correspondence control. 'program standard. … · 2012-11-29 · nmc prairie island nuclear...

CORRESPONDENCE CONTROL. 'PROGRAMSTANDARD. DISTRIBUTIONOutgoing Correspondence

Letter Number: U '-l-'7Document Date:- 2 /Z 1(9/07

Date:_______________ Engineer:_<~ I

Document Type: _________ Attached:____________

Subject: !~~S-&1 iI 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 PalmisanoDirector of Site Ops - Dwight Mims -

Plant Manager - Paul HuffmanSite Eng. Dir. - Mike Carlson

_______Bus Support Mgr - Len ClewettOperations Manager - Freddie ForrestNuclear Safety Assurance Mgr - S NorthardPITC 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--10-

______ Jeff Kivi7_______ ~Dale Vincent ___

_______Marlys Davis_______ ~Matt Klee ___

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

______NL File

Records Management

______MSRC File________Terry Sullivan

Hub MillerLiz BogueDennis Koehl

__~~~ ~ ~~~~ I I _ _ _ _ _ _1_ 1 _ _ _ _

*Note: Review the incoming correspondence to determine which individuals received copies directly from theagencies. 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 tothdistribution list. 9-týc7J:\Iicense\distribution packets~outgoing distribution Iist.doc or 1 Updated 21U(JAlicenseWistribution packets\outgoing distribution list.doc Page 1 or 1 U pdated 210 7

NMC Prairie Island Nuclear Generating PlantCommtte to ucler~xeffnceOperated by Nuclear Management Company, LLC

MAR 1 4 2007L-PI-07-02310 CFR 50.55a

U S Nuclear Regulatory CommissionATTN: Document Control DeskWashington, DC 20555-0001

Prairie Island Nuclear Generating Plant Unit 2Docket 50-306License No. DPR-60

Unit 2 Inservice Inspection Summary Report, Interval 4, Period 1, Outage 2. RefuelinqOutage 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 refuelingoutage, an inservice inspection (I51) examination for the first period of the fourth intervalwas conducted. Enclosure 1 is a copy of the ISI examination summary report for thisoutage.

The summary report is being submitted in accordance with the PINGP AmericanSociety of Mechanical Engineers (ASME) Code Section Xl ISI Program and is intendedto satisfy the inspection reporting requirements contained in IWA-6230 of the ASMEBoiler and Pressure Vessel Code.

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

Summary of Commitments

This letter contains no new commitments and no revisions to existing commitments.

iomas J. PalmisanoSite Vice President, Prairie Island Nuclear Generating PlantNuclear Management Company, LLC

1717 Wakonade Drive East * Welch, Minnesota 55089-9642Telephone: 651.388.1121 o 7

Document Control DeskPage 2

Enclosure

cc: Administrator, Region 1ll, USINRCProject Manager, Prairie Island, USINRCResident Inspector, Prairie Island, USNRCChief 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 ENERGYPRAIRIE ISLAND NUCLEAR GENERATING PLANT

1717 WAKONADE DRIVE EASTWELCH, MINNESOTA 55089

OPERATED BY:NUCLEAR MANAGEMENT COMPANY, LLC

700 FIRST STREETHUDSON, WISCONSIN 54016

INSERVICE INSPECTION SUMMARY REPORTINTERVAL 4, PERIOD 1, OUTAGE 2

REFUELING OUTAGE DATES: 11-15-2006 TO 12-15-2006UNIT 2, FUEL CYCLE 23: 06-11-2005 TO 12-15-2006

COMMERCIAL SERVICE DATE: DECEMBER 21, 1974

Preparedby:

Reviewedby:

Reviewedby:

Reviewedby:

Reviewedby:

Reviewedby:

rga m Eniner, u cera Mangement Co.4 Proar

Shannon Hanson

Steam Generator EC I Engineer, Nuclear Management Co.

Scott Redner

Repair/Replacement Program Engineer, Nuclear Management Co.

Ron Glow

I rogram Engineer, Nuclear Management Go.

Ryan Cox

Jerry Wren

Date: D

Date: A 47

Date: 07__

Date: 6e7

Date: Z/-z.//7

Date: '2- 73-o0--V

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

Lora Drenth

Reviewedby: 9ur er inV er, Nuclear Managehwf o

Reviewed Zýby: Program Engine-eringgMa-nager, u lear Management Go.

Steve Skoyen

Date: 2-/_Z___'

Date: IZ' 12-0 -7

Date: _2-Z7-0

Date: ZfS07Approvedby: i-rector /o ngineering, Nuclear Management Go.

Mike Carlson

. M4

NUCLEAR MANAGEMENT COMPANYPRAIRIE ISLAND UNIT 2 CYCLE 23

INSERVICE INSPECTIONSUMMARY REPORT

Table of Contents

Number of Pages

Section 1.

Section 2.

Section 3.

Section 4.

Section 5.

Section 6.

Section 7.

Section 8.

Discussion

Form NIS-1, Owner's Report for Inservice Inspection

ISI Examinations

IWE Examinations

Pressure Tests

Snubber Inservice Testing and Preservice Examinations

Steam Generator Eddy Current Examination Results

Repair/Replacement Activities for Fuel Cycle 23

2

3

11

2

66

NUCLEAR MANAGEMENT COMPANY INSERVICE INSPECTIONPRAIRIE ISLAND UNIT 2 CYCLE 23 SUMMARY REPORT

Section 1. Discussion

1.0 INTRODUCTION

This summary report identifies the class 1 and 2 components examined, theexamination methods used, the examination number and summarizes theexamination results performed during the 1st period of the 4th interval, unit 2 fuelcycle 23. The 4th inspection interval is based on the examination requirements ofthe ASME Boiler and Pressure Vessel Code Section XI, 1998 Edition with 2000addenda.

2.0 PERSONNEL

Visual and nondestructive examinations were performed by Nuclear ManagementCompany, Lambert MacGill Thomas Inc. (LMT), Westinghouse, Areva, MoreTech,Hudson Global Resources and Zetec Inc. The Hartford Steam Boiler Inspection andInsurance Company of Connecticut, provided the Authorized Inspection services.Examination personnel certifications are maintained on file by Nuclear ManagementCompany.

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 examinationnumber 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) arealso included in this section. There were no examinations with indications requiringevaluation, scope expansion or repa ir/rep la cement. There were no "LimitedExaminations" performed during the cycle.

Section 4 contains the Class MC evaluations that required reporting per1OCFR5O.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 XI1992 Edition and 1992 Addenda, and 10 CFR5O.55a dated Tuesday, September 30,1997.

Section 5 contains the pressure test results. All indications of leakage wereevaluated and corrective measures performed as required by IWB-3142, IWC-3132and IWA-5250. Pressure tests that have not yet been completed but will becompleted prior to the end of the period, will be documented in the 4 th interval, 2nd

period, 1 st outage 90 day summary report.

Section 1. DiscussionPae1o2 Page 1 of 2


Section 6 contains the Snubber inspection results. There were no visual snubberfailures. All snubbers that underwent functional testing had satisfactory resultstherefore no scope expansion was required

During the refueling outage, Eddy Current examinations of 21 and 22 SteamGenerators tubes were performed. The examination results are included in Section7.

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

4.0 EXAMINATION REPORTS, EQUIPMENT AND MATERIALS

The inservice inspection reports in Section 3 and 4 contain references toprocedures, equipment, and materials used to complete the specific examinations.Copies of the examination reports, examination procedures, and equipment recordsare available from Nuclear Management Company.

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

CAP = Corrective Action ProcessCE = Condition EvaluationGEG = Geometry, evaluation of indicationOPR = Operability RecommendationIN = Information NoticeIND = Indication requires further evaluationNAD = No Apparent DefectsSE = Safety EvaluationWO = Work Order

Section 1. DiscussionPae2o2 Page 2 of 2



Section 2. NIS-1 (3 pages)

Section 2. NIS-1Pgeo 3Page 1 of 3

Pý1!-.(. I -I .'F0 R MI N IS- I

OWNEI'S REPORI'FOR INSIKRVI( ' INSPECT IONS

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 U required) N/A

5. Commiercial Service Date 12/2

6. National Board Number har Unit N/A

7. Cormponents Inspected

F Comiponient or Maind'licturer orApp~urtenance Installer

1/1974

Reactor Vessel Creiot-L~oire

Pressurizer Westinghouse

21I Steam Generator Westinlghouse

22 Steam Generator Westinghouse

N antiitlcrctlj mr Iuisial icrScijal No.

1191

1182

IState or 'lNo.

*-' NIINN--2i,-ii--5 I

1,5-1')

(,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) - I14321 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 TankINAVCO I-..

8. Examination Dates 6/11/2005

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

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

11. Applicable Edition of Section XI 1998

to 12/15/2006

to 12/20/2007

to 12/20/2014

Addenda 2000

N IS-1 2 at 2

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, 1 a ~ Con and .

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;111 AN ieijiiiti tIn'

the ASMI: Code, Section X1, and c) corrective mecasures talk-en coniitliiii to IIIe rides 01 111k ASM 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

11, theundersignedl, holding a valid commission issued by the National B oar d olHiletIrand t'ressmie Vessel 1I iSpedi :11) fiil te StAiC Mr 'rA)ViiCe Ot

and emlolslyed by H; Ze 7-.CO - -C - have inspected thle ConinponieminS deCSCribed in this O wnier's R~epil dmmiill ti

- ~~to , - and state that it)t fle best of'in~ kiiowledge and bet ic'fitle Ownvmer his p)

examinations and teats and taken corrective mneasuires descirbed in this O wner's Report in accor[dance witth the inspectio pilian aind as reqignred t i ISection NJ.

By signing this certificate neither the Inspector nor his employer makes any' warranty' , expressed or implied, Concerninig tlie exaniimiatiolis. tests. aimeasures described in this Owner's Report. Furthenmore, neither the Inspector nlor his employer shall he liable in anY mannler fin- any persoiial ilitlidamage 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

Date qk77

lie pci miod

cit 6oilcd

tie \S.\tt Code

)il corrIeci i very oi roet

or

lit's



Section 3. ISI Examinations (11 pages)

Section 3. ISI Examinations Pg f1Page 1 of 11

of 7Attachment 1

Inservice Inspection ReportInterval 4, Period 1, P12RF2006

1. Owner: Nuclear Management Company,700 First Street2. Plant: Prairie Island Nuclear Generating Plant, 1717 Wa3. Plant Unit: 2

4. Owner Certificate of Authorization (if Req.): N/A5. Commercial Service Date: 12/21/19746. National Board Number for Unit: N/A

Procedure Method/Report/ResulIts System Dwg/ISO Exam DateSummary No. Comp. ID Cornp. Desc. ItemClass I Category B-B501482

501536

501594

Class 1505008

505024

505025

505026

505027

505028

505029

Class 1500091

w- 1

W- 2

W- 3

Category B-DN- 6 IR

N- 1 IR

N- 21R

N-31IR

N- 4 IR

N-51IR

N- 61R

Category B-CB- 1

Cap-Integral Tubesht



Nozzle Inner Radius

Nozzle Inner Radius

Nozzle Inner Radius

Nozzle Inner Radius

Nozzle Inner Radius

Nozzle Inner Radius

Nozzle Inner Radius

i-2Valve Bolting (16)

B2.60

B2.60

B2.60

B3.140

B3.160

B3.160

B3.160

B3.160

B3.160

B3.160

B7.70

SWI NDE-VT- VT4.0SWI NDE-VT- VT4.0SWI NDE-VT- VT4.0

SWI NDE-UT-5 UT

SWI NDE-VT- VT4.0SWI NDE-VT- VT4.0SWI NDE-VT- VT4.0SWI NDE-VT- VT4.0SWI NDE-VT- VT4.0SWI NDE-VT- VT4.0

2006V507

2006V508

2006 V509

2006U1 83

2006V51 0

2006V51 1

2006V51 2

2006V51 3

2006V514

2006V515

NAD

NAD

NAD

NAD

NAD

NAD

NAD

NAID

NAD

NAD

VO

VO

VO

SG

VC

VC

VC

VC

VC

VC

RH

RH

2-ISI1-34

2-ISI-34

2-ISI-34

2-ISI-37A

2-ISI1-34

2-ISI1-34

2-ISI1-34

2-ISI-34

2-ISI-34

2-ISI-34

12/13/2006

12/13/2006

12/13/2006

12/6/2006

12/13/2006

12/13/2006

12/13/2006

12/13/2006

12/13/2006

12/13/2006

SWI NDE-VT- VT 2006V296 NAD1.0SWI NDE-VT- VT 2006V297 NAD1.0

Comments:

500515

Comments:

500711

Comments:

Class 1521299

Class 1

Inservice exam,2006V297 was performed as required due to valve disassembly. Preservice exam 2006V296 was peformed following WO 96881-01

8- 1 Flange Bolts 87.50 SWI NDE-VT- VT 2006V309 NAD RC1.0

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

B- 1 Flange Bolts 87.50 SWI NDE-VT- VT 2006V310 NAD RC1.0

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

2-IS I-10OC 11/24/2006

2-ISI-10C 11/25/2006

that replaced two studs and nuts

2-ISI-30A 12/3/2005

2-ISI-30B 12/3/2006

2-ISI-20A 11/22/2006Category B3-K

H-4/IA Int. Attach. Restraint & Support]

Category B-M-2B10.20 SWI NDE-PT-1 PT 2006P017 NAD RC

of 7

Attachment 1Inservice Inspection Report

Interval 4, Period 1, P12RF20061. Owner: Nuclear Management Company,700 First Street2. Plant: Prairie Island Nuclear Generating Plant, 1717 Wa3. Plant Unit: 2

Summary No. Comp. ID Comp. Desc. Item

4. Owner Certificate of Authorization (if Req.): NIAS. Commercial Service Date: 12121119746. National Board Number for Unit: N/A

Procedure Method/Report/ResulIts System DwgIISO Exam Date505423

Class I505619

Class 1500055

501106

501299

501365

512606

Class I501113-RI

501123-RI

501126-RI

501521-RI

501522-RI

501583-RI

V-i1 Valve Int Surfaces

Category B-N-IRV- 1 Interior

Category F-AH-4 Support

H- 1 Restraint

H- 4 Restraint & Support

B 12.50

1313.10

Fil10b

Fil10a

Fli10b

H-66

H-1 4

Category R-AW- 4

W- 5/2LSD

W- 2

W- 9

W- 3

W- 5

Double Snubber/Clamp

Column 2

Pipe To 50 Red Elbow

Pipe To Elbow

Pipe To Pipe

Pipe to Elbow

Fli10c

F1.40

R1 .20-4

R1 .20-4

R1 .20-4

R1 .20-4

SWI NDE-VT-3.0

SWI NDE-VT-5.0

SWI NDE-VT-2.0SWI NDE-VT-2.0SWI NDE-VT-2.0SWI NOE-VT-2.0SWI NDE-VT-2.0SWI NDE-VT-2.0

SWI NDE-UT-11SWI NDE-UT-I1I

SWI NDE-UT-11SWI NDE-UT-1 6ASWI NDE-UT-1 6ASWI NDE-uT-1 6ASWI NDE-UT-1 6ASWI NDE-UT-1 6ASWI NIJE-UT-1 6ASWI NDE-UT-1 6ASWI NOE-UT-1 6A

VT

VT

VT

VT

VT

VT

UT

UT

UT

UT

UT

UT

UT

UT

UT

UT

UT

VT 2006V298 Accept

VT 2006 V299 NAD

2006V307

2006V295

2006V294

2006 V494

2006V301

2006V490

2006U099

2006U098

2006U1.26

20061.1149

2006J1.50

2006U151

2006U1.82

2006U1.81

2006L1-74

2006U1.73

2006U 172

NAD

NAD

NAD

NAD

NAD

NAD

NAD

NAD

NAD

NAD

NAD

NAD

NAD

NAD

NAD

NAD

NAD

RH

RC

RC

SI

RC

RC

SI

SG

RC

RC

RC

RC

RC

RC

RC

RC

RC

RC

RC

2-IS1-i100 11/25/2006

2-ISI-42

2-ISI-14

2-ISI1-23

2-ISI-20A

2-ISI-20A

2-I151i1

2-ISI1-37C

2-IS I-32A

2-IS I-32B

2-ISI1-32C

2-ISI-17

2-ISI1-17

2-ISI-17

2-IS I-20A

2-ISI-20A

2-ISI1-27

2-ISI1-27

2-ISI-27

11/24/2006

11/29/2006

11/22/2006

11/22/2006

12/8/2006

11/24/2006

12/6/2006

11/23/2006

11/23/2006

11/23/2006

11/23/2006

11/23/2006

11/23/2006

12/6/2006

12/6/2006

11/29/2006

11/29/2006

11/29/2006

Pipe to 45 Elbow

Pipe to Elbow

R1 .20-4

R1 .20-4

of 7



Summary No. Comp. ID Comp. Desc. Item


Method/Report/Resu Its System Dwg/ISO ExamIProcedure Date501 856-RI W-1 0 Elbow to Pipe R1. 11-2 SWI NDE-uT- UT 2006U166 NAD

1 6A

501865-RI

501 897-Rl

501956-RI

501998-RI

502025-RI

502039-RI

502082-RI

502165-RI

W-1 0

W- 9

W- 8

W- 7

W- 6

W- 5

W- 4

W-1 7

Tee to Pipe

Pipe to Elbow

45 Elbow to Pipe

Pipe to 45 Elbow

Pipe to Pipe

Elbow to Tee

Pipe to Elbow

Safe End To Nozzle

R1 .20-4

Ri. 11-2

R1. 11-2

SWI NDE-UT-1 6A

SW) NDE-UT-1 6A

SWI NDE-UT-1 6A

SWI NDE-UT-1 6A

SW) NDE-UT-1 6A

SWI NDE-uT-1 6A

SW) NDE-UT-1 6A

SW) NDE-UT-1 6A

SW) NDE-UT-1 6A

SW) NDE-uT-1 6A

SWI NDE-UT-1 6ASW) NoE-uT-1 6ASWI NDE-UT-1 6ASW) NOE-UT-1 6ASWI NDE-UT-1 6ASWI NDE-UT-1 6ASWI NDE-UT-1 6ASWI NDE-UT-1 6ASWI NDE-uT-1 6AFP-PE-NDE-410

UT

UT

UT

UT

UT

LIT

UT

UT

UT

UT

UT

LIT

UT

UT

UT

LIT

UT

UT

UT

UT

2006U 164

2006U 165

2006U110

2006U 109

2006U 161

2006U1 62

2006U 163

2006U1 59

2006U 158

2006U1 60

2006U 167

2006U1 69

2006U 168

2006U 170

2006U 171

2006U1.16

2006U117

2006W 115

2006U114

2006U097

NAD

NAIJ

NAD

NAD

NAD

NAD

NAD

NAD

NAD

NAD

NAD

NAD

NAD

NAD

NAD

NAD

NAD

NAD

NAD

NAD

RC

RC

RC

RC

RC

RC

RC

RC

RC

RC

RC

RC

RC

RC

RC

RC

SI

SI

SI

SI

RC

2-ISI-1 3A

2-IS I-13A

2-ISI1-27

2-ISI-27

2-ISI-1 3A

2-ISI-1 3A

2-ISI-1 3A

2-ISI-1 3A

2-ISI-1 3A

2-ISI-1 3A

2-ISI-1 3A

2-ISI-1 3A

2-IS I-i3A

2-ISI-1 3A

2-ISI-1 3A

2-IS I-22A

2-ISI-22A

2-ISI-22A

2-ISI-22A

2-ISI-3 1

2-ISI-13A 11/27/2006

11/27/2006

11/27/2006

11/23/2006

11/23/2006

11/27/2006

11/27/2006

11/27/2006

11/27/2006

11/27/2006

11/27/2006

11/27/2006

11/27/2006

11/27/2006

11/27/2006

11/27/2006

11/24/2006

11/24/2006

11/24/2006

11/24/2006

11/20/2006

R1.11-2

Rl-11-2

R1 .20-4

R1 .20-4

R1.15-2

of 7



Summary No. Cornp. ID Comp. Desc.

4. Owner Certificate of Authorization (if Req.): NIA5. Commercial Service Date: 12/21119746. National Board Number for Unit: N/A

ort/Results System Dwg/ISO ExamIItem Procedure Method/Rep Date502193-RI W- 3 Pipe to Elbow R1. 11-2 SWI NDE-uT- UT 2006U104 NAD

1 6A

502194-RI

502222-RI

502226-RI

502250-RI

502271 -RI

502316-RI

502330-RI

W- 5

W- 6

W- 4

W- 5

W- 6

W-21

Pipe To 45 Elbow

Elbow To Pipe

R1 .20-4

Ri .20-4

R1.1 1-2Elbow to Pipe

Pipe to 45 Elbow R1. 11-2

SWI NDE-uT-1 6ASWI NDE-UT-1 6A

SWI NDE-LJT-1 6ASWI NDE-UT-1 6A

SWI NDE-UT-1 6ASWI NDE-UT-1 6ASWI NDE-UT-1 6ASWI NDE-UT-1 6ASWI NDE-uT-1 6ASWI NDE-UT-1 6ASWI NDE-UT-1 6ASWI NDE-UT-1 6ASWI NDE-UT-1 6ASWI NDE-UT-1 6ASWI NDE-UT-1 6ASWI NDE-UT-1 6ASWI NDE-UT-1 6ASWI NDE-UT-1 6A

SWI NDE-UT-1 6A

SWI NDE-UT-1 6A

UT

UT

UT

UT

UT

UT

UT

UT

UT

UT

UT

UT

UT

UT

UT

UT

UT

UT

UT

UIT

20061-1105

2006U1 03

2006U 128

2006U1 27

2006U1 113

2006U1.25

20061-1106

2006U1,07

2006U1 08

20061.1121

2006U1 20

2006U 119

2006U1 23

20061.1124

2006U1-18

2006U1 52

2006U1 54

2006U 153

2006U1-57

2006U1 55

NAD

NAD

NAD

NAD

NAD

NAD

NAD

NAD

NAD

NAD

NAD

NAD

NAD

NAD

NAD

NAD

NAD

NAD

NAD

NAD

RC

RC

RC

RH

RH

RH

RH

RC

RC

RC

RC

RC

RC

RC

RC

RC

RC

RC

RC

RC

RC

2-ISI-7F

2-ISI-7F

2-IS I-7F

2-ISI-1 0B

2-ISI-10B

2-IS I-10B

2-ISI-10B

2-ISI-7F

2-ISI-7F

2-ISI-7F

2-IS I-7F

2-ISI-7F

2-IS I-7F

2-IS I-7F

2-ISI-7F

2-IS I-7F

2-ISI-15

2-ISI-15

2-ISI1-15

2-ISI-15

2-ISI1-15

11/23/2006

11/23/2006

11/23/2006

11/25/2006

11/25/2006

11/25/2006

11/25/2006

11/23/2006

11/23/2006

11/23/2006

11/23/2006

11/23/2006

11/23/2006

11/23/2006

11/23/2006

11/23/2006

11/23/2006

11/23/2006

11/23/2006

11/23/2006

11/23/2006

Elbow to Pipe R1.1 1-2

Elbow to Pipe R1 .20-4

W-20 Pipe to Elbow R1 .20-4

of 7Attachment 1



4. Owner Certificate of Authorization (If Req.): N/A5. Commercial Service Date: 12/21/19746. National Board Number for Unit: N/A

Summary No. Comp. ID Comp. Desc. Item Procedure Method/Report/ResulIts System Dwg/ISO Exam Date

502342-RI

502352-RI

502359-RI

502371-RI

502446-RI

502485-RI

502492-RI

W- 2

W- 3

W- 3

W- 4

w-l1

W-1 3

W- 12

Pipe to Elbow

Elbow to Pipe

Pipe to Elbow

Elbow to Pipe

Pipe to Elbow

R1 .20-4

Ri .20-4

Ri1.20-4

R1 .20-4

SWI NDE-UT-1 6ASWI N!)E-uT-1 6ASWI NDE-UT-1 6ASWI N!)E-UT-1 6ASWI NDE-UT-1 6ASWI NDE-UT-1 6ASWI N!)E-UT-1 6ASWI NDE-UT-1 6ASWI N!)E-uT-1 6ASWI NDE-UT-1 6ASWI N!)E-UT-1 6ASWI N!)E-UT-1 6ASWI N!)E-UT-1 6ASWI N!)E-UT-1 6ASWI N!)E-UT-1 6ASWI N!)E-UT-1 6A

R1.11-5

UT

UT

UT

UT

UT

UT

UT

UT

UT

UT

UT

UT

UT

UT

UT

UT

UT

2006U1 89

2006U1-88

20061J184

2006U1-85

20061.1191

2006U1 90

20061.1187

2006U 186

2006U1J36

2006U 137

2006U 135

20061.1134

2006U1 33

2006U 129

2006U1 30

UT 20061-156 NAID

NA!)

NA!)

NA!)

NAID

NA!)

NAID

NA!)

NA!)

NA!)

NA!)

NA!)

NA!)

NA!)

NA!)

NAD

RC

RH

RH

RH

RH

RH

RH

RH

RH

Vo

Vo

Vo

vc

vc

vc

vc

SG

SG

SG

2-ISI-1 5

2-ISI-1 OC

2-ISI-10OC

2-ISI-10OC

2-ISI-1 OC

2-IS I-20C

2-ISI-20C

2-IS I-20C

2-ISI-20C

2-ISI-1 3B3

2-ISI-1 3B

2-ISI-1 38

2-ISI-1 3C

2-ISI-1 3C

2-ISI-1 3C

2-ISI-1 3C

2-ISI-37A

2-ISI-37A

11/23/2006

12/7/2006

12/7/2006

12/7/2006

12/7/2006

12/7/2006

12/7/2006

12/7/2006

12/7/2006

11/29/2006

11/29/2006

11/29/2006

11/28/2006

11/28/2006

11/28/2006

11/28/2006

11/29/2006

11/29/2006

Pipe to Reducer

Reducer to Pipe

R1. .11-5

R1. 11-5

Class 2 Category C-A502628 W-H Top Head to Shell C1.20 SWI N!)E-UT-

15SWI N!)E-UT-15

20061.1142 NA!)

20061-141 NA!)

Class 2 Category C-B501017 N- 1 IR FW Nozzle Inner Radii

502678 N- 1 Feedwater Nozzle

C2.22 SWIN!)E-UT- UT 20061-122 NA!)13

2-ISI-37B 11/22/2006

C2.21 SWI N!E-MT-1 MT 2006MV007 NA!) S -S-7B 1/220SG 2-ISI-37B 11/22/2006

of 7



Summary No. Comp. ID Cornp. Desc. Item

4. Owner Certificate of Authorization (if Req.): NIA5. Commercial Service Date: 12121/19746. National Board Number for Unit: N/A

Procedure Method/Report/ResulIts System DwgIISO Exam )ateSWI NDE-UT- UT 2006UI01 NAD15

SWI NDE-UT-15SWI NDE-MT-1

UT

MT

2006U102 NAD

2006MV009 NAD

SG

SG

SG

2-ISI-37B 11/22/2006

2-ISI-37B

2-ISI-37B

2-ISI-70

11/22/2006

11/29/2006

11/22/2006Class 2 Category F-A501367 H- 3 Snubber F1.20c SWI NIJE-VT- VT 2006V293 NAD

2.0SI

Comments:

502643

Comments:

502647

520695

Comments:

520932

520990

Comments:

Class 2505062-RI

505099-RI

5051 00-RI

Preservice examination to work order 0157371.

H- 1 Snubber 1

Preservice examination to WO 157599-01.

H- 1 Snubber 1

H-i10A Double Snubber/Clamp

Preservice examination to WO#0157365

H-6A Double Snubber/Clamp

H-8A Double Snubber/Clamp

Preservice exam to WO 0 157373.

F1.40

F1.40

F1.20c

F1.20c

Fl .20c

SWI NDE-VT-2.0

SWI NDE-VT-2.0SWI NDE-VT-2.0

SWI NDE-VT-2.0SWI NDE-Vr-2.0

VT 2006V308 NAD SG 2-ISI-37C 11/29/2006

VT

VT

VT

VT

2006 V306 NAD

2006 V305 NAD

2006 V304 NAD

2006 V300 NAD

SG

FW

2-ISI-37D

2-ISI1-48

11/29/2006

11/25/2006

11/28/2006

11/24/2006

MVS

MVS

2-IS I-47B

2-ISI-46A

Category R-AW-1 8

W-20

W-21



SWI NDE-UT-1 6A

SWI NDE-UT-1 6ASWI NDE-UT-1 6A

SWI NDE-UT-1 6A

SWI NDE-UT-1 6A

SWI NDE-UT-1 6ASWI NDE-UT-1 6A

UT

LIT

UT

UT

UT

UT

UT

2006U091

2006U090

2006U089

20061-1111

2006U1 00

20061J112

2006U 177

NAD

NAD

NAD

NAD

NAD

NAD

NAD

SI

SI

SI

SI

SI

SI

SI

2-ISI-90A

2-ISI-90A

2-ISI-90A

2-IS I-90B

2-ISI-90B

2-IS I-90B

2-ISI-90B

11/14/2006

11/14/2006

11/14/2006

11/18/2006

11/18/2006

11/18/2006

11/30/2006Pipe to Elbow R1 .20-4

of 7Attachment 1



Summary No. Comp. ID Cornp. Desc.


Method/Report/ResulIts System Dwg/ISO ExamIItem Procedure DateSW, NL)E-UI- UT 2006U180 NAD1 6A

SI 2-ISI-90B 11/30/2006

505103-RI

505117-RI

505239-RI

505240-RI

505357-RI

505427-RI

W-24

W- 8

W- 9

W-1 0

W- 4

W-23

Reducer to Pipe

Elbow to Pipe

R1 .20-4

R1 .20-4

Pipe to Elbow R1 .20-4

SWI NDE-UT-1 6ASWI NDE-UT-1 6ASWI NDE-UT-1 6ASWI NDE-UT-1 6ASWI NDE-UT-1 6ASWI NDE-UT-1 6ASWI NDE-UT-1 6ASWI NDE-UT-1 6A

SWI NDE-UT-1 6A

SWI NDE-UT-1 6A

SWI NDE-uT-1 6A

SWI NDE-UT-1 6ASWI NDE-UT-1 6ASWI NOE-UT-1 6ASWI NDE-UT-1 6ASWI NDE-UT-1 6ASWI NDE-UT-1 6AS\M NDE-UT-1 6A

UT

UT

UT

UT

UT

UT

UT

UT

UT

UT

UT

UT

UT

UT

UT

UT

LIT

UT

2006J1 79

2006U1 78

2006U1 76

2006J1 75

2006U 145

2006U144

2006U1 43

2006U1 39

2006U 140

2006U1 38

2006U 148

2006U 146

2006U1 47

2006U094

2006U092

2006U093

2006U1 31

2006U1 32

NAD

NAD

NAD

NAD

NAD

NAD

NAD

NAD

NAD

NAD

NAD

NAD

NAD

NAD

NAD

NAD

NAD

NAD

2-ISI-90B

2-ISI-90B

2-IS I-90B

2-ISI-90B

2-ISI-90C

2-ISI-90C

2-ISI-90C

2-ISI-94A

2-ISI-94A

2-ISI-94A

2-IS I-94A

2-ISI-94A

2-ISI-94A

2-ISI-93A

2-ISI-93A

2-IS I-93A

2-ISI-90C

2-ISI-90C

11/30/2006

11/30/2006

11/30/2006

11/30/2006

11/28/2006

11/28/2006

11/28/2006

11/28/2006

11/28/2006

11/28/2006

11/28/2006

11/28/2006

11/28/2006

11/14/2006

11/14/2006

11/14/2006

11/28/2006

11/28/2006


Pipe to Elbow Ri .20-4

Pipe to Pipe R1 .20-4

Nuclear Management CompanyPrairie Island Unit 2

Completion Code Compliance Summary - 4th Interval - 1st PeriodISI - Code Edition - 1998 Edition, 2000 Addenda

PERIOD 1TOTAL# TOTAL# NUMBER PERCENT

PERCENT REQUIRED PERCENT REQUIRED COMPLETED jCOMPLETETOTAL REO'D FOR FOR REQ'D FOR FOR 1ST FOR 1ST jFOR 1IST

CAT ITEM CODECASE POPULATION INTERVAL INTERVAL 1ST PERIOD PERIOD PERIOD PERIOD

B-A Bill1 3 100% 3 0% 0 0 0%

B-A 81.21 1 100% 1 0% 0 0 0%

B-A B31.30 N-623 1 100% 1 0% 0 0 0%

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

B-B 82.60 RR-4-2 3 600% 18 One-third 6 6 One-third

Total: 6 5 16-50% 2 2 40%

8-0 B3.100 N-648-1 N- 6 100% 6 0 0521

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

8-0 83.90 N-521 6 100% 6 0 0

Total: 27 9 16-50% 2 2 22%

B-G-1 86.10 48 100% 48 0-34% 0-16 16 33%

B-G-1 86.180 48 *0 0 0%

B-G-1 836.190 2 0 0 0%

8-G-1 86.30 48 100% 48 0-34% 0-16 16 33%

8-G-1 86.40 48 100% 48 0-100% 0-46 0 0%

B-G-1 86.50 48 100% 48 0-34% 0-16 16 33%

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%

8-0-2 87.60 2 1 100% 1 1 100%B-G-2 87.70 9 groups as 5 100% 5 5 100%

defined by 8-M-2

Total: 34 5 16-50% 1 1 20%

B-K 810.10 3 2 0 0

B-K 810.20 41 10% 4 1 1

Total: 3 6 16-50% 1 1 17%

NOTES

Deferral allowed per Table IWB-2500-1



Limited to one of each~ similar vessel

Each item to be examined once each outage

Total percentage completed excludes 82.60


Each item to be examined once each outage


Total percentage completed for B3.120 and 83.140. Other items NA


Only required when required by 8-L-2

Only required when disassembled


Deferral allowed per Table IWNB-2500-1

Deferral allowed per Table IWVB-2500-1

Only required if flange disassembled or bolting removed

Only required when required by 8-L-2

Only required when required by B-M-2

Total percentage completed for 87.20 and 87.30. Other items NA

Only one welded attachment of one of the multiple vessels shall be examined

Page 1 of 3



PERIOD 1TOTAL#U TOTAL # NUMBER PERCENT

PERCENT REQUIRED PERCENT REQUIRED COMPLETED COMPLETE

TOTAL REO'D FOR FOR REO'D FOR FORI1ST FORI1ST FOR 1STCAT ITEM CODECASE POPULATION INTERVAL INTERVAL 1ST PERIOD PERIOD PERIOD PERIOD

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%

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%

Total: 1 1 1 100%

B-N-2 813.50 1 100% 1 0- 100% 0-1 0 0%

B-N-2 813.60 1 100% 1 0-100% 0-1 0 0%

Total: 2 2 0-100% 0-2 0 0%

B-N-3 B13.70 1 100% 1 0- 100% 0-1 0 0%

Total: 1 0-100% 0-1 0 0%

B-0 814.10 40 10% 4 0-100% 0 0 0%

Total: 40 0-100% 0 0 0%

B-P 815.00 Multiple 2 600% 12 One-third 4 4 One-third

Total: 2 One-third 4 4 One-third

B-0 816.20

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%

NOTES

Only requiercl when disassembled

All accessible areas to be examined each period.




Deferral allowed per IWB-241 2(a)(3)

2 pressure testing procedures required each outage

SG Tubing inspections are performed iaw the Technical Requirements Manual Section, 5.5.8

Page 2 of 3



PERIOD 1TOTAL# TOTAL # NUMBER PERCENT

PERCENT REQUIRED PERCENT REQUIRED COMPLETED COMPLETETOTAL REQ'D FOR FOR REQ'D FOR FOR 1ST FORI1ST FOR 1ST

CAT ITEM CODECASE POPULATION INTERVAL INTERVAL 1IST PERIOD PERIOD PERIOD JPERIOD

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%

C-H CT00 N-533-1 12 300% 36 One-third 12 9 25%

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 5F-A F1.400Class 1 17 50% 9 4 4

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

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%

NOTES

At least 16% must be completed in 2nd period since 1 st period completion greater than 34%

Some exams not yet complete. These exams required to be completed by 2/20/2007. These examswill be outlined during the following summary report

* Class 1 F-A were also prorated over each system as required by footnote (2) of Code Table WEF-2500-1

*Class 2 F-A were also prorated over each system as required by footnote (2) of Code Table IWF-2500-1

Page 3 of 3


Section 4. IWE Examinations (2 pages)

The following evaluation is being performed per 1 OCFR5O.55a(b)(2)(ix)(D) as analternative to IWE-2430, Additional Examinations. The three indications reported beloware of a similar type on penetrations with the same service conditions.

Summar # Component ID Report Number600661 C37A 2006V473600663 C37C 2006V475600664 C37D 2006V476

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

* The rust is only being seen on the annulus side of each penetration. Themajority 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. Nopitting 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 thepenetrations should be recoated during the next refueling outage. Work Request00017404 was initiated to recoat the penetrations during 2R25.

* There are eight penetrations associated with the Fan Coil Units, one supply andreturn for each of the four Fan Coil Units. These are the only penetrationssusceptible to the condensation related corrosion due to cold water flowingthrough the penetrations. All eight of these penetrations are having examinationsperformed in accordance with the requirements of Table IWE-2500-1,Examination Category E-C and are inspected each period. All eight of thepenetrations were inspected during 2R24. These three penetrations were theonly that had indications. Because all susceptible penetrations were examinedno 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 shell600476 G66 2006 V492 Approximately 0.5" tear which does not

Section 4. IWE ExaminationsPae1o2 Page 1 of 2


extend to the containment shell600477 G67 ý2006 V493 Approximately 1.5" tear which extents to

the containment shellDuring 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 barrierand cause damage. The damaged found during this outage appears to be new. Eachoutage a 100% inspection of the moisture barrier is performed by SP 2123 in order toidentify and repair any areas where damaged was caused by stored equipment. Theseareas were identified by this inspection, an 151 inspection was then completed prior tothe repair. All areas have been identified by SP 2123 and repaired;, no additional orsuccessive inspections are required as a result of this indication.

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

Summary Component ID Report #600669 S-84A 2006V481600670 S-87A 2006V482600671 S-.73B 2006V483600672 S-77A 2006V484600674 C6C 2006V485600675 C7C 2006V486600676 C7D 2006V487-600677 C6D 2006V488

VT-i inspections were performed on all of these components and identified there hasbeen no change since the last inspection. The condition was initially reported in the2003 Unit 2 outage Summary Report.

The coatings degradation is limited to the penetration and the immediate area aroundthe penetrations. The heat from the feedwater and main steam piping causes blisteringof the paint. Any contact with the blistered paint results in flaking and pealing. Underthe pealing and flaking paint the primer is intact with no signs of degradation. Nocorrective actions are required to maintain the integrity of the structure as the blisteringcondition does not affect the structural integrity of the containment. All susceptibleareas are currently on an Augmented inspection schedule so no additionalexaminations are required.

Section 4. IWE ExaminationsPae2o2 Page 2 of 2



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 12/13/2006Bolting

Component Cooling C-H/All SP 2168.4A 2 00265202 11/15/2006

Cooling Water C-H/All SP 2168.8 2 00292958 12/11/2006System to Unit 2FCUs

Residual Heat C-H/All SP 2168.10 2 00265194 12/9/2006Removal

SI Accumulator C-H/All SP 2168.12 2 00265192 11/15/2006

Post LOCA C-H/All SP 2168.15 2 00265188 11/16/2006Hydrogen 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 12/13/2006Vent System

Auxiliary Building C-H/All SP 2168.25 2 00265193 11/17/2006Trench

Boric Acid Leakage Identified at Bolted ConnectionsDuring the performance of these pressure tests, nine components were identified as having minorboric 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. Thefollowing 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 ControlProgram.

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



Section 6. Snubber Inservice Testing and Preservice Examinations

Inspection results showed no visual snubber failures. All snubbers that underwent functional testing hadsatisfactory results therefore no scope expansion was required.

2-RBDH-548 157625291847376 291847-03 SAT 330 291847

2-AFSH-46 602 157266-03 SAT 125 157266 1572662-RBDH-337 192 157374-04 SAT 600 157374 1573742-MSDH-19 397 157367-04 SAT 184 157367 1573672-PSR-106A 372 157623-03 SAT 448 157623 1576232-PSR-106B 434 157624-05 SAT 413 157624 1576242-CCH-160 242 157354-04 SAT 535 157354 1573542-SIRH-48 299 157370-04 SAT 95 157370 1573702-SIRH-7 344 157371-03 SAT 248 157371 1573712-ZX-PSSH-127 383 157372-03 SAT 88 157372 1573722-CCH-161 33 157590-04 SAT 245 157590 1575902-RHRH-54 312 88116-05 SAT 346 88116 881162-FWH-72B 258 157365-03 SAT 163 157365 1573652-MSH-54B 43 157373-04 SAT 255 157373 1573732-MSDH-17 488 157366-04 SAT 157 157366 1573662-MSH-107B 539 157369-04 SAT 338 157369 1573692-MSH-103A 528 157368-04 SAT 544 157368 1573682-RCRH-45 567 157376-04 SAT 567 157376 1573762-MSH-23B 518 157375-01 SAT 518 157375 15737521S/GOl SG02 157599-04 SAT SG1 1 157599 15759922S/GOl SG03 157378-02 SAT SG19 157378 1573782-CCH-1 79B 464 158200-03 SAT 4 158200 158200

Section 6. Snubber Inservice Testing and Preservice ExamsPae1o1 Page 1 of 1


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 beincluded with the summary reports of ASME Code Section XI inspections submitted within 90 days of the end ofeach 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 11 provides the location and extent of wall-thickness penetration for each indication of animperfection. 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 SteamGenerator Inspection Results - 15-Day Report".

Table III provides the identification of tubes plugged or sleeved.

TABLE INumber 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 f1Page 1 of 11



TABLE 11Extent of Wall-thickness Penetration for Each Indication of an ImperfectionLocation and

NO, S/G ROW COL PERCENT LOCATION ELEVATION STATUS1 21 16 4 14 0iC -0.03 <TS2 21 16 5 6 02C -0.03 <TS3 21 18 5 1 01C -0.18 <TS4 21 14 6 14 01C -0.10 '<TS5 21 19 6 22 NV1 -0.17 <TS6 21 20 6 1 01C -0.08 <TS7 21 21 7 1 01C -0.05 <TS8 21 23 7 18 01C -0.30 <TS9 21 21 9 25 NV1 1.19 <TS10 21 25 10 1 0iC -0.24 <TS11 21 27 10 26 07H 25.93 <TS12 21 25 11 1 020 0.24 <TS13 21 29 13 1 01C -0.27 <TS14 21 31 17 1 01C -0.35 <TS15 21 33 17 1 02C -0.05 <TS16 21 34 17 1 02C -0.05 <TS17 121 31 18 22 01C -0.32 <TS18 21 34 18 1 01C -0.26 <TS19 21 36 18 1 02C -0.23 <TS20 21 36 21 13 02C 0.13 <TS21 21 41 26 31 01C 0.23 <TS22 21 41 26 28 01C -0.26 <TS23 21 23 27 29 NV4 4.42 <TS24 21 41 27 1 01C 0.16 <TS25 21 41 27 27 01C -0.19 <TS26 21 18 28 23 NV2 0.80 <TS27 21 118 28 20 NV2 12.60 <TS28 21 34 28 17 NV3 -0.22 <TS29 21 25 30 24 NV2 0.78 <TS30 21 25 30 37 NV2 19.70 <TS31 21 25 30 22 NV4 2.30 <TS32 21 139 30 27 NV4 2.69 <TS33 21 25 32 29 NV2 0.38 <TS34 21 25 32 31 NV2 19.50 <TS35 21 41 32 19 NV1 -0.08 .<TS

36 21 41 32 13 NV2 -0.19 '<TS37 21 141 32 15 NV3 0.32 <TS38 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 <TS41 21 25 33 34 NV2 20.48 <TS

42 21 25 33 20 NV4 0.89 <TS43 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 Pae2f1Page 2 of 11



NO. S/G ROW COL PERCENT- LOCATION ELEVATION STATUS45 21 44 34 1 01C -0.18 <TS46 21 44 34 30 05C -0.10 <TS47 21 23 37 33 NV2 17.35 <TS48 21 17 38 15 NV2 0.33 <TS49 21 45 42 16 02C -0.08 <TS50 21 11 43 7 NV1 -0.06 <TS51 21 36 43 24 07H 33.94 <TS52 21 36 43 24 NV2 2.50 <TS53 21 36 43 25 NV2 32.94 . <TS54 21 46 43 1 1 0iC -0.21 <TS55 21 43 44 8 01C -0.29 <TS56 21 44 44 6 01C -0.19 <TS57 21 28 45 36 07H 29.93 <TS58 21 28 45 37 NV2 -0.08 <TS59 21 28 45 33 NV2 22.12 <TS60 21 28 45 23 NV2 24.59 <TS61 21 28 45 31 NV4 2.42 <TS62 21 36 45 26 NV2 1.29 <TS63 21 44 45 25 0iC -0.05 <TS64 21 45 45 27 01C 0.03 <T565 21 44 46 20 01C -0.13 <TS66 21 46 46 1 010 0.16 <T567 21 36 47 36 07H 34.22 Cr5S68 21 36 47 32 NV2 2.48 <TS69 21 36 47 26 NV2 32.10 <TS70 21 39 47 29 NV2 35.52 <T571 21 39 47 31 NV4 3.12 <TS72 21 35 48 36 07H 32.97 <TS73 21 35 48 23 NV2 1.86 <TS74 21 45 48 1 01C 0.13 <T575 21 29 50 38 NV2 1.03 <TS76 21 29 50 41 NV2 23.90 <TS77 21 45 50 27 010 -0.03 <TS78 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




NO. S/G ROW COL PERCENT LOCATION ELEVATION STATUS92 21 43 59 24 01C 0.00 <TS93 21 36 60 31 NV2 2.42 <TS94 21 42 60 1 0iC 0.00 <TS95 21 121 61 23 NV2 1.12 <TS96 21 21 61 11 NV4 -0.05 <TS97 21 23 61 29 1 NV2 1.26 <TS98 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 <TS105 21 21 64 20 NV2 17.08 <TS106 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 <TS109 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 <TS112 21 39 69 12 01C -0.29 <TS

113 21 40 70 16 02C -0.05 <TS114 21 18 71 21 NV2 13.25 <TS115 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 <TS121 21 39 72 13 0iC -0.16 <TS122 21 38 73 26 0iC -0.08 <TS123 121 37 75 6 0iC 0.00 <TS124 21 34 76 1 02C 0.13 <TS125 21 33 77 5 03C -0.31 <TS126 21 35 77 23 02C -0.13 <TS127 21 32 78 17 0iC -0.24 <TS128 21 32 78 20 02C -0.08 <TS129 21 23 85 8 01C 0.00 <TS130 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 <TS133 21 17 89 9 02C -0.08 'ZTS134 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 <T5138 21 7 91 28 01C -0.18 <TS




NO. S/G ROW COL PERCENT LOCATION ELEVATION STATUS139 21 14 91 1 01C 0.00 <TS140 21 _ 16 91 12 01C -0.03 <TS141 21 3 92 24 01C 0.13 T142 21 6 92 8 01C -0.16 <TS143 121 1 8 92 18 0iC -0.08 <TS144 21 8 92 1 02C -0.18 '<TS145 21 9 92 15 01C -0.03 <TS146 21 10 92 1 01C -0.03 <TS147 21 13 92 1 02C -0.24 <TS148 21 14 92 12 01C 0.03 <TS149 21 114 92 24 NV1 2.65 <TS150 21 2 93 14 01C -0.11 <TS151 21 2 93 5 02C 0.00 <TS152 21 5 93 20 01C -0.03 <TS153 21 6 93 36 01C -0.23 <TS154 21 6 93 15 02C -0.10 <TS155 21 5 94 20 01C 0.00 <TS156 21 7 94 25 O1C 0.08 <TS1 22 6 1 4 02C -0.05 <TS2 22 12 3 32 02C 0.08 <TS3 22 16 4 15 01C 0.13 <TS4 22 17 5 4 01C 0.13 <TS5 22 16 6 7 01C -0.11 <TS6 22 117 6 21 0iC -0.05 <TS7 22 19 6 2 02C 0.13 <TS8 22 20 6 33 01C -0.03 <TS9 22 21 7 7 01C -0.03 <TS10 22 21 7 15 02C 0.00 <TS11 22 125 9 38 01C 0.00 <TS12 22 20 10 20 01C -0.05 <TS13 22 24 10 20 01C -0.11 <TS14 22 26 10 20 02C 0.19 <TS15 22 28 11 9 02C 0.16 <TS16 22 29 13 20 01C -0.05 <TS17 22 129 13 20 02C -0.03 <TS18 22 31 13 33 0iC -0.13 <TS19 22 29 15 1 01C -0.16 <TS20 22 30 15 14 01C -0.03 <TS21 22 34 16 29 01C 0.13 <TS22 22 34 16 30 02C 0.00 <TS23 22 34 17 19 01C -0.08 <TS24 22 134 17 32 02C -0.08 T25 22 30 19 14 01C -0.16 <TS26 22 31 19 19 01C -0.21 <TS27 22 32 20 15 01C -0.18 <TS28 22 30 21 19 0iC 0.18 <TS29 22 36 22 25 02C 0.05<T




NO. S/G ROW COL PERCENT LOCATION ELEVATION STATUS30 22 37 23 11 01C 0.16 <TS31 22 37 24 29 0iC -0.11 <TS32 22 38 25 27 0iC 0.23 <TS33 22 38 25 22 02C -0.16 <TS34 122 41 26 15 01C 0.00 <TS35 22 39 29 16 02C -0.13 <TS36 22 41 29 19 NV1 0.00 <TS37 22 41 29 15 NV3 0.00 <TS38 22 19 31 _ 22 NV2 2.48 <TS39 22 19 31 __ 15 NV3 0.00 <TS40 22 19 34 15 NV1 -0.05 <TS41 22 43 34 23 03C -0.05 <TS42 22 43 35 36 02C -0.16 <TS43 22 38 36 21 NV2 2.38 <TS44 22 44 36 21 02C -0.08 <TS45 22 42 38 1 14 02C -0.21 <TS46 22 42 38 12 NV1 -0.26 <TS47 22 42 38 14 NV2 -0.11 <TS48 22 38 39 6 NV1 -0.08 <TS49 22 38 39 10 NV2 0.00 <TS50 22 43 39 17 02C -0.24 <TS51 22 144 39 13 02C -0.13 <TS52 22 44 40 14 02C 0.00 <TS53 22 33 41 7 NV1 -0.27 <TS54 22 40 41 16 NV1 0.00 <TS55 22 40 41 22 NV2 0.00 <TS56 22 40 41 13 NV3 0.00 <TS57 22 44 42 24 02C -0.16 <TS58 22 46 42 19 02C -0.03 <TS59 22 37 43 35 NV2 33.18 <TS60 22 37 43 32 NV4 3.91 <TS61 22 45 43 2 01C 0.13 <TS62 22 145 44 23 02C 0.08 <TS63 22 39 45 11 NV1 -0.21 <TS64 22 32 46 21 NV2 0.77 <TS65 22 38 46 24 07H 36.1 <TS66 22 33 47 20 NV4 2.12 <TS67 22 38 47 23 NV2 1.91 <TS68 22 145 47 11 01C -0.11 <TS69 22 38 48 29 NV2 2.43 <TS70 22 41 48 15 NV2 0.00 <TS71 22 44 48 13 01C -0.03 <TS72 22 45 48 14 0iC 0.21 <TS73 22 45 48 22 02C -0.11 <TS74 22 25 49 9 NV4 0.26 <TS75 122 26 49 13 1 NV4 0.34 <TS

L76 122 111 50 13 1 NV1 0.00 <TS




NO. S/G ROW COL PERCENT LOCATION ELEVATION STATUS77 22 33 50 24 NV2 28.63 <TS78 22 38 50 16 NV1 -0.05 <TS79 22 38 50 33 NV4 0.00 <TS80 22 45 50 36 01C 0.16 <TS81 22 37 51 24 NV2 2.13 <TS82 22 37 51 24 NV2 32.81 '<TS83 22 46 51 34 01C -0.16 <TS84 22 33 52 21 07H 35.39 <TS85 22 45 52 34 01C 0.13 <TS86 22 40 53 22 01C 0.18 <TS87 22 44 53 22 01C 0.13 <TS88 22 46 53 26 02C -0.13 <TS89 22 36 54 30 NV4 3.51 <TS90 22 39 54 21 07H 35.64 <TS91 22 45 54 1 01C 0.03 <TS92 22 45 54 1 02C 0.03 <TS93 22 39 55 23 NV2 3.91 <TS94 22 36 56 26 NV2 32.55 <TS95 22 38 56 9 NV1 0.13 <TS96 22 38 56 23 NV2 35.71 <TS97 122 42 56 4 02C -0.03 <TS98 22 43 56 23 01C -0.03 <TS99 22 43 57 4 01C -0.19 <TS100 22 43 57 33 NV3 0.00 <TS101 22 43 57 14 NV4 0.00 <TS102 22 45 57 6 01C -0.05 <TS103 22 35 58 20 07H 32.96 <TS104 22 43 58 20 01C -0.11 <TS105 22 43 58 15 NV2 -0.08 <TS106 22 40 59 21 07H 35.09 <TS107 122 41 60 9 02C -0.16 <TS108 22 43 60 1 15 02C 0.00 <TS109 22 41 61 30 02C -0.08 <TS110 22 44 61 20 02C -0.13 <TS111 22 44 62 4 02C -0.13 <TS112 22 143 63 4 02C -0.24 <TS113 22 32 64 27 NV2 3.17 <TS114 22 32 64 27 NV2 27.97 <TS115 22 38 64 27 NV2 34.28 <TS116 22 39 64 25 02C -0.24 <TS117 22 142 64 30 02C -0.21 <TS118 22 19 65 22 NV2 1.2 <TS119 22 42 65 17 02C -0.11 <TS120 22 43 65 22 02C -0.21 <TS121 22 32 66 16 NV4 -0.03 <TS122 22 40 66 10 1 02C 0.13 <TS123 22 41 66 31 1 02C -0.11 <TS

Section 7. Steam Generator Eddy Current Examination Results Page 7 of 11



NO. S/G ROW COL PERCENT LOCATION ELEVATION STATUS124 22 32 67 21 NV1 -0.27 <TS125 22 32 67 32 NV2 0.00 <TS126 22 32 67 23 NV2 28.18 <TS127 22 32 67 34 NV3 0.00 <TS128 22 32 67 24 NV4 0.00 <TS129 22 32 68 21 NV2 28.73 <TS130 22 36 69 20 NV1 0.08 <TS131 22 36 69 35 NV3 -0.19 <TS132 22 36 69 22 NV4 -0.03 <TS133 22 40 69 31 02C -0.13 <TS134 22 41 69 16 02C -0.08 <TS135 22 36 70 35 NV2 4.8 <TS136 22 36 70 1 39 NV2 32.56 <TS137 22 16 71 14 NV3 -0.32 <TS138 22 38 71 31 01C -0.08 <TS139 22 40 71 28 02C -0.16 <TS140 22 36 72 12 02C -0.13 <TS141 22 37 72 1 02C -0.18 <TS142 22 36 73 1 02C -0.16 <TS143 22 35 74 1 02C 0.1 <TS144 22 33 75 37 0iC -0.05 <TS145 22 35 75 33 01C -0.03 <TS146 22 36 75 31 02C -0.16 <TS147 22 33 76 32 0iC -0.03 <TS148 22 33 76 25 02C -0.13 <TS149 22 30 79 3 01C 0.11 <TS150 22 30 79 15 02C 0.13 <TS151 22 29 81 13 NV2 0.16 <TS152 22 30 81 17 01C 0.00 '<TS153 22 29 82 34 01C -0.11 <TS154 22 29 82 26 02C -0.23 <TS155 22 30 82 17 02C -0.13 <TS156 22 30 83 1 02C -0.2 <TS157 22 29 84 1 02C -0.24 <TS158 122 122 85 1 01C -0.13 <TS159 22 24 85 1 01C -0.13 <TS160 22 28 85 14 01C 0.08 <TS161 22 28 85 20 01C -0.16 <TS162 22 26 86 14 02C -0.13 <TS163 22 20 87 1 0iC -0.16 <TS164 22 14 88 7 02C -0.11 <TS165 22 22 88 7 02C -0.16 <TS166 22 116 89 19 01C -0.24 <TS167 22 16 89 23 02C -0.11 <TS168 22 17 89 29 01C 0.00 <TS169 22 18 89 20 02C -0.03 <TS170 22 19 89 21 01C 0.00 <TS




NO. S/G ROW COL PERCENT LOCATION ELEVATION STATUS171 22 20 89 1 02C -0.16 <TS172 22 21 89 1 02C -0.18 <TS173 22 6 90 19 01C -0.03 <TS174 22 12 90 17 01C -0.08 <TS175 22 16 90 39 01C 0.00 <TS176 22 17 90 1 01C -0.13 <TS177 22 2 91 17 01C 0.08 <TS178 22 7 91 15 01C 0.11 <TS179 22 11 91 32 02C -0.05 <TS180 22 12 91 1 01C 0.06 <TS181 22 12 91 7 02C -0.05 <TS182 22 13 91 13 02C -0.08 <TS183 22 1 92 1 1 Q0C 0.11 <TS184 22 3 92 7 01C 0.06 <TS185 22 6 92 5 02C 0.00 <TS186 22 7 92 36 01C 0.03 <TS187 22 9 92 16 01C 0.03 <TS188 22 4 93 27 0iC 0.11 <TS189 22 4 93 12 02C 0.03 <TS190 22 5 93 26 01C 0.05 <TS191 22 2 94 10 01C 0.25 <TS192 122 1 4 94 14 02C -0.06 <TS

19 2 5 94 1 02C -0.03 <TS

TABLE IIIIdentification of Tubes Plugged or Sleeved

NO. IS/GTROW COL PERCENT LOCATION ELEV FROM ELEV TO STATUS1 21 4 11 MAI EB3H -0.02 0.08 PLG2 21 3 22 MAI EBH -0.05 0.13 PLG3 21 19 25 SAl EB3H 0.00 0.08 PLG4 21 28 27 FPC EBH 0.30 PLG5 121 11 32 SAl TRH 16.64 17.77 PLG6 21 19 32 SAl EBH 2.11 2.17 PLG7 21 23 34 SAl EBH 3.43 4.18 PLG8 21 23 39 MAI EBH 0.05 0.14 PLG9 21 10 43 MAI EBH -0.01 0.03 PLG10 21 3 45 SAl 1131- 16.48 16.84 PLG11 21 14 47 SAl 213H- 14.96 15.38 PLG12 21 18 47 TBP (D PLG13 21 8 49 SAl E13H -0.04 0.04 PLG14 21 25 49 SAl E13H 0.13 0.23 PLG15 21 12 54 TBP Q PLG16 21 11 57 SAl EBH -0.02 0.05 PLG17 21 7 67 MAI EBH -0.09 0.06 PLG18 21 4 68 MAI 2131- 14.75 14.93 PLG




NO. S/G ROW COL PERCENT LOCATION ELEV FROM ELEV TO STATUS19 21 17 89 48 01C 0.03 PLG1 22 12 20 FPC EBH 0.3 PLG2 22 29 24 SVI 0iC -0.08 0.1 PLG3 22 19 30 SAl TRH 18.05 18.49 PLG4 22 20 30 SAl TSH -0.01 0.08 PLG5 22 11 36 SAl TRH 17.87 18.14 PLG6 22 17 38 SAl TRH 17.35 17.6 PLG7 22 19 44 SAl TRH 17.7 18.26 PLG8 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 ~f1Page 10 of 11



LEGEND OF FIELDS AND CODES

FIELDNO.S/GROWCOLPERCENTLOCATIONELEVATIONELEV FROMELEV TOSTATUS

FIELD

PERCENT

EXPLANATIONCumulative number per table per S/GSteam Generator Number (21 or 22)Row number of tube locationColumn number of tube locationMeasured percent or three digit code - see belowPhysical Location of Indication - see belowMeasurement in inches from the LOCATION to the center of the indicationMeasurement in inches from the LOCATION to the lower edge of the indicationMeasurement in inches from the LOCATION to the upper edge of the indicationRepair status - see below

CODE EXPLANATION

ADRCUDDEPDNIDNTDRIDSIDTIFPCINRMAIMBMMRINQIPLPPSISAlSVITBP0-100

Absolute DriftCopper DepositDepositDent with IndicationDentDistorted Roll Transition with IndicationDistorted Support Signal with IndicationDistorted Tube Sheet Signal with IndicationFailed Profilometry CriteriaIndication Not ReportableMultiple Axial IndicationManufacturing Burnish MarkMix Residual IndicationNon Quantifiable IndicationPossible Loose PartPossible Support IndicationSingle Axial IndicationSingle Volumetric IndicationTo Be PluggedAs measured percent through wall

Tube end hot (primary face)Top of roll expansion hot legBottom of Additional roll expansion #1 hot legBottom of Additional roll expansion #2 hot legBottom of Elevated roll expansion hot legTube sheet hot (secondary face)

?= First through Seventh tube support plate on hot leg side?= First through Fourth new antivibration bar?= First through Seventh tube support plate on cold leg side

Tube sheet cold (secondary face)Top of roll expansion cold legTube end cold (primary face)

Less Than the Technical Specification repair limitTube Plugged

LOCATION TEHTRH113H2131-EBHTSH0?HNV?0?CTSCTRCTEC

STATUS <TSPLG




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 itemnumber sequence are due to cancelled or unfinished R/R activities.

UbU4bj 14,1SPCE-ME-

12-23-001 0453

2-23-004, 92790-01

Replaced the mechanical seal gland22BATP plate and fasteners. -~__2 -~VC

~Pressurizer PORV RelcdPui1 R

2-23-0059278,91-0110505924

2-23-009 10409796

!2-23-013 1154068

Pressurizer PORVA __ Replaced Plug. 1 RCj22_Charging Pump i Replaced packing assemblies. 2 VC

IReplaced plungers in packinglassemblies 13, 14, and 15 and

'Spare Charging !replaced gland plates in assemblies~Pum114 and 15.2 VC

i22 CHG PmpSuction 1Replaced Bonnet and fasteners. _ 2 'VC

Replaced the mechanical seal gland2BATP _plate. .~__- 2 VC

!22 Charging Pump Re laced packing assemblies. 2 VC1SG Snubber BlocklValve I Replaced valve block. 12 :SGiSG Snubber Block

12-23-014 157443-01270329-0 1

12-23-020 1157378-05

223-02 1 157599-01

2-23-025 EEC-i 096157619-01,

t22-261EEC-1096

!Valve I eplaced valve block. _____

I I Replaced the mechanical seal gland121 SIPump___ plate.__Main Steam Safety IReplaced applicable valve to flange

__Valve____nuts with superbolt material.ManSteam Safety 1Replaced applicable valve to flange

'Valve nuts with superbolt material.Replaced mechanical seal gland

121 RHR Pum 'fasteners.

2 SG

2 SI

ý2 MS

2 MS

.2 RH2-23-027

2-23-028

99275-0 1ý2RCS LP AHot

ý96881-01, 'Leg RHR Supply 'Replaced body to bonnet fastener1EEC-1620 Valve

2-23-029 110617-01153609-01,

12-23-030 1EEC-1096

,Mod. 02VC012-23-0311 EC-07688

Wyle Labsý2-23-032P.O. 89882-23-034'303811 1-01

12-23-035 154839-11

ý22 RHR F,Main SteaValve

!Charging1 PressurizilValvei23 Chariý22/24 ECI

Iset.1!Replaced mechanical seal gland

lump fas~teners 12im Safety 1,Replaced applicable valve to flange

I nuts with superbolt material. i 2IDrilled and tapped holes in chargingIpump packing assembly gland plates

Pump land stuffing boxes!/er Safety

Replaced disc.1

ng Pump Replaced Packing assemblie2U CHLD Replacement main plug and body to 3

.RH_

.RH

1MS

VC

VCzx

Section 8. Repair/Replacement Activities for Cycle 23Pae1o2 Page 1 of 2



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

2-23-036 199284-07_1154791-12,lAlteration

2-23-037 92A229

2-23-038 154513-08306250-01,

!2-23-039 EC-9602

2-23-04 1 306550-01

2~-23-042 1305364-02'2-23-045 154582-05

2-23-046 :154582-05

2-23-047 i96871 -01

2-2-4 3720-01

WVTR RTRN21/23 ECU CHLD-WTR-RTRN

Sbonnet fasteners.

122 SG MS ISOLI cv -, - - - - -121 CC Heat!Exchanger

jCL Pipe SectionBoric Acid FLTR.. ... ... ... .

122 SG MS OUTLJS~to~p- OK

121 PRZR RELIEF121 PRZR RELIEFPressurizer to CV-31229_BypassRH support'RFLG WVTR TO;SAF INJ PMPSPHDR ISQL

'Replacement main plug.. __ 3'Replaced 5 bonnet studs, 5 nuts, andýdamaged helical coil. Repaired 4 MS (Mainistud holes w/ helical coil inserts. 2 Steam)__iWeld build up of wasted areas inshell and attachment weld areas. .3 _CC:

Installed branch connection in 24"--------section of pipe., 3 CL

'Re-welded Canopy after BA depositýiremoval 2 ,VC;Machined the disc and seat sealingsurface. 2 M

R~ep~l~ace~din~l~e~tflange fasteners.Replaced inlet flange fasteners.

!Replaced bonnet.Buffed out indication.

1 MS....... M S........ .....

11

:RC-RH

SIlReplaced body to bonnet fasteners. ý2

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

Name2. Plant Praire Island Nuclear Generating Plant Sheet 1 of 2

Name1717 Wakonade Dr. E, Welch Minnesota 55089 0504674, SPCE-ME-0453

Address Repair Organization P.O. No., Job No., etc3. Work Performed by Owner Type Code Symbol Stamp N/A

NameSame Authorization N/A

Address Expiration Date N/A4. 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 1 998E / 2000A

(c) Applicable Section Xl Code Cases None

6. Identification of Components

Component Name Manufacturer Manufacturer Nat'l Bd # Other ID Yr Built Corrected, ASMEName Serial # RemIveI or Code

_ _ _ _ ____ ___I _ _Installed Stamp

2 APGoulds 792A1 92-2 I245-032 J ____JCorrected 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. 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 items1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.


ITEM 2-23-001

'9. Remarks n/a

CERTIFICATE OF COMPLIANCEWe 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 VesselInspectors and the State or Province of ' -Minnesota and employedby HSB Insp. and Ins. Co. of Connecticut of Hartford Conn. haveinspected 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 performedexaminations and taken corrective measures described in this Owner's Report in accordance with therequirements of the ASME Code, Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed orimplied, 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 ofproperty 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


ITEM 2-23-004

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

Name2. Plant Prairie Island Nuclear Generating Plant Sheet 1 of 2

Name1717 Wakonade Dr. E, Welch Minnesota 55089 92790-01



Address Expiration Date N/A

4. Identification of System RC Code Class 1

5. (a) Applicable Construction Code B 16.34 n/a Edition


(b) Applicable Edition of S -ection Xl Utilized for Repair/Replacement Activity 1 998E /2000A



Component Name Manufacturer Manufacturer Nat'l Bd # Other ID Yr Built Corrected, ASMEName 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. 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. xl11 in., (2) information in items1 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 2-23-004

9. Remarks

CERTIFICATE OF COMPLIANCEWe 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


1, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure VesselInspectors and the State or Province of. Minnesota and employedby HSB Insp. and Ins. Co. of Connecticut of Hartford Conn. have inspectedthe components described in this Owner's Report durin g the period .O~2~a to lsý/o 41o6 Iand state that to the best of my knowledge and belief, the Owner has performed examinations and take'n correctivemeasures 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, neitherthe 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:Z71SInspector's Signature National Board, Province' arid Endorsements

Date


ITEM 2-23-005

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





Address Expiration Date N/A4. Identification of System RC Code Class 1




(c) Applicable Section XI Code Cases None



Installed Stamp

Pressurizer PORV A SPX / Copes CV-31234 1968 Corrected EDVulcan

7. Description of Work Replaced Plug.

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

Other F- Pressure psi -Test Temp. OF

Other: n/a


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

ITEM 2-23-005

9. Remarks


Type Code Symbol Stamp 614

Certificate of Aut aExpiration Date _______________________

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

Owner or Owner's Designee ,Title


1, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure VesselInspectors and the State or Province of. Minnesota and employedby - HSB Insp. and Ins. Co. of Connecticut of Hartford Conn. have inspectedthe 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 correctivemeasures 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, neitherthe Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss ofany 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



Name1717 Wokonade Dr. E, Welch Minnesota 55089 0505924






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



Component Name I Manufacturer fManufacturer 1 Nat'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.



ITEM 2-23-008

9. Remarks


Type Code Symbol Stamp W11

Certificate of Authorization No. Expiration Date _______________________

Signed ,ASMVE Program Engineer Date _________ /as-_



1, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure VesselInspectors and the State or Province of. Minnesota and employedby HSB Insp. and Ins. Co. of Connecticut of Hartford Conn. have inspectedthe components described in this Owner's Report during the period /FYVL or to 14 SEPO 3and state that to the best of my knowledge and belief, the Owner has performed examinations and taken correctivemeasures 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, neitherthe Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss ofany kind arising from or connected with this inspection.Sel. Commissions .~Io• ~

nsoector's Signat Iure National Board, Province and Endorsements

Date L fQndmfn IL~ ,


ITEM 2-23-009

1. Owner Nuclear Management Company, LLC

Name2. Plant Praire Island Nuclear Generating Plant

Name1717 Wakonade Dr. E, Welch Minnesota 55089

Date 8/9/2005

Sheet 1

0409796

2of






(b) Applicable Edition of Section XI Utilized for Repair/Replacement Activity 1 998E / 2000A



IComponent Name I Manufacturer IManufacturer I Nat'l Bd # I Other ID Yr Built 1Corrected, tASME

7. Description of Work

8. Tests conducted:

Replaced plungers in packing assemblies 13, 14, and 15 and replaced gland plates in assemblies 14 and15.

Hy drostatic F- PneumaticD- Nominal Operating Pressure E] Exempt F./


Other: n/a



ITEM 2-23-009

9. Remarks

CERTIFICATE OF COMPLIANCEWe 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

Certificate of Auth ni)~ A 4/// Expiration Date______________________

Signed ,ASME Program Engineer Date FA;______ __/65_7



1, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure VesselInspectors and the State or Province of ' Minnesota and employedby HSB Insp. and Ins. Co. of Connecticut of Hartford Conn. haveinspected 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 performedexaminations and taken corrective measures described in this Owner's Report in accordance with therequirements of the ASME Code, Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed orimplied, 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 ofproperty 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'/


ITEM 2-23-013



Name1717 Wakonade Dr. E, Welch Minnesota 55059 154068






(b) Applicable Edition of Section-XI, Utilized for Repair/Replacement Activity 1 998E / 2000A




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. O F

Other: n/a



ITEM 2-23-013

9. Remarks

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


Certificate of Au honz inNo. 4/ /A. Expiration Date ________________________

Signed _ n ,ASME Program Engineer Date _ _



1, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure VesselInspectors and the State or Province of Minnesota and employedby HSB Insp. and Ins. Co. of Connecticut of Hartford Conn. have inspectedthe 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 correctivemeasures described in this Owner's Report in accordance with the requirements of the ASME Code, Section XI.


___ __ __ __ __ __ Commissions Alwog 0-54/3 /36zvInspector's Signature National Board, Province and Endorsements

Date


ITEM 2-23-0 14









(b) Applicable Edition of Section Xl Utilized for Repair/Replacement Activity 1998E / 2000A,



Component Name Manufacturer Manufacturer Nat'l Bd # Other ID Yr Built Corrected, ASMEName Serial # 11Removed, or Code

In stalled Stamp

7.

a.

22 BATIP Goulds 792A192-2 245-032 11Corrected I

Description of Work Replaced the mechanical seal gland plate.

Tests conducted: HydrostaticDE Pneumatic[] Nominal Operating Pressure 0j Exempt VF

Other El Pressure psi Test Temp. 0 F

Other: n/a


PRAIRIE ISLAND NUCLEAR GENERATING PLANTFORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITYI

ITEM 2-23-014

9. Remarks

CERTIFICATE OF COMPLIANCEWe 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


1, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure VesselInspectors and the State or Province of Minnesota and employedby -HSB3 Insp. and Ins. Co. of Connecticut of Hartford Conn. have inspectedthe components described in this Owner's Report during the period /d APR 04~ to OC. MAJOGand state that to the best of my knowledge and belief, the Owner has performed examinations and taken correctivemeasures described in this Owner's Report in accordance with the requirements of the ASME Code, Section XI.


V) Commissions ____________________I 5p-ector's Signature National Board, Province and Endorsements

Date 4.- r( oOltn

(9


ITEM 2-23-015













_________________________ _____________ I___________ ________________Installed___ nsalldaSam22 Charging Pump Ajax 245-042 1969 CorrectedD


8. Tests conducted: Hydrostaticfý PneumaticDF- Nominal Operating Pressure 7 Exempt

Other Pressure psi Test Temp. 0 F

Other: n/a


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

ITEM 2-23-015

9. Remarks


Type Code Symbol Stamp 41/4Certificate of Au Expiration Date ________________________

Signed ,ASME Program Engineer Date 4A_ _ _



1, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure VesseiInspectors and the State or Province of. Minnesota and employedby HSB Insp. and Ins. Co. of Connecticut of Hartford Conn. have inspectedthe 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 correctivemeasures described in this Owner's Report in accordance with the requirements of the ASME Code, Section XI.


Commissions 13IQZG3 M~l rrJ 4M-2L

I n sp tor', Signature National Board, Province and Endorsements

Date /pknd.n e Qoe(-IKU

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

ITEM 2-23-020

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






4. Identification of System SG Code Class 2

5. (a) Applicable Construction Code 831.1 1967 Edition


(b) Applicable Edition of Section Xl Utilized for Repair/Replacement Activity 1998E /2000A




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. 0 F

Other: n/a


OWNE'S EPOT FO REAIR RELACEENTACTVITFOR N 5-2PRAIRIE ISLAND NUCLEAR GENERA TING PLANT

ITEM 2-23-020

9. Remarks


Type Code Symbol Stamp ý1

Certificate of on Expiration Date ________________________

Signed ASEPogramn Engineer Date 4___



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 employedby HSB Insp. and Ins. Co. of Connecticut of Hartford Conn. have inspectedthe components described in this Owner's Report during the period 611#06& to ,g/.2/06/0and state that to the best of my knowledge and belief, the Owner has performed examinations and taken correctivemeasures described in this Owner's Report in accordance with the requirements of the ASME Code, Section XI.


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

Date


ITEM 2-23-021

1.

2.

Owner

Plant

Nuclear Management Company, LLC

NamePrairie Island Nuclear Generating Plant


Date 12/6/2006

Sheet 1

157599-01

2of




4. Identification of System SG Code Class 2

5. (a) Applicable Construction Code B31.1 1967 Edition


(b) Applicable Edition of Section Xl Utilized for Repair/Replacement Activity 1 998E /2000A




Installed Stamp

SG Snubber Block Valve McDowell Welman 72218-000-02 21S/G 01 RemovedD

SG Snubber Block Valve McDowell Welman 721-001 2- 1 -/ 1Intle

7.

8.

Description of Work

Tests conducted:

Replaced valve block.

Hydrostatic

Other[-

Pneumatic F- Nominal Operating Pressure F- Exempt F./

Pressure psi Test Temp.

Other: n/a


FOR N 5-2PRAIRIE ISLAND NUCLEAR GENERATING PLANT

ITEM 2-23-021

9. Remarks


Type Code Symbol Stamp A$214

Certificate of Aut~h ýýJ .4'4. Expiration Date _______________________

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



1, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure VesselInspectors and the State or Province of ' Minnesota and employedby HSB Insp. and Ins. Co. of Connecticut of Hartford Conn. have inspectedthe~components described in this- Owner's Report during the period -611A6.16 to 1-216646 1and state that to the best of my knowledge and belief, the Owner has performed examinations and tak~en correctivemeasures described in this Owner's Report in accordance with the requirements of the ASME Code, Section XI.


4e ~Commissions /p'id 0-54&3/ 9AInspector's Signature National Board, Province and Endorsements

Date I r,7006

mmý


ITEM 2-23-024

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





Address Expiration Date N/A4. Identification of System SI Code Class 2


Addenda ____________ Code Cases ___________

(b) Applicable Edition of Section Xl Utilized for Repair/Replacement Activity 1998E / 2000A




Installed Stamp

21 SI Pump Bingham- 290698 245-071 CorrectedDWillamette

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

8. Tests conducted: Hydrostatic F- PneumaticD- Nominal Operating Pressure 7 Exempt FV


Other: IST Pump Testing



ITEM 2-23-024

9. Remarks

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


Certificate of Authorization Expiration Date ________________________

Signed ,ASMVE Program Engineer Date AJ/ 4 ____



1, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure VesselInspectors and the State or Province of. Minnesota and employedby HSB Insp. and Ins. Co. of Connecticut of Hartford Conn. have inspectedthe components described in this Owner's Report during the period .1/VS/oý6 to /2~ cand state that to the best of my knowledge and belief, the Owner has performed examinations and taken correctivemeasures described in this Owner's Report in accordance with the requirements of the ASME Code, Section XI.


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

Date mo5


ITEM 2-23-025


Name2. Plant Prairie Island Nuclear Generating Plant

Date 11/27/2006

Sheet 1 2ofName

1717 Wakonade Dr. E, Welch Minnesota 55089

Address

157421-01, EEC-i1096

Repair Organization P.O. No., Job No., etc3. Work Performed by Owner

Same

4. Identification of System

Name

AddressMS


Authorization

Expiration Date

Code Class 2

5. (a) Applicable Construction Code B 16.34 Edition

Addenda N/A Code Cases N/A(b) Applicable Edition of Section Xl Utilized for Repair/Replacement Activity 1 998E / 2000A




Installed Stamp

Main Steam Safety Valve Consolidated RS-21-20 CorrectedD


8. Tests conducted:

Replaced applicable valve to flange nuts with superbolt material.

Hydrostatic El Pneumaticn Nominal Operating Pressure n Exempt n.

Other F Pressure psi Test Temp.

Other:


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

ITEM 2-23-025

9. Remarks



Certificate of A ithojrUen Atkt Expiration Date _______________________

Signed ,ASME Program Engineer Date Ia7 A__(0



1, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure VesselInspectors and the State or Province of. Minnesota and employedby 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 correctivemeasures described in this Owner's Report in accordance with the requirements of the ASME Code, Section XI.


______ ______ ______Commissions M,4. 0 51/531 144/1 5Inspector's Signature National Board, Province and Endors'ements

Date DateI a~O0O

FOR N 5-2PRAIRIE ISLAND NUCLEAR GENERATING PLANT

ITEM 2-23-026


Name2. Plant Prairie Island Nuclear Generating Plant Sheet 1 of

Name1717 Wakonade Dr. E, Welch Minnesota 55089 15761 9-01, EEC-i1096

Address Repair Organization P.O. No., J3. Work Performed by Owner Type Code Symbol Stamp N/A



4. Identification of System MS Code Class 2


Addenda N/A Code Cases N/A




Coinponent Name IManufacturer IManufacturer I Nat'l Bd # I Other ID Yr Built IC,

2

ob No., etc

7.

8.

Description of Work

Tests conducted:

Replaced applicable valve to flange nuts with superbolt material.

Hydrostatic PneumaticDF- Nominal Operating Pressure F- Exempt Fvo


Other:



ITEM 2-23-026

9. Remarks



Certificate of Auth 0 6IdExpiration Date _______________________

Signed ,ASME Program Engineer Date 7___ AI



1, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure VesselInspectors and the State or Province of. Minnesota and employedby HSB Insp. and Ins. Co. of Connecticut of Hartford Conn. have inspectedthe components described-in this Owner's Report during the period 'e l26o to 11107606and state that to the best of my knowledge and belief, the Owner has performed examinations and tak~en correctivemeasures 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, neitherthe Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss ofany kind arising from orcyeted with this inspection.

_________& 0 ____" Commissions /A/d O'S"153 /6 /ZInspector's Signature National Board, Province and Endorsemehts

Date 1 .7CO6


ITEM 2-23-027



Name1717 Wakonade Dr. E, Welch Minnesota 55089 .99275-01




4. Identification of System RH Code Class 2



(b) Applicable Edition of Section Xl Utilized for Repair/Replacement Activity 1 998E /2000A



Component Name Manufacturer Manufacturer Nat'l Bd # Other ID Yr Built Corrected, ASMEName Serial # I_ TRemoved, or Code

_ _ __ _ __ _ __ _ _ I _ Installed Stamp

21 RHR Pump Byron Jackson 681 -N-0274 245-111 Corrected

7. Description of Work Replac ed 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


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

ITEM 2-23-027

9. Remarks

CERTIFICATE OF COMPLIANCEWe 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 ______ ___



1, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure VesselInspectors and the State or Province of. Minnesota and employedby HSB InsD. and Ins. Co. of Connecticut of Hartford Conn. have inspectedthe components described in this Owner's Report during the period 6Ac o(, t o /0,Zo,and state that to the best of my knowledge and belief, the Owner has performed examinations and taken correctivemeasures described in this Owner's Report in accordance with the requirements of the ASME Code, Section XI.


_______________Commissions /41A10,VT3SA'/S1ý G f-Inspector's Signature National Board, Province and Endorsements

Date lall ooo61 07Cý06


ITEM 2-23-028



Date 12/12/2006

Sheet 1 2ofName

1717 Wakonade Dr. E, Welch Minnesota 55089 96881-01, EEC-i1620

Address Repair Organization P.O. No., Job No., etc3. Work Performed by Owner

Same

4. Identification of System

Name

AddressRH


Authorization

Expiration Date

Code Class, 1


Addenda n/a Code Cases n/a*

(b) Applicable Edition of Section XI Utilized for Repair/Replacement Activity 1 998E /2000A




Installed Stamp

2RCS LP A Hot Leg RHR Supply Velan MV-32193 1968 CorrectedDValve


8. Tests conducted:

Replaced body to bonnet fastener set.

Hydrostatic F-1 Pneumaticn Nominal Operating Pressure F- Exempt FV

Other 11 Pressure psi Test Temp.

Other: n/a



ITEM 2-23-028

9. Remarks

CERTIFICATE OF COMPLIANCE

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

Type Code Symbol Stamp 4ll,

Certificate of Authori' Expiration Date ________________________

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



1, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure VesselInspectors and the State or Province of. Minnesota and employedby _ HSB Insp. and Ins. Co. of Connecticut of Hartford Conn. have inspectedthe components described in this Owner's Report during the period WA/'106~ to 14,/~ 6and state that to the best of my knowledge and belief, the Owner has performed examinations and taken correctivemeasures 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, neitherthe Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss ofany kind arising from orcnpted with this inspection.

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

Date


ITEM 2-23-029






Address Expiration Date N/A4. Identification of System RH Code Class 2







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: n/a



ITEM 2-23-029

9. Remarks

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


Certificate of AuthoiizRrN v"AExpiration Date ________________________

Signed ,ASME Program Engineer Date 1-2 2 _____



1, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure VesselInspectors and the State or Province of ' Minnesota and employedby HSB lnsp. and Ins. Co. of Connecticut of Hartford Conn. have inspectedthe 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 correctivemeasures described in this Owner's Report in accordance with the requirements of the ASME Code, Section XI.


___ ___ __16 !5" _ __ Commissions MAqAI5'VSSI t

Inspector's Signature National Board, Province and Endorsements

Date 121 0I

MMMMEI PRAIRIE ISLAND NUCLEAR GENERATING PLANT

FORM NIS-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY IITEM 2-23-030



Name1717 Wakonade Dr. E, Welch Minnesota 55089 153609-01, EEC-1096

Address Repair Organization P.O. No., J3. Work Performed by Owner Type Code Symbol Stamp N/A


Address Expiration Date N/A4. Identification of System MS Code Class 2


Addenda ___________ Code Cases__________




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

2

ob No., etc

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

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


Other:


FOR N 5-2PRAIRIE ISLAND NUCLEAR GENERA TING PLANT

ITEM 2-23-030

9. Remarks


Type Code Symbol Stamp A11l

Certificate of AuthojJi11 A 4 Expiration Date ________________________

Signed ( ,ASMVE Program Engineer Date ___L___7_A0_1



1, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure VesselInspectors and the State or Province of Minnesota and employedby HSB Insp. and Ins. Co. of Connecticut of Hartford Conn. have inspectedthe components desonrbed in this Owner's Report during the period iD/o9/o& to Wi .2(06oand state that to the best of my knowledge and belief, the Owner has performed examinations and taken correctivemeasures 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, neitherthe Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss ofany kind arising from oronce ihthis inspection.

___ __ __ ___ __ __ __Commissions MA-1 oS$V$3/.e,,Inspector's Signature National Board, Province and Endorsements

Date 1 .2006Date ,b2c~o~,


ITEM 2-23-031


Name2. Plant Praire Island Nuclear Generating Plant


Address3. Work Performed by Owner

NameSame

Address

Date 9/22/2006

Sheet 1 2of

Mod. O2VCO1, EC-07688

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

Type Code Symbol Stamp N/A

Authorization N/A

Expiration Date N/A

4. Identification of System VC Code Class 2

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






8. Tests conducted:

Drilled and tapped holes in charging pump packing assembly gland plates and stuffing boxes/

HydrostaticF- . PneumaticnJ Nominal Operating Pressure F- Exempt pe

OtherF- 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 11/2 in. x 11 in., (2) information in items1 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.

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 COMPLIANCEWe 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 __________________



1, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure VesselInspectors and the State or Province of - Minnesota and employedby HSB Insp. and Ins. Co. of Connecticut of Hartford Conn. have inspectedthe 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 correctivemeasures described in this Owner's Report in accordance with the requirements of the ASME Code, Section Xl.


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

In ýector's Signature National Board, Province and Endorsements

Date A-Lmh ,2 2

1\1ý

PRAIRIE ISLAND NUCLEAR GENERATING PLANTFORM NIS-2 OWNER'S REPORT FOR REPAIRI REPLACEMENT ACTIVITYI

ITEM 2-23-032



Name1717 Wakonade Dr. E, Welch Minnesota 55089 Wyle Labs P.O. 8988

Address Repair Organization P.O. No., Job No., etc3. Work Performed by Wyle Labs. Inc. Type Code Symbol Stamp N/A

Name7800 Hwy 20 West, Huntsville, AL 35807 Authorization N/A



5. (a) Applicable Construction Code ASME Ill, Class 1 1969 Edition

Addenda ______________ Code Cases ,.4





Installed Stamp

Pressurizer Safety Valve Crosby N57872-00- 1969 Corrected R0002

7. Description of Work Replaced disc.

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


Other:



ITEM 2-23-032

9. Remarks


Type Code Symbol Stamp ,vl14Certificate of Au4 Expiration Date _______________________

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



1, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure VesselInspectors and the State or Province of. Minnesota and employedby HSB Insp. and Ins. Co. of Connecticut of Hartford Conn. ýave inspectedthe components described in this Owner's Report during the period 1V//?L/06 - -to O/Lgl / 7and state that to the best of my knowledge and belief, the Owner has performed examinations and taken correctivemeasures described in this Owner's Report in accordance with the requirements of the ASME Code, Section XI.


__________________Commissions AlA,' o-S-V31 /&A, T3 'Inspector's Signature National Board, Province and Endorsements

Date 4e-. /89 ~ o,I ý00 I


ITEM 2-23-034

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






4. Identification of System VC Code Class 2






Component Name Manufacturer Manufacturer Nat'l Bd # Other ID Yr Built Corrected, IASMEName Serial # Removed, or jCode

______Installed jStamp23 Charging Pump Ajax 245-043 1969 CorrectedD


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


Other: n/a



ITEM 2-23-034

9. Remarks

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


Certificate of Authoriz .Expiration Date ________________________

Signed 774,ASMVE Program Engineer Date JV9,



1, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure VesselInspectors and the State or Province of Minnesota and employedby HSB Insp. and Ins. Co. of Connecticut of Hartford Conn. have inspectedthe components described in this Owner's Report during the period' 111/ 14 toand state that to the best of my knowledge and belief, the Owner has performed examinations and taken correctivemeasures described in this Owner's Report in accordance with the requirements of the ASME Code, Section XI.


_____ ____ _____ ____Commissions ^A1d 0-T453/-Co AO3 , 1 4Inspector'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 1.ITEM 2-23-035




Date 2/7/2007

Sheet 1

154839-11

2of


.NameSame Authorization N/A

Address Expiration Date N/A4. Identification of System ZX Code Class 3


Addenda ____________ Code Cases___________

(b) Applicable Edition of Section Xl Utilized for Repair/Replacement Activity 1998E /2000A




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: Hydrostatic F- PneumaticDF Nominal Operating Pressure r_ Exempt W-


Other: Non-code leakage check per SP-1596



ITEM 2-23-035

9. Remarks


Type Code Symbol Stamp A&109

Certificate of Autor Expiration Date ________________________

Signed ,ASME Program Engineer Date______



1, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure VesselInspectors and the State or Province of Minnesota and employedby - HSB Insp. and Ins. Co. of Connecticut of Hartford Conn. have inspectedthe 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 correctivemeasures 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, neitherthe Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss ofany 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 IITEM 2-23-036




Address3. Work Performed by Owner

NameSame

Address

Date

Sheet 1 2of

99284-07

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

Type Code Symbol Stamp N/A

Authorization N/A

Expiration Date N/A

4. Identification of System ZX Code Class 3






7. Description of Work Replacement main plug.

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

OtherF

Other: Non-code leakage check per SP-1596

Pressure psi Test Temp.

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 items1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.


ITEM 2-23-036

9. Remarks


Type Code Symbol Stamp A/

Certificate of Auth izai Expiration Date ________________________

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



1, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure VesselInspectors and the State or Province of Minnesota and employedby HSB Insp. and Ins. Co. of Connecticut of Hartford Conn. have inspectedthe components described in this Owner's Report during the period F tand 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, neitherthe Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss ofany kind arising from or connected with this inspection.

___ ___ ___ ___ __Commissions AIAI oS'/5-3 t d,6 k4.gZtdSI nspeclor's Signature National Board, Province and Endorsements

Date


ITEM 2-23-037

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


Name1717 Wakonade Dr. E, Welch Minnesota 55089 154791-1 2, Alteration 92A229




4. Identification of System MS (Main Ste Code Class 2



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




Installed Stamp

22 SG MS ISOL CV Schutte and n/a n/a CV-31117 1970 CorrectedDKoerting

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

8. Tests conducted: Hydrostatic F PneumaticD- Nominal Operating Pressure R ExemptD

Other DPressure n/a psi Test Temp. n/a 0 F

Other: n/a


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

ITEM 2-23-037

9. Remarks


Type Code Symbol Stamp ,2/' ,JZ

Certificate of Authonrz i 9aw -//'o Expiration Date _______________________

Signed ,ASMVE Program Engineer Date ,21,r-le.7__Owner or Owner's Designee , Title


1, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure VesselInspectors and the State or Province of Minnesota and employedby HSB Insp. and Ins. Co. of Connecticut of Hartford Conn. -have inspectedthe components described in this Owner's Report during the period 0-iI o~ to 57/Io1and state that to the best of my knowledge and belief, the Owner has performed examinations and taken correctivemeasures described in this Owner's Report in accordance with the requirements of the ASME Code, Section XI.


___ ___ __ ___ ___ __Commissions MAIO.SS'/$. A18a -r, ,-1sInspector's Signature National Board, Province' and Endorsements

Date


ITEM 2-23-038

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





Address Expiration Date N/A4. Identification of System cc Code Class 3

5. (a) Applicable Construction Code ASME III, Class C 1968 Edition


(b) Applicable Edition of Section Ml Utilized for Repair/Replacement Activity 1 998E /2000A




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. 0 F

Other: n/a



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 ___________ _____



1, the undersigned, holding a valid commission issued by Ithe National Board of Boiler and Pressure VesselInspectors and the State or Province of. Minnesota and employedby 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 3L6and state that to the best of my knowledge and belief, the Owner has performed 'exa miinations and taken correctivemeasures 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, neitherthe Inspector nor his employer shall be liable in any manner for any personal injury of property damage or a loss ofany kind arising from orcnetdwith this inspection.

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

Inspector's Signature National Board, Province alnd *Endorsements

Date . C20040Date ~2oot~~

FOR NI-2OWNER'S REPORT FOR REPAIR! REPLACEMENT ACTIVITY

ITEM 2-23-039



Name1717 Wakonade Dr. E, Welch Minnesota 55089 306250-01, EC-9602



Address Expiration Date N/A4. Identification of System CL Code Class 3




(c) Applicable Section Xl Code Cases N-513-2



___________________ __________ _________ ______ 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 O F

Other: n/a



ITEM 2-23-039

9. Remarks


Type Code Symbol Stamp I"/

Certificate of Au a' .Expiration Date ________________________

Signed 2 SEProgram Engineer Date 2 _______



1, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure VesselInspectors and the State or Province of. Minnesota and employedby HSB Insp. and Ins. Co. of Connecticut of Hartford Conn. have inspectedthe components described in this Owner's Report during the period /2 a~ /0/ ,y to ol o a 0'and state that to the best of my knowledge and belief, the Owner has performned examinations and taken correctivemeasures described in this Owner's Report in accordance with the requirements of the ASME Code, Section XI.


____ ___ ____ ___ ___ Commissions i/W S'&/3 411 x-Z sInspector's Signature National Board, Province and Enidorsements

Date'_ _ _

(I


ITEM 2-23-041

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












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: IST test per SP2366



ITEM 2-23-041

9. Remarks



Certificate of Auh Expiration Date ________________________

Signed ,ASME Program Engineer Date _ _



1, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure VesselInspectors and the State or Province of Minnesota and employedby HSB Insp. and Ins. Co. of Connecticut of Hartford Conn. have inspectedthe 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 correctivemeasures described in this Owner's Report in accordance with the requirements of the ASME Code, Section XI.


~j 4Commissions AiA./ cSV-531 / q ,B, &1ZWj~S


Date


ITEM 2-23-042









Addenda ___________ Code Cases__________




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: Hydrostatic F PneumaticD Nominal Operating Pressure F- Exempt F-/


Other: Disc leak by in accordance with IST requirements.

NOTE: Supplemental sheets in for m of lists, sketches, or drawings may be used, provided (1) size is 8 1 /2 in. x 11 in., (2) information in items1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded at the top of this form.


ITEM 2-23-042

9. Remarks


Type Code Symbol Stamp-4

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

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



1, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure VesselInspectors and the State or Province of Minnesota and employedby. HSB Insp. and Ins. Co. of Connecticut of Hartford Conn. have inspectedthe components described in this Owner's Report during the period M*. 3.0ý Zcn6 to fZc3. iq acao rand state that to the best of my knowledge and belief, the Owner has performed examinations and take'n correctivemeasures described in this Owner's Report in accordance with the requirements of the ASME Code, Section XI.


_______ _______ ______Commissions M,41 553 I iInspector's Signature National Board, Provinde and ýndorsements

Date / (. -4/ o~Oobc) I


ITEM 2-23-045








5. (a) Applicable Construction Code 8 16.34 n/a Edition






Installed Stamp

21 PRZR RELIEF Crosby Model HB-BP- n/a j2RC-1 0-1 Corrected i86I

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 O F

Other: n/a


F PRAIRIE ISLAND NUCLEAR GENERATING PLANT

FORM N 15-2 OWNER'S REPORT FOR REPAIR/ REPLACEMENT ACTIVITY IITEM 2-23-045

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


Type Code Symbol Stamp W 1

Certificate of Auth __ _ _Expiration Date __ _ _ _ _ _

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



1, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure VesselInspectors and the State or Province of Minnesota and employedby HSB Insp. and Ins. Co. of Connecticut of Hartford Conn. have inspectedthe 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 correctivemeasures described in this Owner's Report in accordance with the requirements of the ASME Code, Section XI.


Commissions A%1A1/0551$3/Inspector's Signature National Board, Provi -nce and Endorsements

DateV

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

ITEM 2-23-046

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



Address Repair Organization P.O. No., Jc3. Work Performed by Owner Type Code Symbol Stamp N/A



4. Identification of System MVS Code Class 1

5. (a) Applicable Construction Code B16.34 Edition





IComponent Name I Manufacturer IManufacturer I Nat'l Bd # I Other ID IYr Built IC,

2

)b No., etc


8. Tests conducted:

Replaced inlet flange fasteners.

Hydrostatic F- Pneumatic[

Other W- Pressure

] Nominal Operating Pressure F- Exempt R.

n/a psi Test Temp. n/a

Other: n/a



ITEM 2-23-046

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


Type Code Symbol Stamp A//4

Certificate of Aut _ _ _ Expiration Date __ _ _ _ _

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



1, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure VesselInspectors and the State or Province of ' Minnesota and employedby HSB Insp. and Ins. Co. of Connecticut of Hartford Conn. have inspectedthe components described in this Owner's Report during the period ._____2_0__7/ __4 to 0,//8/oand state that to the best of my knowledge and belief, the Owner has performed examinations and taken correctivemeasures 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 ofany kind arising from or..connected with this inspection.

__ __ __ __ __ __ __ _ Commissions Mt/v0!9i45 41


Date ,ý-.00-L

C,

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

ITEM 2-23-047




Date 12/5/2006

Sheet 1

96871-01

of 2










Component Name Manufacturer Manufacturer Nat') Bd # Other ID Yr Built Corrected, ASMEName Serial # Removed, or Code

Installed Stamp

7.

8.

Pressurizer to CV-31229 Bypass Kerotest 2RC-7-1 CorrectedD

Description of Work Replaced bonnet.

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

Other F1 Pressure psi Test Temp. CF

Other: n/a



ITEM 2-23-047

9. Remarks


Type Code Symbol Stamp Ak

Certificate of Au 414.- Expiration Date______________________

Signed ,ASME Program Engineer Date ______ ___



1, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure VesselInspectors and the State or Province of Minnesota and employedby HSB Insp. and Ins. Co. of Connecticut of Hartford Conn. have inspectedthe components described in~this.Owner's Report during the period 102/o3/o4 to /a7A/oýh-o6and state that to the best of my knowledge and belief, the Owner has performed examinations and taken correctivemeasures described in this Owner's Report in accordance with the requirements of the ASME Code, Section XI.


/~ Commissions /W,%/ O5 VS3/ q,34~Inspector's Signature National Board, Province and Endorsements

Date 1 C90.06,


ITEM 2-23-048

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






4. Identification of System RH Code Class 1

5. (a) Applicable Construction Code 831.1 1967 Edition


(b) Applicable Edition of Section Xl Utilized for RepairiReplacement Activity 1 998E / 2000A



7. Description of Work Buffed out indication.

8. Tests conducted: Hydrostatic E PneumaticD Nominal Operating Pressure [_ Exempt

Other F] Pressure psi Test Temp. 0 F

Other: n/a



ITEM 2-23-048

9. Remarks


Type Code Symbol Stamp 4kAZ4

Certificate of Authoriz Expiration Date _______________________

Signed ,ASME Program Engineer Date X?1 , ___



1, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure VesselInspectors and the State or Province of. Minnesota and employedby HSB Insp. and Ins. Co. of Connecticut of Hartford Conn. have inspectedthe 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 correctivemeasures described in this Owner's Report in accordance with the requirements of the ASME Code, Section Xl.


___ __ __ ___ __ __ Commissions A-TA] OSIS'/3//,AInspector's Signature National Board, Province and Endorsements

Date


ITEM 2-23-049

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

Name2. Plant Prairie island Nuclear Generating Plant Sheet 1 of 2





4. Identification of System SI Code Class 2


Addenda n/a Code Cases n/a(b) Applicable Edition of Section XI Utilized for Repair/Replacement Activity 1 998E / 2000A



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 0 F

Other: n/a



ITEM 2-23-049

9. Remarks


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


1, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure VesselInspectors and the State or Province of Minnesota and employedby HSB Insp. and Ins. Co. of Connecticut of Hartford Conn. have inspectedthe 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 correctivemeasures described in this Owner's Report in accordance with the requirements of the ASME Code, Section XI.


__ __ __ __ __ __ __Commissions 1WA10,5'/5731 A 'X, A15'Inspector's Signature National Board, Province and En'dorsements

Date . -,F' A

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