Text

Inservice Inspection Summary Report, Interval 4, Period 1, Outage 2, Refueling Outage Dates: 11-15-2006 to 12-15-2006, Fuel Cycle 23: 06-11-2005 to 12-15-2006
	ML070780140
Person / Time
Site:	Prairie Island
Issue date:	03/14/2007
From:	Thomas J. Palmisano; Nuclear Management Co
To:	; Document Control Desk, NRC/NRR/ADRO
References
	L-PI-07-023
	Download: ML070780140 (104)
	v • d • e

CORRESPONDENCE CONTROL. 'PROGRAM STANDARD. DISTRIBUTION Outgoing Correspondence Letter Number: U '-l-'7Document Date:- 2 /Z 1(9/07 Date:_______________ Engineer:_<~ I Document Type: _________ Attached:____________

Subject:

iI !~~S-&1 SvJtA4J4t Action Info NA Recipient Elect HC Comments

_______ ~Document Control Desk____________

_______Project Manager - Mahesh Chawla

_______Region III Administrator

_______ Sr. Resident Inspector -

_______ ~Dept. of Commerce - Glenn Wilson __________________

_______Charlie Bomberger - RS-8

______Jonathan Rogoff - NMVC Hudson Site VP - Tom Palmisano Director of Site Ops - Dwight Mims -

Plant Manager - Paul Huffman Site Eng. Dir. - Mike Carlson

_______Bus Support Mgr - Len Clewett Operations Manager - Freddie Forrest Nuclear Safety Assurance Mgr - S Northard PITC Training Manager - Jim Sternisha

_______Production Planning Mgr - R Womack

_______Maintenance Mgr - P. W~iltse

______Nuclear Oversight Mgr - R Brown LERs Only

_______ Maintenance Rule Coord. - B Stephens ____ LERs Only

___ k- ______ Jeff Kivi7

_______ ~Dale Vincent ___

_______Marlys Davis

_______ ~Matt Klee ___

______ S 7-&Q6-0,-e-

______NL File Records Management

______MSRC File

________Terry Sullivan Hub Miller Liz Bogue Dennis Koehl

~~~~ ~

__~~~ _ _ I I

_ _ _ _1_ 1 _ _ _ _

Note: Review the incoming correspondence to determine which individuals received copies directly from the agencies. No distribution to these individuals is required for this incoming correspondence.

Contact Marlys Davis at ext. 4154 if you did not receive what is indicated or to request a change toth distribution list.

Updated 21U(

9-týc7 packets~outgoing distribution J:\Iicense\distribution packets\outgoing JAlicenseWistribution Iist.doc distribution list.doc Page 1 Page or 1 1 or 1 Updated 210 7

NMC Prairie Island Nuclear Generating Plant Commtte to ucler~xeffnceOperated by Nuclear Management Company, LLC MAR 1 4 2007 L-PI-07-023 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 Unit 2 Inservice Inspection Summary Report, Interval 4, Period 1, Outage 2. Refuelinq Outage Dates: 11-15-2006 to 12-15-2006, Fuel Cycle 23: 06-11-2005 to 12-15-2006 During the 2006 Prairie Island Nuclear Generating Plant (PINGP) Unit 2 refueling outage, an inservice inspection (I51) examination for the first period of the fourth interval was conducted. Enclosure 1 is a copy of the ISI examination summary report for this outage.

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 components examined, the examination methods used, the examination number, and summarizes the results. All anomalies were either corrected or an engineering evaluation was performed to accept "as-is" conditions. A description of the corrective work and the corresponding work request numbers are provided in the ASME Section XI Repair/Replacement portion of the report. In addition, the number and percentage of examinations or tests completed per IWA-6220(f)l during the first period are included in this report.

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

iomas J. Palmisano Site Vice President, Prairie Island Nuclear Generating Plant Nuclear Management Company, LLC 1717 Wakonade Drive East

Welch, Minnesota 55089-9642 Telephone: 651.388.1121 o 7

Document Control Desk Page 2 Enclosure cc: Administrator, Region 1ll, USINRC Project Manager, Prairie Island, USINRC Resident Inspector, Prairie Island, USNRC Chief Boiler Inspector, State of Minnesota

ENCLOSURE I Inservice Inspection Summary Report, Interval 4, Period 1, Outage 2, Refueling Outage Dates: 11-15-2006 to 12-15-2006 Unit 2, Fuel Cycle 23: 06-11-2005 to 12-15-2006

XCEL ENERGY PRAIRIE ISLAND NUCLEAR GENERATING PLANT 1717 WAKONADE DRIVE EAST WELCH, MINNESOTA 55089 OPERATED BY:

NUCLEAR MANAGEMENT COMPANY, LLC 700 FIRST STREET HUDSON, WISCONSIN 54016 INSERVICE INSPECTION

SUMMARY

REPORT INTERVAL 4, PERIOD 1, OUTAGE 2 REFUELING OUTAGE DATES: 11-15-2006 TO 12-15-2006 UNIT 2, FUEL CYCLE 23: 06-11-2005 TO 12-15-2006 COMMERCIAL SERVICE DATE: DECEMBER 21, 1974 Prepared Date: D by: 4 rga Proar mEniner, u cera Mangement Co.

Shannon Hanson Reviewed by:

Date: 47A Reviewed Date: 07__

by: Steam Generator EC I Engineer, Nuclear Management Co.

Scott Redner Reviewed Date: 6e7 by: Repair/Replacement Program Engineer, Nuclear Management Co.

Ron Glow Reviewed Date: Z/-z.//7 by: I rogram Engineer, Nuclear Management Go.

Ryan Cox Reviewed Date: '2- 73-o0--V by:

Jerry Wren

Reviwdr Date: 2-/_Z___'

by: Pres-sure Testýing lzngaine~er, Nuclear Management Co.

Lora Drenth Reviewed Date: IZ' 12-0 -7 by: 9ur er inV er, Nuclear Managehwf o Reviewed Zý Date: _2-Z7-0 by: Program Engine-eringgMa-nager, u lear Management Go.

Steve Skoyen Approved Date: ZfS07 by: i-rector /o ngineering, Nuclear Management Go.

Mike Carlson

. M4

NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION PRAIRIE ISLAND UNIT 2 CYCLE 23

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 11 Section 4. IWE Examinations 2 Section 5. Pressure Tests Section 6. Snubber Inservice Testing and Preservice Examinations Section 7. Steam Generator Eddy Current Examination Results Section 8. Repair/Replacement Activities for Fuel Cycle 23 66

NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION PRAIRIE ISLAND UNIT 2 CYCLE 23

SUMMARY

REPORT Section 1. Discussion

1.0 INTRODUCTION

This summary report identifies the class 1 and 2 components examined, the examination methods used, the examination number and summarizes the examination results performed during the 1st period of the 4th interval, unit 2 fuel cycle 23. 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 Nuclear Management Company, Lambert MacGill Thomas Inc. (LMT), Westinghouse, Areva, MoreTech, Hudson Global Resources and Zetec Inc. The Hartford Steam Boiler Inspection and Insurance Company of Connecticut, provided the Authorized Inspection services.

Examination personnel certifications are maintained on file by Nuclear Management 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 23.

The number and percentage of examinations or tests completed per IWA-6220(f) are also included in this section. There were no examinations with indications requiring evaluation, scope expansion or repa ir/rep la cement. There were no "Limited Examinations" performed during the cycle.

Section 4 contains the Class MC evaluations that required reporting per 10CFR5O.bba (b)(2)(xi)(D) during unit 2 cycle 23. The first interval, September 9, 1996 to May 8, 2008 is based on the examination requirements of ASME Section XI 1992 Edition and 1992 Addenda, and 10 CFR5O.55a dated Tuesday, September 30, 1997.

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 th interval, 2 nd period, 1 st outage 90 day summary report.

Section 1. DiscussionPae1o2 Page 1 of 2

NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION PRAIRIE ISLAND UNIT 2 CYCLE 23

SUMMARY

REPORT Section 6 contains the Snubber inspection results. There were no visual snubber failures. All snubbers that underwent functional testing had satisfactory results therefore no scope expansion was required During the refueling outage, Eddy Current examinations of 21 and 22 Steam Generators tubes were performed. The examination results are included in Section 7.

Section 8 contains 32 Repair/Replacement Activities completed under the 4th Interval during the unit 2 cycle 23.

4.0 EXAMINATION REPORTS, EQUIPMENT AND MATERIALS The inservice inspection reports in Section 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 Nuclear Management Company.

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

CAP = Corrective Action Process CE = Condition Evaluation GEG = 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 Section 1. DiscussionPae2o2 Page 2 of 2

NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION PRAIRIE ISLAND UNIT 2 CYCLE 23

SUMMARY

REPORT Section 2. NIS-1 (3 pages)

Section 2. NIS-1Pgeo Page 1 of 3

Pý1!-.(.I -I .'

F0 R MI N IS- I OWNEI'S REPORI'FOR INSIKRVI( ' INSPECTIONS

1. Okviicr Nuclear Management Company, 700 First Street, H-udson, Wisconsin !.iA016

2. Plant Prairie Island Nuclear Generating Plant, 1717 Wakoniade Drive East, Welch, MN 55089 (Nane miid .\,ldjvs: I Plnt

3. Plant IOuit 2

4. Ownerc Certificate ofAuthorizatioti (i Urequired) N/A

5. Commiercial Service Date 12/2 1/1974

6. National Board Number har Unit N/A

7. Cormponents Inspected Maind'licturer or N antiitlcrctlj mrIuisial icr IState or 'l F Comiponient or No.

App~urtenance Installer Scijal No.

Reactor Vessel Creiot-L~oire *-' NIINN--2i,-ii--5 I Pressurizer Westinghouse 1191 21I Steam Generator Westinlghouse 1,5-1')

1182 22 Steam Generator Westinghouse (,X-..to 121 Reactor Coolant Pump IWestinghouse 1W5 10 22 Reactor Coolant Pump Westinghouse W5 I5 21 RHR Heat Exchanger Joseph Oats & Sons I1817-IC I-22 RHR Heat Exchanger Joseph Oats & Sons 1817-11) - I143 21 RHR Pump IByron Jackson 22 RHR Pump Byron Jackson - --

21 Safety Injection Pump Bingham - --

22 Safety Injection Pump Bingham- -

21 Accumulator Tank Delta Southern 41037-68-I1 - 2575 22 Accumulator Tank Delta Southemn 4 1037-69-I 2576 21BrcAid Tank INAVCO I-..

8. Examination Dates 6/11/2005 to 12/15/2006

9. Inspection Period Identification: (First) 12/21/2004 to 12/20/2007

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

11. Applicable Edition of Section XI 1998 Addenda 2000

2 at 2 N IS-1

12. Date/lkevision of Inspection Plani: 11/19/2006, Revision 2

13. Abstract of'Exarninations and teSt.s. tiniclidea list at e.\;iiiI1ii;Itiui1i; :1iid ic:;tsait

Id;: i;i:Iniciii .oic ilga:itis atokijac In le Inspection Plan.

See Sections 3 through 7

14. Abstrtact of Results of Ex iiiUMN1, a ~

1 and Con .

See Sections 3 through 7

15. Abstraict of Corrective Meatsines.

See Sections 3 through 8 WNe certify that a) the stateentis inade in this report ite*COrreCt.1 1) the CV\;iiiil;itiiie1.; diii teNts HI ilette tiiSjIeCtiAii 1'1;111ANieijiiiti tIn' the ASMI: Code, Section X1, and c) corrective mecasures talk-en coniitliiii to IIIe rides 01 111kASM I ( ode Sect on XL.

,Certificate of Authorization Na. ( if app~licablel) N/A I !Xpimlion t ):1 Date 2S2] - igned CERTIFICATE OF INSERVICE.' INSPECTION te StAiC Mr 'rA)ViiCe

11) fiil Ot bythe National B oar d olHiletIrand t'ressmie Vessel 1I iSpedi 11, theundersignedl, holding a valid commission issued H; or andemlolslyed by Ze 7-.

CO - -C- have inspected thle ConinponieminS deCSCribed in this O wnier's R~epil dmmiill tilie pci miod

- ~~to , - and state that it)tfle best of'in~ kiiowledge and bet ic'fitle Ownvmer his p) cit 6oilcd examinations and teats and taken corrective mneasuires descirbed in this O wner's Report in accor[dance witth the inspectio pilianaind as reqignred ti I tie \S.\tt Code Section NJ.

By signing this certificate neither the Inspector nor his employer makes any' warranty' , expressed or implied, Concerninig tlie exaniimiatiolis. tests. ai )il corrIeci i ve measures described in this Owner's Report. Furthenmore, neither the Inspector nlor his employer shall he liable in anY mannler fin- any persoiial ilitliry oi roet damage or a loss of any kind arising ftrm or connected with this inspection.

Commlliss ionls 4 / 3 I , 8, T Inspector's Signature Nait onal Board, State, Prmovince, and Lnrdorsemne lit's Date qk77

NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION PRAIRIE ISLAND UNIT 2 CYCLE 23

SUMMARY

REPORT Section 3. ISI Examinations (11 pages)

Section 3. ISI Examinations Pg 1 off111 Page

Page 1 of 7 Attachment 1 Inservice Inspection Report Interval 4, Period 1, P12RF2006

1. Owner: Nuclear Management Company,700 First Street 4. Owner Certificate of Authorization (if Req.): N/A

2. Plant: Prairie Island Nuclear Generating Plant, 1717 Wa 5. Commercial Service Date: 12/21/1974

3. Plant Unit: 2 6. National Board Number for Unit: N/A Summary No. Comp. ID Cornp. Desc. Item Procedure Method/Report/ResulIts System Dwg/ISO Exam Date Class I Category B-B 501482 w- 1 Cap-Integral Tubesht B2.60 SWI NDE-VT- VT 2006V507 NAD VO 2-ISI1-34 12/13/2006 4.0 501536 W- 2 Cap-Integral Tubesht B2.60 SWI NDE-VT- VT 2006V508 NAD VO 2-ISI-34 12/13/2006 4.0 501594 W- 3 Cap-Integral Tubesht B2.60 SWI NDE-VT- VT 2006 V509 NAD VO 2-ISI-34 12/13/2006 4.0 Class 1 Category B-D 505008 N- 6 IR Nozzle Inner Radius B3.140 SWI NDE-UT-5 UT 2006U1 83 NAD SG 2-ISI-37A 12/6/2006 505024 N- 1 IR Nozzle Inner Radius B3.160 SWI NDE-VT- VT 2006V51 0 NAD VC 2-ISI1-34 12/13/2006 4.0 505025 N- 21R Nozzle Inner Radius B3.160 SWI NDE-VT- VT 2006V51 1 NAD VC 2-ISI1-34 12/13/2006 4.0 505026 N-31IR Nozzle Inner Radius B3.160 SWI NDE-VT- VT 2006V51 2 NAD VC 2-ISI1-34 12/13/2006 4.0 505027 N- 4 IR Nozzle Inner Radius B3.160 SWI NDE-VT- VT 2006V51 3 NAID VC 2-ISI-34 12/13/2006 4.0 505028 N-51IR Nozzle Inner Radius B3.160 SWI NDE-VT- VT 2006V514 NAD VC 2-ISI-34 12/13/2006 4.0 505029 N- 61R Nozzle Inner Radius B3.160 SWI NDE-VT- VT 2006V515 NAD VC 2-ISI-34 12/13/2006 4.0 Class 1 Category B-Ci-2 500091 B- 1 Valve Bolting (16) B7.70 SWI NDE-VT- VT 2006V296 NAD RH 2-IS I-10OC 11/24/2006 1.0 SWI NDE-VT- VT 2006V297 NAD RH 2-ISI-10C 11/25/2006

1.0 Comments

Inservice exam,2006V297 was performed as required due to valve disassembly. Preservice exam 2006V296 was peformed following WO 96881-01 that replaced two studs and nuts 500515 8- 1 Flange Bolts 87.50 SWI NDE-VT- VT 2006V309 NAD RC 2-ISI-30A 12/3/2005

1.0 Comments

Preservice examination to WO 0154582 that replaced 12 studs and 24 nuts.

500711 B- 1 Flange Bolts 87.50 SWI NDE-VT- VT 2006V310 NAD RC 2-ISI-30B 12/3/2006

1.0 Comments

Preservice examination to WO 0154582 that replaced 12 studs and 24 nuts.

Class 1 Category B3-K 521299 H-4/IA Int. Attach. Restraint & Support] B10.20 SWI NDE-PT-1 PT 2006P017 NAD RC 2-ISI-20A 11/22/2006 Class 1 Category B-M-2

Page 2 of 7 Attachment 1 Inservice Inspection Report Interval 4, Period 1, P12RF2006

1. Owner: Nuclear Management Company,700 First Street 4. Owner Certificate of Authorization (if Req.): NIA

2. Plant: Prairie Island Nuclear Generating Plant, 1717 Wa S. 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/ResulIts System DwgIISO Exam Date 505423 V-i1 Valve Int Surfaces B12.50 SWI NDE-VT- VT 2006V298 Accept RH 2-IS1-i100 11/25/2006 3.0 Class I Category B-N-I 505619 RV- 1 Interior 1313.10 SWI NDE-VT- VT 2006 V299 NAD RC 2-ISI-42 11/24/2006 5.0 Class 1 Category F-A 500055 H-4 Support Fil10b SWI NDE-VT- VT 2006V307 NAD RC 2-ISI-14 11/29/2006 2.0 501106 H- 1 Restraint Fil10a SWI NDE-VT- VT 2006V295 NAD SI 2-ISI1-23 11/22/2006 2.0 501299 H- 4 Restraint & Support Fli10b SWI NDE-VT- VT 2006V294 NAD RC 2-ISI-20A 11/22/2006 2.0 SWI NOE-VT- VT 2006 V494 NAD RC 2-ISI-20A 12/8/2006 2.0 501365 H-66 Double Snubber/Clamp Fli10c SWI NDE-VT- VT 2006V301 NAD SI 2-I151i1 11/24/2006 2.0 512606 H-1 4 Column 2 F1.40 SWI NDE-VT- VT 2006V490 NAD SG 2-ISI1-37C 12/6/2006 2.0 Class I Category R-A 501113-RI W- 4 Pipe To 50 Red Elbow R1 .20-4 SWI NDE-UT- UT 2006U099 NAD RC 2-IS I-32A 11/23/2006 11 501123-RI W- 5/2LSD Pipe To Elbow R1 .20-4 SWI NDE-UT- UT 2006U098 NAD RC 2-IS I-32B 11/23/2006 I1I 501126-RI W- 2 Pipe To Pipe R1 .20-4 SWI NDE-UT- UT 2006U1.26 NAD RC 2-ISI1-32C 11/23/2006 11 501521-RI W- 9 Pipe to Elbow R1 .20-4 SWI NDE-UT- UT 20061.1149 NAD RC 2-ISI-17 11/23/2006 16A SWI NDE-UT- UT 2006J1.50 NAD RC 2-ISI1-17 11/23/2006 16A SWI NDE-uT- UT 2006U151 NAD RC 2-ISI-17 11/23/2006 16A 501522-RI W- 3 Pipe to 45 Elbow R1 .20-4 SWI NDE-UT- UT 2006U1.82 NAD RC 2-IS I-20A 12/6/2006 16A SWI NDE-UT- UT 2006U1.81 NAD RC 2-ISI-20A 12/6/2006 16A 501583-RI W-5 Pipe to Elbow R1 .20-4 SWI NIJE-UT- UT 2006L1-74 NAD RC 2-ISI1-27 11/29/2006 16A SWI NDE-UT- UT 2006U1.73 NAD RC 2-ISI1-27 11/29/2006 16A SWI NOE-UT- UT 2006U 172 NAD RC 2-ISI-27 11/29/2006 16A

Page 3 of 7 Attachment 1 Inservice Inspection Report Interval 4, Period 1, P12RF2006

1. Owner: Nuclear Management Company,700 First Street 4. Owner Certificate of Authorization (if Req.): N/A

2. Plant: Prairie Island Nuclear Generating Plant, 1717 Wa 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/Resu Its System Dwg/ISO ExamI Date 501 856-RI W-1 0 Elbow to Pipe R1. 11-2 SWI NDE-uT- UT 2006U166 NAD RC 2-ISI-13A 11/27/2006 16A SWI NDE-UT- UT 2006U 164 NAD RC 2-ISI-1 3A 11/27/2006 16A SW) NDE-UT- UT 2006U 165 NAIJ RC 2-IS I-13A 11/27/2006 16A 501865-RI W-1 0 Tee to Pipe R1 .20-4 SWI NDE-UT- UT 2006U110 NAD RC 2-ISI1-27 11/23/2006 16A SWI NDE-UT- UT 2006U 109 NAD RC 2-ISI-27 11/23/2006 16A 501 897-Rl W- 9 Pipe to Elbow Ri. 11-2 SW) NDE-UT- UT 2006U 161 NAD RC 2-ISI-1 3A 11/27/2006 16A SWI NDE-uT- LIT 2006U1 62 NAD RC 2-ISI-1 3A 11/27/2006 16A SW) NDE-UT- UT 2006U 163 NAD RC 2-ISI-1 3A 11/27/2006 16A 501956-RI W- 8 45 Elbow to Pipe R1. 11-2 SW) NDE-UT- UT 2006U1 59 NAD RC 2-ISI-1 3A 11/27/2006 16A SW) NDE-UT- UT 2006U 158 NAD RC 2-ISI-1 3A 11/27/2006 16A SW) NDE-uT- UT 2006U1 60 NAD RC 2-ISI-1 3A 11/27/2006 16A 501998-RI W- 7 Pipe to 45 Elbow R1.11-2 SWI NDE-UT- UT 2006U 167 NAD RC 2-ISI-1 3A 11/27/2006 16A SW) NoE-uT- LIT 2006U1 69 NAD RC 2-ISI-1 3A 11/27/2006 16A SWI NDE-UT- UT 2006U 168 NAD RC 2-IS I-i3A 11/27/2006 16A 502025-RI W- 6 Pipe to Pipe Rl-11-2 SW) NOE-UT- UT 2006U 170 NAD RC 2-ISI-1 3A 11/27/2006 16A SWI NDE-UT- UT 2006U 171 NAD RC 2-ISI-1 3A 11/27/2006 16A 502039-RI W- 5 Elbow to Tee R1 .20-4 SWI NDE-UT- LIT 2006U1.16 NAD SI 2-IS I-22A 11/24/2006 16A SWI NDE-UT- UT 2006U117 NAD SI 2-ISI-22A 11/24/2006 16A 502082-RI W- 4 Pipe to Elbow R1 .20-4 SWI NDE-UT- UT 2006W 115 NAD SI 2-ISI-22A 11/24/2006 16A SWI NDE-uT- UT 2006U114 NAD SI 2-ISI-22A 11/24/2006 16A 502165-RI W-1 7 Safe End To Nozzle R1.15-2 FP-PE-NDE- UT 2006U097 NAD RC 2-ISI-3 1 11/20/2006 410

Page 4 of 7 Attachment 1 Inservice Inspection Report Interval 4, Period 1, P12RF2006

1. Owner: Nuclear Management Company,700 First Street 4. Owner Certificate of Authorization (if Req.): NIA

2. Plant: Prairie Island Nuclear Generating Plant, 1717 Wa 5. Commercial Service Date: 12/2111974

3. Plant Unit: 2 6. National Board Number for Unit: N/A Summary No. Cornp. ID Comp. Desc. Item Procedure Method/Rep ort/Results System Dwg/ISO ExamI Date 502193-RI W- 3 Pipe to Elbow R1. 11-2 SWI NDE-uT- UT 2006U104 NAD RC 2-ISI-7F 11/23/2006 16A SWI NDE-uT- UT 20061-1105 NAD RC 2-ISI-7F 11/23/2006 16A SWI NDE-UT- UT 2006U1 03 NAD RC 2-IS I-7F 11/23/2006 16A 502194-RI W- 5 Pipe To 45 Elbow R1 .20-4 SWI NDE-LJT- UT 2006U 128 NAD RH 2-ISI-1 0B 11/25/2006 16A SWI NDE-UT- UT 2006U1 27 NAD RH 2-ISI-10B 11/25/2006 16A 502222-RI W- 6 Elbow To Pipe Ri .20-4 SWI NDE-UT- UT 2006U1 113 NAD RH 2-IS I-10B 11/25/2006 16A SWI NDE-UT- UT 2006U1.25 NAD RH 2-ISI-10B 11/25/2006 16A 502226-RI W- 4 Elbow to Pipe R1.1 1-2 SWI NDE-UT- UT 20061-1106 NAD RC 2-ISI-7F 11/23/2006 16A SWI NDE-UT- UT 2006U1,07 NAD RC 2-ISI-7F 11/23/2006 16A SWI NDE-uT- UT 2006U1 08 NAD RC 2-ISI-7F 11/23/2006 16A 502250-RI W- 5 Pipe to 45 Elbow R1. 11-2 SWI NDE-UT- UT 20061.1121 NAD RC 2-IS I-7F 11/23/2006 16A SWI NDE-UT- UT 2006U1 20 NAD RC 2-ISI-7F 11/23/2006 16A SWI NDE-UT- UT 2006U 119 NAD RC 2-IS I-7F 11/23/2006 16A 502271 -RI W- 6 Elbow to Pipe R1.1 1-2 SWI NDE-UT- UT 2006U1 23 NAD RC 2-IS I-7F 11/23/2006 16A SWI NDE-UT- UT 20061.1124 NAD RC 2-ISI-7F 11/23/2006 16A SWI NDE-UT- UT 2006U1-18 NAD RC 2-IS I-7F 11/23/2006 16A 502316-RI W-21 Elbow to Pipe R1 .20-4 SWI NDE-UT- UT 2006U1 52 NAD RC 2-ISI-15 11/23/2006 16A SWI NDE-UT- UT 2006U1 54 NAD RC 2-ISI-15 11/23/2006 16A SWI NDE-UT- UT 2006U 153 NAD RC 2-ISI1-15 11/23/2006 16A 502330-RI W-20 Pipe to Elbow R1 .20-4 SWI NDE-UT- UT 2006U1-57 NAD RC 2-ISI-15 11/23/2006 16A SWI NDE-UT- UIT 2006U1 55 NAD RC 2-ISI1-15 11/23/2006 16A

Page 5 of 7 Attachment 1 Inservice Inspection Report Interval 4, Period 1, P12RF2006

1. Owner: Nuclear Management Company,700 First Street 4. Owner Certificate of Authorization (If Req.): N/A

2. Plant: Prairie Island Nuclear Generating Plant, 1717 Wa 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/ResulIts System Dwg/ISO Exam Date SWI NDE-UT- UT 20061-156 NAID RC 2-ISI-1 5 11/23/2006 16A 502342-RI W- 2 Pipe to Elbow R1 .20-4 SWI N!)E-uT- UT 2006U1 89 NA!) RH 2-ISI-1 OC 12/7/2006 16A SWI NDE-UT- UT 2006U1-88 NA!) RH 2-ISI-10OC 12/7/2006 16A 502352-RI W- 3 Elbow to Pipe Ri .20-4 SWI N!)E-UT- UT 20061J184 NA!) RH 2-ISI-10OC 12/7/2006 16A SWI NDE-UT- UT 2006U1-85 NAID RH 2-ISI-1 OC 12/7/2006 16A 502359-RI W- 3 Pipe to Elbow Ri1.20-4 SWI NDE-UT- UT 20061.1191 NA!) RH 2-IS I-20C 12/7/2006 16A SWI N!)E-UT- UT 2006U1 90 NAID RH 2-ISI-20C 12/7/2006 16A 502371-RI W- 4 Elbow to Pipe R1 .20-4 SWI NDE-UT- UT 20061.1187 NA!) RH 2-IS I-20C 12/7/2006 16A SWI N!)E-uT- UT 2006U 186 NA!) RH 2-ISI-20C 12/7/2006 16A 502446-RI w-l1 Pipe to Elbow R1.11-5 SWI NDE-UT- UT 2006U1J36 NA!) Vo 2-ISI-1 3B3 11/29/2006 16A SWI N!)E-UT- UT 2006U 137 NA!) Vo 2-ISI-1 3B 11/29/2006 16A SWI N!)E-UT- UT 2006U 135 NA!) Vo 2-ISI-1 38 11/29/2006 16A 502485-RI W-1 3 Pipe to Reducer R1. .11-5 SWI N!)E-UT- UT 20061.1134 NA!) vc 2-ISI-1 3C 11/28/2006 16A SWI N!)E-UT- UT 2006U1 33 NA!) vc 2-ISI-1 3C 11/28/2006 16A 502492-RI W-12 Reducer to Pipe R1. 11-5 SWI N!)E-UT- UT 2006U 129 NA!) vc 2-ISI-1 3C 11/28/2006 16A SWI N!)E-UT- UT 2006U1 30 NAD vc 2-ISI-1 3C 11/28/2006 16A Class 2 Category C-A 502628 W-H Top Head to Shell C1.20 SWI N!)E-UT- UT 20061.1142 NA!) SG 2-ISI-37A 11/29/2006 15 SWI N!)E-UT- UT 20061-141 NA!) SG 2-ISI-37A 11/29/2006 15 Class 2 Category C-B 501017 N- 1 IR FW Nozzle Inner Radii C2.22 SWIN!)E-UT- UT 20061-122 NA!) SG 2-ISI-37B 11/22/2006 13 502678 N- 1 Feedwater Nozzle C2.21 SWI N!E-MT-1 MT 2006MV007 NA!) S SG -S-7B 2-ISI-37B 1/220 11/22/2006

Page 6 of 7 Attachment 1 Inservice Inspection Report Interval 4, Period 1, P12RF2006

1. Owner: Nuclear Management Company,700 First Street 4. Owner Certificate of Authorization (if Req.): NIA

2. Plant: Prairie Island Nuclear Generating Plant, 1717 Wa 5. Commercial Service Date: 12121/1974

3. Plant Unit: 2 6. National Board Number for Unit: N/A Summary No. Comp. ID Cornp. Desc. Item Procedure Method/Report/ResulIts System DwgIISO Exam )ate SWI NDE-UT- UT 2006UI01 NAD SG 2-ISI-37B 11/22/2006 15 SWI NDE-UT- UT 2006U102 NAD SG 2-ISI-37B 11/22/2006 15 SWI NDE-MT-1 MT 2006MV009 NAD SG 2-ISI-37B 11/29/2006 Class 2 Category F-A 501367 H- 3 Snubber F1.20c SWI NIJE-VT- VT 2006V293 NAD SI 2-ISI-70 11/22/2006

2.0 Comments

Preservice examination to work order 0157371.

502643 H- 1 Snubber 1 F1.40 SWI NDE-VT- VT 2006V308 NAD SG 2-ISI-37C 11/29/2006

2.0 Comments

Preservice examination to WO 157599-01.

502647 H- 1 Snubber 1 F1.40 SWI NDE-VT- VT 2006V306 NAD SG 2-ISI-37D 11/29/2006 2.0 520695 H-i10A Double Snubber/Clamp F1.20c SWI NDE-VT- VT 2006V305 NAD FW 2-ISI1-48 11/25/2006

2.0 Comments

Preservice examination to WO#0157365 520932 H-6A Double Snubber/Clamp F1.20c SWI NDE-VT- VT 2006 V304 NAD MVS 2-IS I-47B 11/28/2006 2.0 520990 H-8A Double Snubber/Clamp Fl .20c SWI NDE-Vr- VT 2006V300 NAD MVS 2-ISI-46A 11/24/2006

2.0 Comments

Preservice exam to WO 0157373.

Class 2 Category R-A 505062-RI W-1 8 Elbow to Pipe R1 .20-4 SWI NDE-UT- UT 2006U091 NAD SI 2-ISI-90A 11/14/2006 16A SWI NDE-UT- LIT 2006U090 NAD SI 2-ISI-90A 11/14/2006 16A SWI NDE-UT- UT 2006U089 NAD SI 2-ISI-90A 11/14/2006 16A 505099-RI W-20 Elbow to Pipe R1 .20-4 SWI NDE-UT- UT 20061-1111 NAD SI 2-IS I-90B 11/18/2006 16A SWI NDE-UT- UT 2006U1 00 NAD SI 2-ISI-90B 11/18/2006 16A SWI NDE-UT- UT 20061J112 NAD SI 2-IS I-90B 11/18/2006 16A 5051 00-RI W-21 Pipe to Elbow R1 .20-4 SWI NDE-UT- UT 2006U 177 NAD SI 2-ISI-90B 11/30/2006 16A

Page 7 of 7 Attachment 1 Inservice Inspection Report Interval 4, Period 1, P12RF2006

1. Owner: Nuclear Management Company,700 First Street 4. Owner Certificate of Authorization (if Req.): N/A

2. Plant: Prairie Island Nuclear Generating Plant, 1717 Wa 5. Commercial Service Date: 12/21/1974

3. Plant Unit: 2 6. National Board Number for Unit: N/A Summary No. Comp. ID Cornp. Desc. Item Procedure Method/Report/ResulIts System Dwg/ISO ExamI Date SW, NL)E-UI- UT 2006U180 NAD SI 2-ISI-90B 11/30/2006 16A SWI NDE-UT- UT 2006J1 79 NAD 2-ISI-90B 11/30/2006 16A SWI NDE-UT- UT 2006U1 78 NAD 2-ISI-90B 11/30/2006 16A 505103-RI W-24 Reducer to Pipe R1 .20-4 SWI NDE-UT- UT 2006U1 76 NAD 2-IS I-90B 11/30/2006 16A SWI NDE-UT- UT 2006J1 75 NAD 2-ISI-90B 11/30/2006 16A 505117-RI W- 8 Elbow to Pipe R1 .20-4 SWI NDE-UT- UT 2006U 145 NAD 2-ISI-90C 11/28/2006 16A SWI NDE-UT- UT 2006U144 NAD 2-ISI-90C 11/28/2006 16A SWI NDE-UT- UT 2006U1 43 NAD 2-ISI-90C 11/28/2006 16A 505239-RI W- 9 Pipe to Elbow R1 .20-4 SWI NDE-UT- UT 2006U1 39 NAD 2-ISI-94A 11/28/2006 16A SWI NDE-UT- UT 2006U 140 NAD 2-ISI-94A 11/28/2006 16A SWI NDE-UT- UT 2006U1 38 NAD 2-ISI-94A 11/28/2006 16A 505240-RI W-1 0 Elbow to Pipe R1 .20-4 SWI NDE-uT- UT 2006U 148 NAD 2-IS I-94A 11/28/2006 16A SWI NDE-UT- UT 2006U 146 NAD 2-ISI-94A 11/28/2006 16A SWI NDE-UT- UT 2006U1 47 NAD 2-ISI-94A 11/28/2006 16A 505357-RI W- 4 Pipe to Elbow Ri .20-4 SWI NOE-UT- UT 2006U094 NAD 2-ISI-93A 11/14/2006 16A SWI NDE-UT- UT 2006U092 NAD 2-ISI-93A 11/14/2006 16A SWI NDE-UT- UT 2006U093 NAD 2-IS I-93A 11/14/2006 16A 505427-RI W-23 Pipe to Pipe R1 .20-4 SWI NDE-UT- LIT 2006U1 31 NAD 2-ISI-90C 11/28/2006 16A S\M NDE-UT- UT 2006U1 32 NAD 2-ISI-90C 11/28/2006 16A

Nuclear Management Company Prairie Island Unit 2 Completion Code Compliance Summary - 4th Interval - 1st Period ISI - Code Edition - 1998 Edition, 2000 Addenda PERIOD 1 TOTAL# TOTAL# NUMBER PERCENT PERCENT REQUIRED PERCENT REQUIRED COMPLETED jCOMPLETE TOTAL REO'D FOR FOR REQ'D FOR FOR 1ST FOR 1ST jFOR 1IST CAT ITEM CODECASE POPULATION INTERVAL INTERVAL 1ST PERIOD PERIOD PERIOD PERIOD NOTES B-A Bill1 3 100% 3 0% 0 0 0% Deferral allowed per Table IWB-2500-1 B-A 81.21 1 100% 1 0% 0 0 0% Deferral allowed per Table IWB-2500-1 B-A B31.30 N-623 1 100% 1 0% 0 0 0% Deferral allowed per Table IWB-2500-1 Total* 5 5 NA B-B 82.11 2 100% 2 1 1 B-B 82.12 2 100% 2 11 B-B B2.40 2 50% 1 0 0 Limited to one of each~ similar vessel B-B 82.60 RR-4-2 3 600% 18 One-third 6 6 One-third Each item to be examined once each outage Total: 6 5 16-50% 2 2 40% Total percentage completed excludes 82.60 8-0 B3.100 N-648-1 N- 6 100% 6 0 0 521 Deferral allowed per Table IWB-2500-1 8-0 B3.120 5 100% 5 1 1 8-0 83.140 4 100% 4 1 1 8-0 83.160 RR-4-2 6 600% 36 One-third 12 12 One-third Each item to be examined once each outage 8-0 83.90 N-521 6 100% 6 0 0 Deferral allowed per Table IWB-2500-1 Total: 27 9 16-50% 2 2 22% Total percentage completed for B3.120 and 83.140. Other items NA B-G-1 86.10 48 100% 48 0-34% 0-16 16 33% Deferral allowed per Table IWB-2500-1 B-G-1 86.180 48 *0 0 0% Only required when required by 8-L-2 B-G-1 836.190 2 0 0 0% Only required when disassembled 8-G-1 86.30 48 100% 48 0-34% 0-16 16 33% Deferral allowed per Table IWB-2500-1 8-G-1 86.40 48 100% 48 0-100% 0-46 0 0% Deferral allowed per Table IWNB-2500-1 B-G-1 86.50 48 100% 48 0-34% 0-16 16 33% Deferral allowed per Table IWVB-2500-1 Total: 192 192 48 NA 8-G-2 87.20 1 100% 1 0- 50% 0 0 0%

B-G-2 87.30 4 100% 4 0-50% 1 1 25%

8-G-2 87.50 9 3 100% 3 3 100% Only required if flange disassembled or bolting removed 8-0-2 87.60 2 1 100% 1 1 100% Only required when required by 8-L-2 B-G-2 87.70 9 groups as 5 100% 5 5 100% Only required when required by B-M-2 defined by 8-M-2 Total: 34 5 16-50% 1 1 20% Total percentage completed for 87.20 and 87.30. Other items NA B-K 810.10 3 2 0 0 Only one welded attachment of one of the multiple vessels shall be examined B-K 810.20 41 10% 4 1 1 Total: 3 6 16-50% 1 1 17%

Page 1of 3

Nuclear Management Company Prairie Island Unit 2 Completion Code Compliance Summary - 4th Interval - 1st Period ISI - Code Edition - 1998 Edition, 2000 Addenda PERIOD 1 TOTAL#U TOTAL # NUMBER PERCENT PERCENT REQUIRED PERCENT REQUIRED COMPLETED COMPLETE TOTAL REO'D FOR FOR REO'D FOR FORI1ST FORI1ST FOR 1ST CAT ITEM CODECASE POPULATION INTERVAL INTERVAL 1ST PERIOD PERIOD PERIOD PERIOD NOTES B-L-1 812.10 2 50% 1 0% 0 0 0%

Total, 2 1 0% 0 0 0%

B-L-2 812.20 2 0 0 0% Only requiercl when disassembled Total: 2 0-2 0 NA B-M-2 812.50 9 groups 0 0 0%

Total: NA 8-N-I 813.10 1 300% 1 100% 1 1 100% All accessible areas to be examined each period.

Total: 1 1 1 100%

B-N-2 813.50 1 100% 1 0- 100% 0-1 0 0% Deferral allowed per Table IWB-2500-1 B-N-2 813.60 1 100% 1 0-100% 0-1 0 0% Deferral allowed per Table IWB-2500-1 Total: 2 2 0-100% 0-2 0 0%

B-N-3 B13.70 1 100% 1 0- 100% 0-1 0 0% Deferral allowed per Table IWB-2500-1 Total: 1 0-100% 0-1 0 0%

B-0 814.10 40 10% 4 0-100% 0 0 0% Deferral allowed per IWB-241 2(a)(3)

Total: 40 0-100% 0 0 0%

B-P 815.00 Multiple 2 600% 12 One-third 4 4 One-third 2 pressure testing procedures required each outage Total: 2 One-third 4 4 One-third B-0 816.20 SG Tubing inspections are performed iaw the Technical Requirements Manual Section, 5.5.8 Total:

C-A Gil10 8 50% 4 1 1 C-A C1.20 4 50% 2 1 1 C-A C1.30 2 50% 1 0 0 Total: 14 7 16-50% 2 2 29%

C-B C2.21 4 50% 2 1 1 C-B 02.22 4 50% 2 1 1 C-B C2.31 4 50% 2 0 0 Total: 12 6 16-50% 2 2 33%

Page 2 of 3

Nuclear Management Company Prairie Island Unit 2 Completion Code Compliance Summary - 4th Interval - 1st Period ISI - Code Edition - 1998 Edition, 2000 Addenda PERIOD 1 TOTAL# TOTAL # NUMBER PERCENT PERCENT REQUIRED PERCENT REQUIRED COMPLETED COMPLETE TOTAL REQ'D FOR FOR REQ'D FOR FOR 1ST FORI1ST FOR 1ST CAT ITEM CODECASE POPULATION INTERVAL INTERVAL 1IST PERIOD PERIOD PERIOD JPERIOD NOTES C-C C3.10 4 50% 2 0 0 C-C C3,20 99 10% 10 4 4 C-C C3.30 16 10% 2 2 2 C-C C3.40 2 10% 1 0 0 Total: 121 15 16-50% 6 6 40% At least 16% must be completed in 2nd period since 1st period completion greater than 34%

Some exams not yet complete. These exams required to be completed by 2/20/2007. These exams C-H CT00 N-533-1 12 300% 36 One-third 12 9 25% will be outlined during the following summary report Total: 12 12 9 25%

F-A Elb1a 70 25% 18 7 7 F-A FlI10b 76 25% 19 6 6 F-A F1.i0c 65 25% 16 5 5 F-A F1.400Class 1 17 50% 9 4 4

Class 1 F-A were also prorated over each system as required by footnote (2) of Code Table WEF-2500-1 Total: 228 62 16-50% 22 22 35%

F-A F1.20a 118 15% 18 7 7 0%

F-A F1.20b 81 15% 13 2 2 0%

F-A F1.20c 61 15% 9 2 2 0%

F-A F1.40 Class 2 38 50% 19 6 6 *Class 2 F-A were also prorated over each system as required by footnote (2) of Code Table IWF-2500-1 Total: 298 59 16- 50% 17 17 29%

R-A. R1.11-2 85 25% 22 9 9 R-A Rl-11-5 48 10% 6 3 3 R-A R1.15-2 1 25% 1 0 0 R-A R1.16-2 4 25% 1 0 0 N-A R1.16-5 4 10% 2 0 0 R-A R1.19-5 4 10% 1 0 0 R-A R1.20-4 782 10% 80 26 26 N-A Total 928 113 One-third 38 38 1 34%

Page 3 of 3

NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION PRAIRIE ISLAND UNIT 2 CYCLE 23

SUMMARY

REPORT Section 4. IWE Examinations (2 pages)

The following evaluation is being performed per 10CFR5O.55a(b)(2)(ix)(D) as an alternative to IWE-2430, Additional Examinations. The three indications reported below are of a similar type on penetrations with the same service conditions.

Summar # Component ID Report Number 600661 C37A 2006V473 600663 C37C 2006V475 600664 C37D 2006V476

" The discoloration is caused by rusting as a result of condensation due to cold water flowing through the penetration. These penetrations provide Cooling Water/Chilled Water to the Fan Coil Units (FCUs). The corrosion is limited to the interface of the penetration weld to the containment plate.

The rust is only being seen on the annulus side of each penetration. The majority of the rusting is seen at the bottom where the condensation is collecting.

No corrosion is witnessed inside of containment on any of the penetrations. No pitting is being seen as a result of the rusting on any of the three penetrations.

The rusting is not affecting the structural integrity of the penetration.

No immediate corrective action is necessary. To prevent further degradation the penetrations should be recoated during the next refueling outage. Work Request 00017404 was initiated to recoat the penetrations during 2R25.

There are eight penetrations associated with the Fan Coil Units, one supply and return for each of the four Fan Coil Units. These are the only penetrations susceptible to the condensation related corrosion due to cold water flowing through the penetrations. All eight of these penetrations are having examinations performed in accordance with the requirements of Table IWE-2500-1, Examination Category E-C and are inspected each period. All eight of the penetrations were inspected during 2R24. These three penetrations were the only that had indications. Because all susceptible penetrations were examined no additional examinations are required.

Three areas of the moisture barrier inside of containment were found damaged.

Summary -Component -Report -Description of condition

___ ID Number ______ ________

600472 G62 2006 V491 Approximately 0.5" tear which does not

___________________extend to the containment shell 600476 G66 2006 V492 Approximately 0.5" tear which does not Section 4. IWE ExaminationsPae1o2 Page 1 of 2

NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION PRAIRIE ISLAND UNIT 2 CYCLE 23

SUMMARY

REPORT extend to the containment shell 600477 G67 ý2006 V493 Approximately 1.5" tear which extents to the containment shell During an outage it is common to store equipment on the outside wall of containment.

There is potential for this stored equipment to come in contact with the moisture barrier and cause damage. The damaged found during this outage appears to be new. Each outage a 100% inspection of the moisture barrier is performed by SP 2123 in order to identify and repair any areas where damaged was caused by stored equipment. These areas were identified by this inspection, an 151 inspection was then completed prior to the repair. All areas have been identified by SP 2123 and repaired;, no additional or successive inspections are required as a result of this indication.

Follow up E-C exams were performed on eight hot pipe penetrations. All eight of the exams showed signs of blistering. The components showing signs of blistering are:

Summary Component ID Report #

600669 S-84A 2006V481 600670 S-87A 2006V482 600671 S-.73B 2006V483 600672 S-77A 2006V484 600674 C6C 2006V485 600675 C7C 2006V486 600676 C7D 2006V487-600677 C6D 2006V488 VT-i inspections were performed on all of these components and identified there has been no change since the last inspection. The condition was initially reported in the 2003 Unit 2 outage Summary Report.

The coatings degradation is limited to the penetration and the immediate area around the penetrations. The heat from the feedwater and main steam piping causes blistering of the paint. Any contact with the blistered paint results in flaking and pealing. Under the pealing and flaking paint the primer is intact with no signs of degradation. No corrective actions are required to maintain the integrity of the structure as the blistering condition does not affect the structural integrity of the containment. All susceptible areas are currently on an Augmented inspection schedule so no additional examinations are required.

Section 4. IWE ExaminationsPae2o2 Page 2 of 2

NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION PRAIRIE ISLAND UNIT 2 CYCLE 23

SUMMARY

REPORT Section 5 Pressure Tests The following scheduled pressure tests were conducted during Unit 2 cycle 23. All indications were evaluated and corrective measures performed as required by IWB-3 142 and IWA-5250.

SSYSTEM CATEGORY/ ITEM PROCEDURE. .ASME Xl WOR!K COMPLETION

... CODE ORDER> DATE CLASS Reactor Coolant B-P/All SP 2070 1 00155119 12/1312006 Reactor Coolant B-P/All SP 2392 1 00155131 12/13/2006 Bolting Component Cooling C-H/All SP 2168.4A 2 00265202 11/15/2006 Cooling Water C-H/All SP 2168.8 2 00292958 12/11/2006 System to Unit 2 FCUs Residual Heat C-H/All SP 2168.10 2 00265194 12/9/2006 Removal SI Accumulator C-H/All SP 2168.12 2 00265192 11/15/2006 Post LOCA C-H/All SP 2168.15 2 00265188 11/16/2006 Hydrogen Control Feedwater C-H/All SP 2168.17 2 00265198 11/14/06 Sampling System C-H/All SP 2168.19 2 00265190 12/13/06 Reactor Coolant Gas C-H/All SP 2168.23 2 00265195 12/13/2006 Vent System Auxiliary Building C-H/All SP 2168.25 2 00265193 11/17/2006 Trench Boric Acid Leakage Identified at Bolted Connections During the performance of these pressure tests, nine components were identified as having minor boric acid leakage. In each instance the leakage was stopped and Code Case N-566-1, "Corrective action for Leakage Identified at Bolted Connection" evaluations were performed. The following items were considered in these evaluations:

" The number and service age of the bolts;

" Bolt and component material;

" Corrosiveness of product fluids;

" Leakage location and system function;

" Leakage history at the connection or other system components

" Visual examination of corrosion at the assembled connection.

The associated components were evaluated and found to be acceptable for continued use.

These locations are recorded and monitored in the Prairie Island Boric Acid Corrosion Control Program.

Section 5. Pressure Testing 3 rd IntervalPae1o1 Page 1 of 1

NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION PRAIRIE ISLAND UNIT 2 CYCLE 23

SUMMARY

REPORT Section 6. Snubber Inservice Testing and Preservice Examinations Inspection results showed no visual snubber failures. All snubbers that underwent functional testing had satisfactory results therefore no scope expansion was required.

2-RBDH-548 157625 376 291847-03 SAT 330 291847 291847 2-AFSH-46 602 157266-03 SAT 125 157266 157266 2-RBDH-337 192 157374-04 SAT 600 157374 157374 2-MSDH-19 397 157367-04 SAT 184 157367 157367 2-PSR-106A 372 157623-03 SAT 448 157623 157623 2-PSR-106B 434 157624-05 SAT 413 157624 157624 2-CCH-160 242 157354-04 SAT 535 157354 157354 2-SIRH-48 299 157370-04 SAT 95 157370 157370 2-SIRH-7 344 157371-03 SAT 248 157371 157371 2-ZX-PSSH-127 383 157372-03 SAT 88 157372 157372 2-CCH-161 33 157590-04 SAT 245 157590 157590 2-RHRH-54 312 88116-05 SAT 346 88116 88116 2-FWH-72B 258 157365-03 SAT 163 157365 157365 2-MSH-54B 43 157373-04 SAT 255 157373 157373 2-MSDH-17 488 157366-04 SAT 157 157366 157366 2-MSH-107B 539 157369-04 SAT 338 157369 157369 2-MSH-103A 528 157368-04 SAT 544 157368 157368 2-RCRH-45 567 157376-04 SAT 567 157376 157376 2-MSH-23B 518 157375-01 SAT 518 157375 157375 21S/GOl SG02 157599-04 SAT SG1 1 157599 157599 22S/GOl SG03 157378-02 SAT SG19 157378 157378 2-CCH-1 79B 464 158200-03 SAT 4 158200 158200 Section 6. Snubber Inservice Testing and Preservice ExamsPae1o1 Page 1 of 1

NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION PRAIRIE ISLAND UNIT 2 CYCLE 23

SUMMARY

REPORT Section 7 Steam Generator Eddy Current Examination Results Technical Specification 5.6.7.2 requires the results of steam generator tube in-service inspections shall be included with the summary reports of ASME Code Section XI inspections submitted within 90 days of the end of each refueling outage. The report Shall include:

1. number and extent of tubes inspected,

2. location and extent of wall-thickness penetration for each indication of an imperfection, and

3. identification of tubes plugged or sleeved.

Table I provides the number (as a percentage) and extent of tubes inspected.

Table 11provides the location and extent of wall-thickness penetration for each indication of an imperfection. Tubes with degradation below the F* or EF* distance left in service using an F* or EF*

repair criteria are not included in this report. F* and EF* tubes are reported in "2006 Unit 2 Steam Generator Inspection Results Day Report".

Table III provides the identification of tubes plugged or sleeved.

TABLE I Number and Extent of Tubes Inspected SCOPE PROBE TYPE S/G 21 S/G 22 Full LengthOD Bobbin 100% 100%

Rows 1 through 4 U-Bends MRPC 100% 100%

Rows 5 through 8 U-Bends MRPC 33% 33%

Hot Leg Tubesheets MRPC 100% 100%

Hot Leg Roll Plugs MRPC 25% 25%

Cold Leg Tubesheets MRPC 20% 20%

Post In Situ Pressure Test MRPC N/A N/A Supplemental(D MRPC 100% 100%

Plug Visual N/A 100% 1 100%

Baseline new Re-Rolls Bobbin/MRPC 100% 100%

(D Except the bend portion of rows 1 through 4 u-bends.

0 ADR, CUD, DEP, DNI, Tube Support Plate DNT Ž! 2.OV, Freespan ONT Ž SOy, DRI, DSI, DTI, Tube Support Plate INR Ž! 1.5V, MBM, MRI, NQI, PLP (Bound MRPC PLP's), PSI, Cold Leg Thinning Ž! 40%

or < 40% and Ž! 1.5V.

Section 7. Steam Generator Eddy Current Examination Results Pg 1 off111 Page

NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION PRAIRIE ISLAND UNIT 2 CYCLE 23

SUMMARY

REPORT TABLE 11 Location and Extent of Wall-thickness Penetration for Each Indication of an Imperfection NO, S/G ROW COL PERCENT LOCATION ELEVATION STATUS 1 21 16 4 14 0iC -0.03 <TS 2 21 16 5 6 02C -0.03 <TS 3 21 18 5 1 01C -0.18 <TS 4 21 14 6 14 01C -0.10 '<TS 5 21 19 6 22 NV1 -0.17 <TS 6 21 20 6 1 01C -0.08 <TS 7 21 21 7 1 01C -0.05 <TS 8 21 23 7 18 01C -0.30 <TS 9 21 21 9 25 NV1 1.19 <TS 10 21 25 10 1 0iC -0.24 <TS 11 21 27 10 26 07H 25.93 <TS 12 21 25 11 1 020 0.24 <TS 13 21 29 13 1 01C -0.27 <TS 14 21 31 17 1 01C -0.35 <TS 15 21 33 17 1 02C -0.05 <TS 16 21 34 17 1 02C -0.05 <TS 17 121 31 18 22 01C -0.32 <TS 18 21 34 18 1 01C -0.26 <TS 19 21 36 18 1 02C -0.23 <TS 20 21 36 21 13 02C 0.13 <TS 21 21 41 26 31 01C 0.23 <TS 22 21 41 26 28 01C -0.26 <TS 23 21 23 27 29 NV4 4.42 <TS 24 21 41 27 1 01C 0.16 <TS 25 21 41 27 27 01C -0.19 <TS 26 21 18 28 23 NV2 0.80 <TS 27 21 118 28 20 NV2 12.60 <TS 28 21 34 28 17 NV3 -0.22 <TS 29 21 25 30 24 NV2 0.78 <TS 30 21 25 30 37 NV2 19.70 <TS 31 21 25 30 22 NV4 2.30 <TS 32 21 139 30 27 NV4 2.69 <TS 33 21 25 32 29 NV2 0.38 <TS 34 21 25 32 31 NV2 19.50 <TS 35 21 41 32 19 NV1 -0.08 .<TS 36 21 41 32 13 NV2 -0.19 '<TS 37 21 141 32 15 NV3 0.32 <TS 38 21 17 33 25 NV2 12.10 <TS 39 21 24 33 22 NV3 2.00 <TS 40 21 25 33 35 NV2 1.62 <TS 41 21 25 33 34 NV2 20.48 <TS 42 21 25 33 20 NV4 0.89 <TS 43 21 39 34 22 1 NV2 35.58 <TS 44 21 39 34 30 1 NV4 2.67 <TS Section 7. Steam Generator Eddy Current Examination Results Pae2f1 Page 2 of 11

NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION PRAIRIE ISLAND UNIT 2 CYCLE 23

SUMMARY

REPORT NO. S/G ROW COL PERCENT- LOCATION ELEVATION STATUS 45 21 44 34 1 01C -0.18 <TS 46 21 44 34 30 05C -0.10 <TS 47 21 23 37 33 NV2 17.35 <TS 48 21 17 38 15 NV2 0.33 <TS 49 21 45 42 16 02C -0.08 <TS 50 21 11 43 7 NV1 -0.06 <TS 51 21 36 43 24 07H 33.94 <TS 52 21 36 43 24 NV2 2.50 <TS 53 21 36 43 25 NV2 32.94 . <TS 54 21 46 43 1 1 0iC -0.21 <TS 55 21 43 44 8 01C -0.29 <TS 56 21 44 44 6 01C -0.19 <TS 57 21 28 45 36 07H 29.93 <TS 58 21 28 45 37 NV2 -0.08 <TS 59 21 28 45 33 NV2 22.12 <TS 60 21 28 45 23 NV2 24.59 <TS 61 21 28 45 31 NV4 2.42 <TS 62 21 36 45 26 NV2 1.29 <TS 63 21 44 45 25 0iC -0.05 <TS 64 21 45 45 27 01C 0.03 <T5 65 21 44 46 20 01C -0.13 <TS 66 21 46 46 1 010 0.16 <T5 67 21 36 47 36 07H 34.22 Cr5S 68 21 36 47 32 NV2 2.48 <TS 69 21 36 47 26 NV2 32.10 <TS 70 21 39 47 29 NV2 35.52 <T5 71 21 39 47 31 NV4 3.12 <TS 72 21 35 48 36 07H 32.97 <TS 73 21 35 48 23 NV2 1.86 <TS 74 21 45 48 1 01C 0.13 <T5 75 21 29 50 38 NV2 1.03 <TS 76 21 29 50 41 NV2 23.90 <TS 77 21 45 50 27 010 -0.03 <TS 78 21 11 51 12 NV4 0.00 <TS 79 21 29 52 23 NV2 1.01 <TS 80 21 41 53 23 0iC -0.18 <TS 81 21 43 54 18 010 -0.05 <TS 82 21 46 54 1 01C -0.08 <TS 83 21 22 55 25 NV2 18.37 <TS 84 21 22 55 21 NV4 0.84 <TS 85 21 34 56 17 NV3 0.00 <TS 86 21 40 57 30 010 0.26 <TS 87 21 43 57 19 010 0.21 <TS 88 21 141 58 15 010 -0.16 <T5 89 21 45 58 16 010 0.05 <T5 90 21 8 59 34 04H 1.45 <TS 91 21 9 59 34 04H 1.45 <TS Section 7. Steam Generator Eddy Current Examination Results Pae3f1 Page 3 of 11

NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION PRAIRIE ISLAND UNIT 2 CYCLE 23

SUMMARY

REPORT NO. S/G ROW COL PERCENT LOCATION ELEVATION STATUS 92 21 43 59 24 01C 0.00 <TS 93 21 36 60 31 NV2 2.42 <TS 94 21 42 60 1 0iC 0.00 <TS 95 21 121 61 23 NV2 1.12 <TS 96 21 21 61 11 NV4 -0.05 <TS 97 21 23 61 29 1 NV2 1.26 <TS 98 21 23 61 21 NV2 19.16 <TS 99 21 23 61 23 NV4 0.00 <TS 100 21 139 61 6 01C -0.26 <TS 101 21 44 61 1 02C -0.27 <TS 102 21 42 62 1 01C -0.05 <TS 103 21 36 63 40 NV2 2.68 <TS 104 21 39 63 13 01C 0.18 <TS 105 21 21 64 20 NV2 17.08 <TS 106 21 142 64 1 02C -0.27 <TS 107 21 43 64 9 0iC -0.16 <TS 108 21 40 66 18 02C -0.19 <TS 109 21 21 67 15 NV2 0.48 <TS 110 21 26 69 28 07H 28.98 <TS 111 21 26 69 27 NV2 22.96 <TS 112 21 39 69 12 01C -0.29 <TS 113 21 40 70 16 02C -0.05 <TS 114 21 18 71 21 NV2 13.25 <TS 115 21 18 71 14 NV3 0.03 <TS 116 21 39 71 24 01C -0.18 <TS 117 21 40 71 1 01C -0.27 <TS 118 121 26 72 25 NV2 1.08 <TS 119 21 26 72 32 NV2 21.82 <TS 120 21 36 72 11 01C -0.11 <TS 121 21 39 72 13 0iC -0.16 <TS 122 21 38 73 26 0iC -0.08 <TS 123 121 37 75 6 0iC 0.00 <TS 124 21 34 76 1 02C 0.13 <TS 125 21 33 77 5 03C -0.31 <TS 126 21 35 77 23 02C -0.13 <TS 127 21 32 78 17 0iC -0.24 <TS 128 21 32 78 20 02C -0.08 <TS 129 21 23 85 8 01C 0.00 <TS 130 21 23 86 9 01C 0.08 <TS 131 21 25 86 1 01C -0.03 <TS 132 21 18 87 4 01C -0.18 <TS 133 21 17 89 9 02C -0.08 'ZTS 134 21 12 90 1 11 01C -0.16 <TS 135 21 15 90 1 01C 0.00 <TS 136 21 18 90 1 02C -0.11 <TS 137 21 4 91 21 0iC -0.19 <T5 138 21 7 91 28 01C -0.18 <TS Section 7. Steam Generator Eddy Current Examination Results Pae4f1 Page 4 of 11

NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION PRAIRIE ISLAND UNIT 2 CYCLE 23

SUMMARY

REPORT NO. S/G ROW COL PERCENT LOCATION ELEVATION STATUS 139 21 14 91 1 01C 0.00 <TS 140 21 _ 16 91 12 01C -0.03 <TS 141 21 3 92 24 01C 0.13 T 142 21 6 92 8 01C -0.16 <TS 143 121 1 8 92 18 0iC -0.08 <TS 144 21 8 92 1 02C -0.18 '<TS 145 21 9 92 15 01C -0.03 <TS 146 21 10 92 1 01C -0.03 <TS 147 21 13 92 1 02C -0.24 <TS 148 21 14 92 12 01C 0.03 <TS 149 21 114 92 24 NV1 2.65 <TS 150 21 2 93 14 01C -0.11 <TS 151 21 2 93 5 02C 0.00 <TS 152 21 5 93 20 01C -0.03 <TS 153 21 6 93 36 01C -0.23 <TS 154 21 6 93 15 02C -0.10 <TS 155 21 5 94 20 01C 0.00 <TS 156 21 7 94 25 O1C 0.08 <TS 1 22 6 1 4 02C -0.05 <TS 2 22 12 3 32 02C 0.08 <TS 3 22 16 4 15 01C 0.13 <TS 4 22 17 5 4 01C 0.13 <TS 5 22 16 6 7 01C -0.11 <TS 6 22 117 6 21 0iC -0.05 <TS 7 22 19 6 2 02C 0.13 <TS 8 22 20 6 33 01C -0.03 <TS 9 22 21 7 7 01C -0.03 <TS 10 22 21 7 15 02C 0.00 <TS 11 22 125 9 38 01C 0.00 <TS 12 22 20 10 20 01C -0.05 <TS 13 22 24 10 20 01C -0.11 <TS 14 22 26 10 20 02C 0.19 <TS 15 22 28 11 9 02C 0.16 <TS 16 22 29 13 20 01C -0.05 <TS 17 22 129 13 20 02C -0.03 <TS 18 22 31 13 33 0iC -0.13 <TS 19 22 29 15 1 01C -0.16 <TS 20 22 30 15 14 01C -0.03 <TS 21 22 34 16 29 01C 0.13 <TS 22 22 34 16 30 02C 0.00 <TS 23 22 34 17 19 01C -0.08 <TS 24 22 134 17 32 02C -0.08 T 25 22 30 19 14 01C -0.16 <TS 26 22 31 19 19 01C -0.21 <TS 27 22 32 20 15 01C -0.18 <TS 28 22 30 21 19 0iC 0.18 <TS 29 22 36 22 25 02C 0.05<T Section 7. Steam Generator Eddy Current Examination Results Pae5f1 Page 5 of 11

NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION PRAIRIE ISLAND UNIT 2 CYCLE 23

SUMMARY

REPORT NO. S/G ROW COL PERCENT LOCATION ELEVATION STATUS 30 22 37 23 11 01C 0.16 <TS 31 22 37 24 29 0iC -0.11 <TS 32 22 38 25 27 0iC 0.23 <TS 33 22 38 25 22 02C -0.16 <TS 34 122 41 26 15 01C 0.00 <TS 35 22 39 29 16 02C -0.13 <TS 36 22 41 29 19 NV1 0.00 <TS 37 22 41 29 15 NV3 0.00 <TS 38 22 19 31 _ 22 NV2 2.48 <TS 39 22 19 31 __ 15 NV3 0.00 <TS 40 22 19 34 15 NV1 -0.05 <TS 41 22 43 34 23 03C -0.05 <TS 42 22 43 35 36 02C -0.16 <TS 43 22 38 36 21 NV2 2.38 <TS 44 22 44 36 21 02C -0.08 <TS 45 22 42 38 1 14 02C -0.21 <TS 46 22 42 38 12 NV1 -0.26 <TS 47 22 42 38 14 NV2 -0.11 <TS 48 22 38 39 6 NV1 -0.08 <TS 49 22 38 39 10 NV2 0.00 <TS 50 22 43 39 17 02C -0.24 <TS 51 22 144 39 13 02C -0.13 <TS 52 22 44 40 14 02C 0.00 <TS 53 22 33 41 7 NV1 -0.27 <TS 54 22 40 41 16 NV1 0.00 <TS 55 22 40 41 22 NV2 0.00 <TS 56 22 40 41 13 NV3 0.00 <TS 57 22 44 42 24 02C -0.16 <TS 58 22 46 42 19 02C -0.03 <TS 59 22 37 43 35 NV2 33.18 <TS 60 22 37 43 32 NV4 3.91 <TS 61 22 45 43 2 01C 0.13 <TS 62 22 145 44 23 02C 0.08 <TS 63 22 39 45 11 NV1 -0.21 <TS 64 22 32 46 21 NV2 0.77 <TS 65 22 38 46 24 07H 36.1 <TS 66 22 33 47 20 NV4 2.12 <TS 67 22 38 47 23 NV2 1.91 <TS 68 22 145 47 11 01C -0.11 <TS 69 22 38 48 29 NV2 2.43 <TS 70 22 41 48 15 NV2 0.00 <TS 71 22 44 48 13 01C -0.03 <TS 72 22 45 48 14 0iC 0.21 <TS 73 22 45 48 22 02C -0.11 <TS 74 22 25 49 9 NV4 0.26 <TS 75 122 26 49 13 1 NV4 0.34 <TS L76 122 111 50 13 1 NV1 0.00 <TS Section 7. Steam Generator Eddy Current Examination Results Pae6f1 Page 6 of 11

NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION PRAIRIE ISLAND UNIT 2 CYCLE 23

SUMMARY

REPORT NO. S/G ROW COL PERCENT LOCATION ELEVATION STATUS 77 22 33 50 24 NV2 28.63 <TS 78 22 38 50 16 NV1 -0.05 <TS 79 22 38 50 33 NV4 0.00 <TS 80 22 45 50 36 01C 0.16 <TS 81 22 37 51 24 NV2 2.13 <TS 82 22 37 51 24 NV2 32.81 '<TS 83 22 46 51 34 01C -0.16 <TS 84 22 33 52 21 07H 35.39 <TS 85 22 45 52 34 01C 0.13 <TS 86 22 40 53 22 01C 0.18 <TS 87 22 44 53 22 01C 0.13 <TS 88 22 46 53 26 02C -0.13 <TS 89 22 36 54 30 NV4 3.51 <TS 90 22 39 54 21 07H 35.64 <TS 91 22 45 54 1 01C 0.03 <TS 92 22 45 54 1 02C 0.03 <TS 93 22 39 55 23 NV2 3.91 <TS 94 22 36 56 26 NV2 32.55 <TS 95 22 38 56 9 NV1 0.13 <TS 96 22 38 56 23 NV2 35.71 <TS 97 122 42 56 4 02C -0.03 <TS 98 22 43 56 23 01C -0.03 <TS 99 22 43 57 4 01C -0.19 <TS 100 22 43 57 33 NV3 0.00 <TS 101 22 43 57 14 NV4 0.00 <TS 102 22 45 57 6 01C -0.05 <TS 103 22 35 58 20 07H 32.96 <TS 104 22 43 58 20 01C -0.11 <TS 105 22 43 58 15 NV2 -0.08 <TS 106 22 40 59 21 07H 35.09 <TS 107 122 41 60 9 02C -0.16 <TS 108 22 43 60 1 15 02C 0.00 <TS 109 22 41 61 30 02C -0.08 <TS 110 22 44 61 20 02C -0.13 <TS 111 22 44 62 4 02C -0.13 <TS 112 22 143 63 4 02C -0.24 <TS 113 22 32 64 27 NV2 3.17 <TS 114 22 32 64 27 NV2 27.97 <TS 115 22 38 64 27 NV2 34.28 <TS 116 22 39 64 25 02C -0.24 <TS 117 22 142 64 30 02C -0.21 <TS 118 22 19 65 22 NV2 1.2 <TS 119 22 42 65 17 02C -0.11 <TS 120 22 43 65 22 02C -0.21 <TS 121 22 32 66 16 NV4 -0.03 <TS 122 22 40 66 10 1 02C 0.13 <TS 123 22 41 66 31 1 02C -0.11 <TS Section 7. Steam Generator Eddy Current Examination Results Page 7 of 11

NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION PRAIRIE ISLAND UNIT 2 CYCLE 23

SUMMARY

REPORT NO. S/G ROW COL PERCENT LOCATION ELEVATION STATUS 124 22 32 67 21 NV1 -0.27 <TS 125 22 32 67 32 NV2 0.00 <TS 126 22 32 67 23 NV2 28.18 <TS 127 22 32 67 34 NV3 0.00 <TS 128 22 32 67 24 NV4 0.00 <TS 129 22 32 68 21 NV2 28.73 <TS 130 22 36 69 20 NV1 0.08 <TS 131 22 36 69 35 NV3 -0.19 <TS 132 22 36 69 22 NV4 -0.03 <TS 133 22 40 69 31 02C -0.13 <TS 134 22 41 69 16 02C -0.08 <TS 135 22 36 70 35 NV2 4.8 <TS 136 22 36 70 1 39 NV2 32.56 <TS 137 22 16 71 14 NV3 -0.32 <TS 138 22 38 71 31 01C -0.08 <TS 139 22 40 71 28 02C -0.16 <TS 140 22 36 72 12 02C -0.13 <TS 141 22 37 72 1 02C -0.18 <TS 142 22 36 73 1 02C -0.16 <TS 143 22 35 74 1 02C 0.1 <TS 144 22 33 75 37 0iC -0.05 <TS 145 22 35 75 33 01C -0.03 <TS 146 22 36 75 31 02C -0.16 <TS 147 22 33 76 32 0iC -0.03 <TS 148 22 33 76 25 02C -0.13 <TS 149 22 30 79 3 01C 0.11 <TS 150 22 30 79 15 02C 0.13 <TS 151 22 29 81 13 NV2 0.16 <TS 152 22 30 81 17 01C 0.00 '<TS 153 22 29 82 34 01C -0.11 <TS 154 22 29 82 26 02C -0.23 <TS 155 22 30 82 17 02C -0.13 <TS 156 22 30 83 1 02C -0.2 <TS 157 22 29 84 1 02C -0.24 <TS 158 122 122 85 1 01C -0.13 <TS 159 22 24 85 1 01C -0.13 <TS 160 22 28 85 14 01C 0.08 <TS 161 22 28 85 20 01C -0.16 <TS 162 22 26 86 14 02C -0.13 <TS 163 22 20 87 1 0iC -0.16 <TS 164 22 14 88 7 02C -0.11 <TS 165 22 22 88 7 02C -0.16 <TS 166 22 116 89 19 01C -0.24 <TS 167 22 16 89 23 02C -0.11 <TS 168 22 17 89 29 01C 0.00 <TS 169 22 18 89 20 02C -0.03 <TS 170 22 19 89 21 01C 0.00 <TS Section 7. Steam Generator Eddy Current Examination Results Page 8 of 11

NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION PRAIRIE ISLAND UNIT 2 CYCLE 23

SUMMARY

REPORT NO. S/G ROW COL PERCENT LOCATION ELEVATION STATUS 171 22 20 89 1 02C -0.16 <TS 172 22 21 89 1 02C -0.18 <TS 173 22 6 90 19 01C -0.03 <TS 174 22 12 90 17 01C -0.08 <TS 175 22 16 90 39 01C 0.00 <TS 176 22 17 90 1 01C -0.13 <TS 177 22 2 91 17 01C 0.08 <TS 178 22 7 91 15 01C 0.11 <TS 179 22 11 91 32 02C -0.05 <TS 180 22 12 91 1 01C 0.06 <TS 181 22 12 91 7 02C -0.05 <TS 182 22 13 91 13 02C -0.08 <TS 183 22 1 92 1 1 Q0C 0.11 <TS 184 22 3 92 7 01C 0.06 <TS 185 22 6 92 5 02C 0.00 <TS 186 22 7 92 36 01C 0.03 <TS 187 22 9 92 16 01C 0.03 <TS 188 22 4 93 27 0iC 0.11 <TS 189 22 4 93 12 02C 0.03 <TS 190 22 5 93 26 01C 0.05 <TS 191 22 2 94 10 01C 0.25 <TS 192 122 1 4 94 14 02C -0.06 <TS 19 2 5 94 1 02C -0.03 <TS TABLE III Identification of Tubes Plugged or Sleeved NO. IS/GTROW COL PERCENT LOCATION ELEV FROM ELEV TO STATUS 1 21 4 11 MAI EB3H -0.02 0.08 PLG 2 21 3 22 MAI EBH -0.05 0.13 PLG 3 21 19 25 SAl EB3H 0.00 0.08 PLG 4 21 28 27 FPC EBH 0.30 PLG 5 121 11 32 SAl TRH 16.64 17.77 PLG 6 21 19 32 SAl EBH 2.11 2.17 PLG 7 21 23 34 SAl EBH 3.43 4.18 PLG 8 21 23 39 MAI EBH 0.05 0.14 PLG 9 21 10 43 MAI EBH -0.01 0.03 PLG 10 21 3 45 SAl 1131- 16.48 16.84 PLG 11 21 14 47 SAl 213H- 14.96 15.38 PLG 12 21 18 47 TBP (D PLG 13 21 8 49 SAl E13H -0.04 0.04 PLG 14 21 25 49 SAl E13H 0.13 0.23 PLG 15 21 12 54 TBP Q PLG 16 21 11 57 SAl EBH -0.02 0.05 PLG 17 21 7 67 MAI EBH -0.09 0.06 PLG 18 21 4 68 MAI 2131- 14.75 14.93 PLG Section 7. Steam Generator Eddy Current Examination Results Pae9f1 Page 9 of 11

NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION PRAIRIE ISLAND UNIT 2 CYCLE 23

SUMMARY

REPORT NO. S/G ROW COL PERCENT LOCATION ELEV FROM ELEV TO STATUS 19 21 17 89 48 01C 0.03 PLG 1 22 12 20 FPC EBH 0.3 PLG 2 22 29 24 SVI 0iC -0.08 0.1 PLG 3 22 19 30 SAl TRH 18.05 18.49 PLG 4 22 20 30 SAl TSH -0.01 0.08 PLG 5 22 11 36 SAl TRH 17.87 18.14 PLG 6 22 17 38 SAl TRH 17.35 17.6 PLG 7 22 19 44 SAl TRH 17.7 18.26 PLG 8 22 15 46 SAl 213H- 15.3 15.45 PLG 0D EF* re-roll candidate repaired by plugging due to tooling inaccessibility.

0 Administratively repaired by plugging due to excessive permeability variation at re-roll elevation.

Section 7. Steam Generator Eddy Current Examination Results Pg Page 10 ~f1 of 11

NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION PRAIRIE ISLAND UNIT 2 CYCLE 23

SUMMARY

REPORT LEGEND OF FIELDS AND CODES FIELD EXPLANATION NO. Cumulative number per table per S/G S/G Steam Generator Number (21 or 22)

ROW Row number of tube location COL Column number of tube location PERCENT Measured percent or three digit code - see below LOCATION Physical Location of Indication - see below ELEVATION Measurement in inches from the LOCATION to the center of the indication ELEV FROM Measurement in inches from the LOCATION to the lower edge of the indication ELEV TO Measurement in inches from the LOCATION to the upper edge of the indication STATUS Repair status - see below FIELD CODE EXPLANATION PERCENT ADR Absolute Drift CUD Copper Deposit DEP Deposit DNI Dent with Indication DNT Dent DRI Distorted Roll Transition with Indication DSI Distorted Support Signal with Indication DTI Distorted Tube Sheet Signal with Indication FPC Failed Profilometry Criteria INR Indication Not Reportable MAI Multiple Axial Indication MBM Manufacturing Burnish Mark MRI Mix Residual Indication NQI Non Quantifiable Indication PLP Possible Loose Part PSI Possible Support Indication SAl Single Axial Indication SVI Single Volumetric Indication TBP To Be Plugged 0-100 As measured percent through wall LOCATION TEH Tube end hot (primary face)

TRH Top of roll expansion hot leg 113H Bottom of Additional roll expansion #1 hot leg 2131- Bottom of Additional roll expansion #2 hot leg EBH Bottom of Elevated roll expansion hot leg TSH Tube sheet hot (secondary face) 0?H ?= First through Seventh tube support plate on hot leg side NV? ?= First through Fourth new antivibration bar 0?C ?= First through Seventh tube support plate on cold leg side TSC Tube sheet cold (secondary face)

TRC Top of roll expansion cold leg TEC Tube end cold (primary face)

STATUS <TS Less Than the Technical Specification repair limit PLG Tube Plugged Section 7. Steam Generator Eddy Current Examination Results Page 11 of 11

NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION PRAIRIE ISLAND UNIT 2 CYCLE 23

SUMMARY

REPORT Section 8. Repair/Replacement Activities for Cycle 23, ISI Interval 4 32 NIS-2 forms are attached which identify Prairie Island Unit 2 Repair/

Replacement Activities during fuel cycle 23, 4 th ISI Interval. The gaps in item number sequence are due to cancelled or unfinished R/R activities.

UbU4bj 14, 1SPCE-ME- Replaced the mechanical seal gland 12-23-001 0453 22BATP plate and fasteners. -~__2 -~VC

~Pressurizer PORV RelcdPui1 R 2-23-004, 92790-01 Pressurizer PORV 9278,91-011 A __ Replaced Plug. 1 RC 2-23-005 j22_Charging Pump i Replaced packing assemblies. 2 VC 0505924 IReplaced plungers in packing lassemblies 13, 14, and 15 and

'Spare Charging !replaced gland plates in assemblies 2-23-009 10409796 ~Pum114 and 15.2 VC i22 CHG Pmp

!2-23-013 1154068 Suction 1Replaced Bonnet and fasteners. _ 2 'VC Replaced the mechanical seal gland 12-23-014 157443-01 2BATP _plate. 2

.~__- VC 270329-0 1 !22 Charging Pump Re laced packing assemblies. 2 VC 1SG Snubber Block 12-23-020 1157378-05 lValve IReplaced valve block. 12 :SG iSG Snubber Block 223-02 1 157599-01 !Valve I eplaced valve block. _____ 2 SG I IReplaced the mechanical seal gland 121 SIPump___ plate.__ 2 SI Main Steam Safety IReplaced applicable valve to flange 2-23-025 EEC-i 096 __Valve____nuts with superbolt material. ý2 MS 157619-01, ManSteam Safety 1Replaced applicable valve to flange t22-261EEC-1096 'Valve nuts with superbolt material. 2 MS Replaced mechanical seal gland 2-23-027 99275-0 1 121 RHR Pum 'fasteners. .2 RH

ý2RCS LP AHot

ý96881-01, 'Leg RHR Supply 'Replaced body to bonnet fastener 1EEC-1620 Valve Iset.1 .RH_

2-23-028 !Replaced mechanical seal gland 2-23-029 110617-01 ý22 RHR Flump fas~teners 12 .RH 153609-01, ,Main Stea im Safety 1,Replaced applicable valve to flange 12-23-030 1EEC-1096 Valve I nuts with superbolt material. i2 1MS IDrilled and tapped holes in charging

,Mod. 02VC01 Ipump packing assembly gland plates 2-23-0311 EC-07688 !Charging Pump land stuffing boxes!/ VC Wyle Labs 1Pressurizi er Safety

ý2-23-032P.O. 8988 lValve Replaced disc.1 2-23-034'3038111-01 i23 Chari ng Pump Replaced Packing assemblie2 VC 12-23-035 154839-11 ý22/24 ECI UCHLD Replacement main plug and body to 3 zx Section 8. Repair/Replacement Activities for Cycle 23Pae1o2 Page 1 of 2

NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTION PRAIRIE ISLAND UNIT 2 CYCLE 23

SUMMARY

REPORT

.Item # IMOD #s ý,pcomp Name [Description of Work Completed lClass ýSYSTEMV WVTR RTRN Sbonnet fasteners.

21/23 ECU CHLD 2-23-036 199284-07_ -WTR-RTRN 'Replacement main plug.. __ 3 1154791-12, 'Replaced 5 bonnet studs, 5 nuts, and lAlteration 122 SG MS ISOL ýdamaged helical coil. Repaired 4 MS (Main 2-23-037 92A229 Icv -, - - - - - istud holes w/ helical coil inserts. 2 Steam)__

121 CC Heat iWeld build up of wasted areas in 2-23-038 154513-08 !Exchanger shell and attachment weld areas. .3 _CC:

306250-01, Installed branch connection in 24"--------

!2-23-039 EC-9602 jCL Pipe Section section of pipe., 3 CL Boric Acid FLTR 'Re-welded Canopy after BA depositý 2-23-04 1 306550-01 ..

. iremoval 2 ,VC 122 SG MS OUTL ;Machined the disc and seat sealing 2~-23-042 1305364-02 JS~to~p- OK surface. 2 M

'2-23-045 154582-05 121 PRZR RELIEF R~ep~l~ace~din~l~e~tflange fasteners. 1 MS

............M S........

2-23-046 :154582-05 121 PRZR RELIEF Replaced inlet flange fasteners.

Pressurizer to CV-2-23-047 i96871 -01 31229_Bypass !Replaced bonnet. 1 :RC-RH support Buffed out indication. 1 RH

'RFLG WVTR TO

SAF INJ PMPS 2-2-4 3720-01 PHDR ISQL lReplaced body to bonnet fasteners. ý2 SI Section 8. Repair/Replacement Activities for Cycle 23Pae2o2 Page 2 of 2

MEMO FORM IS-2PRAIRIE ISLAND NUCLEAR GENERATING PLANT ITEM 2-23-001

1. Owner Nuclear Management Company, LLC Date 8/3/2005 Name

2. Plant Praire Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 0504674, SPCE-ME-0453 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 # RemIveI or Code 2 APGoulds 792A1 92-2

___I _ _Installed I245-032 J____JCorrected Stamp E-

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

eC. ./,

8. Tests conducted: H~ydrostaticDr- PneumaticD- Nominal Operating Pressure F- Exempt f/-

Other F1 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.

FORM IS-2PRAIRIE ISLAND NUCLEAR GENERATING PLANT ITEM 2-23-001

'9. Remarks n/a 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 Certificate of AuIet ' i 111 Expiration Date _______________________

Signed ý M, ASME Program Engineer Date _ _ _ _ _ _ _

Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION 1,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 20Wo~u.cr 'to 18 AU6-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.

rJ-4,V&QQ.9Commissions '3 L1Q09. A,4- rJIq.L 1 _)spec-tor'sSignature National Board, Province and Endorsements Date ,1LU 6

FORM IS-2PRAIRIE ISLAND NUCLEAR GENERATING PLANT ITEM 2-23-004

1. Owner Nuclear Management Company, LLIC Date 12/7/2006 Name

2. Plant Prairie Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 92790-01 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 B16.34 n/a Edition Addenda n/a Code Cases n/a (b) Applicable Edition of S-ection 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 Pressurizer PORV B SPX / Copes CV-31 233 1968 Corrected F-Vulca n

7. Description of Work Replaced Plug.

8. Tests conducted: HydrostaticED PneumaticD Nominal Operating Pressure F] Exempt nV 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. xl11 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.

FORNI-2OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-23-004

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

Type Code Symbol Stamp 41I$?4 Certificate of Auh. Expiration Date ________________________

Signed 7 ?ASME Program Engineer Date zZ L _____

Owner or Owner's Designee , Title CERTIFICATE OF INSERVICE INSPECTION 1,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 .O~2~a to lsý/o 41o6 I and state that to the best of my knowledge and belief, the Owner has performed examinations and take'n 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.

-IM 14 Commissions MAI O$~S-3/5-- 44-6:Z71S Inspector's Signature National Board, Province' arid Endorsements Date

FORNI-2OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-23-005

1. Owner 'Nuclear Management Company, LLC Date 12/7/2006 Name

2. Plant Prairie Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 92789-01 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 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 Manufacturer Manufacturer Nat'l Bd # Other ID Yr Built Corrected, ASME Name Serial # Removed, or Code Installed Stamp Pressurizer PORV A SPX / Copes CV-31234 1968 Corrected ED Vulcan

7. Description of Work Replaced Plug.

8. Tests conducted: HydrostaticE PneumaticDE Nominal Operating Pressure r] Exempt FV 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.

E:MIS-2OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-23-005

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

Type Code Symbol Stamp 614 Certificate of Aut aExpiration Date _______________________

Signed ,ASME Program Engineer Date /ob+'7 1iAcý____

Owner or Owner's Designee ,Title CERTIFICATE OF INSERVICE INSPECTION 1,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 ..

_____________ 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 IA4& 0 5,163/ % 8 6 Inspector's Signature National Board, Province ancf Endorsements Date _________ _________ a00o,1

OWNIRER'SLN REPORTEFR RENEATIRI RPLACEETNCIVT FORM NIS-2 PRAIRIE'SLN NUCLEAFR GENEATING RPLANTET CIVT ITEM 2-23-008

1. Owner Nuclear Management Company, LLC Date 9/16/2005 Name

2. Plant Praire Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wokonade Dr. E, Welch Minnesota 55089 0505924 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 I Manufacturer fManufacturer 1Nat'l Bd # IOther ID 1Yr Built Corrected, ASME

7. Description of Work Replaced packing assemblies.

8. Tests conducted; Hydrostatic F- Pneumatic[] Nominal Operating Pressure F- Exempt ke Other Fý Pressure psi Test Temp. 0 IF Other: A non-code leakage exam will be performed.

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.

FORM IS-2PRAIRIE ISLAND NUCLEAR GENERATING PLANT ITEM 2-23-008

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

Type Code Symbol Stamp W11 Certificate of Authorization No. Expiration Date _______________________

Signed ,ASMVE Program Engineer Date _________ /as-_

Owner or Owner's Designee , Title CERTIFICATE OF INSERVICE INSPECTION 1,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 /FYVL or to 14 SEPO3 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.

Sel. Commissions .~Io* ~

nsoector's Signat Iure National Board, Province and Endorsements Date L fQndmfn IL~ ,

FORM IS-2PRAIRIE ISLAND NUCLEAR GENERATING PLANT ITEM 2-23-009

1. Owner Nuclear Management Company, LLC Date 8/9/2005 Name

2. Plant Praire Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 0409796 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 IComponent Name I Manufacturer IManufacturer I Nat'l Bd # I Other ID Yr Built 1Corrected, tASME

7. Description of Work Replaced plungers in packing assemblies 13, 14, and 15 and replaced gland plates in assemblies 14 and 15.

8. Tests conducted: Hy drostaticF- PneumaticD- Nominal Operating Pressure E] Exempt F./

Other F1 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.

FORM IS-2PRAIRIE ISLAND NUCLEAR GENERATING PLANT ITEM 2-23-009

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 XJ.

Type Code Symbol Stamp 4

Certificate of Auth ni)~ A

/// Expiration Date______________________

Signed ,ASME Program Engineer Date FA;______ __/65_7 Owner or Owner's Designee , Title CERTIFICATE OF INSERVICE INSPECTION 1,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 XMA14Lor to 22A06*9 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.

-- Itrs Commissions 44S lI& Agi MI211 I pector's Signature National Board, Province and Endorsements Date ( 2 ,Unb 21 LOS

'/

FORM IS-2PRAIRIE ISLAND NUCLEAR GENERATING PLANT ITEM 2-23-013

1. Owner Nuclear Management Company, LLC Date 12/12/2006 Name

2. Plant Prairie Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55059 154068 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, 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 CHG Pmp Suction Grinnell 2VC-6-6 Corrected El

7. Description of Work Replaced Bonnet and fasteners.

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

FORNI-2OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-23-013

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

Type Code Symbol Stamp 114 Certificate of Au honz inNo. 4/ /A. Expiration Date ________________________

Signed _ n ,ASME Program Engineer Date _ _

Owner or Owner's Designee , Title CERTIFICATE OF INSERVICE INSPECTION 1,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 aA,/0-/a to 'l ,,

and state that to the best of my knowledge and belief, the Owner has performed eiaminations 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 Alwog 0-54/3 /36zv Inspector's Signature National Board, Province and Endorsements Date

FORM IS-2PRAIRIE ISLAND NUCLEAR GENERATING PLANT ITEM 2-23-0 14

1. Owner Nuclear Management Company, LLC Date 5/5/2006 Name

2. Plant Praire Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 157443-01 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 Name Manufacturer Serial #

Nat'l Bd # Other ID 11Removed, Yr Built Corrected, ASME or Code 11Corrected In stalled Stamp 22 BATIP Goulds 792A192-2 245-032 I

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

a. Tests conducted: HydrostaticDE Pneumatic[] Nominal Operating Pressure 0j Exempt VF 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 GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITYI ITEM 2-23-014

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 /V24 Certificate of Auth 4/'Expiration Date______________________

Signed (JASME Program Engineer Date 3571',5-66___

Owner or Owner's Designee , Title CERTIFICATE OF INSERVICE INSPECTION 1,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 -HSB3 Insp. and Ins. Co. of Connecticut of Hartford Conn. have inspected the components described in this Owner's Report during the period /d APR 04~ to OC.MAJOG 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.

V) Commissions ____________________

I 5p-ector's Signature National Board, Province and Endorsements Date 4.- r( oOltn (9

FORM IS-2PRAIRIE ISLAND NUCLEAR GENERATING PLANT ITEM 2-23-015

1. Owner Nuclear Management Company, LLC Date 9/6/2006 Name

2. Plant Praire Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 270329-01 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

_____________ I___________ ________________Installed___ nsalldaSam 22 Charging Pump Ajax 245-042 1969 CorrectedD

7. Description of Work Replaced packing assemblies.

8. Tests conducted: Hydrostaticfý PneumaticDF- 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.

E:NIS-2OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-23-015

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 41/4 Certificate of Au Expiration Date ________________________

Signed ,ASME Program Engineer Date 4A_ _ _

Owner or Owner's Designee , Title CERTIFICATE OF INSERVICE INSPECTION 1,the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessei 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 1I4APR&o to 6- f.-

and state that to the best of my knowledge and beiief, 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 13IQZG3 M~l rrJ 4M-2L Insp tor', Signature National Board, Province and Endorsements Date /pknd.n e I Qoe(-

KU

E:NIS-2OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-23-020

i. Owner Nuclear Management Company, LL-C Date 12/6/2006 Name

2. Plant Prairie Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 157378-05 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 831.1 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 72218-000-03 22S/G 01 RemovedD SG Snubber Block Valve McDowell Welman 72218-000-19 22S/G 01 Installed ED

7. Description of Work Replaced valve block.

8. Tests conducted: Hydrostatic F1 PneumaticD- Nominal Operating Pressure F Exempt FV-Otherl 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.

OWNE'S EPOT FO REAIR RELACEENTACTVIT FOR N 5-2PRAIRIE ISLAND NUCLEAR GENERA TING PLANT ITEM 2-23-020

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 ý1 Certificate of on Expiration Date ________________________

Signed ASEPogramn Engineer Date 4 ___

Owner or Owner's Designee ,Title CERTIFICATE OF INSERVICE INSPECTION 1,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 611#06& to ,g/.2/06/0 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.

Inspector's Signature S Commissions AiA/ 0-5,/53/ ~/9/ 6 National Board, Province and Endorsements I

Date

FORNI-2OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-23-021

1. Owner Nuclear Management Company, LLC Date 12/6/2006 Name

2. Plant Prairie Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 157599-01 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 72218-000-02 21S/G 01 RemovedD SG Snubber Block Valve McDowell Welman 721-001 1 2- -/ 1Intle

7. Description of Work Replaced valve block.

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

Other[- Pressure psi Test Temp.

Other: n/a NOTE: Supplemental sheets inform 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.

FOR N 5-2PRAIRIE ISLAND NUCLEAR GENERATING PLANT ITEM 2-23-021

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 XI.

Type Code Symbol Stamp A$214 Certificate of Aut~h ýýJ .4'4. Expiration Date _______________________

Signed ( <,ASME Program Engineer Date /?~/ ~ _ _

Owner or Owner's Designee , Title CERTIFICATE OF INSERVICE INSPECTION 1,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 -611A6.16 to 1-216646 1 and state that to the best of my knowledge and belief, the Owner has performed examinations and tak~en 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.

Inspector's Signature 4e ~Commissions /p'id 0-54&3/ 9A National Board, Province and Endorsements Date I r,7006

mmý FORM IS-2PRAIRIE ISLAND NUCLEAR GENERATING PLANT ITEM 2-23-024

1. Owner Nuclear management Company, LLC Date 12/4/2006 Name

2. Plant Prairie Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 89775-01 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 B31.1 1967 Edition Addenda ____________ Code Cases ___________

(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 SI Pump Bingham- 290698 245-071 CorrectedD Willamette

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

8. Tests conducted: Hydrostatic F- PneumaticD- Nominal Operating Pressure 7 Exempt FV Other F1 Pressure psi Test Temp. 0F Other: IST Pump Testing 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.

FOR NI-2OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-23-024

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 Authorization Expiration Date ________________________

4 Signed ,ASMVE Program Engineer Date AJ/ ____

Owner or Owner's Designee , Title CERTIFICATE OF INSERVICE INSPECTION 1,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/VS/oý6 to /2~ c 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.

____ ___ ___e__4& "_ Commissions A~,/3 ~y Inspector's Signature National Board, Province and E'nd'orsements Date mo5

FORNI-2OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-23-025

1. Owner Nuclear Management Company, LLC Date 11/27/2006 Name

2. Plant Prairie Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 157421-01, EEC-i1096 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 MS Code Class 2

5. (a) Applicable Construction Code B16.34 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 Main Steam Safety Valve Consolidated RS-21-20 CorrectedD

7. Description of Work Replaced applicable valve to flange nuts with superbolt material.

8. Tests conducted: Hydrostatic El Pneumaticn Nominal Operating Pressure n Exempt n.

Other F Pressure psi Test Temp.

Other:

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 2-23-025

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 416 Certificate of A ithojrUenAtkt Expiration Date _______________________

Signed ,ASME Program Engineer Date Ia7 A__(0 Owner or Owner's Designee , Title CERTIFICATE OF INSERVICE INSPECTION 1,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 602 -to 1U/q28/d' and state that to the best of my knowledge and belief, the Owner has performed examinations and tak en 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,4. 0 51/531 14 4/1 5 Inspector's Signature National Board, Province and Endors'ements Date a~O0O DateI

FOR N 5-2PRAIRIE ISLAND NUCLEAR GENERATING PLANT ITEM 2-23-026

1. Owner Nuclear Management Company, LLC Date 11/27/2006 Name

2. Plant Prairie Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 15761 9-01, EEC-i1096 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 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 Coinponent Name IManufacturer IManufacturer I Nat'l Bd # IOther ID Yr Built IC,

7. Description of Work Replaced applicable valve to flange nuts with superbolt material.

8. Tests conducted: Hydrostatic PneumaticDF- Nominal Operating Pressure F- Exempt Fvo Other F1 Pressure psi Test Temp. 0F Other:

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.

FORNI-2OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-23-026

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

Type Code Symbol Stamp Certificate of Auth 0 6IdExpiration Date _______________________

Signed ,ASME Program Engineer Date 7___

AI Owner or Owner's Designee , Title CERTIFICATE OF INSERVICE INSPECTION 1,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 'e l26o to 11107606 and state that to the best of my knowledge and belief, the Owner has performed examinations and tak~en 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 orcyeted with this inspection.

_________& 0 ____" Commissions /A/d O'S"153 /6 /Z Inspector's Signature National Board, Province and Endorsemehts Date 1 .7CO6

FORNI-2OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-23-027

1. Owner Nuclear management Company, LLC Date 12/11/2006 Name

2. Plant Prairie Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 .99275-01 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 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 Name Manufacturer Serial #

Nat'l Bd #

Other ID II_Yr Built Corrected, Installed ASME TRe moved, or Code Stamp 21 RHR Pump Byron Jackson 681 -N-0274 245-111 Corrected

7. Description of Work Replaced mechanical seal gland fasteners.

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

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 2-23-027

9. Remarks CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this conforms to the requirements of the ASMVE Code, Section X1.

Type Code Symbol Stamp 1,1 Certificate of Aut >riz~atio . A1,1,4 Expiration Date _______________________

Signed ASMVE Program Engineer Date ______ ___

Owner or Owner's Designee , Title CERTIFICATE OF INSERVICE INSPECTION 1,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 InsD. and Ins. Co. of Connecticut of Hartford Conn. have inspected the components described in this Owner's Report during the period 6Ac o(, to /0,Zo, 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 /41A10,VT3SA'/S1ý f- G Inspector's Signature National Board, Province and Endorsements Date lall ooo6 1 07Cý06

FORM IS-2PRAIRIE ISLAND NUCLEAR GENERATING PLANT ITEM 2-23-028

1. Owner Nuclear Management Company, LLC Date 12/12/2006 Name

2. Plant Prairie Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 96881-01, EEC-i1620 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 RH 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 2RCS LP A Hot Leg RHR Supply Velan MV-32193 1968 CorrectedD Valve

7. Description of Work Replaced body to bonnet fastener set.

8. Tests conducted: Hydrostatic F-1 Pneumaticn Nominal Operating Pressure F- Exempt FV Other 11 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.

FORNI-2OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-23-028

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

Type Code Symbol Stamp 4ll, Certificate of Authori' Expiration Date ________________________

Signed ASME Program Engineer Date /~/~ e _ _

Owner or Owner's Designee ,Title CERTIFICATE OF INSERVICE INSPECTION 1,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 WA/'106~ to 14,/~

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

By signing this certificate neither the 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 orcnpted with this inspection.

_________ K "____ Commissions /WPoxISS-f3 1 4 zý Inspector's Signature National Board, Province and End'orsements Date

FORM IS-2PRAIRIE ISLAND NUCLEAR GENERATING PLANT ITEM 2-23-029

1. Owner Nuclear management Company, LLC Date 12/12/2006 Name

2. Plant Prairie Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 110617-01 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 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 RHR Pump Byron Jackson 245-112 Corrected E]

7. Description of Work Replaced mechanical seal gland fasteners.

8. Tests conducted: Hydrostatic [- PneumaticD- Nominal Operating Pressure F] Exempt RV Other F1 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.

FORNI-2OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-23-029

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 X1.

Type Code Symbol Stamp 4 Certificate of AuthoiizRrN v"AExpiration Date ________________________

Signed ,ASME Program Engineer Date 1-2 2 _____

Owner or Owner's Designee , Title CERTIFICATE OF INSERVICE INSPECTION 1,the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of ' Minnesota and employed by HSB lnsp. and Ins. Co. of Connecticut of Hartford Conn. have inspected the components described in this Owner's Report during the period _ v g -to 14113 "

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.

___ ___ __16 !5" _ __ Commissions MAqAI5'VSSI t Inspector's Signature National Board, Province and Endorsements Date 121 I 0

MMMME I PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-23-030 I

1. Owner Nuclear Management Company, LLC Date 11/27/2006 Name

2. Plant Prairie Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 153609-01, EEC-1096 Address Repair Organization P.O. No., J ob 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 Edition Addenda ___________ Code Cases__________

(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 IManufacturer Manufacturer INat'l Bd # IOther ID Yr Built C1

7. Description of Work Replaced applicable valve to flange nuts with superbolt material.

8. Tests conducted: HydrostaticE PneumaticD] Nominal Operating Pressure E] Exempt'p]

Other F1 Pressure psi Test Temp. 0F Other:

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.

FOR N 5-2PRAIRIE ISLAND NUCLEAR GENERA TING PLANT ITEM 2-23-030

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 Xl.

Type Code Symbol Stamp A11l Certificate of AuthojJi11 A 4 Expiration Date ________________________

Signed ( ,ASMVE Program Engineer Date ___L___7_A0_1 Owner or Owner's Designee , Title CERTIFICATE OF INSERVICE INSPECTION 1,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 desonrbed in this Owner's Report during the period iD/o9/o& to Wi.2(06o 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 neithe r 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 oronce ihthis inspection.

___ __ __ ___ __ __ __Commissions MA-1 oS$V$3/.e,,

Inspector's Signature National Board, Province and Endorsements Date 1 .2006

,b2c~o~,

Date

FORNI-2OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-23-031

1. Owner Nuclear Management Company, LLC Date 9/22/2006 Name

2. Plant Praire Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 Mod. O2VCO1, EC-07688 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 Edition Addenda ____________ Code Cases ___________

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

6. Identification of Components

7. Description of Work Drilled and tapped holes in charging pump packing assembly gland plates and stuffing boxes/

8. Tests conducted: HydrostaticF- . PneumaticnJ Nominal Operating Pressure F- Exempt pe 0

OtherF- 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 11/2 in. x 11 in., (2) information in items 1through 6 on this report is included on each sheet, and (3)each sheet is numbered and number of sheets is recorded at the top of this form.

EFOM NS-2OWN ER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-23-031

9. Remarks This Repair/Replacement documents the activities completed previously (since -2000) without R/R Plans. This is documented in CAP 1043653.

CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this conforms to the requirements of the ASMVE Code, Section X1.

Type Code Symbol Stamp Xý11 Certificate of Authorization No. /4Expiration Date ________________________

Signed (127ý *., ASME Program Engineer Date __________________

Owner or Owner's Designee , Title CERTIFICATE OF INSERVICE INSPECTION 1,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 c?5EP66 to 0,5 SEpm -

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.

ý-- 0PCommissions

-0 [8/qoys- 4,J' n7A} 2192Y

ýector's Signature In National Board, Province and Endorsements Date A-Lmh,2 2 1\1ý

PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIRI REPLACEMENT ACTIVITYI ITEM 2-23-032

1. Owner Nuclear management Company, LLC Date 1/11/2007 Name

2. Plant Prairie Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 Wyle Labs P.O. 8988 Address Repair Organization P.O. No., Job No., etc

3. Work Performed by Wyle Labs. Inc. Type Code Symbol Stamp N/A Name 7800 Hwy 20 West, Huntsville, AL 35807 Authorization N/A Address Expiration Date N/A

4. Identification of System RC Code Class 1

5. (a)Applicable Construction Code ASME Ill, Class 1 1969 Edition Addenda ______________ Code Cases ,.4 (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 Pressurizer Safety Valve Crosby N57872 1969 Corrected R 0002

7. Description of Work Replaced disc.

8. Tests conducted: Hydrostatic F] PneumaticD] Nominal Operating Pressure F- Exempt FV-Other El Pressure psi Test Temp. 0F Other:

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.

FOR NI-2OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-23-032

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 ,vl14 Certificate of Au4 Expiration Date _______________________

Signed ,ASME Program Engineer Date //~'~7 __

Owner or Owner's Designee ,Title CERTIFICATE OF INSERVICE INSPECTION 1,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. ýave inspected the components described in this Owner's Report during the period 1V//?L/06 - -to O/Lgl

/ 7 and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

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

__________________Commissions AlA,' o-S-V31 /&A, T3 '

Inspector's Signature National Board, Province and Endorsements Date 4e-. /89 ~I o, I

ý00

FOR NI-2OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-23-034

1. Owner Nuclear Management Company, LL-C Date 11/14/2006 Name

2. Plant Prairie Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 303811-01 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 Name Manufacturer Serial #

Nat'l Bd # Other ID Yr Built Corrected, Removed, or IASME jCode

______Installed jStamp 23 Charging Pump Ajax 245-043 1969 CorrectedD

7. Description of Work Replaced packing assemblies.

8. Tests conducted: Hydrostatic [- PneumaticDF- Nominal Operating Pressure F- 'Exempt pvo 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.

FORNI-2OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-23-034

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

Type Code Symbol Stamp Certificate of Authoriz .Expiration Date ________________________

Signed 774,ASMVE Program Engineer Date JV9, Owner or Owner's Designee , Title CERTIFICATE OF INSERVICE INSPECTION 1,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' 111/ 14 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 ^A1d 0-T453/-Co AO3 , 14 Inspector's Signature National Board, Province and E'ndo'rsem6nts Date ILv /~' f

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

.ITEM 2-23-035 1

1. Owner Nuclear Management Company, LLC Date 2/7/2007 Name

2. Plant Prairie Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 154839-11 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 Edition Addenda ____________ Code Cases___________

(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 ECU CHILD WTR RTRN Masoneilan CV-39422 Corrected ED

7. Description of Work Replacement main plug and body to bonnet fasteners.

8. Tests conducted: HydrostaticF- PneumaticDF Nominal Operating Pressure r_ Exempt W-Other El Pressure psi Test Temp. 0F Other: Non-code leakage check per SP-1596 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.

FORM IS-2PRAIRIE ISLAND NUCLEAR GENERATING PLANT ITEM 2-23-035

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&109 Certificate of Autor Expiration Date ________________________

Signed ,ASME Program Engineer Date______

Owner or Owner's Designee , Title CERTIFICATE OF INSERVICE INSPECTION 1,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 1I /040&~ to / 7 -

and state that to the best of my knowledge and belief, the Owner has performed examinations a 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 cnnected with this inspection.

_________________Commissions Md-Ao S'YST3/ A, Inspector's Signature National Board, Province 'and Enidorsements Date -. A4)//-to'7

I PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-23-036 I

1. Owner Nuclear Management Company, LLC Date Name

2. Plant Prairie Island Nuclear Generating Plant Sheet 1 2 of Name 1717 Wakonade Dr. E, Welch Minnesota 55089 99284-07 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 ZX Code Class 3

5. (a) Applicable Construction Code B16.34 Edition Addenda ____________ Code Cases ___________

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

6. Identification of Components

7. Description of Work Replacement main plug.

8. Tests conducted: HydrostaticF- Pneumatic F- Nominal Operating Pressure F- Exempt F/

OtherF Pressure psi Test Temp.

Other: Non-code leakage check per SP-1596 NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. xl1i 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.

FORNI-2OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-23-036

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 A/

Certificate of Auth izai Expiration Date ________________________

Signed : :.ASME Program Engineer Date A, '3 /Id -2 ___

Owner or Owner's Designee , Title CERTIFICATE OF INSERVICE INSPECTION 1,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 t F 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 AIAI oS'/5-3 t d,6 k4.gZtdS Inspeclor's Signature National Board, Province and Endorsements Date

FORM IS-2PRAIRIE ISLAND NUCLEAR GENERATING PLANT ITEM 2-23-037

1. Owner Nuclear management Company, ILLC Date 2/8/2007 Name

2. Plant Prairie Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 154791-1 2, Alteration 92A229 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 (Main Ste Code Class 2

5. (a)Applicable Construction Code B16.34 Edition Addenda ____________ Code Cases ___________

(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 SG MS ISOL CV Schutte and n/a n/a CV-31117 1970 CorrectedD Koerting

7. Description of Work Replaced 5 bonnet studs, 5 nuts, and damaged helicoil. Repaired 4 stud holes w/ helicoil inserts.

8. Tests conducted: HydrostaticF PneumaticD- Nominal Operating Pressure R ExemptD Other DPressure n/a psi Test Temp. n/a 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.

FOR:NI-2OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-23-037

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/' ,JZ Certificate of Authonrzi 9aw -//'o Expiration Date _______________________

Signed ,ASMVE Program Engineer Date ,21,r-le.7__

Owner or Owner's Designee , Title CERTIFICATE OF INSERVICE INSPECTION 1,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-iI o~ to 57/Io1 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 MAIO.SS'/$. A18a -r, ,-1s Inspector's Signature National Board, Province' and Endorsements Date

FORNI-2OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-23-038

1. Owner Nuclear management Company, LL-C Date 12/7/2006 Name

2. Plant Prairie Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 154513-08 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 MlUtilized 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 Heat Exchanger Yuba 69G229-1C 235-031 1969 Corrected ED

7. Description of Work Weld build up of wasted areas in shell and attachment weld areas.

8. Tests conducted: Hydrostatic 1- Pneumatic -] Nominal Operating Pressure Fý Exempt Other Fý 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.

FORNI-2OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-23-038

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

Type Code Symbol Stamp A/

Certificate of Auth Expiration Date ________________________

Signed ,. ASME Program Engineer Date ___________ _____

Owner or Owner's Designee , Title CERTIFICATE OF INSERVICE INSPECTION 1,the undersigned, holding a valid commission issued byIthe 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 ta106 o 3L6 and state that to the best of my knowledge and belief, the Owner has performed 'examiinations 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 orcnetdwith this inspection.

__ __ __ _ __ __ __ _Commissions &W 05V5./31 443;A ,--

Inspector's Signature National Board, Province alnd *Endorsements Date C20040

. ~2oot~~

Date

FORNI-2OWNER'S REPORT FOR REPAIR! REPLACEMENT ACTIVITY ITEM 2-23-039

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

2. Plant Prairie Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 306250-01, EC-9602 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 1989 Edition Addenda ____________ Code Cases ___________

(b) Applicable Edition of Section Xl Utilized for Repair/Replacement Activity 1998E / 2000A (c) Applicable Section Xl Code Cases N-513-2

6. Identification of Components Component Name Manufacturer Manufacturer Nat'l Bd # Other ID Yr Built Corrected, ASME Name Serial # Removed, or Code 1

__________ _________ ______ 2-CL16Installed Stamp CL Pipe Section 24CL1 Corrected I

7. Description of Work installed branch connection in 24" section of pipe.

8. Tests conducted: Hydrostatic F- Pneumatic -1 Nominal Operating Pressure F~ Exempt F-1 Other F1 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.

FOR NI-2OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-23-039

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

Type Code Symbol Stamp I"/

Certificate of Au a' .Expiration Date ________________________

Signed 2 SEProgram Engineer Date 2 _______

Owner or Owner's Designee , Title CERTIFICATE OF INSERVICE INSPECTION 1,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~

/2 /0/ ,y to ol a o0' and state that to the best of my knowledge and belief, the Owner has performned 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/W S'&/3 411 x-Z s Inspector's Signature National Board, Province and Enidorsements Date'_ _ _

(I

FORNI-2OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-23-041

1. Owner Nuclear management Company, LLIC Date 12/14/2006 Name

2. Plant Prairie Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 306550-01 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 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 Boric Acid FLTR Chk Rockwell Edwards 2VC-8-15 Corrected ED

7. Description of Work Re-welded Canopy after BA deposit removal

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

Other El Pressure psi Test Temp. 0F Other: IST test per SP2366 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.

FORNI-2OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-23-041

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

Type Code Symbol Stamp Certificate of Auh Expiration Date ________________________

Signed ,ASME Program Engineer Date _ _

Owner or Owner's Designee , Title CERTIFICATE OF INSERVICE INSPECTION 1,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 _______________ to ___________I and state that to the best of my knowledge and belief, the Owner has performed examinations andf taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

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

~j Inspector's Signature 4Commissions AiA./ cSV-531/ q

,B, &1ZWj~S National Board, Province and Endorsements Date

FORM IS-2PRAIRIE ISLAND NUCLEAR GENERATING PLANT ITEM 2-23-042

1. Owner Nuclear Management Company, LLC Date 2/8/2007 Name

2. Plant Prairie Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 305364-02 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 MS Code Class 2

5. (a)Applicable Construction Code B16.34 Edition Addenda ___________ Code Cases__________

(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 IManufacturer Manufacturer INat'l Bd # IOther ID Yr Built ICorrected, IASME

7. -Description of Work Machined the disc and seat sealing surface.

8. Tests conducted: HydrostaticF PneumaticD Nominal Operating Pressure F- Exempt F-/

Other El Pressure psi Test Temp. 0F Other: Disc leak by in accordance with IST requirements.

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.

FORNI-2OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-23-042

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 Certificate of A, f~ o.- Expiration Date _____ ____________________

Signed L ZASME Program Engineer Date -2?/ 7 _____

Owner or Owner's Designee ,Title CERTIFICATE OF INSERVICE INSPECTION 1,the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Minnesota and employed by. HSB Insp. and Ins. Co. of Connecticut of Hartford Conn. have inspected the components described in this Owner's Report during the period M*. 3.0ý Zcn6 to fZc3. iq acao r and state that to the best of my knowledge and belief, the Owner has performed examinations and take'n 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,41 553 I i Inspector's Signature National Board, Provinde and ýndorsements Date / -4/(. obc)I o~O

FORNI-2OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-23-045

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

2. Plant Prairie Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 154582-05 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 1

5. (a) Applicable Construction Code 8 16.34 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 PRZR RELIEF Crosby Model HB-BP- n/a j2RC-1 0-1 Corrected i 86I

7. Description of Work Replaced inlet flange fasteners.

8. Tests conducted: HydrostaticDF PneumaticD] Nominal Operating Pressure Exempt Other F Pressure n/a psi Test Tem p. n/a 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.

F PRAIRIE ISLAND NUCLEAR GENERATING PLANT FORM N15-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-23-045 I

9. Remarks VT-i completed for 151Summary # 500515 on report number 2006V309.

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 W 1 Certificate of Auth __ _ _Expiration Date __ _ _ _ _ _

Signed 2ASME Program Engineer Date 1/,31/.7__ _

Owner or Owner's Designee ,Title CERTIFICATE OF INSERVICE INSPECTION 1,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 ul/o.41o6 to 0 /7/d/o;,

and state that to the best of my knowledge and belief, the Owner has performed 'exam inations 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%1A1/0551$3/

Inspector's Signature National Board, Provi -nce and Endorsements Date V

FOR:NI-2OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-23-046

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

2. Plant Prairie Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 154582-05 Address Repair Organization P.O. No., Jc)b 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 MVS Code Class 1

5. (a) Applicable Construction Code B16.34 Edition Addenda ____________ Code Cases ___________

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

6. Identification of Components IComponent Name I Manufacturer IManufacturer I Nat'l Bd # I Other ID IYr Built IC,

7. Description of Work Replaced inlet flange fasteners.

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

Other W- Pressure n/a psi Test Temp. n/a 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.

FORNI-2OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-23-046

9. Remarks VT-i completed for Summary # 50711 on report 2006V311 0.

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 Aut _ _ _ Expiration Date __ _ _ _ _

Signed (~~,ASIME Program Engineer Date / a _ _

Owner or Owner's Designee , Title CERTIFICATE OF INSERVICE INSPECTION 1,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_0__7/ __4 to 0,//8/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 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 Mt/v0!9i45 41 Inspector's Signature National Board, Province and Endorsements Date ,ý-.00-L C,

E:M NS-2OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-23-047

1. Owner Nuclear Management Company, LLC Date 12/5/2006 Name

2. Plant Prairie Island Nuclear Generating Plant Sheet 1 2 of Name 1717 Wakonade Dr. E, Welch Minnesota 55089 96871-01 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 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') Bd # Other ID Yr Built Corrected, ASME Name Serial # Removed, or Code Installed Stamp Pressurizer to CV-31229 Bypass Kerotest 2RC-7-1 CorrectedD

7. Description of Work Replaced bonnet.

8. Tests conducted: Hydrostatic 1- PneumaticD- Nominal.Operating Pressure F- Exempt F,/

Other F1 Pressure psi Test Temp. CF 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.

FORM IS-2PRAIRIE ISLAND NUCLEAR GENERATING PLANT ITEM 2-23-047

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 XI.

Type Code Symbol Stamp Ak Certificate of Au 414.- Expiration Date______________________

Signed ,ASME Program Engineer Date ______ ___

Owner or Owner's Designee , Title CERTIFICATE OF INSERVICE INSPECTION 1,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 102/o3/o4 to /a7A/oýh-o6 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 /W,%/ O5 VS3/ q,34~

Inspector's Signature National Board, Province and Endorsements Date 1 C90.06,

FORM IS-2PRAIRIE ISLAND NUCLEAR GENERATING PLANT ITEM 2-23-048

1. Owner .Nuclear Management Company, LLC Date 12/11/2006 Name

2. Plant Prairie Island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 307255-01 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 1

5. (a)Applicable Construction Code 831.1 1967 Edition Addenda n/a Code Cases n/a (b) Applicable Edition of Section Xl Utilized for RepairiReplacement Activity 1998E / 2000A (c) Applicable Section Xl Code Cases None

6. Identification of Components

7. Description of Work Buffed out indication.

8. Tests conducted: HydrostaticE PneumaticD 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.

FORNI-2OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-23-048

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 XI.

Type Code Symbol Stamp 4kAZ4 Certificate of Authoriz Expiration Date _______________________

Signed ,ASME Program Engineer Date 1, X? ___

Owner or Owner's Designee , Title CERTIFICATE OF INSERVICE INSPECTION 1,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 /W2/oi3/o to .2 ///06.

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 A-TA] OSIS'/3//,A Inspector's Signature National Board, Province and Endorsements Date

FORNI-2OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY ITEM 2-23-049

1. Owner Nuclear Management Company, LL-C Date 12/13/2006 Name

2. Plant Prairie island Nuclear Generating Plant Sheet 1 of 2 Name 1717 Wakonade Dr. E, Welch Minnesota 55089 307520-01 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 Xl Code Cases None

6. Identification of Components

7. Description of Work Replaced body to bonnet fasteners.

8. Tests conducted: Hydrostatic F- PneumaticD1 Nominal Operating Pressure FV- Exempt E]

Other Pressure NOP psi Test Temp. NOT 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.

FORM IS-2PRAIRIE ISLAND NUCLEAR GENERATING PLANT ITEM 2-23-049

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 X1.

Type Code Symbol Stamp-41 Certificate of Authorization . 46//4 Expiration Date _______________________

Signed W1k, ASME Program Engineer Date /, /,13 /06_

Owner or Owner's Designee , Title CERTIFICATE OF INSERVICE INSPECTION 1,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 &?/o/a7 ' 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 1WA10,5'/5731 A 'X, A15' Inspector's Signature National Board, Province and En'dorsements Date . -,F' A

L-PI-07-023, Inservice Inspection Summary Report, Interval 4, Period 1, Outage 2, Refueling Outage Dates: 11-15-2006 to 12-15-2006, Fuel Cycle 23: 06-11-2005 to 12-15-2006

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L-PI-07-023, Inservice Inspection Summary Report, Interval 4, Period 1, Outage 2, Refueling Outage Dates: 11-15-2006 to 12-15-2006, Fuel Cycle 23: 06-11-2005 to 12-15-2006

Text

Subject:

SUMMARY

SUMMARY

SUMMARY

1.0 INTRODUCTION

SUMMARY

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SUMMARY

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1.0 Comments

1.0 Comments

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