View source for 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

{{Adams
| number = ML090330172
| issue date = 01/28/2009
| title = 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
| author name = Wadley M
| author affiliation = Northern States Power Co, Xcel Energy
| addressee name = 
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000306
| license number = DPR-060
| contact person = 
| case reference number = L-PI-09-015
| document type = Inservice/Preservice Inspection and Test Report, Letter type:L
| page count = 162
}}

=Text=
{{#Wiki_filter: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 byl&#xfd;__*                                                        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    &#xfd; 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
(-Commrents&#xfd;     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&#xa3; IS' RC"              24SI-46 501861           H-6                oulSpring                                  Fil10c           FP&#xfd;-PE-NDE-   VT I 2008V1 38 IIND 530 Commentts:&#xfd;      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
______________________________________________________                                                                                                                                                             &#xa3; __________________________________
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.. ::::::*-: :.:::, .`:.,
                                                                                                                                                                     &#xfd;- .:::         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 ombl1&#xfd; 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.                                                             ':;P&#xfd;-
* 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,                                    /,-
C           -*.*
V7-c        *,04"7                     Z4-,*            405 t2Cd-i13    :3,346                    2:77                  L7 2-c--                -     A7-3
                                        ~4            5             241                  1*71 2CC14 -11                   3-&3 0   4 21-714-      _____tell
            *z - C C A4     - Ie ,       3--2,5       1t
                                                   *_.,_7_.                                 Iq 2,- Ct..         - 15,2..      35 ..3040                   91
                                                                      ,10 w 14   W      I&#xfd;0'(e      &33O01.0&#xfd;               3a4                  ___33_W6_                                       4 z-4(o___        ______9 z--*.*    I             3.3,%5059              57               t
                         -- 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_
2- -           4- 1 A           *33 o3S3              z13               43_o Z I.S         4l-1*              33-, 0 Z                      jjj)      Z o                       ./
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                                        ,     j&#xfd;&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 QQs&#xfd;GI6Pt&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 &sect;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    i&#xfd;tip' 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,'&#xfd;                     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 is&#xfd; 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]&#xfd;:' 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 Authorizaj&#xfd;&#xfd; --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]&#xfd;. 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            41&#xfd;4//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. Test&#xfd; 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             Mit&#xfd;     I~
sp ctor's SignAe                                               National Board, Province and Endorsements Date                                                9g , .200 K&#xfd;A           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
                          &#xfd;J

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
                             &#xfd;K)

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 ce&#xfd;tify 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 &deg;rs*'0-9                               Commissions              tLDmA1L%
Inspector       ignature                                          National Board, Province and Endorsements Date                             &#xfd;I*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 &#xfd;                           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' &#xfd;'    ','.             . 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_*(QQot&#xfd;                      _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                                       fl&#xfd;   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                       (&#xfd;?-       uLAru4   r2 a}}