Restraint F1.20b FP-PE-NDE- VT/ 2008Vl98 I NAD FW 2-1SI-49 1011812008 PSI 530 500667 H- 1 Seismic Restraint F1.20b FP-PE-NDE- VT / 2008V1 99 / NAD FW - 2-ISI-48 10/18/2008 PSI 530 500695 H-10 Double Snubber/Clamp F1.20c FP-PE-NDE- VT / 2008V167 1 NAD FW 2-ISI-48 9/2912008 PSI 530 501234 H-. 3 Snubber/Clamp F1.20c FP-PE-NDE- VT / 2008Vl81 / NAD RH 2-4SI-51 10/21008 PSI 530 530 501286 H- 8 Sway Strut/Clamp F1.20a FP-PE-NDE- VT t 2008V143 I NAD SI 2-4SI-72 9W22/2008 151 530

~501367 h3 H- ~ Snubber, ~ ,.20c~ ~FP-P-NDE - ~ -1420 SI IT20V3/N~~-~~7 530 Comments : Setting for collar out of tolerance. Cotter pin broken and will be replaced on W0290580. Snubber acceptable as is. CAP 1152070 502643 H- 1 Snubber 1 F1.40 FP-PE-NDE- VT / 2008V1 54 / NAD SG 2-4SI-37C 912612008 ISI 530 FP-PE-NDE- VT / 2008V178 / NAD SG 2-ISI-37C 9/28/2008 PSI 530 502644 H- 2 Snubber 2 F1.40 FP-PE-NDE- VT / 2008V1 55 / NAD SG 2-ISI-37C 9126/2008 Isi 530 502645 H- 3 Snubber 3 F1.40 FP-PE-NDE- VT / 2008V1 56 / NAD SG 2-ISI-37C 9/2612008 ISI 530 502646 H- 4 Snubber 4 F1.40 FP-PE-NDE- VT / 2008V1 57 / NAD SG 2-1SI-37C 9M2612008 ISI 530

Page 10 of 12 Unit 2 Fuel Cycle 24,12/15/2006 to 11/01/2008 Inservice Inspection Report Interval 4, Period 2, Outage 1 (2R25)

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. Comp. ID Comp. Desc. Item Procedure Method/Report/Results System Dwg/ISO Ex:am Date Scope 502647 H- 1 Snubber 1 F1.40 FP-PE-NDE- VT / 2008V1 79 / NAD SG 2-ISI-37D 9/2.8/2008 PSI 530 502651 H- 5 Spring 1 F1.40 FP-PE-NDE- VT / 2008V1 52 / NAD SG 2-ISI-37C 9/2.6/2008 ISI 530 502652 H- 6 Spring 2 F1.40 FP-PE-NOE- VT I 2008V1 53 / NAD SG 2-ISI-37C 9/226/2008 ISl 530 ISI 505106 H- 3 Box Restraint F1.20a FP-PE-NDE- VT / 2008V166 / NAD Sl 2-151-908 9B28/2008 530 505169 H- 4 Rigid Hanger F1.20a FP-PE-NDE- Vr / 2008V144 / NAD S1 2-iSI-95B 9, 22/2008 IS]

.530 25/2008 ISI 515614 H-6 Seismic Restraint F1.20b FP-PE-NDE- VT / 2008V183 / NAD RH 2-ISI-52 IC 530 521000 H-8A Double Snubber/Clamp F1.20c FP-PE-NDE- VT / 2008V1 49 / NAD MS 2-ISI-47B 9) 5r2m PSI 530 Class 2 Category R-A UT / 2008U040 (Page 1) / GEO FW 94 OWN 500634-RI W-24 Reducer to Nozzle R1.11-5 FP-PE-NDE- 2-ISI-48 23/2008 401 91 OWN FP-PE-NDE- UT / 2008U040 (Page 2) / GEO FW 2-ISt-48 401 21232008 500635-RI W-23 Pipe to Reducer R1.11-5 FP-PE-NDE- UT / 2008U035 (Page 1) / NAD FW 2-ISI-48 OWN 401 FP-PE-NDE- UT / 2008U035 (Page 2) I NAD FW 2-ISI-48 9126/2oo8 OWN 401 UT / 2008U047 (Page 1) / NAD 2-151-56 /23r2008 IS' 502261-Rl W- 6/LSD Pipe to Tee R1.20-4 FP-PE-NDE- RH 402 FP-PE-NDE- UT I 2008U047 (Page 2) 1NAD 24ISI-56 10=22008 ISI RH 402 R1.20-4 FP-PE-NDE- UT / 2008U046 (Page 1) / NAD RH 2-ISI-56 )/23/2008 IS[

502267-RI W-12/LSU Elbow to Pipe 402 FP-PE-NDE- UT / 2008U046 (Page 2) I NAD RH 24ISI-56 10/202008 ISI 402

Page 11 of 12 Unit 2 Fuel Cycle 24,12/15/2006 to 11101/2008 Inservice Inspection Report Interval 4, Period 2, Outage I (2R25)

1. Owner: Xcel Energy

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

2. Plant: Prairie Island Nuclear Generating Plant

3. Plant Unit: 2 5. Commercial Service Date: 12/21/1974

6. National Board Number for Unit: N/A Summary No. Comp. ID Comp. Desc. Item Procedure Method/Report/Results System Dwg/ISO E:xam Date Scope 502281-RI W-15 Pipe to Pipe R1.20-4 FP-PE-NDE- UT / 2008U048 (Page 1) / NAD RH 2-ISI-56 9r23/2008 ISI 402 FP-PE-NDE- UT / 2008U048 (Page 2) / NAD RH 2-1SI-56 10r2/2008 IS' 402 505219-RI W- 3 Pipe to Elbow R1.20-4 FP-PE-NDE- UT/ 2008U049 (Page 1)/ NAD SI 2-ISI-93C 9/23/2008 402 ISI FP-PE-NDE- UT / 200811049 (Page 2)/ NAD SI 2-ISt-93C 9/24/2008 ISI 402 FP-PE-NDE- UT / 2008U049 (Page 3) / NAD SI 2-ISI-93C 9/2412008 ISl 402 W- 4 I Elbow 505220-RI to Pipe R1.20-4 FP-PE-NDE- UT / 2008U026 (Page 1) / NAD 912312008 SI 2-ISt-93 ISI 402 FP-PE-NDE- UT / 2008U026 (Page 2) / NAD Sl 912412008 2-ISt-93C ISI 402 FP-PE-NDE- UT / 2008U026 (Page 3) / NAD S1 912412008 'Si 24ISI-93C 402 912412008 505223-RI W- 7 Pipe to Elbow R1.20-4 FP-PE-NDE- UT / 2008U027 (Page 1) / NAD Sl 2-ISI-93C 402 SIS 91262008 FP-PE-NDE- UT / 200811027 (Page 2) I NAD Si 24ISI-93C ISI 402 FP-PE-NDE- UT / 2008U027 (Page 3) / NAD Sl 9r26/rZo8 2-ISI-93C IS1 402 505224-RI W- 8 Elbow to Pipe RI.20-4 FP-PE-NDE- UT / 2008U028 (Page 1) / NAD SI 2-1SI-93C ISl 402 FP-PE-NDE- UT /2008U028 (Page 2) / NAD Sl 9r2612008 24ISI-93C IS!

Is' 402 FP-PE-NDE- UT / 2008U028 (Page 3) / NAD SI 9W6312008 24ISI-93C Is[

402 Class 3 Category D-A 522990 CCH-182/IA Int. Attach[SNUBBER] D1.20 FP-PE-NDE- VT / 2008V132 ! NAD cc ND-2-3-75 9121/2008 ISI 510 Class 3 Category F-A 501249 H-1 Support A F1.40 FP-PE-NDE- Vr / 2008V1 33 iNAD cc ND-2-3-81C 9/20/2008 ISi 530 501250 H-2 Support B F1.40 FP-PE-NDE- VT / 2008V134 I NAD CC ND-2-3-81C 9120/2008 ISI 530

Page 12 of 12 Unit 2 Fuel Cycle 24, 12/15/2006 to 11/01/2008 Inservice Inspection Report Interval 4, Period 2, Outage I (2R25)

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. Comp. ID Comp. Desc. Item Procedure Method/Report/Results System Dwg/ISO E: xam Date Scope 512759 CCH-1 79C DOUBLE SNUBBER & SEI Fl.30a FP-PE-NDE- VT / 2008V1 71 / NAD CC ND-2-3-85 9r 30/2008 ISI 530 512770 CCH-186 Snubber/Clamp F1.30c FP-PE-NDE- VT / 2008V1 74 / NAD CC ND-2-3-88 1I1/1/2008 PSI 530 512778 CCH-179A DOUBLE SNUBBER & SEI F1.30c FP-PE-NDE- VT I 200BV1737 NAD CC ND-2-3-85 1i)/1/2008 PSI 530 512919 CWH-33 ROD F1.30a FP-PE-NDE- Vr / 2008V1 65 / NAD CW ND-2-3-3 9/2812008 ISI 530 F1.30c FP-PE-NDE- VT / 2008V1 70 / NAD /30/2008 PSI 512936 CCH-181 Snubber/Clamp CC ND-2-3-81 9i 530 F1.30c FP-PE-NDE- VT / 2008V1 72 / NAD CC ND-2-3-85 1 0/11/2008 PSI 512953 CCH-180 Snubber/Clamp 530 F1,30c FP-PE-NDE- VTI / 2008V131 / NAD CC ND-2-3-75 /21/2008 ISI 512990 CCH-182 Snubber 530 U'3012008 PSI FP-PE-NDE- VT / 2008V169 / NAD CC ND-2-3-75 9 530

,2/2008 PSI 515087 CCH-1 73 Snubber F1.30c FP-PE-NDE- VT / 2008V168 / NAD CC NO-2-3-78A 9 530

'Si 515255 2EGH-5083 GUIDE F1.30b FP-PE-NDE- Vr / 2008V1 75 / NAD D5 ND-2-3-342 1 530 Fl .30b FP-PE-NDE- VT / 2008V1 77 / NAD 5 ND-2-3-343 10/2/2008 ISI 515259 2EGH-5057 GUIDE .

530 F1.30b FP-PE-NDE- VT 12008V176 / NAD 06 ND-2-3-346 1 (r7.200 ISI 515279 2EGH-6065 GUIDE 530

Prairie Island Nuclear Plant Completion: Code Compliance. Slummary -.4th Interval -2nd Period ISI - Code Editiion- 1998 E-dition, 2000 Addenda Number Percent Total# Total# Comp. in Required for Required for Comp to 2nd % Camp. to Cat. Item No. Code Case Population Interval Interval Date Period DateI Notes B-A B1.11 3 100% 3 0 0 0% Deferral to end of interval allowed per IWB-2500-1 B-A B1.30 N-623 1 100% 1 0 0 0% Deferral to end of interval allowed per N-623 iiii~i!

A. X.-Xx: .....

.......... ERR B-B B2.11 2 100% 2 1 0 50%

B-B B2.12 2 100% 2 0 50%

B-B B2.40 2 50% 1 1 100% One of each similar vessel.

B-B B2.60 RR-4-2 3 600% 18 9 3 50% VT-2 each outage per RR-4-2. Not included in count

i. ------ ..............

..... . Total Percentage completed excludes 82.60 N-648-1, N-BD B3.100 521 6 100% 6 0 0 0% Deferral to end of interval allowed per IPVB-2500-1 BD B3.120 5 100% 5 1 0 20%

B-D B3.140 4 100% 4 2 1 50%

B-D B3.160 RR-4-2 6 600% 36 18 6 50% VT-2 each outage per RR-4-2. Not included in count B-D 83.90 N-521 100% 6 0 0 0% Deferral to end of interval allowed per FWB-2500-1

............... Total Percentage completed for B3.120 and B3.140.

~%Othe items NA.

Deferral to end of interval allowed per IWB-2500-1 B-G-1 B6.10 3 100% 3 1 0 34% Each component is a set of 16.

Deferral to end of interval allowed per IWB-2500-1.

Each component is a set of 24 RCP bolts. Only 25% 1 0 0 0% required when required by B-L-2, B-G-1 B6.180 2 2 25% 1 0 0 0% Only required when disassembled B-G-1 66.190 1120/2009 ScheduleWorks V. 8.1 Page 1 - 5

Prairie Island Nuclear Plant Completion Code Compliance Sium~mary - 4th Intervaal -.:2nd. Period ISi - Code Edition - 1998 Edition, 2000 Addenda Number Percent Total# Total# Comp. in Required for Required for Comp to 2nd % Comp. to Cat. Item No. Code Case Population Interval Interval Date Period Date Notes I Notes Deferral to end of interval allowed per IWB-2500-1.

B-G-1 B6.30 3 100% 3 1 0 34% Each component is a set of 16.

Deferral to end of interval allowed per IWB-2500-1.

B-G-1 66.40 1 100% 1 0 0 0% Each component is a set of 48.

Deferral to end of interval allowed per IWB-2500-1:

B-G-1 B6.50 3 100% 3 1 0 34% Each component is a set of 16.

M1WM B-G-2 B7.20 N-652 1 100% 1 0 0 0%

B-G-2 B7.30 N-652 4 100% 4 1 0 25%

B-G-2 B7.50 N-652 9 0% 3 .3 U 100% If disassembled or bolting removed.

B-G-2 B7.60 N-652 4 0% 0 1 0 0% Only required when required by B-L-2 B-G-2 87.70 N-652 18 120% Only required when required by B-M-2

!iii 6 25% 5 0 iii

....... iiti i i iiiiiiii

.................... Total Percentage completed for 8720 and 8730. Other

--- items NA.

B-K B10.10 3 66.6% 2 0 0 0% Only one attachment of one of multiple vessels B-K B10.20 41 10% 5 2 40%

.......... X, 4I.:- ... i.....

ii~i i i .......

liiiiii ... ........

. 0.%... imitd L... npmiehgu..u S-L-1 B12.10 2 50% 1 0 0 Limited to one pump in each group of simrar pumps-Umfed to one pump m*each group of smnlar pumps-B-L-2 812.20 2 0%000 0% Only required when disassembled.

!iii*iiii~iiiiiiiiiiiiliiiiiiii~

iiii iiili iiii~

i~iiii ..iiiiiii i i~ii~iiiiiiii iiiiiiiiiii~ ....

iiiiiiiiiiii iiiii~ii11 i iiii~iiiii~ii iiiiiiii!!ii* iii.........

.... ii!i~i~i Limited to one valve in each group. Only required when B-M-2 812.50 10%0 2 1 12% diassembled.

1/20/2009 ScheduleWorks V. 8.1 Page 2 - 5

Prairie Island Nuclear Plant Completion Code Compliance Summary - 4th Interval - 2nd Period ISI -Code Edition - 1998 Edition, 2000 Addenda Number Percent Total# Total# Comp. In Required for Required for Comp to 2nd % Comp. to Cat. Item No. Code Case Population Interval Interval Date Period Date Notes

______________________________________________________ £ __________________________________

B-N-1 B13.10 1 300% 3 1 0 100% All accessible areas to be examined once each period.

T............ .ii.A......

B-N-2 B13.50 100% 0 0 0% Deferral to end of interval allowed per IWB-2500-1 1 1 B-N-2 B13.60 100% 0 0 0% Deferral to end of interval allowed per IWB-2500-1

.o..l..... ::::::: :: .:::::::::

2. ..

B-N-3 813.70 1 100% 1 0 0 0% Deferral to end of interval allowed per IWB-2500-1 0 40.10. .-............ 4.0.

0% Deferral allowed per IVB-2412(a)3 RR.3N...-.. ................ .

B- 53- .. ....%

1500. 12.. 6.2 ot... .. ... ... .. .... ..

50% Two pressure test procedures each outage.

B-Q 816.20 2 0% 0 0 0 0% SG tubing per Technical Requirements Manual

.......:..:-.......... - . . :r.. ::::::*-: :.:::, .`:.,

ý- .::: X . . - - ...........

C-A C1.10 8 31.25% 4 1 0 25% Welds at gross structural discniuity Only.

.0-A C1.20 4 50% 2 1 0 50%

C-A C1.30 2 50% 1 0 0 0%

tFor multiple vessels such as SG required exams may be to one vessel. .limited I

1/20/2009 ScheduleWorks V. 8.1 Page 3 - 5

Prairie Island Nuclear Plant Completion Code Compliance Summary - 4th Interval d 2nd Period 1St - Code Edition'- 1998 Edition, 2000 Addenda Number Percent Total# Total# Comp. in Required for Required for Comp to 2nd % Comp. to Cat. Item No. Code Case Population Interval Interval Date Period Date Notes C-B C2.21 4 50% 2 0 50%

C-B C2.22 4 50% 2 1 0 50%

C-B C2.31 4 50% 2 0 0 0%

For multiple vessels of similar design exams may be limited to one vessel C-C C3.10 4 50% 2 0 0 0% One of each similar vessel.

C-C C3.20 99. 10% 10 6 2 60%

C-C C3.30 16 10% 2 2 0 100%

C-C C3.40 2 10% 1 0 0 0%

.i........................... : :: : : : ::: : : :: : : : : :: : : ::..- :: ::: : ::.....::::: : : : ::: 5 : :::::

.E MS:::::::::::::::::

:::2 ::: :::::::: : :::: ::: :: ::: :: :::::: ::..:....:

:::5::::::::::::::

C-H C7.00 N-533-1 13 300% 39 17 4 44% Class 2 pressure tests, comlted once each period.

D-A D~lO .5...4.2.

D-A~..... 9610 .12.0 D-A.. 2 10.13.. 1.0. 50%

t .. .0 ....

30%

0%

N-533-1, N-7 300% 21 33% Class 3 pressure tests comrpnl once each pelod.

D-B D2.10 498-4

7. . ..7

............. 0

.... . a....l*i . .. . . . . .. .. *;;::::i :

F-A F1.lOa 70 25% 18 10 3 56%

F-A FlilOb 76 25% 19 8 2 43%

F-A F1.10c 65 25% 17 7 2 42%

F-A F1.20a 118 15% 18 10 3 56%

1/20/2009 ScheduleWorks V. 8.1 Page 4 - 5

Prairie Island Nuclear Plant Completion. Code Compliance-Summary - 4th Interval - 2nd Period ISI - Code Edition - 1998 Edition, 2000 Addenda Number Percent Total# Total# Comp. in Required for Required for Comp to 2nd % Comp. to Cat. Item No. Code Case Population Interval Interval Date Period Date Notes

~4~rfl. -Notes F I .4UU 81 15%o 13 6 4 47%

F-A F1.20c 61 15% 10 5 3 50%

F-A F1.30a 174 10% 18 9 2 50%

F-A F1.30b 203 10% 21 7 1 34%

F-A F1.30c 49 10% 5 2 1 40%

Examination of supports required for only one of multiple F-A F1.40 74 50% 37 27 15 73% components within each system t8i .. .. . . .. .. .. ..

,. ,:::,.:: .. .. ...... $i

.. ::..:::..::..::..::,.::,,. : .. .. ::.,::..:::+ .::..... .. .. .. .. . .. .. .. .. .. .. .. .. .. . .. .. .. .. : . ::....

.+

iiiiiii ii R-A R1.11-2 RR-4-5 85 25% 22 15 6 69%

R-A R1.11-5 RR-4-5 48 10% 5 3 0 60%

R-A R1.15-2 RR-4-5 1 25% 0 0 0%

R-A R1.16-2 RR-4-5 4 25% 0 0 0%

R-A R1.16-5 RR-4-5 4 10% 0 0 0%

R-A R1.18-6 RR-4-5 2 0% 0 0 0 0%

R-A R1.19-5 RR-4-5 4 10% 1 0 0 0%

R-A R1 .20-4 RR-4-5 782 10% 79 52 26 66%

R-A R1.20-6 RR-4-5 693 0% 0 0 0 0%

R-A R1.20-7 RR-4-5 33 0% 0 0 0 i~

0%

1/20/2009 ScheduleWorks V. 8.1 Page 5 - 5

NSPM INSERVICE INSPECTION PRAIRIE ISLAND UNIT 2 CYCLE 24

SUMMARY

REpORT Section 4. IWE Examinations (7 pages)

The following table summarizes the IWE inspections performed in cycle 24. Inspections are listed by class, category and site summary number. There were no relevant IWE indications in cycle 24. The second table lists the number and percentage of examinations or tests completed. The section includes an evaluation of inaccessible areas as required by IOCFR50.55a (b)(2)(ix)(A).

Page 1 of 1 Attachment 1 Inservice Inspection Report Interval 1, Period 3, P12RF2008_IWE

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

2. Plant: Prairie Island Nuclear Generating Plant 5. Commercial Service Date: 12/2111974

3. Plant Unit: 2 6. National Board Number for Unit: N/A Summary No. Comp. ID Comp. Desc. Item Procedure Method/Report/Results System Dwg/ISO E*<am Date Class MC Category E-A 600683 C61A Accessible Surface Area E1.12 SWI NDE-VT- VT / 2008V127 / NAD PC 2-Is0310 8/ 4/2008 2.1 600687 C62A Accessible Surface Area E1.12 SWI NDE-VT- VT / 2008V128 / NAD PC 2-1SI-307 8/ 4/2008 2.1 Class MC Category E-D 600472 G62 MOISTURE BARRIER E5.30 SWI NDE-VT- VT / 2008V201 / NAD PC 2-ISI-302 10121/2008 2.1 600473 G63 MiOISTURE BARRIER E5.30 SWI NDE-VT- VT / 2008V202 / NAD PC 2-ISt-302 10/21/2008 2.1 600474 G64 MOISTURE BARRIER E5.30 SWl NDE-VT- VT / 2008V203 / NAD PC 24ISI-302 10121r2008 2.1 600482 G71 MOISTURE BARRIER E5.30 SW NDE-VT- VT / 2008V204 / NAD PC 2-ISt-303 10121r2008 2.1 Class MC Category E-G 600684 B7 B'OLTED CONNECTION E8.10 SWi NDE-VT- VT / 2008V125 / NAD PC 2-St1-310 81412008 1.1 600688 B5 BOLTED CONNECTION E8.10 SW NDE-VT- VT 12008V126 1NAD PC 2-ISI-307 8/142008 1.1

Prairie Island Nuclear Plant Completion Code Compliance Summary - 1st Interval ISI -:Code Edition - 1992 Edition, 1992 Addenda Period 1 Period 2 Period 3 Percent Total Total Total Cat. Item No. Code Case Population Required Required Sched Comp. Sched Comp, Cummi % Sched Comp. Cumm % Sched Comp. Cumin % %Comp.

E-A E1.1 1 1 100% 1 0 1 0 1 100% 0 0 100% 0 0 100% 100%

E-A E1.12 317 100% 317 0 317 0 56 18% 0 118 55% 0 143 100% 100%

Totat~~.. .................. X: i ::.:.55%+..:.:

oii; 143:*::iiii100iiiiiiii~~i~

iiii Tota. ... . ....

0 0 0% 0 8 100% 0 16 100% 100%

I ..I o ................

E-D* E4.11 416 100% 416 0 416 0 14 35% 0 16 74% 0 11 100% 100%

T-D E5.3 41 10% 41 04 foo%

0 10 E-G E8.10 29 100% 29 0 29 0 11 38% 0 8 66% 100% 100%

Thtal ;i i il!: ,liii:!:*iiiiiii* i: :*~ iiii!: :*9i~ i*:* ii:i :i::i~~i;ii:~ ~~~* i:i:iiiiii

EG Augmented Examination are scheduled for each period for 3 consecutive periods starting with the period of identified.

1/20/2009 ScheduleWorks V. 8.1 Page 1 -1

Inaccessible Areas Evaluation 50.55a(b)(2)(ix)(A)

The Code of Federal Regulations, Title 10, Part 50.55a(b)(2)(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 ISI Summary Report as required by IWA-6000:

(1) 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 2R25 (cycle 24) resulted in water leaking from behind the concrete in containment sump B indicating that borated refuel water had come in contact with inaccessible areas of the steel containment vessel. This leakage is considered a condition in an accessible area that could indicate the presence of or result in degradation of inaccessible areas. As such, the following evaluation is included as required by 10CFR50.55a(b)(2)(ix)(A).

1. A description of the type and estimated extent'of degradation' and the conditions that led to the degradation.

The site believes there has been 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 sump B 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 in sump B was again removed to allow direct visual examination of the containment vessel and UT thickness readings. The vessel showed no visual indicaiton of corrosion and all thickness readings were above the nominal plate thickness. In addition, approximately an 18' x 2' area of the lowest accessible containment vessel plates were lUT scanned with all readings above the nominal plate thickness. Based on the results of the 1998 and 2006 professional engineering studies indicating no detrimental affects of refuel cavity leakage on containment over an extended period of time, and recent visual and thickness examinations of the containment vessel, there is reasonable assurance of no significant degradation.

The condition that could indicate the presence of or result in degradation is refuel cavity leakage that has come in contact with the containment vessel. Refuel cavity leakage into unit 2 sump B was noted in 2R24 (fall of 2006) and again in 2R25 (fall of 2008). In both cases inspection of the sump showed that leakage was coming into the sump through the concrete at the containment vessel near the RH suction lines at a rate of 1 of 4

Inaccessible Areas Evaluation 50.55a(b)(2)(ix)(A) approximately 1 gph. Similar leakage has been experienced in previous outages on both units with documentation dating back to at least 1998. In addition to sump B, past outages have shown leakage at other locations such as the regen HX room, nuclear instrument electrical penetrations and the floor near the RC drain tank.

2. An evaluation of the area, and the result of the evaluation.

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 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 borated 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.

2 of 4

Inaccessible Areas Evaluation 50.55a(b.)(2)(ix)(A)

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. 4]. However, most of the studies conducted involved reactor coolant at high concentration (13,000-15,000 PPM of boron with small amounts of lithium) and at high temperatures (>200 0 F). Reference 4 concludes that the maximum corrosion rates occurred where moisture can be replenished by a flowing solution, keeping a wet/dry 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.

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) were not compromised.

3. A description of necessary corrective actions.

Actions have been taken to prevent leakage including caulking refuel cavity leakage points prior to pool flood under maintenance procedure D99. In addition, a section of concrete was removed from sump B in the fall 2008 2R25 outage (WO00327768) to allow direct visual inspeciton of the steel containment vessel to assure no significant degradation. It is believed the sump B 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 sump B provides a high level of confidence there is no significant corrosion in other areas of the containment vessel. In addition, aproximately an 18' long x 2' high section 3 of 4

Inaccessible Areas Evaluation 50.55a(b)(2)(ix)(A) of the lowest accessible sections of the conatainment vessel were UT scanned from the annulus in 2008 with all readings above the nominal plate thickness.

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 previous and current inspections. The site continues to take corrective actions to prevent future leakage and perform examinations of the containment vessel to assure no significnat degradation.

4 of 4

NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION PRAIRIE ISLAND UNIT 2 CYCLE 24

SUMMARY

REPORT Section 5. Pressure Tests (3 pages)

The following class 1 and class 2 scheduled pressure tests were conducted during Unit 2 cycle 24. All indications were evaluated and corrective measures performed as required by IWB-3142 and IWA-5250.

Code Class 1 & 2 Pressure Tests Unit 1 Cycle 24 System Category Procedure Class WO# Completion Reactor SP 2070 Reactor B-P Coolant System 1 290012 10/29/2008 Coolant Integrity Test RC, S, VC, SISP 2392 Unit 2 RH, CS, SF B-P, C-H Insulated Bolted 1/2 290020 10/03/2008 Connection Inspection Safety SP 2168.13 Safety Injection C-H Injection System 2 363388 10/29/2008 Pressure Test Containment SP 2168.14 C-H Containment Spray 2 265201 5/10/2007 Spray System Pressure Test Residual SDP 2168.10 Residual Heat C-H Heat2 363389 10/25/08 Removal I I SP 2168.11 Main Main Steam C-H SPressure1Testn Steam Pressure Test 2 265197 1/05/2007 Boric Acid Corrosion Control Seventy-one boric acid indications were identified in cycle 24 as "ASME relevant" meaning boric acid had come in contact with the pressure boundary of a code class component. All ASME relevant indications were entered into the site corrective action program for corrective action and/or evaluation for continued service as appropriate. The majority of indications were characterized as non-active with a small amount of dry white boric acid residue in contact with a stainless steel pressure boundary. Per the H2 Boric Acid program document, boric acid indications found as a result of a boric acid inspection are evaluated as if found during a pressure test. In accordance with Code Case N-566-1 "Corrective action for Leakage Identified at Bolted Connections" evaluations of indications at bolted connections considered:

The number and service age of the bolts;

Bolt and component material;

Corrosiveness of process fluid;

Leakage location and system function;

Leakage history at the connection or other system components; Visual evidence of corrosion at the assembled connection.

BA Indications on Code Class Boundary Cycle 24 Component CAP# WO# or WR#

CS-41 1065133 307690 MV-32176 1073910 318297 MV-32170 1073771 313572 MV-32172 1073772 308797 MV-32173 1073773 327718 245-112 1071644 312023 245-111 1078430 318292 MV-32176 1073910 318297 2S1-13-1 1079274 320795 2VC-16-68 1080206 320796 2RH-6-1 1067261 335719 2FT-415 1080086 N/R 2LT-426 1080119 320139 2LT-427 1080117 320139 2LT-428 1080116 320139 MV-32170 1080104 313572 CV-31462 1080087 306037 MV-32173 1080076 327718 2SI-20-15 1080318 320688 2VC-5-4 1080894 N/R CV-31212 1080906 315375 CV-31212 1084099/1080906 315375 262-393 1084681 N/R 2VC-11-121 1119171 327703 MV-32177 1112536 320038 245-072 1086305 324825 2RH-11-3 1095916 333626 2RH-2-1 1095928 333625 245-042 1093741 332562 CV-31212 1101497 315375 2VC-5-4 1101636 337435 2CS-30-7 1106948 342047 6-2RH-10B 1107030 342098 MV-32172 1111988 308797 245-112 1110540 312023 2VC-11-127 112614 29387 2VC-11-142 1118687 30678 2VC-11-143 1118691 30680 2RH-2-1 1095928 N/R MV-32176 1120463 318297 MV-32177 1112536 320038 245-111 1124882/1132213 329376 2VC-11-122 1126278 N/R I

2VC-11-143 1126417 32435 245-032 1128417/1132721 N/R 2VC-1.1-59 1128400 32978 245-042 1132440 357664 MV-32176 1120463 318297 2RH-6-1 1138442 335719 MV-32170 1138457 313572 245-112 1140094 312023 2RH-11-3 1140104 341641 245-111 1145291 318292 253-041 1147224 N/R CS-43 1147779 37577 CS-41 1147778 37576/37564 245-101 1147767 37574 T/C Ports 34 & 35 1151370 306061 2PT-729 1151431 290019 MV-32170 1138457 319186 CV-31462 1151390 370781 2LT-428 1151391 320139 2FT-413 1151392 290019 2SI-9-2 1151544 93082 2RC-1-17 10799769 320158 245-052 1151385 290306 2SI-9-1 1151548 93081 CV-31347 1151685 352711 CV-31349 115232 370864 245-051 1157264 39954 CV-31347 1157303 352711

NSPM INSERVICE [NSPECTION PRAIRIE ISLAND UNIbbe sPORa 2 CYCLE 24

SUMMARY

Section 6. Snubber lnservice Testing and Preservice Examinations (1 3 pages)

. PRAIRIE ISLAND NUCLEAR GENERATIING PLANT SURVEILLANCE PROCEDURE PRAIRiE ISLAND NUCLEAR GENERAilNO PLANT SURVEILLANCE PROCEDURE NUMBER:

SP 2225

-S p - SNUBBER FUNCTIONAL TESTS REV: 13 ombl1ý 0Vg e Page I of 12 Initia *- --

R===

ESULTSICOMME Work Order Initiated: YES _ NO _ WO No.

Test Performance:

Performed By: _ ___-__'_ _ _ _ _Date: /*-7-0 g (Signature or Initials)

Additional Requirements:

NONE Review of Acceptability:

Acceptance Criteria Met? (3YNO System Engineer:

SP Completion:

System Engineer: .z Date: /4-7 7-0.

SP Surveillance Schedule Satisfied.CES - Surv. Admi Other Actions for Consideration:

System Engineer Review: * *K Date: /0 -0 g O.C. REVIEW DATE: OWNER' EFFECTIVE DATE 12/22/04 S. McCall 12/22/04

PRAIRIE ISLAND NUCLEAR GENERATING PLANT SURVEILLANCE PROCEDURE 1.0 PURPOSE AND GENERAL DISCUSSION INFORMATION USE

Proceduremay be performed from memory.

User remains responsible for procedure adherence.

Procedureshould be available,but not necessarily at, the work location.

1.1 Purpose This procedure documents that the service life review for safety related snubbers has been met in accordance with H20, "Snubber Examination and Functional Test Program." This procedure documents thatsnubbers that will exceed their service lives prior to the next refueling outage are replaced with refurbished snubbers or have their service lives extended by re-evaluation. This procedure performs population sampling and functional testing of safety related snubbers per the requirements of H20 and the ASME OM Code of record. This procedure documents fluid sampling of the steam generator snubbers to satisfy the fluid monitoring requirements of NRC Commitment P-448. This procedure documents functional testing of any snubbers that were found to be unacceptable by visual inspection per SP 2171. This procedure documents that any systems found supported by inoperable snubbers have had an engineering evaluation per H20 to determine whether the system was adversely affected.

1.2 Acceptance Criteria 1.2.1 Service Life Review This test is acceptable when the service life review of safety related snubbers has been completed, and those requiring refurbishment have been so refurbished or replaced and recorded in Table 2. Alternatively, service life may be extended by re-evaluation.

1.2.2 Functional Testinq This test is acceptable when the snubber population for each type of snubber has been sampled and tested for activation and bleed per the requirements of D H20 and ASME OM Code of record and the results recorded in Table 2.

PRAIRIE ISLAND, NUCLEAR. GENERA71NG PLANT SURVEILLANCE PROCEDURE NUMBER:

SP 2225 SP SNUBBER FUNCTIONAL TESTS REV: 13 Page 3 of 12 1.2.3 Visual Inspection This test is acceptable when any snubbers found to be unacceptable by visual examination per SP 2171 have been replaced and functionally tested to determine operability, and the results recorded in Table 2. Other snubbers generically susceptible to the same failure mode must be addressed by using the condition reporting process.

1.2.4 Fluid Sampling This test is acceptable when a volume of fluid has been drawn from the steam generator snubbers for testing for particulate and viscosity.

1.2.5 Engineering Evaluation This test is acceptable when all components found to be supported by inoperable snubbers have been evaluated to determine whether they might have been adversely affected by the failure of the snubber, and results of the evaluation have been recorded in Appendix B. The failure should also be documented in the condition reporting process to capture the operability evaluation of the supported system.

1.2.6 Contingency Actions There are no contingency actions associated with these acceptance criteria.

1.3 General Discussion Steps identified by an asterisk (*) are Acceptance Criteria.

2.0 REFERENCES

2.1 Developmental References 2.1.1 ASME OM Code, 1998, 2000 Addenda ISTD (after December 21,2004) 2.1.2 ASME/ANSI OM-1 987, Part 4, 1988 Addenda (before December 21, 2004) 2.1.3 Commitments P-448, P-449, P-450 2.1.4 Westinghouse Report 87-5B7-SNUBR-R1

. PRAIRIE ISLAND NUCLEAR GENERATING PLANT SURVEILLANCE PROCEDURE NUMBER:

S ~SNUBBER FUNCTIONAL TESTS SP__2226 Pago 4 of 12 2.2 Implementing References

2.2.1 Procedure

H20 "Snubber Examination and Functional Test Program" 2.2.2 Surveillance Procedure: SP 2171 "Tech Spec Shock Suppressor Check" 2.2.3 Maintenance Procedure: D45 "Snubber Test Stand Operating Procedure" 2.2.4 Maintenance Procedure: D45.5 "Snubber As Found Functional Test Procedure" 2.2.5 Maintenance Procedure: 1345.3 "Steam Generator 900 KIP Snubber Maintenance Procedure" 3.0 PRECAUTIONS AND LIMITATIONS 3.1 The sampling of snubbers for testing SHALL be done in accordance with the ASME OM Code of record. Table 1 is a listing of snubbers by type.

3.2 Table 2 is a summary of the snubber functional testing and SHALL list the snubbers tested and the test results.

3.3 Engineering evaluations required SHALL be attached to this surveillance test as per Appendix B.

3.4 Where exemption to functional testing is taken, the qualitative test report SHALL be attached to this surveillance test as Appendix C.

3.5 Sampling and testing must be completed prior to entering Mode 4, Hot Shutdown.

4.0 PERSONNEL AND SPECIAL EQUIPMENT REQUIREMENTS 4.1 Personnel System Engineer 4.2 Special Equipment NONE

SPRAIRIE ISLAND NUCLEAR GENERAT1NG PLANT SURVEILLANCE PROCEDURE NUMBER:

SP 2225 REV: 13 SNUBBER FUNCTIONAL TESTS Page S of 12 5.0 SPECIAL CONSIDERATIONS NONE 6.0 PREREQUISITES AND INITIAL CONDITIONS NONE 7.0 PROCEDURE 7.1 Review the snubber master list for Unit 2. If the Indicated service life will be exceeded prior to the next review, schedule these snubbers for reconditioning. Enter the appropriate information in Table 2. For the replacement snubbers verify service life has not been exceeded in prior use or that the seals have been replaced.

Commitment P-450 to the NRC requires that the replacement ITT steam generator snubbers be rebuilt and retested prior to their use.

Commitment P-449 to the NRC requires that the Nylatron back up ring material in the McDowell Wellman snubbers be changed out at the next Viton seal replacement as recommended in Westinghouse seal life report 87-5B7-SNUBR-R1.

NOTE: Seal life for: BE snubbers 7-10 yrs., ITT snubbers 7-10 yrs.,

Paul Munroe 40 yrs., McDowell Wellman 15 yrs.

7.2 Review SP 2171 for any snubbers found to be unacceptable by visual inspection or otherwise degraded and IF the snubber is to be removed for testing and/or refurbishment, THEN record the information in Table 2. ':;Pý-

7.3 Perform functional testing on a representative sample of snubbers from Table 1, as required by H20 and the current OM Code, and record the results in Table 2.

I N

7.4 Collect fluid samples from the steam generator snubbers for testing for particulate and fluid viscosity. Fluid monitoring is required by Commitment P-448 to the NRC in response to Westinghouse Report 87-5B7-SNUBR-R1.

7.5 Write a Summary Description of the snubber inspection and testing during the refueling interval and include in this SP as Appendix A.

PRAIRIE ISLAND NUCLEAR GENERATING PLANT SURVEILLANCE PROCEDURE 7.6 Forward a copy of the Summary Description to the ISI Program Engineer for inclusion in the IS Summary Report.

7.7 Ensure NIS-2 Forms for any ASME Section XI snubber replacements are completed and forward to the Section XI Coordinator.

7.8 On the cover sheet, list all attachments to this SP.

8.0 ATTACHMENTS 8.1 Table 1 - Snubber Grouping - Unit 2 8.2 Table 2 - Snubber Functional Test Summary 8.3 Appendix A - Summary Description of Snubber Visual Inspection and Functional Testing 8.4 Appendix B - Engineering Evaluation

.PRAIRIE ISLAND NUCLEAR GENERATING PLANT SURVEILLANCE PROCEDURE NUMBER:

REV: 123 SNUBBER FUNCTIONAL TESTS Page 7 of 12 Table I Snubber Grouping - Unit 2 Quantity Group Description 43 Size: 3/4" 8 Size: 1" 65 Size: 1-1/2" 6 Size: 2" 7 Size: 2-1/2" 7 Size: 3-1/4" 10 Size: 4" 3 Size: 5" 2 Size: 8" 151 Manufacturer: Basic Engineers 6 : Paul Munroe 3 : ITT Grinnell 8 : McDowell Wellman NOTE: Per H20, snubbers are grouped by manufacturer only. Size quantities listed above are for Information only.

2

.PRAIRIE ISLAND NUCLEAR GENERATING PLANT SURVEILLANCE PROCEDURE NUMBER:

SP sP22213 REV:

SNUBBER FUNCTIONAL TESTS Page 8 of 12 Table 2 Snubber Functional Test Summary SNUBBER FUNCTIONAL P1# PI # TEST NO. TEST WO REMOVED REPLACED RESULTS

- I ,3q 3.- 3_

Cz,-

=4- - Ito 7, -1 Z, /,-

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V7-c *,04"7 Z4-,* 405 t2Cd-i13 :3,346 2:77 L7 2-c-- - A7-3

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z - C C A4 - Ie , 3--2,5 1t

_.,_7_. Iq 2,- Ct.. - 15,2.. 35 ..3040 91

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-- oSA 33sasoi 55o I -MSi1-G9og 5?,o5-7 05 4-7 J Z_-_.3 - gzg 3o5 3_ ___,_ _S _55b ZgFA)4-339 s s 7, ____ __Z(0_

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2L16"Q1 i5 (0(o

-* - -4 2.- ;S Z)3q 7 6 ? e> '1 q69 5 l-EZVZH----,-_____

PRAIRIE ISLAND NUCLEAR GENERATING PLANT SURVEILLANCE PROCEDURE Table 2 Snubber Functional Test Summary

PRAIRIE ISLAND NUCLEAR GENERATING PLANT SURVEILLANCE PROCEDURE NUMBER:

SNUBBER FUNCTIONAL TESTS REV: 13 Page 10 of 12 Table 2 Snubber Functional Test Summary SNUBBER FUNCTIONAL PI # PI # TEST NO. TEST WO REMOVED REPLACED RESULTS

PRAIRIE ISLAND NUCLEAR GENERATING PLANT -" SURVEILLANCE PROCEDURE Appendix A

SUMMARY

DESCRIPTION OF SNUBBER VISUAL INSPECTION AND FUNCTIONAL TESTING FOR THE TIME PERIOD OF:

D1*L O( TO 2---97-r o*

All , jý&o_2-'

L~~a4 -- D

& PRAIRIE ISLAND NUCLEAR GENERATING PLANT SURVEILLANCE PROCEDURE NUMBER:

SP 2225 S pi SNUBBER FUNCTIONAL TESTS REV: 13 Page 120of12 Appendix B Engineering Evaluation PURPOSE:

An engineering evaluation SHALL be performed for all components supported by

'inoperable snubbers. The purpose of this engineering evaluation SHALL be to determine if the components were adversely affected by the inoperable snubber(s) to ensure that the components remain capable of meeting the designed service.

DISCUSSION:

Ifthe piping system is operated in a normal manner (no accident), the only adverse effects upon components of the piping system from inoperable snubbers are those caused by failure of the snubber to allow the pipe to thermally grow or in the case of a relief valve support, failure of the snubber to support the relief valve during a discharge or a stress imposed upon the relief valve piping during discharge due to excessive bleed rate and consequent ratcheting action. The engineering evaluation SHALL address these effects.

The author of the evaluation should reference the appropriate piping analysis printout and/or engineering evaluation provided by Fluor Power Service, Inc. or other qualified sources.

EVALUATION OF EFFECT OF INOPERABLE SNUBBERS

/0 - 13_1

NSPM [NSERVICE INSPECTION PRAIRIE ISLAND UNIT 2 CYCLE 24 SU.MMARY REPORT Section 7. Steam Generator Eddy Current Examination Results.

Examination Category B-Q, Steam Generator Tubing, is reported per the requirements of the Plant Technical Specifications.

NSPM Nuclear Department INSERVICE INSPECTION Prairie Island Unit 2 Cycle 24

SUMMARY

REPORT Section 8. RepairlReplacement Activities for Cycle 24, ISI Interval 4 54 NIS-2 forms are attached which identify Prairie Island Unit 2 Repair/ Replacement Activities during fuel cycle 24, 4 1h ISI Interval. The gaps in item number sequence are due to cancelled or unfinished R/R activities.

Item onl

_#6 pWtE~MD S4E 1294541-01, I I 2-24-001 294541-02 Replaced plungers in packing assemblies 2 I VC 157413-18, EC-2-24-002 nstalled new cooling water piping supports.

I652 I 3 CL 2-24-003 157413-01, EC- Installed Flow meter branch connection into CL pipe 652 segment 4-CL-8 , 3 CL 2-24-005 325638-01 Replaced the mechanical seal gland plate. 2 I VC 2-24-006 1325744-01 Replaced packing assemblies. 2 VC

.2-24-007i 327771-01 ... Replaced packing assemblies. 2 iVC 1.2-24-008 332042-01 Replaced the mechanical seal gland plate. 2 VC 2-24-009 1332256-01 1Replaced bonnet assembly. 2 VC 2-24-010 335518-01 iReplaced the mechanical seal gland plate. 2 i VC 2-24-011 97098-01 Replaced the mechanical seal gland plate. 2 VC iReplaced bonnet assembly and body to bonnet 2-24-013 .327703-01 fasteners. 2 VC 2-24-014 302367-01 !Replaced valve ball and flange fasteners. 3 CL J...

2-24-01535 180 1Replaced the mechanical seal gland plate. 2 VC 2-24-017 310670-01 j Replaced trim including, the main and inner plugs. 2

.2-24-019 .333052-01 .IRep/aced valve block. .......... .. . . . .

iReplaced valve block 2-24-020 333050-01 2 Rebuilt spare charging pump packing assemblies 13, 2-24-021 ........

357546-02 ........... . . . . . 14, 15.

.........T.... ..... ....... . .. . . . ... .... ........

2 i2-24-022 i317808-01 Replaced upper seal housing fasteners.

4 0. I.....

S 2 ..........

.... 1 72-i .....3 0 8 -01........................

....8......

2-24-023 :317807-01 ..Repaced .upper seal housing fasteners. RC 2-24-025 357904-01 pa 1-....R JRep'laicede. tthe _e...ch ..........................

mechanical

........ c seal gadpae 2 A.. vC Rebuilt spare charging pump packing assemblies 10, 2-24-026 349741-01 111, 12. 2 2-24-028 358409-01 ............!Replaced ..~~e p!a~

packing s..~ r..!.!..

c.i.n aassemblies.

es. ........... .................. . . . ..... 2 2-24-029 342098-01 Replaced flange studs. 2 2-24-0300.....7......1... Replaced disc and cover to body fasteners. 2 MS 93081-01, EEC- IReplace check valve disc, cover and body to cover 12-24-031 1546, EEC-7712 fasteners. 1 SI 93082-01, EEC-2-24-032 .1546, EEC-7712 Replace check valve disc and body to cap fasteners. SI 1*........

!~~ ~ ~:93083-01, ........................

8-.0,T,EEC-.... ......

~~~~~~~...

2-24-033 .1546, EEC-7712 Replace check valve disc and body to cap fasteners. SI 93084-01, EEC- Replace check valve disc and body to cap fasteners.

2-24-034 1546, EEC-7712 1 i sl

.93085-01, EEC- i..

2-24-035 :1546, EEC-7712 !Replace checkvalve disc and body to cap_ fasteners. s_1

NSPM Nuclear Department INSERVICE INSPECTION Prairie Island Unit 2 Cycle 24 f

SUMMARY

REPORT 3/4Itevi WOE4 MOPJ 7 QQsýGI6Pt&i d4 ~ or e~ is ~~TE 93086-01, EEC-2-24-036 1546, EEC-7712 !Replace check valve disc and body to cap fasteners. 1 SI 2-24-038 :357165-01 !Replaced packing assemblies. 2 VC 312023-01,.Ec- I

,2-24-039 11685 Replaced mechanical seal. 2 RH

.318292-01, EiC- i 2-24-040 i111685 j Replaced mechanical seal. t 2 RH i306854-01, EC-lReplaced

. ... ... Bonnet 2-24-042

....... ......8518. ...... : ............

.3..3

.... {i * ...... ... assembly ... and Internal trim.. . RC 1306853-01, EC-2-24-043 J8518 1Replaced Bonnet assembly and plug. 1 IRC 2.-24-044..355!.5-01.I 4 .-024~.*2 i ...~

..... . !6...~.5 -......

.... Rebuilt

!R p a esparec.charging pump packing assemblies. . . .. . . 2 VC 2-24-045 '311167-01 1Replaced disc. 2 MS IRebuilt spare charging pump packing assemblies 22, 2-24-047,349741-02 123,324. 2 VC 2-24-048 :366038-02 1Replaced packing assemblies. 2 VC 304396-01.EC- 1Installed new isolation valve and replaced associated 2-24-049 11442 1piping. 1 RC

.304395-01, EC- Jlnstalled new isolation valve and replaced associated 2-24-050 11442 piping . RC 303891-01, EC- Installed new isolation valve and replaced associated S2-24-051 11442 _pping 1 RC 306015-01, EC- !Installed a full structural overlay over the nozzle - safe 1 2-24-052 :9577 end - piping welds. 1 RC Weld build UD of wasted areas in shell and 2-24-053 100613-07 attachment weld areas. 3 Cc 2-24-054.108896-01 Replaced the disc. 2 SI

.2-24-055 .290306-01 Replaced one Lower Seal Housing Stud. RC 2-24-056 303589-01 ,,Replaced body to bonnet studs. 2 VC 2-24-057.289869-04 Replaced body to bonnet studs and nuts. 2 VC 2-24-058 369324-01 Replaced piping section. 3, ZH 2-24-059 365247-0 1 IReplaced shim packs to correct spacing 2 FW 2-24-060 .154830-01 IReplaced plug... 3 ...

zx ...

Corrected support to meet the drawing and design 2-24-061 297149-01 ,a n a lys is ..... ..............

... 2 FW

!Weld build up of wasted areas in shell and 2-24-062 369624-14 3.....

.......... ...4.......5..

............... attachment weld areas. 32 Cc 12-24-06335480 Replaced packing assemblies. 2 VC

PRAIRIE ISLAND NUCLEAR GENERA TING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-24-001

1. Owner Nuclear Management Company, LLC Date 5/3/2007 Name

2. Plant Prairie Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 294541-01, 294541-02 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 Expiration Date N/A Address

4. Identification of System VC Code Class 2

5. (a) Applicable Construction Code n/a n/a Edition Addenda n/a Code C ases n/a (b) Applicable Edition of Section XI Utilized for Repair/Replacement Activity 1998E / 2000A (c) Applicable Section Xl Code Cases None

6. Identification of Components Component Name Manufacturer Manufacturer Nat'l Bd # Other ID Yr Built Corrected, ASME Name Serial # Removed, or Code Installed Stamp Spare Charging Pump Ajax Spare 1969 Corrected E]

7. Description of Work Replaced plungers in packing assemblies

8. Tests conducted: ' HydrostaticF] PneumaticD] Nominal Operating Pressure -] Exempt W Other [] Pressure psi Test Temp.

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

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-24-001

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

Type Code Symbol Stamp 4114 Certificate of Aut a 4/// . Expiration Date Signed ASME Program Engineer Date "/_____ _ ,

Owner or Owner's Designee , Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minnesota and employed by HSB Insp. and Ins. Co. of Connecticut of Hartford Conn. havy inspected the' components described in this Owner's Report~during the period /O/..I/o ' to 0."/aS o. 0 and state that to the best of my knowledge and belief, the Owner has performed'examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective 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 A 0./. ,,,Wt*Z. ..S 4A-31 Inspector's Signature National Board, Pro,*ince and Endorsements Date o'oo 0

PRAIRIE ISLAND NUCLEAR GENERA TING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-24-002

1. Owner Nuclear Management Company, LLC Date Name

2. Plant Prairie Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 157413-18, EC652 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. Identification of System CL Code Class 3

5. (a) Applicable Construction Code B31.1 1967 Edition Addenda n/a Code Cases n/a (b) Applicable Edition of Section XI Utilized for Repair/Replacement Activity 1998E / 2000A (c) Applicable Section XI Code Cases None

6. Identification of Components Component Name Manufacturer Manufacturer Nat'l Bd # Other ID Yr Built Corrected, ASME Name Serial # Removed, or Code Installed Stamp Cooling Water support 2-CWH-623 2007 Installed D]

Cooling Water support 2-CWH-624 2007 Installed ED

7. Description of Work Installed new cooling water piping supports.

8. Tests conducted: Hydrostatic -] Pneumatic[- Nominal Operating Pressure [] Exempt F]

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

PRAIRIE ISLAND NUCLEAR GENERA TING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-24-002

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

Type Code Symbol Stamp Certificate of Authorization No. / Expiration Date Signed _: Z , ASME Program Engineer Date. ________

Owner or Owner's Designee , Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minnesota and employed by HSB Insp. and Ins. Co. of Connecticut of Hartford Conn. have inspected the components described in this Owner's Report during the period I-/8-/a - to 7/o-,o -

and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss of any kind arising connected with this inspection.

_--* ,0..4 Commissions /A,& 0515-3/* AR.&.1j*XC,,/S Inspector's Signature National Board, Provinc6 ard Endorsements Date 1,, /o

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-24-003

1. Owner Nuclear Management Company, LLC Date 7/10/2007 Name

2. Plant Prairie Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 157413-01, EC-652 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. Identification of System CL Code Class 3

5. (a) Applicable Construction Code B31.1 1967 Edition Addenda n/a Code Cases n/a (b) Applicable Edition of Section Xl Utilized for Repair/Replacement Activity 1998E / 2000A (c) Applicable Section Xl Code Cases None

6. Identification of Components Component Name Manufacturer Manufacturer Nat'l Bd # Other ID Yr Built Corrected, ASME Name Serial # Removed, or Code Installed Stamp Flow meter branch connection in 2007 Installed D 4-CL-8

7. Description of Work Installed Flow meter branch connection into CL pipe segment 4-CL-8

8. Tests conducted: Hydrostatic - PneumaticD Nominal Operating Pressure -] Exempt F]

Other 7] Pressure NOP psi Test Temp. NOT oF Other: n/a NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1 /2 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.

PRAIRIE ISLAND NUCLEAR GENERA TING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-24-003

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

Type Code Symbol Stamp A114 Certificate of Auth a b'74 Expiration Date Signed , ASME Program Engineer Date -_,,_,_,_ _,_ _.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 1-07-o2 0 to 1-/o-o1 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 aris or connected with this inspection.

___Commissions 4 ,e.s'/$3/ A -; /,14 *I.,S Inspector's Signature National Board, Province and Endorsements Date " /)

IC0c, ,o 7

(-I'.-

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY I

ITEM 2-24-005

1. Owner Nuclear Management Company, LLC Date 7/5/2007 Name

2. Plant Prairie Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 325638-01 Address Repair Organization P.O. No., Job No., etc

3. Work Performed by Owner Type Code Symbol Stamp N/A Name Same Authorization N/A Address Expiration Date N/A

. 4. Identification of System VC Code Class 2

5. (a) Applicable Construction Code n/a n/a Edition Addenda n/a Code Cases n/a (b) Applicable Edition of Section Xl Utilized for Repair/Replacement Activity 1998E / 2000A (c) Applicable Section Xl Code Cases None

6. Identification of Components Component Name Manufacturer Manufacturer Nat'l Bd # Other ID Yr Built Corrected, ASME Name Serial # Removed, or Code Installed Stamp 22 BATP Goulds 792A192-2 245-032 Corrected D

7. -Description of Work Replaced the mechanical seal gland plate.

8. Tests conducted: Hydrostatic Li PneumaticD] Nominal Operating Pressure F Exempt F]

Other El Pressure psi Test Temp. 0F Other: n/a NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1 /2 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.

PRAIRIE ISLAND NUCLEAR GENERA TING PLANT FOMNIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-24-005

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

Type Code Symbol Stamp AI/4 Certificate of Aut Expiration Date Signed,, ASME Program Engineer Date ______"

Owner or Owner's Designee , Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid.commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minnesota and employed by HSB Insp. and Ins. Co. of Connecticut of Hartford Conn. h ye inspected the components described in this Owner's Report during the period . it- to ,

and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

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

__ __ ___Commissions A,_1 63 / 4 *,*/, r ^IS Inspector's Signature National Board, Province and Endorsements Date ,1, U

0 PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-24-006

1. Owner Nuclear Management Company, LLC Date 5/4/2007 Name

2. Plant Prairie Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 325744-01 Address Repair Organization P.O. No., Job No., etc

3. Work Performed by Owner Type Code Symbol Stamp N/A Name Same Authorization N/A Address Expiration Date N/A

4. Identification of System VC Code Class 2

5. (a) Applicable Construction Code n/a n/a Edition Addenda n/a Code Cases. n/a (b) Applicable Edition of Section XI Utilizedfor Repair/Replacement Activity 1998E / 2000A (c) Applicable Section XI Code Cases None

6. Identification of Components Component Name Manufacturer Manufacturer Nat'l Bd # Other ID Yr Built Corrected, ASME Name Serial # Removed, or Code Installed Stamp 23 Charging Pump Ajax 245-043 1969 Corrected ED

7. Description of Work Replaced packing assemblies.

8. Tests conducted: HydrostaticsF Pneumatic-] Nominal Operating Pressure -] Exempt F]

Other F] Pressure psi Test Temp. 0F Other: n/a NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1 /2 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.-

FR N-PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-24-006

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

Type Code Symbol Stamp A/1/

Certificate ofA z A114. Expiration Date .

Signed ASME Program Engineer Date _ _

Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minnesota and employed by HSB Insp. and Ins. Co. of Connecticut of Hartford Conn. have inspected the-components described in this Owner's Report-during the period /3 /o 7 - to §4/o/o 7 and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury-9f property damage or a loss of any kind arising ed with this inspection.

Commissions -/5'T,53// 4 !,Jr.Z J S Inspector's Signature National Board, Province and Endorsements Date

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/IREPLACEMENT ACTIVITY ITEM 2-24-007

1. Owner Nuclear Management Company, LLC Date 6/1/2007 Name

2. Plant Prairie Island Nuclear Generating Plant Sheet 1 2 of of Name 1717 Wakonade Dr. E, Welch Minnesota 55089 327771-01 Address Repair Organization P.O. No., Job No., etc

3. Work Performed by Owner Type Code Symbol Stamp N/A Name Same Authorization N/A Address Expiration Date N/A

4. Identification of System VC Code Class 2

5. (a) Applicable Construction Code n/a n/a Edition Addenda n/a Code Cases n/a (b) Applicable Edition of Section XI Utilized for Repair/Replacement Activity 1998E / 2000A (c) Applicable Section XI Code Cases None

6. Identification of Components Component Name Manufacturer Manufacturer Nat'l Bd # Other ID Yr Built Corrected, ASME Name Serial # Removed, or Code Installed Stamp 22 Charging Pump Ajax 245-042 1969 Corrected ED

7. Description of Work Replaced packing assemblies.

8. Tests conducted: Hydrostatic [] Pneumatic[-] ' Nominal Operating Pressure [7 Exempt []

Other Pressure psi Test Temp. 0F Other: n/a NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.

PRAIRIE ISLAND NUCLEAR GENERA TING PLANT FORM:NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-24-007

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 Xl.

Type Code Symbol Stamp W1, Certificate of AuthIV' Expiration Date Signed 77 r , ASME Program Engineer Date 1___ _-_

Owner or Owner's Designee , Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of 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 S---o,- to 6 -o-f-o..

and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

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

__Commissions /'1^/ O TVT3/ 4 -*1sl/ Z9 A/S Inspector's Signature National Board, Province and Endorsements Date 6-,01)-od

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-24-008

1. Owner Nuclear Management Company, LLC Date 6/12/2007 Name

2. Plant Prairie Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 332042-01 Address Repair Organization P.O. No., Job No., etc

3. Work Performed by Owner Type Code Symbol Stamp N/A Name Same Authorization N/A Address Expiration Date N/A

4. Identification of System VC Code Class 2

5. (a) Applicable Construction Code n/a n/a Edition Addenda n/a Code Cases n/a (b) Applicable Edition of Section XI Utilized for Repair/Replacement Activity 1998E / 2000A (c) Applicable Section Xl Code Cases None

6. Identification of Components Component Name Manufacturer Manufacturer Nat'l Bd # Other ID Yr Built Corrected, ASME Name Serial # Removed, or Code Installed Stamp 22 BATP Goulds 792A192-2 245-032 Corrected D

7. Description of Work Replaced the mechanical seal gland plate.

8. Tests conducted: Hydrostatic [] Pneumatic D Nominal Operating Pressure -] Exempt [

Other F] Pressure psi Test Temp. 0F Other: n/a NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.;

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-24-008

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

Type Code Symbol Stamp ///4 Certificate of Authorization No. Expiration Date ___

Signed , ASME Program Engineer Date 4 W/,/ 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 -T7./-07 to ec -/3-0 7 and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss of any kind arisinconnected with this inspection.

Commissions -,W o$"Y/53 i /A, 8,1, Z /S Inspector's Signature National Board, Province and Endorsements Date 63 , ,co I

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-24-009

1. Owner Nuclear Management Company, LLC Date 6/12/2007 Name

2. Plant Prairie Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 332256-01 Address Repair Organization P.O. No., Job No., etc

3. Work Performed by Owner Type Code Symbol Stamp N/A Name Same Authorization N/A Address Expiration Date N/A

4. Identification of System VC Code Class 2

5. (a) Applicable Construction Code B16.34 n/a Edition Addenda n/a Code Cases n/a (b) Applicable Edition of Section Xl Utilized for Repair/Replacement Activity 1998E / 2000A (c) Applicable Section Xl Code Cases None

6. Identification of Components Component Name Manufacturer Manufacturer Nat'l Bd # Other ID Yr Built Corrected, ASME Name Serial # Removed, or Code Installed Stamp 21 Charging Pump Suction valve Grinnell 2VC-6-5 Corrected D

7. Description of Work Replaced bonnet assembly.

8. Tests conducted: Hydrostatic.- PneumaticDl Nominal Operating Pressure E] Exempt W]

Other Pressure psi Test Temp.

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

PRAIRIE ISLAND NUCLEAR GENERATING PLANT I FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-24-009

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

Type Code Symbol Stamp ,,A//1 Certificate of Aut ,zati Expiration Date Signed ASME Program Engineer Date .. 2,_____

Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minnesota and employed by HSB Insp. and Ins. Co. of Connecticut of Hartford Conn. have inspected the components described in this Owner's Report during the period s .//,Lo to (o'3l! ,

and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section Xl.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective 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 AI C /0 S'/-5-3/ A., 4 z^,* 'S Inspector's Signature National Board, Province and Endorsements Date 49 t.-rg /3 , iotA LI

PRAIRIE ISLAND NUCLEAR GENERA TING PLANT ,

FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-24-010

1. Owner Nuclear Management Company, LLC Date 8/7/2007 Name

2. Plant Prairie Island Nuclear Generating Plant Sheet I 2 of Name 1717 Wakonade Dr. E, Welch Minnesota 55089 335518-01 Address Repair Organization P.O. No., Job No., etc

3. Work Performed by Owner Type Code Symbol Stamp Name Same Authorization Address Expiration Date

4. Identification of System VC Code Class 2

5. (a) Applicable Construction Code n/a n/a Edition Addenda n/a Code Cases n/a (b) Applicable Edition of Section XI Utilized for Repair/Replacement Activity 1998E / 2000A (c) Applicable Section XI Code Cases None

6. Identification of Components

7. Description of Work Replaced the mechanical seal gland plate.

8. Tests conducted:' Hydrostatic 11. Pneumatic-] Nominal Operating Pressure -] Exempt [

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

PRAIRIE ISLAND NUCLEAR GENERA TING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-24-010

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

Type Code Symbol Stamp 4/,4 Certificate of Au iýtip' 7 4'/.. Expiration Date Signed , ASME Program Engineer Date o/1, 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 I /o0Jo it to 84LO E*a ,

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 fro ecd with this inspection.

Commissions MAIS0 S53/ ,4,i,91ZAI Inspector's Signature National Board, Province and Endorsements Date 04,'ý 0 "

C,,

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT'ACTIVITY ITEM 2-24-011

1. Owner Nuclear Management Company, LLC Date 1/3/2008 Name

2. Plant Prairie Island Nuclear Generating Plant Sheet -1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 97098-01 Address Repair Organization P.O. No., Job No., etc

3. Work Performed by Owner Type Code Symbol Stamp N/A Name Same Authorization N/A Address Expiration Date N/A

4. Identification of System VC Code Class 2

5. (a) Applicable Construction Code n/a n/a Edition

'Addenda n/a Code Cases n/a (b) Applicable Edition of Section Xl Utilized for Repair/Replacement Activity 1998E / 2000A (c) Applicable Section Xl Code Cases None.

6. Identification of Components Component Name Manufacturer Manufacturer Nat'l Bd # Other ID Yr Built Corrected, ASME Name Serial # Removed, or Code Installed Stamp 21 BA Transfer Pump Goulds 792A192-1 245-031 1970 Corrected D

7. Description of Work Replaced the mechanical seal gland plate.

8. Tests c6nd6cted' Hydeost'aticC' Pneumatic[] Nominal Operating Pressure [] Exempt W Other E] Pressure psi Test Temp. 0 F Other: n/a NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1 /2 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.

F PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-24-011

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

Type Code Symbol Stamp ,/,

Certificate ofAutho izA* ti 1_

,1,,4 Expiration Date Signed 7 ASME Program Engineer Date / /&o /0j, ,.

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 _ "_A_0_-_

_ to 013 a 08 1 and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

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

Commissions c,/5' 3/ A /3,,/,.E',>^IS Inspector's Signature National Board, Province ana Enddrsements Date 7 - -

FR N 2PRAIRIE ISLAND NUCLEAR GENERATING PLANT FLO RM N.IS-2 OWNER'S REPORT FOR REPAIR/ REPL .ACEMENT ACTIVITY ITEM 2-24-013

1. Owner Nuclear Management Company, LLC Date 1/18/2008 Name

2. Plant Prairie Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 327703-01 Address Repair Organization P.O. No., Job No., etc

3. Work Performed by Owner Type Code Symbol Stamp N/A Name Same Authorization N/A Address Expiration Date N/A

4. Identification of System VC Code Class 2

5. (a) Applicable Construction Code B16.34 n/a Edition Addenda n/a Code Cases n/a (b) Applicable Edition of Section XI Utilize4d for Repair/Replacement Activity 1998E / 2000A (c) Applicable Section XI Code Cases None

6. Identification of Components Component Name Manufacturer Manufacturer Nat'l Bd # Other ID Yr Built Corrected, ASME Name Serial # Removed, or Code Installed Stamp 121 BA TNK Outlet ITT Grinell 2VC-11-121 Corrected

7. Description of Work Replaced bonnet assembly and body to bonnet fasteners.

8. Tests conducted: Hydrostatic [] Pneumatic F] Nominal Operating Pressure Mj Exempt V Other Pressure psi Test Temp. OF Other: n/a NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1 /2 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.

I ~ PRAIRIE ISLAND NUCLEAR GENERA TING PLANT FORMNIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-24-013

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

Type Code Symbol Stamp 4114 Certificate of A oz ,4,/_,,_ Expiration Date Signed (. * , ASME Program Engineer Date ________

Owner or Owner's Designee , Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of. Minnesota and employed by HSB Insp. and Ins. Co. of Connecticut of Hartford CorQ. have inspected the components described in this Owner's Report during the period 1 /4Lo-7 to _'/ 81o, and state that to the best of my knowledge and belief, the Owner has p6rforFned examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

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

___ _____ -- __ __Commissions AM/oY5"3 I, 4 X-sIS,,/

.j.,,l5 Inspector's Signature National Board, Province and Endorsements Date .

U/

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-24-014

1. Owner Nuclear Management Company, LLC Date 3/21/2008 Name

2. Plant Prairie Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 302367-01 Address Repair Organization P.O. No., Job No., etc

3. Work Performed by Owner Type Code Symbol Stamp N/A Name Same Authorization N/A Address Expiration Date N/A

4. Identification of System CL Code Class 3

5. (a) Applicable Construction Code B31.1 1967 Edition Addenda n/a Code Cases n/a (b) Applicable Edition of Section XI Utilized for Repair/Replacement Activity 1998E /2000A (c) Applicable Section Xl Code Cases None

6. Identification of Components Component Name Manufacturer Manufacturer Nat'l Bd # Other ID Yr Built Corrected, ASME Name Serial # Removed, or Code Installed

Stamp 21 CLG WTR STRNR BCKWSH Jamesbury CV-31654 Corrected D

7. Description of Work Replaced valve ball and flange fasteners.

8.. Tests conducted:

Hydrostatic'F[" Pneumatic l- Nominal Operating Pressure [ Exempt W Other Pressure psi Test Temp. . OF

.Other: IST in accordance with SP 1151B.

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

FOMNS2PRAIRIE ISLAND NUCLEAR GENERATING PLANT EFORM:NIS-2 OWNER'S REPORT FOR REPAIR/-REPLACEMENT ACTIVITY ITEM 2-24-014

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

Type Code Symbol Stamp Certificate of oriz n Expiration Date Signed ASME Program Engineer Date Owner or Owner's Designee , Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minnesota and employed by HSB Insp. and Ins. Co. of Connecticut of Hartford Conn. have inspected the components described in this Owner's Report during the period /07 6?oC oL 'to 3 .24o6, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

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

_ _ _ _ _ _ _ _ Commissions AWA',osq1S3 I ,A, 1. ,*'Z Inspector's Signature National Board, Province and Endorsements Date I aOO8

FOMNS2PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-24-015

1. Owner Nuclear Management Company, LLC Date. 1/14/2008 Name

2. Plant Prairie Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 352318-01 Address Repair Organization P.O. No., Job No., etc

3. Work Performed by Owner Type Code Symbol Stamp N/A Name Authorization N/A Same Address Expiration Date N/A 4; Identification of System VC Code Class 2

5. (a) Applicable Construction Code . n/a. n/a Edition Addenda n/a Code Cases n/a (b) Applicable Edition of Section Xl Utilized for RepairlReplacement Activity 1998E / 2000A (c) Applicable Section XI Code Cases None

6. Identification of Components

7. Description of Work Replaced the mechanical seal gland plate.

8. Tests conductedi. . Hydrostatic El Pneumatic 7 Nominal Operating Pressure [ Exempt I' Other F-. Pressure psi Test Temp. 0 F Other: n/a NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1 /2 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-24-015

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

Type Code Symbol Stamp A1/4 Certificate of A Expiration Date Signed (S" , ASME Program Engineer Date _ __4_,/

Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the NationalIBoard 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 1/o31o0, to I/ S 08 .

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 fror or connected with this inspection.

Commissions $.- / A4,11 /*AS

',0,3,I Inspector's Signature National Board, Province and Endorsements Date I ?Coe"O LI

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/IREPLACEMENT ACTIVITY ITEM 2-24-017

1. Owner Xcel Energy, NSP-M Nuclear Department Date 11/18/2008 Name

2. Plant Prairie Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 310670-01 Address Repair Organization P.O. No., Job No., etc

3. Work Performed by Owner Type Code Symbol Stamp N/A Name Same Authorization N/A Expiration Date N/A Address

4. Identification of System MS Code Class 2

5. (a) Applicable Construction Code B16.34 n/a Edition Addenda n/a Code Cases n/a (b) Applicable Edition of SectionXl Utilized for Repair/Replacement Activity 1998E / 2000A.

(c) Applicable Section XI Code Cases None

6. Identification of Components Component Name Manufacturer Manufacturer Nat'l Bd # Other ID Yr Built Corrected, ASME Name Serial # Removed, or Code Installed Stamp 22 SG PORV Copse Vulcan 7010-95075-1-1 CV-31107 Corrected D

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

8. Tests conducted: Hydrostatic. - , Pneumatic - Nominal Operating Pressure [ Exempt [

Other [] Pressure psi Test Temp. 0F Other: Inservice testing will be performed in accordance with SP-211 lB.

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

I PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-24-017

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

Type Code Symbol Stamp Certificate of Auth or. i// Expiration Date Signed , ASME Program Engineer Date ,1____,

Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of 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 3oJo4,w 08 to &I40q0o9 and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective.

measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

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

Commissions m 1. q-Si In ector's Si ature National Board, Province and Endorsements Date ' n ov oVqptmla* 18 ,

I

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FOR:MNIS .-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-24-019

1. Owner Xcel Energy, NSP-M Nuclear Department Date 1/5/2009 Name

2. Plant Prairie Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 333052-01 Address Repair Organization P.O. No., Job No., etc

3. Work Performed by Owner Type Code Symbol Stamp N/A Name Same Authorization N/A Address Expiration Date N/A

4. Identification of System SG Code Class 2

5. (a) Applicable Construction Code B31.1 1967 Edition Addenda n/a Code Cases n/a (b) Applicable Edition of Section Xl Utilized for Repair/Replacement Activity 1998E / 2000A (c) Applicable Section XI Code Cases None

6. Identification of Components Component Name Manufacturer Manufacturer Nat'l Bd # Other ID Yr Built Corrected, ASME Name Serial # Removed, or Code Installed Stamp SG Snubber Block Valve McDowell Welman 72218-000-11 21S/G 01 Removed D SG Snubber Block Valve McDowell Welman 72218-000-16 21S/G 01 Installed El

7. Description of Work Replaced valve block.

8. Tests conducted: Hydrostatic [- Pneumatic Nominal Operating Pressure -] Exempt F]

Other El Pressure psi Test Temp. OF Other: n/a NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1 /2 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each ir.

sheet is*,' numbered and number of sheets is recorded at, ,the top of this form.

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-24-019

9. Remarks FE5 MI IC.E_. CUM f E.* *..D W REPOCP 1"COBV*"78 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 Xl.

Type Code Symbol Stamp Certificate of A rz Expiration Date Signed ASME Program Engineer Date L, L'*

Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minnesota and employed

.by HSB Insp. and Ins. Co. of Connecticut of Hartford Conn. have inspected the components described in this Owner's Report during the period 28ft,18 to 16JIrc 0, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

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

'*'Q 0- Commissions * '4 Ipector's Si .re National Board, Province and Endorsements Date 16 , -09

.J

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-24-020

1. Owner Xcel Energy, NSP-M Nuclear Department :-*. . ' -. ,* .,.' .. , > "Date a';, 1/5/2009

, . - .~I, A. -.

Name

2. Plant Prairie Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 333050-01 Address Repair Organization P.O. No., Job No., etc

3. Work Performed by Owner Type Code Symbol Stamp N/A Name Same Authorization N/A Address Expiration Date N/A

4. Identification of System SG Code Class 2

5. (a) Applicable Construction Code B31.1 1967 Edition Addenda n/a Code Cases n/a (b) Applicable Edition of Section Xl Utilized for Repair/Replacement Activity 1998E / 2000A (c) Applicable Section Xl Code Cases None

6. Identification of Components Component Name Manufacturer Manufacturer Nat'l Bd # Other ID Yr Built Corrected, ASME Name Serial # Removed, or Code Installed Stamp SG Snubber Block Valve McDowell Welman 72218-000-19 22S/G 01 Removed Dl SG Snubber Block Valve McDowell Welman 72218-000-10 22S/G 01 Installed ED

7. Description of Work Replaced valve ,block.

"I

8. Tests conducted: Hydrostatic D Pneumatic-] Nominal Operating Pressure 0 Exempt [

0 Other [] Pressure psi Test Temp. F Other: n/a NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1 /2 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets isý recorded at the top of this form.

I ~ PRAIRIE ISLAND NUCLEAR GENERA TING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-24-020

9. Remarks 315EW-C F--M4M 2Z-C.ll2--0 0A REPk-T Z*cV"(*7 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 Xl.

Type Code Symbol Stamp 41 Certificate of A a. Expiration Date Signed , ASME Program Engineer Date __,

Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the. State or Province of Minnesota and employed by HSB Insp. and Ins. Co. of Connecticut of Hartford Conn. have inspected the components described in this Owner's Report during the period 2z.rnkf 08 to 16JNq I and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

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

ci*d- Commissions r114 1qIQ 4 Spector's Si n t National Board, Province and Endorsements Date um..,* *(, , Qcoq J

PRAIRIE ISLAND NUCLEAR GENERA TING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-24-021

1. Owner Nuclear Management Company, LLC Date 4/2/2008 Name

2. Plant Prairie Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 357546-02 Address Repair Organization P.O. No., Job No., etc

3. Work Performed by Owner SType Code Symbol Stamp N/A Name Same - Authorization N/A Address Expiration Date N/A

4. Identification of System VC Code Class 2

5. (a) Applicable Construction Code n/a n/a Edition Addenda n/a Code Cases n/a (b) Applicable Edition of Section Xl Utilized for Repair/Replacement Activity 1998E /2000A (c) Applicable Section Xl Code Cases None

6. Identification of Components Component Name Manufacturer Manufacturer Nat'l Bd # Other ID Yr Built Corrected, ASME Name Serial # Removed, or Code Installed " Stamp Spare Charging Pump packing In/a spares Corrected D assembliesI

7. Description of Work Rebuilt spare charging pump packing assemblies 13, 14, 15.

8. Tests conducted: Hydrostatic F] Pneumatic F Nominal Operating Pressure [ Exempt [

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

FR N 2PRAIRIE ISLAND NUCLEAR GENERATING PLANT

FO:RM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-24-021

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 Xl.

Type Code Symbol Stamp A//4 Certificate of Au Expiration Date Signed , ASME Program Engineer Date _______,

Owner or Owner's Designee , Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minnesota and employed by HSB Insp.. and Ins. Co. of Connecticut of *Hartford Conn. have inspected the components described in this Owner's Report..during the period 3/1.4/o& to /,/o68 and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

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

Commissions M*,*/.5"53 , , ,k/5 r -3, Inspector's Signature National Board, ProvirIce and E'ndorsements Date Date 1

ac 0?006

0 PRAIRIE ISLAND NUCLEAR GENERA TING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-24-022

1. Owner Xcel Energy, NSP-M Nuclear Department Date 12/5/2008 Name

2. Plant Prairie Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 317808-01 Address Repair Organization P.O. No., Job No., etc

3. Work Performed by Owner Type Code Symbol Stamp N/A Name Same Authorization N/A Address Expiration Date N/A

4. Identification of System RC Code Class 1

5. (a) Applicable Construction Code n/a n/a Edition Addenda n/a Code Cases n/a (b) Applicable Edition of Section XI Utilized for Repair/Replacement Activity 1998E / 2000A (c) Applicable Section XI Code Cases None

6. Identification of Components

.Component Name Manufacturer Manufacturer Nat'l Bd # Other ID Yr Built Corrected, ASME Name Serial # _ Removed, or Code Installed Stamp 21 RCP Westinghouse 245-051 iCorrected [

7. Description of Work Replaced upper seal housing fasteners.

8. Tests conducted:, Hydrostatic.DF - Pneumatic [] Nominal Operating Pressure [ Exempt 7 .

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

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-24-022

9. Remarks VT-1 preservice exam recorded on report number 2008V164.

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

Type Code Symbol Stamp A//4 Certificate of Author ion-- Expiration Date Signed , ASME Program Engineer Date __,_______" ___ ,

Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minnesota and employed by HSB Insp. and Ins. Co. of Connecticut of Hartford Conn. have inspected the components described in this Owner's Report during the period (P7/*PiZO to D6teC0,19 and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

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

Commissions VI'2 nspector's Signature National Board, Province and Endorsements Date Q ylt 05 , Q008

PRAIRIEISLAND NUCLEAR GENERA TING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-24-023

1. Owner Xcel Energy, NSP-M Nuclear Department Date 12/5/2008 Name

2. Plant Prairie Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 317807-01 Address Repair Organization P.O. No., Job No., etc

3. Work Performed by Owner Type Code Symbol Stamp N/A Name Same Authorization N/A Address Expiration Date N/A

4. Identification of System RC Code Class 1

5. (a) Applicable Construction Code ASME Ill 1965 Edition Addenda n/a Code Cases n/a >: "

(b) Applicable Edition of Section XI Utilized for RepairlReplacement Activity 1998E / 2000A (c) Applicable Section XI Code Cases None

6. Identification of Components Component Name Manufacturer Manufacturer Nat'l Bd # Other ID Yr Built Corrected, ASME Name Serial # Removed, or Code Installed Stamp 22 RCP Westinghouse 245-052 Corrected D

7. Description of Work Replaced upper seal housing fasteners.

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

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

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-24-023

9. Remarks VT-1 preservice exam recorded on report number 2008V1 89.

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

Type Code Symbol Stamp //,4 Certificate of Autho . Expiration Date _ _ _ _ _ _,_

Signed , ASME Program Engineer Date // P 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 Cg"TA99-05 to - 9 EW. 1 and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

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

.0 Commissions rk 21.,91LA Iispector ignature National Board, Province and Endorsements Date L ,.MDAA Qq ,_,0_____

I

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-24-025

1. Owner Nuclear Management Company, LLC Date 6/26/2008 Name

2. Plant Prairie Island Nuclear Generating Plant Sheet 1 2 of Name 1717 Wakonade Dr. E, Welch Minnesota 55089 357904-01 Address Repair Organization P.O. No., Job No., etc

3. Work Performed by Owner Type Code Symbol Stamp N/A Name Same Authorization N/A Address Expiration Date N/A

4. Identification of System VC Code Class 2

5. (a) Applicable Construction Code n/a n/a Edition Addenda. *n/a Code Cases n/a (b) Applicable Edition of Section'XIUtilized for Repair/Replacement Activity 1998E / 2000A (c) Applicable Section XI Code Cases None

6. Iderntification of Components

7. Description of Work Replaced the mechanical seal gland plate.

8. Tests con8i6cted:" Hydrostatic F]ý:' Pneumatic Nominal Operating Pressure F] Exempt W]

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

PRAIRIE ISLAND NUCLEAR GENERA TING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-24-025

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

Type Code Symbol Stamp A//41 Certificate of Authorizajýý --o ' 1//// L. Expiration Date _ _ _ _,,_ _,_ _

Signed , ASME Program Engineer Date " 12-_,_

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 Oq APaQE, to 21 Juk'oe, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

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

_______- _______Commissions tp ro qnL-I spector's Signature National Board, Province and Endorsements Date r7, Q '2-1

F M 2PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-24-026

1. Owner Nuclear Management Company, LLC Date 9/11/2008 Name

2. Plant Prairie Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 349741-01 Address Repair Organization P.O. No., Job No., etc

3. Work Performed by Owner Type Code Symbol Stamp N/A Name Same Authorization N/A Address Expiration Date N/A

4. Identification of System VC Code Class 2

5. (a) Applicable Construction Code n/a n/a Edition Addenda n/a Code Cases n/a (b) Applicable Edition of Section1 Xl Utilized for Repair/Replacement Activity 1998E / 2000A (c) Applicable.Section XI Code Cases None

6. Identification of Components Component Name Manufacturer Manufacturer Nat'l Bd # Other ID Yr Built Corrected, ASME Name Serial # Removed, or Code Installed Stamp Spare Charging Pump Goiilds spare Corrected D

7. Description of Work Rebuilt spare charging pump packing assemblies 10, 11, 12.

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

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

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-24-026

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

Type Code Symbol Stamp 4 Certificate of Expiration Date Signed , ASME Program Engineer Date _________ "

Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minnesota and employed by HSB Insp. and Ins. Co. of Connecticut of Hartford Conn. have inspected the components described in this Owner's Report during the period M4kae*c to I5sPos and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

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

Commissions 02A91-m spector's Sig ature National Board, Province and Endorsements Date , a ,'-* n" nm JLA

PRAIRIE ISLAND NUCLEAR GENERA TING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-24-028

1. Owner Nuclear Management Company, LLC Date 9/11/2008 Name

2. Plant. Prairie Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 358409-01 Address Repair Organization P.O. No., Job No., etc

3. Work Performed by Owner Type Code Symbol Stamp N/A Name Same Authorization N/A Address Expiration Date N/A

4. Identification of System VC Code Class 2

5. (a) Applicable Construction Code n/a n/a Edition Addenda ... n/a Code Cases n/a (b) Applicable Edition of Section XI Utilized for Repair/Replacement Activity 1998E / 2000A (c) Applicable Section Xl Code Cases None

6. Identification of Components Component Name Manufacturer Manufacturer Nat'l Bd # Other ID Yr Built Corrected, ASME Name Serial # Removed, or Code Installed Stamp 21 Charging Pump Ajax 6917 245-041 1969 Corrected D

7. Description of Work Replaced packing assemblies.

8. Tests conducted: Hydrostatic F]ý. PneumaticD- Nominal Operating Pressure E] Exempt RV Other El Pressure - psi Test Temp. o F Other: n/a NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1 /2 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.

PRAIRIE ISLAND NUCLEAR GENERA TING PLANT I FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-24-028

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

Type Code Symbol Stamp -/2/

Certificate of* oza/, Expiration Date Signed 5 e , ASME Program Engineer Date ________

Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minnesota and employed by HSB Insp. and Ins. Co. of Connecticut of Hartford Conn. have inspected the components described in this Owner's Report during the period IbAPRMtB to l55sejoI 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.

CDP Commissions _____ ____q_-_

In ector's Sign re National Board, Province and Endorsements Date *, 4,15

PRAIRIE ISLAND NUCLEAR GENERA TING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-24-029

1. Owner Xcel Energy, NSP-M Nuclear Department Date 1/6/2009 Name

2. Plant Prairie Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 342098-01 Address Repair Organization P.O. No., Job No., etc

3. Work Performed by Owner Type Code Symbol Stamp N/A Name Same Authorization N/A Address Expiration Date N/A

4. Identification of System RH Code Class 2

5. (a) Applicable Construction Code B31.1 1967 Edition Addenda n/a Code Cases n/a A (b) Applicable Edition of Section Xl Utilized for Repair/Replacement Activity 1998E / 2000A -

(c) Applicable Section XI Code Cases None

6. Identification of Components Component Name Manufacturer Manufacturer Nat'l Bd # Other ID Yr Built Corrected, ASME Name Serial # Removed, or Code Installed Stamp Orifice Flange Studs in pipe 6- Installed D

7. Description of Work Replaced flange studs.

8. Tests conducted: Hydrostatic " Pneumatic D Nominal Operating Pressure F] Exempt V Other Pressure psi Test Temp. oF Other: n/a NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1 /2 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.

SPRAIRIE ISLAN D NUCLEAR GENERA TING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-24-029

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

Type Code Symbol Stamp 4i4 Certificate of A, * - . ,4///i Expiration Date Signed , ASME Program Engineer Date 4___,

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 28,mA'1 cz, to (P"tAA, Oq I and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

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

0 " Commissions ,m4qA4 Inspector's Signature National Board, Province and Endorsements Date / -2L.l*. bi ,9 UJ

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S. REPORT FOR REPAIR/REPLACEMENT ACTIVITY ITEM 2-24-030

1. Owner Xcel Energy, NSP-M Nuclear Department Date 1/9/2009 Name

2. Plant Prairie Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 308076-01 Address Repair Organization P.O. No., Job No., etc

3. Work Performed by Owner Type Code Symbol Stamp N/A Name Same Authorization N/A Address Expiration Date N/A

4. Identification of System MS Code Class 2

5. (a) Applicable Construction Code B16.34 n/a Edition Addenda n/a Code Cases n/a -

(b) Applicable Edition of Section XLUtilized for Repair/Replacement Activity 1998E / 2000A (c) Applicable Section Xl Code Cases None

6. Identification of Components Component Name Manufacturer Manufacturer Nat'l Bd # Other ID Yr Built Corrected, ASME

7. Description of Work Replaced disc and cover to body fasteners.

8. Tests conducted: Hydrostatic.0, Pneumatic[- Nominal Operating Pressure [] Exempt 7.

Other Pressure psi Test Temp. 0F Other: Valve will be tested in accordance with SP 2374 NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1 /2 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet'is numbered and number of sheets is recorded at the top of this form.

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-24-030

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

Type Code Symbol Stamp /1//-

Certificate of Auth 41ý4//4- Expiration Date Signed_, ASME Program Engineer Date ._-A-__-

Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minnesota and employed by HSB Insp. and Ins. Co. of Connecticut of Hartford Conn. have inspected the components described in this Owner's Report during the period 2.e- mA' to ZR,4JA,409 and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

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

___-__ ______ ______ _____ Commissions _ _ _ _'_ _-_ _

National Board, Province and Endorsements

PRAIRIE ISLAND NUCLEAR GENERATING PLANT-FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-24-031

1. Owner Xcel Energy, NSP-M Nuclear Department Date 1/5/2008 Name

2. Plant Prairie Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 93081-01, EEC-1546, EEC-7712 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. Identification of System SI Code Class 1

5. (a) Applicable Construction Code B16.34 n/a Edition Addenda n/a Code Cases n/a (b) Applicable Edition of Section XI Utilized for RepairlReplacement Activity 1998E / 2000A .J (c) Applicable Section XI Code Cases None

6. Identification of Components Component Name Manufacturer Manufacturer Nat'l Bd # Other ID Yr Built Corrected, ASME Name Serial # Removed, or Code Installed Stamp Cold Leg Inject Line to Loop B Velan 2SI-9-1 Corrected Dl Cold Leg Check

7. Description of Work Replace check valve disc, cover and body to cover fasteners.

8. Testý conrducted: Hydriostatic 1 Pneumatic - Nominal Operating Pressure [ Exempt []

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

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-24-031

9. Remarks Preservice exams recorded on reports 2008V1 80 (New Bonnet) and 2008V159 (fasteners).

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

Type Code Symbol Stamp A1/4 Certificate of Auth zato- Expiration Date /_'_ _ _ _ _

Signed ASME Program Engineer Date .____,

Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minnesota and employed by HSB Insp. and Ins. Co. of Connecticut of Hartford Conn. have inspected the components described in this Owner's Report during the period 2.*nhrTIA to AJMacq I and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

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

.0 Commis sions Mitý I~

sp ctor's SignAe National Board, Province and Endorsements Date 9g , .200 KýA 6'

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-24-032

1. Owner Xcel Energy, NSP-M Nuclear Department Date 1/5/2009 Name

2. Plant Prairie Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 93082-01, EEC-1546, EEC-7712 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. Identification of System SI Code Class 1

5. (a) Applicable Construction Code B16.34 n/a Edition n/a Code Cases n/a A Addenda (b).Applicable Edition of Section kI Utilized for Repair/Replacement Activity 1998E / 2000A (c) Applicable Section XI Code Cases None

6. Identification of Components Component Name Manufacturer Manufacturer Nat'l Bd # Other ID Yr Built Corrected, ASME Name* Serial # Removed, or Code Installed Stamp Cold Leg Inject Line to Loop A Velan 2SI-9-2 Corrected D Cold Leg Check

7. Description of Work Replace check valve disc and body to cap fasteners.

8. Tests conducted: Hydrostatic ,f Pneumatic Nominal Operating Pressure Other [] Pressure psi Test Temp. OF Other: n/a NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.

I. ,

- PRAIRIE ISLAND NUCLEAR GENERA TING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-24-032

9. Remarks ,r, ,* .j- kep-, oot/,,6"-

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

Type Code Symbol Stamp IV1, Certificate of Aut or " A114 Expiration Date Signe/' , ASME Program Engineer Date .. _______

Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minnesota and employed by HSB Insp. and Ins. Co. of Connecticut of Hartford Conn. have inspected the components described in this Owner's Report during the period 2-_____, to I"SJA'4" and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

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

. 'Commissions _ _ _,,_ _ _ _

Inspector's Si nature National Board, Province and Endorsements Date I3-* *,. .*4 I.; I

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-24-033

1. Owner Xcel Energy, NSP-M Nuclear Depa tment Date 1/5/2009 Name

2. Plant Prairie Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 93083-01, EEC-1546, EEC-7712 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. Identification of System SI Code Class 1

5. (a) Applicable Construction Code B16.34 n/a Edition Addenda n/a Code Cases n/a (b) Applicable Edition of Section XI Utilized for Repair/Replacement Activity 1998E / 2000A (c) Applicable Section Xl Code Cases None

6. Identification of Components Component Name Manufacturer Manufacturer Nat'l Bd # Other ID Yr Built Corrected, ASME Name Serial # Removed, or Code Installed Stamp Low Head SI to 22 Rx Vessel Velan 2SI-9-3 Corrected ED Check

7. Description of Work Replace check valve disc and body to cap fasteners.

8. Tests ond'uced: Hydrostaticc' I-'Pneumatic] Nominal Operating Pressure Ej Exempt W Other Pressure psi Test Temp. oF Other: n/a NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 on this report is included.on~each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT, ACTIVITY ITEM 2-24-033

9. Remarks Pf-SEIZqJCF Ei.AM " IS IRELOzo 6t. RE.,r t 2aBV/t1o CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code,Section XI.

Type Code Symbol Stamp -///4" Certificate of A t . Expiration Date Signed ,ASME Program Engineer Date /00 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 28(MAH.8 to ISJAlbR ,

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.

r*"CaD Z ) u eCommissions rft% 4q,2t4 I pe tor's Sign re National Board, Province and Endorsements Date I.

1A 2,09

ýJ

PRAIRIE ISLAND NUCLEAR GENERA TING PLANT I FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-24-034

1. Owner Xcel Energy, NSP-M Nuclear Department Date 1/6/2009 Name'.

2. Plant Prairie Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 93084-01, EEC-1546, EEC-7712 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. Identification of System SI Code Class 1

5. (a) Applicable Construction Code B16.34 n/a Edition Addenda n/a Code Cases n/a (b) Applicable Edition of Section XI Utilized for Repair/Replacement Activity 1998E / 2000A (c) Applicable Section XI Code Cases None

6. Identification of Components

7. Description of Work Replace check valve disc and body to cap fasteners.

8. Tests conducted: Hydrostatic [] Pneumatic F] Nominal Operating Pressure - Exempt [

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

,'. -,.. .. .,~ ., . . , . ... .. I

I

PRAIRIE ISLAND NUCLEAR GENERATING PLANT I FORMNIS-2 *OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-24-034

9. Remarks G.I' . 6(.*m I' RECo6-DEO OIS WE *..T'LO'i11.

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

Type Code Symbol Stamp ///

Certificate of Au/ o. 1//// Expiration Date Signed , ASME Program Engineer Date 1 7 4713_

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 8 r9A4 08 to i3J4 ,0q 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 damageor a loss of any kind arising from or connected with this inspection.

Commissions __ _ _ _ _ _

npctor's Sign e National Board, Province and Endorsements Date 7z

ýK)

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-24-035

1. Owner Xcel Energy, NSP-M Nuclear Department .. Date 1/6/2009 Name

2. Plant Prairie Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 93085-01, EEC-1546, EEC-7712 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. Identification of System SI Code Class 1

5. (a) Applicable Construction Code B16.34 n/a Edition Addenda n/a Code Cases n/a "

(b) Applicable Edition of Section XI Utilized for Repair/Replacement Activity 1998E / 2000A (c) Applicable Section Xl Code Cases None

6. Identification of Components Component Name Manufacturer Manufacturer Nat'l Bd # Other ID Yr Built Corrected, ASME Name Serial # Removed, or Code Installed Stamp Hi/Low Head Sl to 22 Rx Vessel Velan 2Sl-9-5 Corrected DJ Check

7. Description of Work Replace check valve disc and body to cap-fasteners.

8. Tests Co~d`utek: ~ Hydrdstatic [- PneumaticD- Nominal Operating Pressure E] Exempt []

Other [] Pressure psi Test Temp. o F Other:' n/a NOTE: Supplemental sheets in form of lists, sketches, or-drawings may be used, provided (1) size is 8 1 /2 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.

PRAIRIE ISLAND NUCLEAR GENERA TING PLANT 1 FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-24-035

9. Remarks -PPE5. dCI* E'AA.M IS RECO.Z.OE Ot- E.Pot?.rT I 2.O84a,,i CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code,Section XI.

Type Code Symbol Stamp 4/

Certificate of Authorization No. Expiration Date Signed - , ASME Program Engineer Date ,9 _____-11, 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 urnnAj0a to 13J,0i9R 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.

0.1 Commissions m ,qI Inspector's nature National Board, Province and Endorsements Date

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-24-036 I

1. Owner Xcel Energy, NSP-M Nuclear Department Date 12/16/2008 Name

2. Plant Prairie Island Nuclear Generating Plant Sheet 1 2 of Name 1717 Wakonade Dr. E, Welch Minnesota 55089 93086-01, EEC-1 546, EEC-7712 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 NI/A

4. Identification of System SI Code Class 1

5. (a) Applicable Construction Code B16.34 n/a Edition/Addenda Addenda n/a Code Cases n/a (b) Applicable Edition of Section.Xl Utilized for Repair/Replacement Activity 1998E / 2000A (c) Applicable Section Xl Code Cases None

6. Identification of Components Component Name Manufacturer Manufacturer Nat'l Bd # Other ID Yr Built Corrected, ASME Name Serial # Removed, or Code Hi/Low Head SI to 21 Rx Vessel Check Velan 2SI-9-6 I j Installed Corrected Stamp D

7. Description of Work Replace check valve disc and body to cap fasteners.

8. Tests c'onduc'ted: Hydrostatic F Pneumatic Nominal Operating Pressure [ Exempt [

Other DY Pressure psi Test Temp.

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

I ~ PRAIRIE ISLAND NUCLEAR GENERA TING PLANT FORM NIS.2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-24-036

9. Remarks Pre-service exams documented in reports 2008V163 and BOP-VT-08-088.

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

Type Code Symbol Stamp

1/4.

Certificate of Aut111 1/4/ Expiration Date Signed , ASME Program Engineer Date z_,____,- ,

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 W.BmAJ O8 to I17 .c(68 I and state that to.the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

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

Ins ector's Signa e National Board, Province and Endorsements Date .10L6,A5I!

Il 2,*

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-24-038

1. Owner Nuclear Management Company, LLC Date 5/20/2008 Name

2. Plant Prairie Island Nuclear Generating Plant Sheet 1 2 of Name 1717 Wakonade Dr. E, Welch Minnesota 55089 357165-01 Address Repair Organization P.O. No., Job No., etc

3. Work Performed by Owner Type Code Symbol Stamp Name Same Authorization.

Address Expiration Date

4. Identification of System VC Code Class 2

5. (a) Applicable Construction Code n/a n/a Edition Addenda n/a Code Cases n/a (b) Applicable Edition of Section Xl'Utiliz'ed for Repair/Replacement Activity 1998E / 2000A, (c) Applicable Section Xl Code Cases None

6. Identification of Components Component Name Manufacturer Manufacturer Nat'l Bd # Other ID Yr Built Corrected, ASME Name Serial # Removed, or Code Installed Stamp 22 Charging Pump Ajax 245-042 1969 Corrected EJ

7. Description of Work Replaced packing assemblies.

8. Tests conducted: Hydrostatic D Pneumatic F Nominal Operating Pressure F] Exempt F]

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

.PRAIRIE ISLAND NUCLEAR GENERA TING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-24-038

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

Type Code Symbol Stamp Certificate of A oriz Expiration Date Signed 2; , ASME Program Engineer Date * /* ,

Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minnesota and employed by HSB Insp. and Ins. Co. of Connecticut of Hartford Conn. have inspected the components described in this Owner's Report during the period 3/1-7-,5/ to 5/,14o/08 and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

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

Commissions ,f1, 45,*dG5S3J ,/, s Inspector's Signature National Board, Province and Endorsements Date -

"-I

PRAIRIE ISLAND NUCLEAR GENERA TING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-24-039

1. Owner Xcel Energy, NSP-M Nuclear Department Date 11/18/2008 Name

2. Plant Prairie Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 312023-01, EC-11685 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. Identification of System RH Code Class 2

5. (a) Applicable Construction Code n/a n/a Edition Addenda n/a Code Cases n/a (b) Applicable Edition of Section XI Utilized for RepairlReplacement Activity 1998E / 2000A (c) Applicable Section Xl Code Cases None

6. Identification of Components Component Name Manufacturer Manufacturer Nat'l Bd # Other ID Yr Built Corrected, ASME Name Serial # Removed, or Code Installed Stamp 22 RHR Pump Byron Jackson 681N0275 245-112 Corrected DJ

7. Description of Work Replaced mechanical seal.

8. Tests conducted: Hydrostatic RTi. PneumaticD--7 Nominal Operating Pressure -] Exempt W]

Other Pressure psi Test Temp. 0F Other: n/a NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1 /2 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-24-039

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

Type Code Symbol Stamp ///4 Certificate of Author i/o Expiration Date Signed , ASME Program Engineer Date .,,___._

Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minnesota and employed by HSB Insp. and Ins. Co. of Connecticut of Hartford Conn. have inspected the components described in this Owner's Report during the period 27nmAY0- to Io'Jo? - I and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

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

A0 Commissions ________________

I pectorsSi ature National Board, Province and Endorsements Date .Q oVri9tMw it ,

/

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-.2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-24-040

1. Owner Xcel Energy, NSP-M Nuclear Department Date 12/4/2008 Name

2. Plant Prairie Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 318292-01, EC-11685 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. Identification of System RH Code Class 2

5. (a) Applicable Construction Code n/a n/a Edition Addenda n/a - Code Cases n/a (b) Applicable Edition of Section.XI Utilized for Repair/Replacement-Activity 1998E / 2000A (c) Applicable Section Xl Code Cases None

6. Identification of Components Component Name Manufacturer Manufacturer Nat'l Bd # Other ID Yr Built Corrected, ASME Name Serial # Removed, or Code Installed Stamp 21 RHR Pump Byron Jackson 681N0274 245-111 Corrected []

7. Description of Work Replaced mechanical seal.

8. Tests conducted: Hydrostatic F. Pneumatic 0 Nominal Operating Pressure E] Exempt W Other [- Pressure psi Test Temp. 0 F Other: n/a NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1 /2 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.

PRAIRIE ISLAND NUCLEAR GENERA TING PLANT [

FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-24-040

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

Type Code Symbol Stamp //14 Certificate of Aut 4i1_ Expiration Date Signed , ASME Program Engineer Date 4 ' ____*

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 2B Mtpi, to ibqwr-cog I and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective 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 rA -'-t I pector's Sign re National Board, Province and Endorsements Date _ .__

PRAIRIE ISLAND NUCLEAR GENERA TING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-24-042

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

2. Plant Prairie Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 306854-01, EC-8518 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. Identification of System RC Code Class 1

5. (a) Applicable Construction Code B16.34 n/a Edition Addenda n/a Code Cases n/a V (b) Applicable Edition of Section.XI Utilized for Repair/Replacement Activity 1998E / 2000A (c) Applicable Section Xl Code Cases None

6. Identification of Components

[ComponentName Manufacturer Manufacturer Nat'l Bd # Other ID Yr Built Corrected, ASME

7. Description of Work Replaced Bonnet assembly and internal trim.

8. Tests conducted: Hydrostatic M Pneumatic D- Nominal Operating Pressure -] Exempt F/

Other Pressure psi Test Temp. 0F Other: IST testing in accordance with SP 2291 NOTE: Supplemental.sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1 /2 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.

PRAIRIE ISLAND NUCLEAR GENERA TING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-24-042

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

Type Code Symbol Stamp 4/1,4 Certificate of A Expiration Date Signed - ASME Program Engineer Date _ __, _______

Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minnesota and employed by HSB Insp. and Ins. Co. of Connecticut of Hartford Conn. have inspected the components described in this Owner's Report during the period 28 MAJI0 to at'404

and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

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

Commissions rA 9-1914q

's ture National Board, Province and Endorsements Date "1f-mAu \- 121, ,

I

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-24-043

1. Owner Xcel Energy, NSP-M Nuclear Department Date 12/16/2008 Name

2. Plant Prairie Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 306853-01, EC-8518

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. Identification of System RC Code Class 1

5. (a) Applicable Construction Code B16.34 n/a Edition Addenda n/a Code Cases n/a (b) Applicable Edition of Section Xl Utilized for RepairlReplacement Activity 1998E / 2000A (c) Applicable Section XI Code Cases None

6. Identification of Components Component Name Manufacturer Manufacturer Nat'l Bd # Other ID Yr Built Corrected, ASME Name Serial # Removed, or Code Installed Stamp Pressurizer PORV 8 SPX / Copes CV-31 233 11968 ICorrected E Vulcan II

7. Description of Work Replaced Bonnet assembly and plug.

8. Tests conrducteld: Hydrostatic6'F Pneumatic F Nominal Operating Pressure F] Exempt IF Other F1 Pressure psi Test Temp. oF Other: n/a NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1 /2 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-24-043

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

Type Code Symbol Stamp ////

Certificate of * //4-' Expiration Date Signed ASME Program Engineer Date / /__ __,

Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minnesota - and employed by HSB Insp. and Ins. Co. of Connecticut of Hartford Conn. have inspected the components described in this Owner's Report during the period 2bolNa .. 9 to IGbE.C.8 I and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

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

'4 nI spec °rs*'0-9 Commissions tLDmA1L%

Inspector ignature National Board, Province and Endorsements Date ýI*rn I1. ,,

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-24-044

1. Owner Nuclear Management Company, LLC Date 8/20/2008 Name

2. Plant Prairie Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 357515-01 Address Repair Organization P.O. No., Job No., etc

3. Work Performed by Owner Type Code Symbol Stamp N/A Name Same Authorization N/A Address Expiration Date N/A

4. Identification of System VC Code Class 2

5. (a) Applicable Construction Code n/a n/a Edition Addenda n/a Code Cases n/a (b) Applicable Edition of Section Xl Utilized for Repair/Replacement Activity 1998E / 2000A (c) Applicable Section Xl Code Cases None

6. Identification of Components Component Name Manufacturer Manufacturer Nat'l Bd # Other ID Yr Built Corrected, ASME Name Serial # Removed, or Code Installed Stamp Spare Charging Pump packing n/a spares Corrected E]

assemblies

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

8. Tests conducted: Hydrostatic [I Pneumatic [ Nominal Operating Pressure [] Exempt []

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

PRAIRIE ISLAND NUCLEAR GENERA TING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-24-044

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 X1.

Type Code Symbol Stamp A11/4 Certificate of oriz414 Expiration Date Signed ASME Program Engineer Date _ __ .___o__

Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minnesota and employed by HSB Insp. and Ins. Co. of Connecticut of Hartford Conn. have inspected the components described in this Owner's Report during the period '21 "lt, o-6 to "-1 ALu*O',

and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report. Furthermore, neither the 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 rn 4, O2.1t1-Ins ector's Signature National Board, Province and Endorsements Date 0_* %! , _ _: _ _

U

PRAIRIE ISLAND NUCLEAR GENERA TING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-24-045

1. Owner Xcel Energy, NSP-M Nuclear Department Date 12/5/2008 Name

2. Plant Prairie Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 311167-01 Address Repair Organization P.O. No., Job No., etc

3. Work Performed by Owner Type Code Symbol Stamp N/A Name Same Authorization N/A Address Expiration Date N/A

4. Identification of System MS Code Class 2

5. (a) Applicable Construction Code ASME Ill Class II 1980 Edition Addenda Summer 1981 Code Cases n/a (b) Applicable Edition of Section Xl Utilized for Repair/Replacement Activity 1998E / 2000A (c) Applicable Section XI Code Cases None

6. Identification of Components Component Name Manufacturer Manufacturer Nat'l Bd # Other ID Yr Built Corrected, ASME Name Serial # Removed, or Code Installed Stamp 22 SG MS SPLY TO 22 TD AFW Powell 2MS-15-1 Corrected I PMP CHECK

7. Description of Work Replaced disc.

8. Tests conducted: Hydrostatic -" Pneumatic -] Nominal Operating Pressure -E] Exempt W Other Pressure psi Test Temp. OF Other: n/a NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1 /2 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.

PRAIRIE ISLAND NUCLEAR GENERA TING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-24-045

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

Type Code Symbol Stamp l*/

Certificate of Autho.Expiration Date Signed , ASME Program Engineer Date 1_2 Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State .or Province of Minnesota and employed by HSB Insp. and Ins. Co. of Connecticut of Hartford Conn. have inspected the components describedin this Owner's Report during the period I I GcTyc to I IE--bt I and state that to the. best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied,.

concerning the examinations and corrective 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 mA .q.

ns ectors Signature National Board, Province and Endorsements Date ,OM/P /5 ,

/I

PRAIRIE ISLAND NUCLEAR GENERA TING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-24-047

1. Owner Nuclear Management Company, LLC Date 9/12/2008 Name

2. Plant Prairie Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 349741-02 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. Identification of System VC Code Class 2

5. (a) Applicable Construction Code n/a n/a Edition Addenda n/a Code Cases n/a (b) Applicable Edition of Section XI Utilized for Repair/Replacement Activity 1998E / 2000A (c) Applicable Section XI Code Cases None

6. Identification of Components Component Name Manufacturer Name Manufacturer Serial #

Nat'l Bd # Other ID I Yr Built Corrected, Removed, or Installed ASME Code Stamp Spare Charging Pump packing n/a j I spares I Corrected D assembliesIII

7. Description of Work Rebuilt spare charging pump packing assemblies 22, 23, 24.

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

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

PRAIRIE ISLAND NUCLEAR GENERA TING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-24-047

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 Xl.

Type Code Symbol Stamp Certificate of nz Expiration Date Signed , ASME Program Engineer Date ___

Owner or Owner's Designee , Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minnesota and employed by HSB Insp. and Ins. Co. of Connecticut of Hartford Conn. have inspected the components described in this Owner's Report during the period C6-SP 0 to 15 -ePo' and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

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

Commissions pector's nature National Board, Province and Endorsements Date-Zk*** m 15

I PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-24-048 I

1. Owner Nuclear Management Company, LLC Date 8/20/2008 Name

2. Plant Prairie Island Nuclear Generating Plant Sheet 1 2 of Name 1717 Wakohade Dr. E, Welch Minnesota 55089 366038-02 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. Identification of System VC Code Class 2

5. (a) Applicable Construction Code n/a n/a Edition Addenda n/a Code Cases n/a (b) Applicable Edition of Section XI Utilized for Repair/Replacement Activity 1998E / 2000A (c) Applicable Section XI Code Cases None

6. Identification of Components

7. Description of Work Replaced packing assemblies.

8. Tests conducted: Hydrostatic F PneumaticD- Nominal Operating Pressure -] Exempt F]

Other F Pressure psi Test Temp.

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

PRAIRIE ISLAND NUCLEAR GENERA TING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-24-048

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 Xl.

Type Code Symbol Stamp 4//4 Certificate o f" or Expiration Date Signed e ASME Program Engineer Date ______/___

Owner or Owner's Designee , Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minnesota and employed by HSB Insp. and Ins. Co. of Connecticut of Hartford Conn. have inspected the components described in this Owner's Report during the period o0-'Aoc-O, to 2UAL)(SO 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.

0 ý Commissions '* O'z,2.,A I_ -'-spector's Signa re National Board, Province and Endorsements Date ( 1,

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-24-049

1. Owner Xcel Energy, NSP-M Nuclear Department Date 12/15/2008 Name

2. Plant Prairie Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 304396-01, EC-11442 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. Identification of System RC Code Class 1

5. (a) Applicable Construction Code B31.1 1967 Elition Addenda n/a Code Cases n/a (b) Applicable Edition of'Section XI Utilized for Repair/Replacement Activity 1998E / 2000A (c) Applicable Section Xl Code Cases None

6. Identification of Components Component Name Manufacturer Manufacturer Nat'l Bd # Other ID Yr Built Corrected, ASME Name Serial # Removed, or Code Installed Stamp N2 TO LOOP B STM GEN Velan I 2RC-8-41 I nstalled ISOL

7. Description of Work Installed new isolation valve and replaced associated piping.

8. Tests conducted: Hydrostatic f- Pneumatic-] Nominal Operating Pressure [ Exempt F]

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

PRAIRIE ISLAND NUCLEAR GENERA TING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-24-049

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.

TypeCodeSymbolStamp z/z Certificate of Aut "t ./ Expiration Date _ _ _ _ _ _ _" _ _ _ _ _

Signed , ASME Program Engineer Date ? _

Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minnesota and employed by HSB Insp. and Ins. Co. of Connecticut of Hartford Conn. have inspected the components described in this Owner's Report during the period _4_9_V&

_ _ to /q198E-and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

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

Commissions m4 djlqg.a nspector's Signature National Board, Province and Endorsements Date _ _ _ _ _ _ _ , ___

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-24-050

1. Owner Xcel Energy, NSP-M Nuclear Department Date 12/15/2008 Name

2. Plant Prairie Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 304395-01, EC-1 1442 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. Identification of System RC Code Class 1

5. (a) Applicable Construction Code B31.1 1967 Edition Addenda n/a Code Cases n/a (b) Applicable Edition of Section XI Utilized for RepairlReplacement Activity 1998E / 2000A (c) Applicable Section XI.Code Cases None

6. Identification of Components Component Name Manufacturer Manufacturer Nat'l Bd # Other ID Yr Built Corrected, ASME Name Serial # Removed, or Code Installed Stamp N2 TO LOOP A STM GEN RCPB Velan 2RC-8-40 Installed

[SOL

7. Description of Work Installed new isolation valve and replaced associated piping.

8. Tests conducted: Hydrostatic B! Pneumatic [- Nominal Operating Pressure -] Exempt []

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

PRAIRIE ISLAND NUCLEAR GENERA TING PLANT I FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-24-050

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

Type Code Symbol Stamp Certificate of Au rizat _414 Expiration Date /__ _ _ _ _ _

Signed , ASME Program Engineer Date 2,2/1*4 _

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 IAU&rb to Iq bEC-06 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 Xl.

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.

9 Commissions M4 QlL~2,4 Ispector's Signature National Board, Province and Endorsements a r.ben I-q , , _og Date

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-24-051

1. Owner Xcel Energy, NSP-M Nuclear Department Date 12/16/2008 Name

2. Plant Prairie Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 303891-01, EC-11442 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. Identification of System RC Code Class 1

5. (a) Applicable Construction Code B31.1 1967 Edition Addenda . n/a Code Cases n/a (b) Applicable Edition of Section Xl Utilized for Repair/Replacement Activity 1998E / 2000A (c) Applicable Section Xl Code Cases None

6. Identification of Components Component Name Manufacturer Manufacturer Nat'l Bd # Other ID Yr Built Corrected, ASME Name Serial # Removed, or Code Installed Stamp Przr Safety Valve Loop Seal Velan RC-8-42 Installed Drain Isol.

7. Description of Work Installed new isolation valve and replaced associated piping.

8. Tests conducted: Hydrostatic -- Pneumatic Nominal Operating Pressure [] Exempt 7]

Other Pressure psi Test Temp. 0F Other: n/a NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.

I ~PRAIRIE ISLAND NUCLEAR GENERA TING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-24-051

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

Type Code Symbol Stamp Certificate of Au Expiration Date _ /_ _ _ _ _ _

Signed , ASME Program Engineer Date _,__

Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minnesota and employed by HSB Insp. and Ins. Co. of Connecticut of Hartford Conn. have inspected the components described in this Owner's Report during the period 16eu&)% to Iq906M . I and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

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

spector's '\Ijl Signature National Board, Province and Endorsements D*ate , I q

PRAIRIE ISLAND NUCLEAR GENERA TING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-24-052

1. Owner Xcel Energy, NSP-M Nuclear epartmnt., Date 1/9/2009 Name

2. Plant Prairie Island Nuclear Generating Plant' ý' ','. . Sheet- of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 306015-01, EC-9577 Address Repair Organization P.O. No., Job No., etc

3. Work Performed by Areva NP Inc. Type Code Symbol Stamp N/A Name 3315 Old Forest Rd, Lynchburg, VA 2450 Authorization N/A

. Address Expiration Date N/A

4. Identification of System RC Code Class 1

5. (a) Applicable Construction Code ASME Xl 1998 Edition Addenda* 2000 Code Cases N-504-2, N638-1 (b) Applicable Edition of Section Xl Uti/iz-ed for Repair/Replacement Activity 1998E / 2000A, (c) Applicable Section XI Code Cases N504-2 and N638-1

6. Identification of Components Component Name Manufacturer Manufacturer Nat'l Bd # Other ID Yr Built Corrected, ASME Name Serial # Removed, or Code Installed Stamp 21 Pressurizer Westinghouse 1191 68-57 263-011 1969 Corrected RC Piping Line 10-2RC-4 Corrected D

7. Description of Work Installeda,full structural overlay over the nozzle - safe end - piping welds.

8. Tests conducted: Hydrostatic [- Pneumatic [- Nominal Operating Pressure [] Exempt [

Other Pressure NOP psi Test Temp. NOT OF Other: n/a NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1 /2 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.

PRAIRIE ISLAND NUCLEAR GENERA TING PLANT*

FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-24-052

9. Remarks Rzes wIl.vcrc E nS AIRE REC O C*. PV_. 12OT" I BVOO AMD 28EMI P'.SSuZE. TFS-" -ZE_*(QQotý _EPO..T- a2tP-VT-r-o6-II CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code,Section XI.

Type Code Symbol Stamp /A/h Certificate of Authorizatiga2oN) Expiration Date Signed , ASME Program Engineer Date "-_,

Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minnesota and employed by HSB Insp. and Ins. Co. of Connecticut of Hartford Conn. have inspected the components described in this Owner's Report during the period 0936o08 to 1'4JAM09 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.

00 Ins ector's Signature' Commissions (A 19 National Board, Province and Endorsements Date I I +/-oo Date 6.rA-f4q 1I44 1 2=9

, I I

I ~ PRAIRIE ISLAND NUCLEAR GENERA TING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-24-053

1. Owner Xcel Energy, NSP-M Nuclear Department Date 12/2/2008 Name

2. Plant Prairie Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 100613-07 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. Identification of System CC Code Class 3

5. (a) Applicable Construction Code ASMEIII, Class C 1968 Edition Addenda n/a Code Cases n/a (b) Applicable Edition of Section XI. Utilized for Repair/Replacement Activity 1998E / 2000A (c) Applicable Section XI Code Cases None

6. Identification of Components Component Name Manufacturer Manufacturer Nat'l Bd # Other ID Yr Built Corrected, ASME Name Serial # Removed, or Code Installed Stamp 2 CC Heat Exchanger Yuba 69G229-1D 235-032 1969 Corrected

7. Description of Work Weld build up of wasted areas in shell and attachment weld areas.

8. Tests conducted: Hydrostatic [. .,Pneumatic-] Nominal Operating Pressure [ Exempt [

Other F7 Pressure psi Test Temp. OF Other: n/a NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1 /2 in. x 11 in., (2) information' in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.

, .., I.

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-24-053

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 Xl.

Type Code Symbol Stamp A/

Certificate of A A,4-1 Expiration Date Signed , ASME Program Engineer Date __-_____

Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minnesota and employed by HSB Insp. and Ins. Co. of-Connecticut of Hartford Conn. have inspected the components described in this Owner's Report during the period of.oe.-roe to fZ-rse- C>8 and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section Xl.

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

~._0_ Commissions Mi 02*.-1l9.L4 nsgnature National Board, Province and Endorsements Date Date kin t~

II 1 11 .2

PRAIRIE ISLAND NUCLEAR GENERA TING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-24-054

1. Owner Xcel Energy, NSP-M Nuclear Department Date 12/3/2008 Name

2. Plant Prairie Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 108896-01 Address Repair Organization P.O. No., Job No., etc

3. Work Performed by Owner Type Code Symbol Stamp N/A Name Same Authorization N/A Address Expiration Date N/A

4. Identification of System SI Code Class 2

5. (a) Applicable Construction Code B16.34 n/a Edition Addenda n/a Code Cases n/a (b) Applicable Edition of Section XI Utilized for Repair/Replacement Activity 1998E / 2000A (c) Applicable Section XI Code Cases None

6. Identification of Components Component Name Manufacturer Manufacturer Nat'l Bd # Other ID Yr Built Corrected, ASME Name Serial # Removed, or Code Installed Stamp SUMP B TO 22 RHR PMP TRN Crane 12-GM54SE MV-32181 ICorrected D B MVI

7. Description of Work Replaced the disc.

8. Tests conducted: Hydrostatic F-1 Pneumatic -] Nominal Operating Pressure j- Exempt W-Other [] Pressure psi Test Temp. 0 F Other: n/a NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1 /2 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-24-054

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

Type Code Symbol Stamp Certificate of h___,Expiration Aut14 Date Signed ASME Program Engineer Date ,'.. /4?'_,_"

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 03ccr 956 to 'aCw I and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

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

0Commissions flý o27-191'-

n r's Signatur National Board, Province and Endorsements Date ,n4 QOA, 20,

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/IREPLACEMENT ACTIVITY ITEM 2-24-055

1. Owner Xcel Energy, NSP-M Nuclear Department Date 11/4/2008 Name

2. Plant Prairie Island Nuclear Generating Plant Sheet 1 2 of Name 1717 Wakonade Dr. E, Welch Minnesota 55089 290306-01 Address Repair Organization P.O. No., Job No., etc

3. Work Performed by Owner Type Code Symbol Stamp N/A Name Same Authorization N/A Address Expiration Date N/A

4. Identification of System RC Code Class 1

5. (a) Applicable Construction Code ASME Ill 1965 Edition Addenda n/a Code Cases n/a (b) Applicable Edition ofSection XI Utilized for Repair/Replacement Activity 1998E / 2000A (c) Applicable Section XI Code Cases None

6. Identification of Components Component Name Manufacturer Manufacturer Nat'l Bd # Other ID Yr Built Corrected, ASME Name Serial # Removed, or Code Installed Stamp 22 RCP Westinghouse 245-052 Corrected D

7. Description of Work Replaced one Lower Seal Housing Stud.

8. Tests conducted: Hydrostatic F] Pneumatic-] Nominal Operating Pressure D Exempt [

Other [] Pressure psi Test Temp.

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

PRAIRIE ISLAND NUCLEAR GENERA TING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-24-055

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

Type Code Symbol Stamp 4/!.

Certificate of Author . *61- Expiration Date _//_.________

Signed , ASME Program Engineer Date /

Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State, or Province of Minnesota and employed by HSB Insp. and Ins. Co. of Connecticut of Hartford Conn. have inspected the components described in this Owner's Report during the period .0c0C-08 to 04twV'J0s and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

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

Commissions _ _ _ _ _ _ _ _ _ _

I spector's Sig re National Board, Province and Endorsements Date _________ ____ ,

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/IREPLACEMENT ACTIVITY ITEM 2-24-056

1. Owner Xcel Energy, NSP-M Nuclear Department Date 12/15/2008 Name

2. Plant Prairie Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 303589-01 Address Repair Organization P.O. No., Job No., etc

3. Work Performed by Owner Type Code Symbol Stamp Name Same Authorization N/A Address Expiration Date N/A

4. Identification of System VC Code Class 2 N

5. (a) Applicable Construction Code B16.34 n/a Edition Addenda n/a Code Cases n/a (b) Applicable Edition of Section Xl Utilized for Repair/Replacement Activity 1998E / 2000A (c) Applicable Section XI Code Cases None

6. Identification of Components Component Name 21 VCT OUTLET TO CHG PUMP SUCT HEADER MV

7. Description of Work Replaced body to bonnet studs.

8. Tests conducted: Hydrostatic F1 Pneumatic Nominal Operating Pressure -] Exempt 7V Other F] Pressure psi Test Temp.

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

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FOR:M NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-24-056

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 Xl.

Type Code Symbol Stamp Certificate of At ,//A- Expiration Date Signed ASME Program Engineer Date _,,,____

Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minnesota and employed by HSB Insp. and Ins. Co. of Connecticut of Hartford Conn. have inspected the components described in this Owner's Report during the period 06C-xX to Ib_*

and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section Xl.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective 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 MA' 9 spector's Signature . National Board, Province and Endorsements Date L x 3-I-1 I 1C6

wv

FRN2PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/IREPLACEMENT ACTIVITY ITEM 2-24-057

1. Owner Xcel Energy, NSP-M Nuclear Department Date 12/4/2008 Name

2. Plant Prairie Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 289869-04 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. Identification of System VC Code Class 2

5. (a) Applicable Construction Code B16.34 n/a Edition Addenda n/a Code Cases n/a (b) Applicable Edition of SectionXI Utilized for Repair/Replacement Activity 1998E'/ 2000A (c) Applicable Section XI Code Cases None

6. Identification of Components Component Name 21 BORIC ACID BLENDER TO Grinnell 21 VCT OUTLET CV 7.

21 VCT DRN valve Description of Work Grinnell Replaced body to bonnet studs and nuts.

2VC-11-60 Corrected j D J

8. Tests conducted: Hydrostatic FD Pneumatic Nominal Operating Pressure -] Exempt F]

Other El Pressure psi Test Temp. OF

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

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-24-057

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 Xl.

Type Code Symbol Stamp it/A Certificate of Authorization No. 461'4 Expiration Date Signed ASME Program Engineer Date __,___,

Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minnesota and employed by HSB Insp. and Ins. Co. of Connecticut of Hartford Conn. have inspected the components described in this Owner's Report during the period 0"t(Y-Trr, to INer*.

and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

By signing %this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in the Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.

Commissions _ _ _ _ ___ _

I pector'sSieature National Board, Province and Endorsements Date _Q 4.1 6o6 ,o ,

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY I

ITEM 2-24-058

1. Owner Xcel Energy, NSP-M Nuclear Department Date 1/9/2009 Name

2. Plant Prairie Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 369324-01 Address Repair Organization P.O. No., Job No., etc

3. Work Performed by Owner Type Code Symbol Stamp N/A Name Same Authorization N/A Address Expiration Date N/A

4. Identification of System ZH Code Class 3

5. (a) Applicable Construction Code 81634 and B31.1 n/a for B16.34, 1967 for B31 1 Edition/Addenda Addenda n/a Code Cases n/a '\ '

(b) Applicable Edition of Section Xl Utilized for Repair/Replacement Activity 1998E / 2000A (c) Applicable Section XI Code Cases None

6. Identification of Components Component Name Manufacturer Manufacturer Nat'l Bd # Other ID Yr Built Corrected, ASME Name Serial # Removed, or Code Installed Stamp 122 Cont. RM Chiller Piping Corrected D ]

7. Description of Work Re placed piping section.

8. Tests conducted-: Hy drostaticD,., .Pneumatic [] Nominal Operating Pressure [ Exempt LI Ot'her [] Pressure NOP psi Test Temp. NOT Other: n/a NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1 /2 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.

FORMI NIS-2

~ OWNER'S PRAIRIE ISLAND REPORT NUCLEAR FOR REPAIR/

GENERA TING REPLACEMENT PLANT ACTIVITY ITEM 2-24-058

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

Type Code Symbol Stamp ,/A Certificate of Author' Expiration Date Signed ,ASME Program Engineer Date Y . __/__J Owner or Owner's Designee , Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minnesota and employed by HSB Insp. and Ins. Co. of Connecticut of Hartford Conn. have inspected the components described in this Owner's Report during the period -7acrB, to I" JA,4 ,

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.

.0 C4 Commissions m .7I9QM Ins ctor's jgnaure National Board, Province and Endorsements Date . 19 ,

J

E PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-24-059

1. Owner Xcel Energy, NSP-M Nuclear Department Date 1/6/2009

- Name

2. Plant Prairie Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 365247-01 Address Repair Organization P.O. No., Job No., etc

3. Work Performed by Owner Type Code Symbol Stamp N/A Name Same Authorization N/A Address Expiration Date N/A

4. Identification of System FW Code Class 2

5. (a) Applicable Construction C'ode B31.1 1967 Edition Addenda n/a Code Cases n/a (b) Applicable Edition of Section XI Utilized for Repair/Replacement Activity 1998E / 2000A (c) Applicable Section Xl Code Cases None

6. Identification of Components Component Name Manufacturer Manufacturer Nat'l Bd # Other ID Yr Built Corrected, ASME Name Serial # Removed, or Code Installed Stamp 2-FWH-54 n/a Corrected E]

7. Description of Work Replaced shim packs to correct spacing.

8. Tests conducted: Hydrostatic,[!F.;. Pneumatic -] Nominal Operating Pressure E] Exempt R]

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

PRAIRIE ISLAND NUCLEAR GENERATING PLANT' FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-24-059

9. Remarks PSI reco ded on report 2008V198 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 Xl.

Type Code Symbol Stamp Certificate of Authorization-)". Expiration Date Signed , ASME Program Engineer Date _

Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and thei 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 13o0CT8 to 044M Q9, 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.

ow Commissions 141191,__ __.1-_

pector's Sig ature National Board, Province and Endorsements Date 0K).AnL

,8 Sy Joj

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/IREPLACEMENT ACTIVITY ITEM 2-24-060

1. Owner Xcel Energy, NSP-M Nuclear Department Date 12/4/2008 Name

2. Plant Prairie Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 154830-01 Address Repair Organization P.O. No., Job No., etc

3. Work Performed by Owner Type Code Symbol Stamp N/A Name Same Authorization N/A Address Expiration Date N/A

4. Identification of System ZX Code Class 3

5. (a) Applicable Construction Code B16.34 n/a Edition Addenda n/a Code Cases n/a (b) Applicable Edition of Section Xl Utilized for Repair/Replacement Activity 1998E / 2000A (c) Applicable Section Xl Code Cases None

6. Identification of Components Component Name Manufacturer Manufacturer Nat'l Bd # Other ID Yr Built Corrected, ASME Name Serial # Removed, or Code Installed Stamp 22/24 FCU CHLD WTR SPLY Masoneilan CV-39414 Corrected

7. Description of Work Replaced plug.

8. Tests conducted: Hydrostatic EL.. Pneumatic FD Nominal Operating Pressure E] Exempt R]

Other F-1 Pressure psi Test Temp.

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

PRAIRIE ISLAND NUCLEAR GENERA TING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-24-060

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 Xl.

Type Code Symbol Stamp A///

Certificate of At__ Expiration Date /___/ __ __ _

Signed , ASME Program Engineer Date ,/,,__,

Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and .the State or Province of Minnesota and employed by HSB Insp. and Ins. Co. of Connecticut of Hartford Conn. have inspected the components described in this Owner's Report during the period iOt..T to 0b'eC.08 I and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective 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 rn 4 O'L19A.V4 Inspector'<Signature National Board, Province and Endorsements Date o'! , 2oos

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-24-061

-I

1. Owner Xcel Energy, NSP-M Nuclear Department Date 1/12/2009 Name 2.. Plant Prairie Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 297149-01 Address Repair Organization P.O. No., Job No., etc

3. Work Performed by Owner Type Code Symbol Stamp N/A Name Same Authorization N/A Address Expiration Date N/A

4. Identification of System FW Code Class 2

5. (a) Applicable Construction Code B31.1 1967 , Edition/Addenda Addenda n/a Code Cases n/a'.

(b) Applicable Edition of Section XI Utilized for Repair/Replacement Activity 1998E / 2000A (c) Applicable Section XI Code Cases None

6. Identification of Components Component Name Manufacturer Manufacturer Nat'l Bd # Other ID Yr Built Corrected, ASME Name Serial # Removed, or Code nstalled II Stamp Feed Water piping restraint 2-FWH-57 Corrected IF I

7. Description of Work Corrected support to meet the drawing and design analysis.

8. Tests conducted: Hydrostatic

. Pneumatic 7 Nominal Operating Pressure [Exempt [

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

I '. ~.. .

PRAIRIE ISLAND NUCLEAR GENERA TING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-24-061

9. Remarks Preservice exam recorded on report 2008V1 99.

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

Type Code Symbol Stamp I//14 Certificate of Authorizatio . "/ Expiration Date Signed , ASME Program Engineer Date . 2/! _-

Owner or Owner's Designee , Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minnesota and employed by HSB Insp. and Ins. Co. of Connecticut of Hartford Conn. have inspected the components described in this Owner's Report during the period I 9&fflA4- c/ to I( I AtJ0b9 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.

Q.0 Commissions rA

Q'L4 Insp ctor's Signature National Board, Province and Endorsements Date .. it I

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-24-062

1. Owner Xcel Energy, NSP-M Nuclear Department Date 1/6/2009 Name 2.- Plant Prairie Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 369624-14 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. Identification of System CC Code Class 3

5. (a) Applicable Construction Code ASME III, Class C 1968 Edition Addenda . n/a Code Cases n/a "

(b) Applicable Edition of Section.XI Utilized for Repair/Replacement Activity 1998E / 2000A (c) Applicable Section Xl Code Cases None

6. Identification of Components Component Name Manufacturer Manufacturer Nat'l Bd # Other ID Yr Built Corrected, ASME Name Serial # Removed, or Code Installed Stamp 21 CC HX Yuba 69G229-1C 235-031 1969 Corrected

7. Description of Work Weld build up of wasted areas in shell and attachment weld areas.

8. Tests conducted:,. HydrostaticF.[],, PneumaticD-] Nominal Operating Pressure E] Exempt []

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

PRAIRIE ISLAND NUCLEAR GENERA TING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-24-062

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

Type Code Symbol Stamp /2///

Certificate of i,49/p &1p. Expiration Date __

Signed ASME Program Engineer Date 9? __

Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minnesota and employed by HSB Insp. and Ins. Co. of Connecticut of Hartford Conn. have inspected the components described in this Owner's Report during the period 17OC.T 06 to Q,7J *,4 Q9 ,

and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied,.

concerning the examinations and corrective measure described in the Owner's. Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.

Commissions PIOl I spector's Signature National Board, Province and Endorsements Date Cg , O9

PRAIRIE ISLAND NUCLEAR GENERA TING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-24-063

1. Owner Xcel Energy, NSP-M Nuclear Department Date 1/23/2009 Name

2. Plant Prairie Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 357548-01 Address Repair Organization P.O. No., Job No., etc

3. Work Performed by Owner Type Code Symbol Stamp N/A Name Same Authorization N/A Address Expiration Date N/A

4. Identification of System VC Code Class 2

5. (a) Applicable Construction Code n/a n/a Edition/Addenda Addenda n/a Code Cases n/a (b) Applicable Edition of Section Xl Utilized for Repair/Replacement Activity 1998E / 2000A (c) Applicable Section Xl Code Cases None

6. Identification of Components Component Name Manufacturer Manufacturer Nat'l Bd # OtherID Yr Built Corrected, ASME Name Serial # Removed, or Code Installed Stamp 22 Charging Pump Ajax 245-042 1969 Corrected D]

7. Description of Work Replaced packing assemblies.

8. Tests conducted: Hydrostatic F] Pneumatic Nominal Operating Pressure F Exempt []

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

PRAIRIE ISLAND NUCLEAR GENERA TING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-24-063

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 X1.

Type Code Symbol Stamp '///4 Certificate of Aut o. Expiration Date Signed , ASME Program Engineer Date ... __

Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minnesota and employed by HSB Insp. and Ins. Co. of Connecticut of Hartford Conn. have inspected the components described in this Owner's Report during the period '2-mV we, to '1-3J*4 A q and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

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

1Commissions Isetot's Sigf ture National Board, Province and Endorsements Date (ý?- uLAru4 r2 a

L-PI-09-015, Submittal of Inservice Inspection Examination Summary Report, Interval 4, Period 2, Outage 1, Refueling Outage, Dates: 09-19-2008 to 11-01-2008 Unit 2, Fuel Cycle 24:12-15-2006 to 11-01-2008

Contents

Text

SUMMARY

SUMMARY

SUMMARY

1.0 INTRODUCTION

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

2.0 REFERENCES

2.2.1 Procedure

SUMMARY

SUMMARY

SUMMARY

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L-PI-09-015, Submittal of Inservice Inspection Examination Summary Report, Interval 4, Period 2, Outage 1, Refueling Outage, Dates: 09-19-2008 to 11-01-2008 Unit 2, Fuel Cycle 24:12-15-2006 to 11-01-2008

Text

SUMMARY

SUMMARY

SUMMARY

1.0 INTRODUCTION

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

2.0 REFERENCES

2.2.1 Procedure

SUMMARY

SUMMARY

SUMMARY

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