ML062090368

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Braidwood Station, Unit 1, Inservice Inspection Summary Report, Cover Through Page 3-53
ML062090368
Person / Time
Site: Braidwood Constellation icon.png
Issue date: 07/28/2006
From: Poison K J
Exelon Generation Co, Exelon Nuclear
To:
Document Control Desk, Office of Nuclear Reactor Regulation
Shared Package
ML062090366 List:
References
BW060076
Download: ML062090368 (61)
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Text

_____Exel_n~xeion GeneTation Co npany.LLC Ni__ci Braidwood Station July 28, 2006 BW060076 U.S.NuclearRegulatory Commission ATTN: DocumentControlDesk Washington.

ft C.20555-0001 Braidwood Station, Unit 1 FacilityOperatingLicense Nos.NPF-72 NRC Docket No.STN 50-456

Subject:

Braidwood Station, Unit I Inservice Inspection Summary Report Enclosedisthe post-outage summary report (Le., the 90dayreport) for Inservice Inspectionexaminationsconductedduringthe BraidwoodStation,Unit 1 twelfth refueling outage (Al R12).This report is submitted in accordance with therequirementsof the American Society of Mechanical Engineers (ASME)Boiler and Pressure VesselCode,Section Xl,"Rules fortheInservice InspectionofNuclear Power PlantComponents,"Article IWA-6200,"Requirements."

Please direct any questions you may have regarding thissubmittalto Mr.DaleAmbler,Regulatory Assurance Manager, at (815)417-2800.Since rely, Keith~~'olson Site Vice President Braidwood Station

Enclosure:

BraidwoodStation lSl Outage Report for Al Rl2 BRAIDWOODSTATION UNIT 1INSERVICEINSPECTION

SUMMARY

REPORT FOR: Interval 2, Period 3, Outage 1 A1R12 Outage STATION ADDRESS: Braidwood Station 35100 S.Rt.53 Suite 84 Braceville,Illinois60407 UNIT 1 COMMERCIAL SERVICE DATE: July 29, 1988 OWNER'S ADDRESS: Exelon Generation Co., LLC 300 Exelon Way Kennett Square PA 19348 Exek~n~Braidwood Station Unit 1 A1R12 ISI Outage Report TABLE OF CONTENTS DESCRIPTION:

PAGE: TITLE PAGE TABLE OF CONTENTS ii 1.0-INSPECTION INFORMATION 1-1 to 1-2 2.0-INSERVICE EXAMINATION

SUMMARY

2-1 to 2-4 3.0-INSERVICE/PRESERVICECOMPONENT DETAILED 3-1 to 3-53 EXAMINATION TABLES 4.0-NIS-1 FORM 4-1 to 4-3(OWNER'SREPORT FOR INSERVICE INSPECTION) 5.0-REPORT OF CONTAINMENT 5-1 to 5-5 DEGRADATION (IWE/IWL)6.0-NIS-2 FORMS, Cover page pIus 32 pages of Attachments 6-1 to 6-33(OWNER'SREPORT FORREPAIRSOR REPLACEMENTS)

Braidwood Station Unit 1AlRl 2 ISI Outage Report 1.0INSPECTIONINFORMATION

1.1 Summary

Second IntervalInserviceInspections (ISI)of ASME Class1,2, and 3 components were conducted at Braidwood Station Unit 1 between November 19, 2003 to May 5, 2006, with the majority of these inspectionsbeingperformed during the Braidwood Station Unit 1 twelfthrefuelingoutage (A1R12).This outage is reflected in the Braidwood ISI schedule by the code 231 (Interval 2, Period 3, Outage 1).Theexaminationswere performed in accordance withtherules and regulations of Section Xl, Division 1, Rules for Inservice InspectionofNuclear Power Plant Components,"

of theAmericanSociety of Mechanical Engineers (ASME)BoilerandPressure Vessel Code, 1989 Edition, no addenda, pursuant to therequirementsof Title 10, Part 50.55a of the Code of Federal Regulations (1 OCFR5O.55a).

The ContainmentInspectionProgram was developed and implemented in accordance with the requirements and intent ofSubsectionsIWEandIWL of ASME Section Xl,1992Edition through the 1992 Addenda, pursuant to the requirements of IOCFR5O.55a.

InadditiontotheASMESectionXlrequirements,certain NRC augmented lSl inspections were required duringA1R12.The Braidwood Unit 1 augmented ISI examinations included: a)Examination of the Class 1 pressure boundary for leakage at nominaloperatingpressure, in accordance withGenericLetter 88-05.b)Bare MetalVisualexamination of the Unit 1 pressurizersteamspace nozzles in accordance withBraidwoodStation response to NRC Bulletin 2004-01,"Inspection of Alloy82/182/600Materials Used in theFabricationof Pressurizer Penetrations andSteamSpacePipingConnectionsat Pressurized-Water Reactors".

c)Visual and volumetric examinations of pressure retaining components above the reactor vessel head andvolumetricexamination of reactor vessel head penetrations in accordance with First Revised NRC Order EA-03-009.

There were no significant findings associated with any of the augmented ISI examinations.

Reportsforthese examinations have been submitted under separate transm ittalswhenrequired.

1.2 Identification

ofExaminationRequirementsTheSecond Interval lSl Program contains the Component Selection tables.Thesetables are presented in a tabularformatconsistent with the tables found in subsections IWB,IWC,IWD, IWE, and IWF-2500 oftheASME code.The NDE tables include the corresponding code category, item number, and component/weldpopulationselection in conformance with examination requirements and intent of Subsection IWA, IWB,IWC,IWD, IWE, and IWF ofSectionXlof the ASME Code.Programnotes and relief requests and additional information are identified in the basis column.Page 1-1 Exek5n~BraidwoodStation Unit 1 A1R12 ISI Outage Report 1.3 Exempted Components ASME Class1,2, and 3components(or partsofcomponents)that are notincludedin the Component inspection tablesandthat are exempt from examination, as specified inSectionXlSubsection IWB, IWC, IWD, and IWF are identified in the Braidwood Station BoundaryBasisdocument,along withreferenceto the justification(s) for exempting the component/system.

1.4 ISI Program Implementation BraidwoodStationpersonnel, or theirdesignee,visuallyexamined (VT-i, VT-2, VT-3, VT-iC,andVT-3C)and/orNDE examined (UT, PT, MT)ASME components.

The components examined comply with the ISI Program Schedule, Braidwood Station Technical Specifications (TS), and/or compliance with the ASME Section Xl Repair/Replacement Program.All ISI NDE,includingevaluation of flaw indications, wereperformedin accordance with the requirements stipulated under Section Xl, Sub-article IWA-2200:"Examination Methods".Certified personnel performedandevaluated all NDE.Personnel were certified to the requirements of theAmericanSociety for Non-destructive Testing SNT-TC-iA, 1984 Edition.The NDE procedures were developedandcertified in conformance with ASME Section VandXl, 1989 Edition, as applicable.

In addition, ultrasonicexaminationpersonnel were qualified in accordance with ANSI/ASME CP-189, 1995.Certified personnel performedandevaluated visual examinations (VT-i, VT-2, and VT-3)of Class 1, 2, and 3 components and supports.Personnel werecertifiedto the requirements of theAmericanSociety for Non-destructive Testing SNT-TC-iA,1984Editionand/orASME Section Xl 1989, as applicable.

Certified personnel performedandevaluated visual examinations (VT-i, VT-3, VT-i CandVT-3C)of Containment Structures.

Personnel werecertifiedto the requirements of the ANSI/ASNT CP-189, 1991 revision, and/or ASMESectionXl 1992 through 1992 Addenda, as applicable.

1.5 Witness

and Verification of Examination The inservice inspections were witnessed and/or verified by the Authorized Nuclear Inservice Inspectors (ANII), L.Malabanan and R.White.The inspectors are associated with Hartford Steam Boiler Inspection and insurance Company of Connecticut, ChicagoBranch,at 2443 Warrenville Rd., Suite 500, Lisle, Illinois 60532.Page 1-2

2.0 INSERVICE

EXAMINATION

SUMMARY

Exe6n~BraidwoodStation Unit 1 A1R12 1StOutageReport The following is a summary of ASME Section XI, Risk Informed IS!, and augmented examinations performed during theBraidwoodStation Unit i AiRi2 refueling outage.Refer to thecomponentdetailed examinationtabulationsofSection 3.0 for additional information on specific welds, components,supports,snubbersand pressure test examinations and their respective results.2.1 Inservice Weld/Component Summary Chemical&VolumeControl (CV)12 Feedwater (FW)i 5MainSteam(MS) i 0ReactorCoolant (RC)16 Residual Heat Removal (RH)1ReactorCoolant (RY)14 Steam Generator (SG)4 SafetyInjection(SI) 4EssentialService Water (SX)i TOTALS 78*Non-SectionXlAugmented examinations and Risk Informed ISI socketweldVT-2examinations are not included in these counts but are contained in Section 3.1.2.2 InserviceComponentSupportSummary Number of SYSTEM EXAMINED Component Supports Containment Spray (CS)Chemical&VolumeControl (CV)4 Feedwater (FW)2ReactorCoolant (RC)8 Residual Heat Removal (RH)4ReactorCoolant (RY)i SafetyInjection(SI) 25EssentialService Water (SX)i TOTALS 50 containment~...(,~)Page 2-i

2.3 InserviceSnubberSummary

Exeloit Braidwood Station Unit 1A1R12ISI Outage Report Main Steam (MS)87 Reactor Coolant (RC)24 18 Residual Heat Removal (RH)44ReactorCoolant (RY)1010 SafetyInjection(SI)2121 TOTALS 68 61 2.4InservicePressureTestSummary 2.4.1 PressureTestTest-Block Inspection SummarySummaryof components contained in this table are those pressure test blocks that were examined for Section XI Inservice Inspectioncredit.Braidwood has adoptedCodeCase N-522 as previously approved forusein Regulatory Guide 1.147 Revision 13,"InserviceInspectionCodeCase Acceptability, ASME Section Xl, Division 1"for systems penetrating primary containment.

Process Sampling (PS)2 1*SafetyInjection(SI) 2 i**PlantSystemsPressurizedDuring Mode 3 (ZZ)1&2 4**TOTALS ii*Tests credited to the second period.Tests were completed after the Al Ri 1reportwas submitted.

    • Portion of three test blocks (AOl Sl-000005-M04-02H, AOl ZZ-000005-M04-02A, and AOi ZZ-000005-M04-02B) were completed during Al Ri 2, the remainder of these test blocks will be completed in AiRi3.Chemical&VolumeControl

(~.,V)11 ContainmentFuelPool CoolinQ O-L~)2 2*Page 2-2 BraidwoodStation Unit 1AlRi 2 ISI Outage Report 2.4.2 BoratedBoltingInserviceInspection SummarySummaryof components containedinthis table are thoseinsulatedboratedboltedconnections that were examined forSectionXl Inservice Inspection credit.Inspections on these connections are performed per the commitments in Relief Request 12R-i2, l2R-i3, and l2R-3O, as applicable, of the IS!Program Plan.NumberofNumber of SYSTEM EXAMINED Connections Connections

_______________________

Examined by VT-2 Examined by VT-i Chemical&VolumeControl 17 1 (CV)Pressurizer (RY)1 0 Reactor Coolant (RC)130 Residual Heat Removal (RH)12 1 TOTALS432 2.5 Steam Generator (SG)EddyCurrentTesting Summary In compliance with Braidwood StationTechnicalSpecification (TS)5.5.9,"Steam Generator TubeSurveillanceProgram,"andAmericanSocietyofMechanical Engineers (ASME)BoilerandPressure Vessel (B&PV)CodeSectionXl 1989 Edition, IWB 2500-i, Examination CategoryB-Q,Item Bi6.20, SG eddy currentexaminationswere performed during the Braidwood Station Unit 1 Cycle 12refuelingoutage (AiR12).In addition, the inspections were performed consistent with the ElectricPowerResearchInstitute (EPRI)"PWR Steam Generator Examination Guidelines,"

Revision 6,andNuclear Energy Institute NE!97-06,"Steam Generator Program Guidelines,"

Revision 2.The following inspections were performed during this outage.100%full lengthbobbincoil eddy current in all four SGs20%hot leg top of tubesheet (+1-3 inches)+Point TM eddy current in all four SGs20%hot leg dents and dings~2.0 volts÷Point TMDiagnostic

+PointTMeddycurrent based onbobbincoileddycurrent results100%Visualinspection ofPreviouslyInstalledTube Plugs100%Visual Inspection of NewlyInstalledTube Plugs The modes of tube degradation found during Al Ri2 were fan bar wear,latticegrid wear and foreign object wear.Asa result of theeddycurrent inspection of the SGs, a total of 28 tubes were removed from service by mechanical tube plugging.The 28 tubes were removed from service duetoeither having wear associated with secondary side foreign objects or were required to be removed from service in order to bound high flow locations where secondary side foreign objects could not be retrieved.Onetube in the 1A SG had tubeweargreater than the TS plugging limit of~40%.PursuanttoTS5.5.9.c,"InspectionResultsClassification,"

the lA SGwasclassified asinspectioncategory C-2.No additional scope expansion wasrequiredsince 100%full-length bobbineddycurrent inspectionwasalready being performed in the iA SG.Page 2-3 BraidwoodStation Unit 1 Al R12 1St Outage ReportOnetube in the lB SG had tubeweargreater than the TS plugginglimitof>40%.PursuanttoTS5.5.9.c,"Inspection Results Classification,"

the 1 B SGwasclassified asinspectioncategoryC-2.

No additional scope expansion wasrequiredsince 100%full-lengtheddycurrent inspectionwasalready being performed in the lB SG.There were no tubes containingweargreater than the TS plugginglimitof~40%in the 1 C and 1 D SGs.PursuanttoTS5.5.9.c,"InspectionResultsClassification,"

the 1 C and 1 D SGs were classified asinspectioncategory C-i.There were no scanning limitationsduringtheeddycurrent examinations.

The table below,"EquivalentTubePluggingLevel,"provides the total tube plugging history andequivalentplugging levels to-date for the Braidwood Station, Unit 1 SGs.Note: The Braidwood Unit 1steamgenerators were replaced during the Cycle 7refuelingoutage (November 1998).Equivalent Tube Plugging Level~__________________________________________

1~~ui~up.~Tubes Plugged at Factory 1 2 0 03 Tubes Plugged in A1RO8 1 000 1 Tubes Plugged inAiRlO 8iO30 2i Tubes Plugged inAiRil 02 2 1 5 Tubes Plugged inAlRl2 11 17 0 0 28 Total Tubes Plugged21315 1 58 Total Tubes Plugged (%)0.32%0.92%0.08%

0.02%0.22%Note:Steam Generator Inspections Were NotPerformedDuring Al R09.Additionalinformation concerningthesteam generatoreddycurrentinspectionresults can be obtained inthereportsubmitted to the Nuclear Regulatory Commission as required by Technical Specification 5.6.9.Page 2-4 Braidwood Station Unit 1 A1R12 151 Outage Report 3.0 COMPONENTDETAILEDEXAMINATION TABLES 3.1 Detailed Inservice Weld/Component Table(s): The table for thissection(Pages 3-5 to 3-22)lists the examinations performed forSectionXlInserviceandAugmented Inspection requirements for Class 1 and 2 welds and components.

The general format of how the table is set-up is shown below.A description of theinformationcontained in each column can be found in Section 3.5.Section~l 181 Identifier Line Relief Program Code Exam Actual Results Cat.Item Descri tion Number/EPN Request Notes Coverage Summary Exam Inspection Comments(A)(B)(C)(D)(E)(F)(G)(H)(I)(K)3.1.1 Detailed Preservice Weld/Component Table(s): The table forthissection (Page 3-23)lists the baseline examinations performed for Section XI Preservice Inspection requirements for Class 1 components replaced during A1R12.The general format of how the table is set-up is shown below.A description of theinformationcontained in each column can be found in Section 3.5.SectionXl~ISIIdentifierLine Relief Program Code Exam Actual Results Lc~t.Item I Description Number/EPN

~q~st Notes Covera e Summary Exam I Inspection Comments(A)(B)(C)(D)(E)(F)(G)(H)(I)(K)(J)3.2 Detailed lnserviceComponentSupport Table: The table for this section (Pages 3-24 to 3-32)lists the examinations performed forSectionXlInserviceInspection requirements for Class i and 2 componentsupports.Thegeneral format of how the table is set-up is shown below.Adescriptionof theinformationcontained in each column can be found in Section 3.5.SectionXi ISI Identifier Line Number/EPN Relief Program Exam Results Cat.Item Description Re uestNotesSummary Inspection Comments(A)(B)(C)(D)(E)(G)(I)(K)li~Page 3-i Exekm Braidwood Station Unit 1AlRi 2 1St Outage Report 3.3 Detailed Inservice Snubber Table: The table for this section (Pages 3-33 to 3-41)lists the examinations performed forSectionXlInservice Inspection requirements for Class 1 and 2 snubbers.The general format of how the table is set-up isshownbelow.

Adescriptionof theinformationcontained in each column can be found inSection3.5.

I Section XI ISI IdentifierLineNumber/EPN Relief Program Exam Results~Item Description Request Notes Summary I Inspection Comments(A)(B)(C)(0)(E)(G)(I)(K)(J)3.3.1 Detailed Preservice Snubber Table: The table for thissection(Pages 3-42 to 3-43)lists the baseline examinations performed for Section XI Preservice Inspection requirements for Class 1 and 2 snubbers replaced during Al Ri2.The general format of how the table is set-up is shown below.Adescriptionof theinformationcontained in each column can be found inSection3.5.

Section XI'ISl identifier Line Number/EPN Relief Program Exam Results Cat.Item Description RequestNotesSummary Inspection Comments(A)(B)(C)(D)(E)(G)(I)(K)(J)3.4 DetailedlnservicePressure Test Table(s): The table forthissection(Pages 3-44 to 3-48)lists the examinations performed forSectionXlInservice and Augmented Inspection requirements for Class 1 and 2 pressure test blocks.The general format of how the table is set-up is shown below.Adescriptionof theinformationcontained in each column can be found in Section 3.5.[Section Xl ISI Identifier Relief Program Exam Results Cat.Item I Desc~p~on Re uest jj~tes Summary I Inspection Comments(A)(B)(0)(E)(G)(i)(K)(J)Page 3-2 Exekit.Braidwood Station Unit 1 A1R12 1St Outage Report 3.4.2BoratedBoltedConnectionInspections The table for this section (Pages 3-49 to 3-53)lists the examinations performed for Inservice Inspection pressure testing requirements ofSectionXlClass 1 and 2 boratedboltedconnections.

The general format of howthetable is set-up isshownbelow.

A description of theinformationcontained in each column can be found in Section 3.5.Relief Program Exam Results ReauestNotesSummary

~-~----1 (D)(E)(G)(I)3.5 General Inservice Report Information

3.5.1 ReportColumnDescriptions

(A)This column contains the Section Xl Category and Item identifiers for the specified component.

There are special cases,likesnubbers, where an"S has been added to the end of the Section XI Item identifier.

This was done to allow easy sorting of the snubber population by the IS!database.(B)This column contains the 151 Identifier that the IS!Program uses todistinguishcomponents.(C)This column contains the linenumberor equipment piece number (EPN)associated with the component for identification.(D)This column identifies the IS!Program Plan relief request(s) that is associatedwiththatcomponent.

A complete copy of the relief request can be found in the ISI Program Plan.(E)This column identifies the IS!Program Plan note(s)that is associated with thatComponent.A complete copy of the Program note can be found in the IS!Program Plan.(F)This Column identifies thepercentageof codecoverageachieved for the associatedvolumetricexamination forthatcomponent.(G)This column summarizes the exams performed during this outage for the associated Component.(H)This column identifies actual exams performed duringthisoutage for the associated Component.(I)This column summarizes the results for exams performed during this outage for the associated component.(J)This row states inspection comments, when applicable, for the associated component.(K)This column specifies the description of the associated component.SectionXl ISI Identifier

[çjte~j~scription I Inspection Comments(A)(B)(K)(J)Page 3-3 BraidwoodStationUnit 1AlRi 2 lSI Outage Report3.5.2Report Abbreviations BMV Bare Metal Visual Inspection FUNCT-Snubber Functional Test GE/IND-Geometry/Indication GEOM-Geometry IND-Indication IR-Issue Report NRI-No Recordable Indications MT-Magnetic Particle Inspection PT-Liquid Penetrant Inspection SUR-SurfaceExam TBD-To Be Developed WO-Work Order UT-Ultrasonic Inspection VOL-Volumetric Exam VOL-E-Volumetric Exam of anExtendedVolume VT-Visual Inspection Page 3-4 Braidwood Station Unit 1 A1RI2 1St Outage Report Section 3.1 DetailedlnserviceInspection Weld I Component Listing (Page 1 of 18)SYSTEM: Containment Spray System (CS)I Section x~I 1St Identifier

[Cat.__Item 10escriptio~~

Inspection Comments Line Number!EPN Relief Program~Exam Summary Actual I Exam Resu~J C-C C03.20 1CS-02-SWO1360DEGREE WELD 1CS1OAA-&ED PIPE SADDLE 12R-15 NOTE 4 100 SUR PT NA!Page 3-5 Exekit Braidwood Station Unit 1 A1R12 1St Outage Report Section 3.1 Detailed Inservice Inspection Weld/Component Listing (Page 2 of 18)SYSTEM: Chemical&Volume Control System (CV)~~juneNumber/EPN

~InspectionComments A-A AOl 11 1 CV-05-03 1 CVA3B-2~NOTE 4VT-2VT-2 NA!PIPE-ELBOW A-A ROi.il 1CV-05-04 1CVA3B-2~NOTE 4 vT-2 VT-2 NA!ELBOW-PIPEA-AAOl.11 1CV-05-05 1CVA3B-2~NOTE 4VT-2VT-2 NA!PIPE-ELBOW_____A-A A01.il 1CV-05-06 1CVA3B-2~NOTE4VT-2VT-2 NA!ELBOW-PIPE________A-A ROill 1CV-05-13 1CVA3B-2"NOTE4 VT-2 VT-2 NA!PIPE-ELBOW_____________A-A A01.I1 1CV-05-14.01 1CVA3B-2"NOTE4 VT-2 VT-2 NA!ELBOW-PIPE B-G-2 807.50 1CV-06-B1 1CV14GA-1.5" VT-i VT-i NA!_____FLANGE BOLTING(4STUDS)__________________________

B-G-2 807.50 ICV-06-B2 1CVI4GD-1.5'VT-iVT-I NA!FLANGE BOLTING(4STUDS)____________________

A-AA01.111CV-11-06 1CVA6AA-2" NOTE4'/T-2 VT-2 NA!PIPE-ELBOW_____________

A-A R0l.11 1CV-li-07 1CVA6AA-2" NOTE4VT-2VT-2 NA!ELBOW-P!PE B-G-2 B07.50 1CV-16-Bi icvi4oc-i,5'VT-iVT-i NA!FLANGE BOLTING (4 STUDS)_____________________

__________

________P-A P01.20 1CV-21-0l 1CVO1PA NOTE450 VOL-E UT-35 NA!1CVO1PA-i PUMP CASING-FLANGE NOTE 7 UT-45 NA!___________________

_____________

_________UT-60L NA!A-A P01.201CV-21-031CVO8AA-4' NOTE 4 93.5 VOL-E UT-35 NA!ELBOW-ELBOW NOTE 7 UT-45 NRI____________________________________

____________________UT-60LNA!A-A P01.20 1CV-21-04 lCV08AA-4~

NOTE 4 98.7 VOL-E UT-35 NA!ELBOW-PIPE NOTE 7 UT-45 NA!UT-60LNA!A-A R01.20 1CV-21-07 1CVO8AA-4 NOTE450 VOL UT-45 NA!VALVE1CV8481A

-PIPE NOTE 7UT-60LNA!A-A A01.20 1CV-21-081CVO8AA-4NOTE450 VOL-E UT-45 NA!PIPE-TEE NOTE 7UT-60LNA!R-A R01.20 1CV-21-ii 1CV08AA-4~

NOTE4 100 VOL-E UT-45 NA!ELBOW-PIPE NOTE 7 A-A P01.201CV-21-121CVO8AA-4 NOTE4 100 VOL-E UT-45 NA!PIPE-ELBOW NOTE 7 A-A Aol 20 1CV-21-13 1CV08AA-4~

NOTE4100 VOL-E UT-45 NA!ELBOW-PIPE NOTE 7 Page 3-6 Exekn.Braidwood Station Unit 1 A1R12 1St Outage Report Section 3.1 DetailedInserviceInspection Weld I Component Listing (Page 3 of 18)SYSTEM: Chemical&Volume Control System (CV)[~ct~~Number/EPNl 8t j~~m 1~~JInspectionComments A-A P01.11 1AC-36-15 1CVA3AA-2~

NOTE4VT-2VT-2 NA!PIPE-ELBOW______A-A AOl.11 1 AC-36-1 6 1 CVA3AA-2~NOTE 4 VT-2 VT-2 NP!ELBOW-PIPE A-A P01.11 1AC-36-17 1cVA3AA-2~

NOTE 4 VT-2 VT-2 NA!PIPE-ELBOW_____A-A P01.11 1AC-36-18 1CVA3AA-2~

NOTE 4VT-2VT-2 NA!________ELBOW-PIPE_____A-A A0i.il lRc-37-i1 1CVA7AA-2" NOTE 4 VT-2 VT-2 NA!PIPE-ELBOW_____P-A P01.11 1AC-37-12 iCVA7AA-2~

NOTE 4VT-2VT-2 NP!ELBOW-PIPE C-CC03.301AHP-01-CVP-01 (A PUMPICVO1PA I2R-02 NOTE4100 VT-1 NP!PUMP SUPPORT PAD I2R-lS 77.7 SUP NA!Examination andcoverageachieved in accordance with Relief Aequest 12A-02.Limitationsforattachments CVP-2 and CVP-4 reduce liquid penetrant examinationcoverageto 77.7%______Page 3-7 Exet~n.Braidwood Station Unit 1 AIR12 1St Outage Report Section 3.1 Detailed Inservice Inspection Weld I Component Listing (Page 4 of 18)SYSTEM:FeedwaterSystem (FW)SectionXI ISI Identifier Line Number!EPN Relief Item Description J,,,Request Program J Code Exam Notes~verag~I,.Summary Actual Exam~esu~J Inspection Comments A-A P01.11 1FW-01-19 1FWO3DD-l&

NOTE4100 VOL-E UT-45 NRI P01.18 PIPE-ELBOW NOTE7 A-A P01.11 1FW-01-20 1FWO3DD-16" NOTE4100 VOL-E UT-45 NA!P01.18 ELBOW-PIPE NOTE7 A-A P01.11 1FW-Oi-33 1FW03DD-16~

NOTE4100 VOL-E UT-45 NP!P01.18 PIPE-ELBOW NOTE7 P-A R01.11 1FW-03-04 1FWO3DB-16" NOTE4 100 VOL-E UT-45 NA!P01.18 VALVE 1FWOO9B-P!PE NOTE 5 NOTE 7 UT-60 NA!A-A P0111 1 FW-03-05 I FWO3DB-16" NOTE4100 VOL-E UT-45 NP!P01.18 P!PE-P!PE NOTES NOTE 7 A-A P01.11 1FW-03-O5A 1FW03DB-16~

NOTE4 100 VOL-E UT-45 NP!P01.18 PIPE-PENETRAT!ON(1PC-084)NOTES NOTE_7 A-A P01.11 1FW-04-0461FW03DC-16~NOTE4 100 VOL-E UT-45 NA!P01.18 PIPE-PIPE NOTE5 NOTE 7 A-A P01.11 1FW-04-05 1FWosDc-16" NOTE4100 VOL-E UT-45 NP!P01.18 PIPE-PENETRATION (1Pc-o87)NOTE 5 NOTE 7 A-A P01.11 1FW-04-17 1FwosDc-16' NOTE4100 VOL-E UT-45 NA!P01.18 PIPE-ELBOW NOTE7 P-A P01.11 1FW-04-18 1FWO3DC-16" NOTE4100 VOL-E UT-45 NA!P01.18 ELBOW-PIPE NOTE7 A-A P01.11 1FW-04-19 1FWO3DC-16° NOTE4 100 VOL-E UT-45 NA!P01.18 PIPE-ELBOW NOTE7 A-A P01.11 1F\N-05-29 1FW81BB-6" NOTE4 100 VOL-E UT-45 NPI P01.18 PIPE-TEE NOTES NOTE 7 UT-45 NA!Two different examination frequencies (2.25 MHz and 5.0 MHz)were utilized.P-A P01.11 1FW-05-31 1FW87CB-6~

NOTE4100 VOL-E UT-45 NP!P01.18 TEE-PIPE NOTES NOTE 7 UT-45 NP!Two different examination frequencies (2,25 MHz and 5.0 MHz)were utilized.P-A P01.11 1FW-05-36 1FW87CB-6" NOTE4 100 VOL-E UT-45 NA!P01.18 PIPE-l6~x6~VESSELET NOTES NOTE 7 A-A P01.111FW-10-321FW87CC-6" NOTE4 100 VOL-E UT-45 NP!P01.18 TEE-PIPE NOTES NOTE 7 UT-45 GEO Two different examination frequencies (2.25 MHz and 5.0 MHz)were utilized.Page 3-8 Exekn.BraidwoodStationUnit 1 A1R12 IS!Outage Report Section 3.1 DetailedInserviceInspection Weld/Component Listing (Page 5 of 18)SYSTEM: MainSteamSystem (MS)I~I td~nf e jJne Number/EPN~e!ief~~~rc~9ram~~

Inspection Comments I C-C C03.20 1MS-01-SWO8 TO SWO9 1MSO1AD-30.25"

!2A-15 NOTE4100 (8)LUG ATrACH.FOP 1MSO8007S P-A P01.20 1MS-06-3O lMS13AB-8~

NOTE4100 PIPE-ELBOWNOTE 5 NOTE 7 P-A P01.20 1MS-06-31 1MS13AB-8" NOTE4100 ELBOW-PIPE NOTES NOTE 7 A-AP01.201MS-06-32 PIPE-ELBOW IMS13AB-&NOTE 4 NOTE S NOTE 7 100 P-A AOl.20 IMS-06-33 ELBOW-PIPE 1MS13AB-8' NOTE 4 NOTE 5 NOTE 7 100 P-A P01.20 IMS-06-34 PIPE-ELBOW IMS13AB-8" NOTE 4 NOTE S NOTE 7 100 P-A P01.20 1MS-08-34 ELBOW-PIPE 1MS13AC-8" NOTE 4 NOTES NOTE 7 100 P-A P01.20 IMS-08-35 PIPE-ELBOW 1MS13AC-8' NOTE 4 NOTE 5 NOTE 7 100 P-AP01.201MS-08-36 ELBOW-PIPE 1MS13AC-8~

NOTE 4 NOTES NOTE 7 100 P-A AOl.20 1MS-08-37 PIPE-ELBOW 1MS13AC-8~

NOTE 4 NOTE S NOTE 7 100 SUP MT MT NP!NP!VOL-E UT-45 NP!VOL-EUT-45 NP!VOL-E UT-45 NP!VOL-E UT-45 NP!VOL UT-45 NA!VOL-E UT-45 NP!VOL-E UT-45 NA!VOL-E UT-45 NA!VOL-E UT-45 NA!Page 3-9 Exek n.BraidwoodStationUnit 1 AIRI2 151 Outage Report Section 3.1 DetailedInserviceInspection Weld I Component Listing (Page 6 of 18)SYSTEM: ReactorCoolantSystem (RC)::ti:~J~jjsj~zam LC0ve4mma4E~mJ1 Inspection Comments P-A P01.20 1 PC-02-04A THERMOWELL NOTE 4VT-2VT-2 NA!BRANCH CONNECTION

-THEPMOWELL P-A AOl.201PC-02-091PC29AB-10NOTE4100 VOL-E UT-45L NP!10'BPANCHNOZZLE

-27.5"PIPE A-A P01.20 1AC-03-21A THEPMOWELL NOTE 4VT-2VT-2 NP!BRANCH CONNECTION

-THEPMOWELL P-A P01.20 1PC-17-05 1RC24AA-4~

NOTE4100 VOL-E UT-45 NP!PIPE-ELBOW________________

_____P-AAOl.201PC-17-061PC24AA-4" NOTE4100 VOL-E UT-45 NP!ELBOW-PIPE_________________

__________

A-A P01.20 1PC-17-09 1RC24AA-4" NOTE4 100 VOL-E UT-45 NP!ELBOW-PIPE___________P-A P01.20 1PC-17-1O lPC24AA-4~

NOTE4100 VOL-E UT-4S NP!PIPE-PIPE A-A P01.20 1AC-17-11 1AC24AA-4~

NOTE4100 VOL-E UT-45 NP!PIPE-ELBOW____________________________________________P-AAOl.20 1PC17-13 lPC24AA-4~

NOTE450 VOL-E UT-45 NP!PIPE-VALVE 1AY022__________

P-A P01.201AC-23-011PC22AA-1.S" NOTE 4VT-2VT-2 NP!3'Xl.S'PEDUCEP-PIPE P-A P01.20 1PC-23-02 1PC22AA-1.5~

NOTE 4VT-2VT-2 NP!PIPE-ELBOW_________________

_______P-AAOl.20 1PC-23-03 1RC22AA-1.S~

NOTE 4 VT-2 VT-2 NP!ELBOW-PIPE P-A P01.20 1PC-23-04 lRC22AA-1.5~'

NOTE 4 VT-2 VT-2 NP!PIPE-ELBOW P-A P01.20 1PC-23-OS 1PC22AA-1.5~

NOTE 4VT-2VT-2 NP!ELBOW-PIPE A-A P01.20 1PC-27-O4AA 1PC22AA-1.5' NOTE 4VT-2VT-2 NA!PIPE-ELBOW P-A P01.20 1PC-27-O5AA 1PC22AA-1.5' NOTE 4 VT-2 VT-2 NP!ELBOW-PIPE P-A P01.20 1PC-27-O6AA 1AC22AA-i.5~

NOTE 4 VT-2 VT-2 NPI PIPE-ELBOW P-A P01.20 1PC-27-O7AA 1PC22AA-1.5~

NOTE 4 VT-2 VT-2 NP!ELBOW-PIPE P-A P01.20 1PC-27-O8AA1AC22AA-1.5~NOTE4VT-2VT-2 NA!PIPE-VALVE1PC8045A P-A P01.11 1PC-29-01-03 1PC16AC-2~

NOTE4 VT-2 VT-2 NA!PIPE-BRANCH CONNECTIONPage3-10 Exekn.BraidwoodStation Unit 1A1R12ISI Outage Report Section 3.1 DetailedInserviceInspection Weld I Component Listing (Page 7 of 18)SYSTEM: ReactorCoolantSystem (RC)[~tion Xl I!Sl Identifier Line Number/EPN Relief Program Code Exam Actual Results Item ,[~~criPtion

~j,~iequest__Notes

~f~rage__Summary Exam[InspectionComments P-A P01.11 1PC-29-0l-04 1RC16AD-2~

NOTE4 VT-2 VT-2 NA!PIPE-BRANCH CONNECTION A-A P01.11 1PC-29-02-03 1RC16AC-2' NOTE4 VT-2 VT-2 NP!ELBOW-PIPE P-A P01.11 1RC-29-02-04 1PC16AD-2' NOTE4 VT-2 VT-2 NRI ELBOW-PIPE P-A P01.111PC-29-03-031PC16AC-2" NOTE4 VT-2 VT-2 NP!PIPE-ELBOW P-AP01.111RC-29-03-04 1PCl6AD-2~

NOTE4 VT-2 VT-2 NP!PIPE-ELBOW______________

______________

_____P-A P01.111PC-29-04-031RC16AC-2" NOTE 4 VT-2 VT-2 NP!ELBOW-PIPE P-A P01.111PC-29-04-041RC16AD-2" NOTE4 VT-2 VT-2 NP!ELBOW-PIPE____________________________________________

___________A-A P01.11 1RC-29-05-03 1AC16Ac-2" NOTE 4 VT-2 VT-2 NP!PIPE-ELBOW P-A P01.111PC-29-05-041AC16AD-2' NOTE 4 VT-2 VT-2 NP!PIPE-ELBOW A-AP01.111RC-29-06-03 lPC16AC-2~

NOTE 4VT-2VT-2 NRIVALVE1PC8038C

-PIPE P-A P01.111PC-29-06-041PC16AD-2" NOTE 4VT-2VT-2 NP!VALVE1AC8038D

-PIPE P-AP01.111RC-31-01 1PC14AB-2 NOTE 4 VT-2 VT-2 NP!BRANCH CONNECTION

-PIPE P-A P01.11 1AC-3l-02 1ACl4AB-2~

NOTE 4VT-2VT-2 NP!PIPE-VALVE 1 PC8039B P-A P01.11 1PC-31-03 1AC14AB-2' NOTE 4 VT-2 VT-2 NA!VALVE 1PC8039B-PIPE A-A P01.11 1PC-3l-04 lPCl4AB-2~

NOTE 4VT-2VT-2 NP!PIPE-TEE P-A P01,11 1PC-3l-05 1PC14AB-2' NOTE 4 VT-2 VT-2 NA!TEE-2X.75~REDUCER_____P-A P01.11 1PC-3l-06 1PCl4AB-2~

NOTE4VT-2VT-2 NA!TEE-PIPE P-A P01.11 1PC-3l-07 1PC14AB-2~

NOTE4 VT-2 VT-2 NA!PIPE-VALVE 1 PC8037B P-A P01.20 1PC-31-081PC26A-ZNOTE4VT-2VT-2 NA!BRANCH CONNECTION

-PIPE P-A P01.11 1PC-36-o1 1PC14AA-2" NOTE4VT-2VT-2 NP!BRANCH CONNECTION

-PIPE Page 3-li Exek:n.BraidwoodStationUnit 1 A1R12 1Sf Outage Report Section 3.1 Detailed Inservice Inspection Weld/Component Listing (Page 8 of 18)SYSTEM: ReactorCoolantSystem (RC)Section Xl IIS!Identifier I Line Number!EPN L~tem~J,~~riPtlon Inspection Comments P-A P01.11 1PC-36-02 1AC14AA-2" NOTE4VT-2VT-2 NP!PIPE-ELBOW________________________________________

______P-AP01.111RC-36-03 1PC14AA-2" NOTE4VT-2VT-2 NA!ELBOW-PIPE_________________________________

_______P-AP01.111RC-36-04 1Ac14AA-2" NOTE 4VT-2VT-2 NP!PIPE-VALVE 1AC8039A______________________________________________________

P-A P01.11 IPC-36-O5 IRC14AA-2" NOTE 4 VT-2 VT-2 NA!VALVE 1PC8039A-PIPE________P-A P01.11 1PC-36-06 1PC14AA-2° NOTE4VT-2VT-2 NP!PIPE-TEE____________________________________________________

P-A P01.11 1AC-36-07 1PC14AA-2° NOTE 4 VT-2 VT-2 NRi TEE-2X.75~REDUCER____________

_____A-A P01.11 1PC-36-08 1PC14AA-2~

NOTE 4VT-2VT-2 NP!TEE-PIPE__________________

______________________________

P-A P01.11 1AC-36-09 IPC14AA-2' NOTE 4 VT-2 VT-2 NP!PIPE-VALVE 1AC8037A_____P-AP01.111RC-36-20 1AC14AA-2" NOTE 4 VT-2 VT-2 NP!PIPE-TEE________________________________

_____P-AP01.111RC-36-22 lPC86AA-2~

NOTE 4VT-2VT-2 NA!TEE-2"Xl'REDUCER P-A P01.11 1RC-37-01 1AC14AD-2" NOTE 4VT-2VT-2 NP!BRANCH-PIPE_______________________________

P-A P01.11 IPC-37-02 1PCI4AD-2' NOTE 4VT-2VT-2 NA!_______PIPE-ELBOW_____P-A P01.111PC-37-031PC14AD-2' NOTE 4 VT-2 VT-2 NA!ELBOW-PIPE P-A P01.11 1PC-37-04 1AC14AD-2~

NOTE4VT-2VT-2 NA!PIPE-VALVE 1 RC8039D____________________P-A P01.11 1PC-37-05 1AC14AD-2~

NOTE 4VT-2VT-2 NP!VALVE 1 PC8039D-PIPE P-A P01.11 IPC-37-06 1PCl4AD-2~

NOTE 4VT-2VT-2 NP!PIPE-TEE P-A P01.11 1AC-37-07 1PCl4AD-2~

NOTE 4 VT-2 VT-2 NA!TEE-2~X,7S REDUCER A-A P01.11 1RC-37-08 1AC14AD-2~

NOTE4 VT-2 VT-2 NA!TEE-PIPE P-A P01.11 1PC-37-09 1PCl4AD-2~

NOTE 4VT-2VT-2 NP!PIPE-VALVE 1 PC8037D P-A P01.11 1PC-41-O1AA 1PC16AA-2~

NOTE4 VT-2 VT-2 NP!PIPE-BRANCH CONNECTIONPage3-12 Bcekn.BraidwoodStation Unit 1 A1R12 ISI Outage Report Section 3.1 Detailed Inservice Inspection Weld I Component Listing (Page 9 of 18)SYSTEM: ReactorCoolantSystem (RC)SectionXI IS!Identifier I Line Number/EPN Item DescriptionInspectionComments P-A P01.11 1AC-4l-O1AB1PC16AB-2"NOTE 4 VT-2 VT-2 NP!PIPE-BRANCH CONNECTION

______________________

P-A P01.11 1PC-4l-O2AA 1RC16AA-2" NOTE 4VT-2VT-2 NA!ELBOW-PIPE A-A P01.11 1AC-4l-O2AB1AC16AB-2"NOTE 4VT-2VT-2 NP!ELBOW-PIPE__________________

_____________________

P-AP01.11 1PC-41-03AA 1PCI6AA-2" NOTE 4VT-2VT-2 NP!P!PE-ELBOW___________________

P-A P01.11 1AC-41-O3AB 1AC16AB-Z' NOTE 4 VT-2 VT-2 NA!PIPE-ELBOW______P-A P01.11 1AC-41-O4AA 1Pc16AA-2~

NOTE 4VT-2VT-2 NP!ELBOW-PIPE______________________

______P-A R01.11 IPC-41-O4AB 1Pc16AB-2~

NOTE 4VT-2VT-2 NP!VALVE 1PC8038B-PIPE___________________________________________

P-A P01.11 1AC-41-O5AA 1AC16AA-2~

NOTE 4 VT-2 VT-2 NA!______PIPE-ELBOW___________

P-A P01.11 1AC-41-O6AA lACl6AA-2~

NOTE 4VT-2VT-2 NP!VALVE 1 PCSO38A-PIPE P-AP01.111PC-42-01 1PC14AC-2~

NOTE 4VT-2VT-2 NPI BRANCH CONNECTION

-PIPE A-A P01.111PC-42-021PC14AC-2' NOTE 4 VT-2 VT-2 NP!PIPE-ELBOW____________________________________________________

P-A P01.11 1PC-42-03 1PC14AC-2~

NOTE 4VT-2VT-2 NP!ELBOW-PIPE A-A P01.11 1RC-42-04 lPC14AC-2~

NOTE 4 VT-2 VT-2 NP!PIPE-VALVE 1 PC8039C___________

_____A-A P01.11 1AC-42-05 1PCl4AC-2~

NOTE4 VT-2 VT-2 NP!VALVE1PC8039C

-PIPE A-A P01.11 1PC-42-06 1PC14AC-2~

NOTE 4VT-2VT-2 NP!PIPE-TEE P-A P01.11 1PC-42-07 1PC14AC-2~

NOTE4 VT-2 VT-2 NP!TEE-2 X3/4 REDUCER A-A P01.11 1 PC-42-08 1 PC1 4AC-2~NOTE 4 VT-2 VT-2 NP!TEE-PIPE P-A P01.11 1PC-42-09 1PC14AC-2~

NOTE4 VT-2 VT-2 NP!PIPE-VALVE 1 PCBO37C P-A P01.11 IPC-42-lO 1PC14AC-2" NOTE4VT-2VT-2 NP!PIPE-TEE A-AP01.111PC-42-11 1PC14AC-2~

NOTE 4VT-2VT-2 NP!TEE-PIPE Page 3-13 Exekn.BraidwoodStationUnit 1 A1R12 IS!Outage Report Section 3.1 Detailed Inservice Inspection Weld/Component Listing (Page 10 of 18)SYSTEM: ReactorCoolantSystem (RC)Section XI IS!Identifier Cat.Item Description FInspectionComments P-A P01.11 1PC-42-12 TEE-2'Xl REDUCER 1 PC14AC-2"6-G-1B06.1801ACP-Ol-PCP-PA-01 TO 24 PCO1PA 606.190 PCPMAINFLANGE BOLT(0l TO 24)NOTE 2VT-1VT-1 NP!P-A P01.15 1PV-01-022 1ACO1R!-600 NOZZLE-SAFE END (22 DEG.)Bare metal visual examination in accordance with MAP 2003-039.!2A-16 NOTE4 BMV BMV NA!NP!P-A P01.15 1PV-01-023 1RCO1R 1-600 SAFE END-NOZZLE (67 DEG.)Bare metal visual examination in accordance with MAP 2003-039.!2P-16NOTE 4BMVBMV P-A P01.15 1PV-O1-024 1PCO1P 1-600 SAFE END-NOZZLE (113 DEG.)Bare metal visual examination in accordance with MAP 2003-039.!2P-16 NOTE 4 BMV BMV NP!P-A P01.15 1AV-0l-025 1RCO1R 1-600 NOZZLE-SAFE END (158 DEG.)Bare metal visual examination in accordance with MRP 2003-039.12P-16 NOTE 4BMVBMV NP!P-A P01.15 1AV-01-026 1ACO1P 1-600 NOZZLE-SAFE END (202 DEG.)Bare metal visual examination in accordance with MAP 2003-039.12P-16 NOTE 4BMVBMV NP!P-A P01.15 1AV-01-027 1RCO1P 1-600 SAFE END-NOZZLE (247 DEG.)Bare metal visual examination in accordance with MAP 2003-039.I2R-16 NOTE 4 BMV BMV NP!P-A P01.15 1AV-01-028 1PCOIA 1-600 SAFE END-NOZZLE (293 DEG.)Bare metal visual examination in accordance with MAP 2003-039.l2P-16 NOTE 4 BMV BMV NP!P-A P01.15 1RV-01-029 1PCO1R 1-600 NOZZLE-SAFE END (338 DEG.)Bare metal visual examination in accordance with MAP 2003-039.12P-16 NOTE4 BMV BMV NPI B-E B04.13 1AV-02-!NSTA.

NOZZLES 1ACO1A 1-600 Ax VESSEL INSTRUMENTATION NOZ.VT-2VT-2 NA!B-G-l 606.10 1AV-03-NUTS (01 TO 54)1PC01P 12R-19 VT-i VT-iCLOSUREHEADNUTS (54 TOTAL)Examined nuts 89-2-4014-51-27,28,29,30,32,33,34, 35,36,37,38,39,40,41,42,43,44, 45 per original scope.Also examined 31perrequest of Reactor Services to check for damage from stud detensioner.

NP!B-G-1 806.30 IRV-03-STUDS(01 TO 54)1RC01RVOLUT-0 NRICLOSUREHEAD STUDS (54 TOTAL>Examined studs in stud holes23,24,25,26,27,28,29,30,31,32,33,34,35,36,37,38,39, and 40.Surface examination is no longer required perCodeCase N-652 approved inRegulatoryGuide 1.147, Revision 14.8-G-1 606.50 1PV-03-WASHEPS 1PCO1RVT-iVT-i NA!CLOSURE WASHERS (01 TO 54)Examined 89-4401 4-51 Top Washers (89-A3-401 4-SI Bottom Washers)-28,29,30,31,32,33,34,35,36,37,38,39,40,41,42,43,44,45.I Line Number/EPN NOTE 4VT-2VT-2 NAIPage3-14 Exek;BraidwoodStation Unit 1 A1R12 ISI Outage Report Section 3.1 DetailedInserviceInspection Weld I Component Listing (Page 11 of 18)SYSTEM: ReactorCoolantSystem (RC)Section Xl lSl Identifier Cat.Item Description Inspection Comments 8-0 816.20 1SG-0S-1RCO1BA TUBING 1PCO1BA ET ET STEAM GENERATOR TUBING See Section 2.5 of report for details of examination.

Eleven tubes were plugged in this steam generator during A1P12.IND.B-Q 816.20 1SG-06-1PCO1BBTUBING1PCO1BB ET ET IND.STEAMGENERATORTUBING See Section 2.5 of report for details ofexamination.Seventeentubes were plugged in this steam_generator during Al P12.6-0 616.20 1SG-07-1PCO1BCTUB!NG1PCO1BC ET ET NRI STEAMGENERATORTUBING See Section 2.5 of report for details of examination.

No tubes were plugged in this generator during Al P12.6-G-1 806.90 1SG-07-SGB-0i 1PCO1BCVT-iVT-i NP!806.100 PRIMARY MANWAY (20 STUDS and NUTS)100 VOL UT-70 NR!806.110 UT-80L NP!B-C-i 806.90 1SG-07-SGB-02 1RCO1BC VT-i VT-I NP!806.100 PRIMARY MANWAY (20 STUDS and NUTS)100 VOL UT-70 NP!806.110 UT-80L NP!8-0 816.20 1SG-08-1RCO1BDTUBING1PCO1BDETET NRI STEAM GENERATOR TUBING See Section 2.5 of report for details of examination.

No tubes were plugged in this generator during Al P12.B-C-i 806.90 1SG-08-SGB-01 1PCO1BDVT-IVT-I NP!606.100 PRIMARY MANWAY (20 STUDS and NUTS)100 VOL UT-70 NP!806.110 UT-80L NRI B-C-i 806.90 1SG-08-SGB-02 1PCO1BDVT-IVT-I NP!806.100 PRIMARY MANWAY (20 STUDS and NUTS)100 VOL UT-70 NRI 806.110 UT-80L NP!P-A P01.11 ISI-16-22.01 IRC3OAD-l.5° NOTE4 VT-2 VT-2 NPI VALVE 1S!89000-PIPE A-A P01.11 1S1-16-23 lPC3OAD-1.5~

NOTE4VT-2VT-2 NP!PIPE-3'X11/2'REDUCER P-A P01.11 1S!-17-01 lPC30AB-1.5~

NOTE4 VT-2 VT-2 NP!PIPE-3X11/2"REDUCER______

P-A P01.11 1SI-17-021PC30AB-1.5~NOTE4VT-2VT-2 NP!VALVE 1S18900B-PIPE A-A P01.11 1SI-31-Oi 1PC30AA-1.5~

NOTE 4 VT-2 VT-2 NP!PIPE-REDUCER P-A P01.11 1S1-31-02 1PC30AA-1.5~

NOTE 4 VT-2 VT-2 NA!VALVE 1SIS900A-PIPE I Line Number/EPNPage3-15 Ecekn.Braidwood Station Unit 1 A1R12 IS!Outage Report Section 3.1 Detailed Inservice Inspection Weld/Component Listing (Page 12 of 18)SYSTEM: Residual Heat Removal System (RH)~Section Xl IS!Identifier Cat, Item~Re!~ef~Req I Program I Code I~J Exam Summary I Actual Exam I Resu!J~ispection Comments C-C C03.20 1RH-05-21B&22 1PHO2AA-8 l2P-lO NOTE4100 SUP PT NP!PENETRATION (1AB-064)-PIPE 12R-1S____Page3-16 Exekn.Braidwood Station Unit 1 A1R12 IS!Outage Report Section 3.1 Detailed Inservice Inspection Weld I Component Listing (Page 13 of 18)SYSTEM: ReactorCoolantSystem (RY)ion Xl~i Identifier

~Ie Number/EPN~S~:;~I1j_~eS;~ry

_____InspectionComments P-AP01.111CV-02-13 1PYl8A-2~NOTE 4VT-2VT-2 NP!VALVE 1CV8377-PIPE P-A P01.11 1CV-02-l4 lAY18A-2~NOTE 4VT-2VT-2 NA!PIPE-ELBOW P-AP01.111CV-02-15 1RY18A-2~NOTE4 VT-2 VT-2 NP!ELBOW-PIPE P-AP01.111CV-02-161PY18A-2" NOTE4VT-2VT-2 NP!PIPE-ELBOW________________

________________________________________

P-AA01.111CV-02-17 1PY18A-2"NOTE4 VT-2 VT-2 NP!ELBOW-PIPE________________

P-A P01.11 1CV-02-18 IRYI8A-2"NOTE 4VT-2VT-2 NA!PIPE-ELBOW P-AP01.111CV-02-19 1PY18A-2"NOTE 4 VT-2 VT-2 NA!___________

ELBOW-PIPE____________

B-B 602.11 1PZR-01-08E 1PYO1S NOTE 4 99.1 VOL UT-45 NP!SHELL-UPPER HEAD UT-60 NP!B-B 80212 1PZP-01-09D 1PYO1S NOTE4100 VOL UT-45 NP!SHELLLONGSEAM UT-60 NP!Per Note 2 ofTable!WB-2500-i Category B-B, extent of exam length is twelve inches from the associated circumferential weld.B-G-2 807.20 1PZP-01-B1 1PYO1SVT-iVT-l NP!MANWAY BOLTING_(16 TOTAL)_______________

B-E 604.20 1PZR-01-HEATEP PENET.1RYO1SBMVVT-2 IND.PRESSURIZER HEATERPENETRATIONVisual NRI VT-2 NP!During insulation removal for bare metal visual examination of pressuizer surge nozzle (non-Section Xl examination), boricacidwas identified (reference IA 480489).Leakage was at Penetration

  1. 52.Portionof Penetration
  1. 52containingsocket welded coupling was removed and replaced by a welded plug (WO 915754-03/

EC 360630).The removed material was for analysis.FinalVT-2 wasperformedduringascending Mode 3 walk down.Reference Braidwood LEA 2006-001-00 (June 26, 2006).________________

______B-D 603.110 1PZR-0l-N1 1RYO1S!2P-08 NOTE4 20 VOL UT-4S NP!PRESSURIZER

-SURGE NOZZLE UT-60 NP!Two insulation panels providing approximatelyan80 degree arc of accessibility were removed to identify source of boric acid on surge nozzle mirrorinsulation.Accessibleportions of nozzle-ta-vesselweldwereexaminedper Relief Request l2P-08.B-D 603.120 1PZP-0l-N1 (NIP)1PYO1S I2P-08 NOTE440 VOL UT-SO NA!PRESSURIZER

-SURGENOZZLEINNEA RADIUS UT-55 NA!Two insulation panels providing approxima~eIyan80 degree arc of accessibility were removedtoidentify source of boric acid on surge nozzle mirrorinsulation.Accessible portions ofnozzleinner radius were examined in accordance with Relief Request 12R-08.B-D 803.110 1PZA-01-N4A 1PYO1S NOTE 4 100 VOL UT-45 NA!PPESSUP!ZER

-SAFETYNOZZLE UT-60 NP!B-D 603.120 IPZP-01-N4A (NIP>IPYO1S NOTE 4 100 IPS UT-24 NA!PPESSUAIZEP

-SAFETYNOZZLEINNERRADIUSUT-6S NA!UT-70 NP!Page 3-17 Eekn.Braidwood Station Unit 1 A1R12 IS!Outage Report Section 3.1 DetailedInserviceInspection Weld I Component Listing (Page 14 of 18)SYSTEM: ReactorCoolantSystem (RY)[~tion XI IS!Identifier Line N Description

[Inspection Comments umber I EPN Relief Request Program Notes Code Coverage Exam Summary Actual Results Exam B-K 610.10 1PZP-0l-PSL-01,-02,-03, 1PYO1SI2P-09NOTE 4 VT-i AND-04 SEISMIC SUPPORT LUG I2P-IS SUP NP!Best effort VT-l and liquidpenetrantexaminations performed in accordance with Relief Request 12P-09.achieved onPSL-1,PSL-2, and PSL-3 for liquid penetrant examination.

PSL-4 is totally inaccessible (0°/Approximatel

~coverage).

y21.4%coverage P-A P01.11 1PZP-Ol-SE-01 1PY11A-14" NOTE4 BMV BMV NP!P01.15 PZR SURGE NOZZLE-SAFE END 1-600 Bare metal visual examination in accordance with MAP 2003-039.P-A P01.15 1PZR-01-SE-02 1PY03AA-6~

NOTE 4 BMV BMV NP!1-600 PZP SAFETY NOZZLE-SAFE END Bare metal visual examination every outage per NRC Bulletin_2004-01 commitment.

P-A AOl.15 1PZP-0l-SE-03 1RYO3AB-6" NOTE 4BMVBMV NP!1-600 PZRSAFETYNOZZLE

-SAFE END Bare metal visual examination every outage per NRC Bulletin 2004-01_commitment.

P-A P01.15 1PZR-01-SE-04 1PYO3AC-6" NOTE 4BMVBMV NP!1-600 PZRSAFETYNOZZLE

-SAFE END Bare metal visual examination every outage per NRC Bulletin 2004-01 commitment.

A-A P01.11 1PZR-Ol-SE-05 1PY01B-6~NOTE 4BMVBMV NP!POllS PZR SPRAY NOZZLE-SAFE END 1-600 Bare metal visual examination every outage per NRC Bulletin 2004-01 commitment..

P-AP01.151PZP-01-SE-06 1PY02A-6~NOTE 4BMVBMV NP!1-600 PZP RELIEF NOZZLE-SAFE END Bare metal visual examination every outage per NRC Bulletin 2004-01 commitment.

P-A P01.11 1AC-04-03 1RYllA-l4~

NOTE 4 37.5 VOL-EUT-45LNA!14"BRANCH NOZZLE-29"PIPE P-A P01.11 1PC-05-081PY11A-i4"NOTE4 100 VOL-E UT-45 NP!PIPE-14"NOZZLEBRANCH CONNECTION P-A P01.20 1 PC-32-01 1 PYO3AA-6"NOTE 4 81.9 VOL-E UT-45 NA!SAFE END-ELBOW P-A P01.20 1RC-32-03 1PYO3AA-6" NOTE 4 SO VOL-E UT-45 NP!PIPE-ELBOWUT-60LNPI P-A AOl.20 1AC-32-04 1PYO3AA-6" NOTE 4 99.3 VOL-E UT-45 NA!ELBOW-PIPE B-G-2 807.50 1PC-32-B4 1PYO3BA-6~VT-iVT-i NP!FLANGEDCONNECTION (12 STUDS)Page 3-18 Ecekn.Braidwood Station Unit 1 A1R12 IS!Outage Report Section 3.1 DetailedInserviceInspection Weld I Component Listing (Page 15 of 18)SYSTEM: Steam Generator (SG)SectionXl IS!Identifier DescriptionInspectionComments C-A C01.10 C-B C02.21 1SG-05-SGN-03 1PCO1BA AUX FW NOZZLE-STEAMDRUMLOWER SHELL NOTE4100 100 SUP VOL MT UT-45 UT-6O NP!NP!NP!C-B CO2.21 1SG-05-SGN-O4 1RCO1BA FW NOZZLE-STEAM DRUM LOWER SHELL NOTE4100 95 SUP VOL MT UT-45 UT-60 NP!NP!NP!C-B CO2.22 1SG-OS-SGN-O4 (NIP)1RCO1BA FW NOZZLE-STEAMDRUMLOWER SHELL NIP NOTE495IRS UT-35 UT-40 UT-45 UT-59 UT-60 NP!NA!NP!NP!NP!I Line Number I EPN 1 SG-05-SGC-06 1 PCO1 BA SHELL CONE-STEAMDRUMLOWER SHELL NOTE4100 VOL UT-45 NP!UT-60 NRI Page 3-19 Bcekn.Braidwood Station Unit 1AlRi 2 151 Outage Report Section 3.1 DetailedInserviceInspection Weld I Component Listing (Page 16 of 18)SYSTEM: SafetyInjectionSystem (SI)Section Xl IS!Identifier I Line Number!EPN[f~__ltem~j~~riPtion Inspection Comments B-G-2 807.70 1SI-03-1S18818A(BLT)1 SIO5DA-6'1S18818A CHECK VALVE (16 BLT)Boltingexaminedin-place andundertension.

A-A P01.16 lSl-05-23 1SI09BB-lO" PIPE-ELBOW NOTE4 100 VOL UT-45 UT-60 NP!NP!A-A P01.16 1SI-O5-24 iSlO9BB-10~

ELBOW-PIPE NOTE 4 97.8 VOL UT-45 UT-60 NP!P-A P01.11 lSl-10-2S 1SI18FC-2" PIPE-ELBOW NOTE 4 VT-2 VT-2 NP!P-A P01.11 151-10-26.01 1S!18FC-2" ELBOW-PIPE NOTE4 VT-2 VT-2 NP!P-A P01.11 1SI-18-23 1SIO8JB-i.S' VALVE 1S!8810B-PIPE NOTE4 VT-2 VT-2 NP!P-A P01.11 1SI-18-24 1SIO8JB-1.5" PIPE-ELBOW NOTE4VT-2VT-2 NA!P-A P01.11 1SI-18-2S 1SIO8JB-1.S~

ELBOW-PIPE NOTE4VT-2VT-2 VT-2 NP!

NP!P-A P01.11 1SI-18-26 1S!O8JB-1.5' PIPE-ELBOW NOTE 4 VT-2 P-A P01.11 1SI-19-01 1S!O8GA-1.5' BRANCH CONNECTION

-PIPE NOTE4VT-2VT-2 NRI P-A P01.11 1SI-i9-06 1S!O8HA-2~

COUPLING-PIPE NOTE4 VT-2 VT-2 NP!P-A P01.11 1SI-19-07 1SIO8HA-2~

PIPE-FLANGE NOTE4 VT-2 VT-2 NP!P-A P01.11 1SI-19-08 1SIO8HA-2" FLANGE-PIPE NOTE4VT-2VT-2 NP!P-A P01.11 1S1-19-14 1SIO8JA-1.S" PIPE-ELBOW NOTE4VT-2VT-2 NP!P-A P01.11 1SI-19-15 1SI08JA-l.5~

ELBOW-PIPE NOTE 4 VT-2 VT-2 NA!P-A P01.11 lSl-19-l6 1SlO8JA-l.5~

PIPE-VALVE 1SI881OA NOTE 4 VT-2 VT-2 NRI P-A P01.11 131-19-17 1SIO8JA-l.5~

VALVE 1S18810A-PIPE NOTE4 VT-2 VT-2 NP!P-A P01.11 1SI-19-18 1SI08JA-1.5~

PIPE-FLANGE NOTE 4VT-2VT-2 NP!P-A P01.11 1SI-19-20 1SlO8JA-1.5~

PIPE-ELBOW NOTE4VT-2VT-2 NP!P-A P01.11 lSl-19-22 1Sl08JA~1.5a PIPE-ELBOW NOTE4 VT-2 VT-2 NA!NOTE 3 VT-i VT-i NA!Page3-20 Bcek~.n.BraidwoodStation Unit 1 A1R12 IS!OutageReport Section 3.1 Detailed lnservice Inspection Weld/Component Listing (Page l7of 18)SYSTEM:Safety Injection System (SI)Section XI IS!Identifier I Line Number!EPN f~tem DescriptionInspectionComments A-A P01.11 1S!-19-23 lSl08JA-1.5~

______ELBOW-PIPE A-A P01.11 1Sl-19-24 1 SIO8JA-i.5"PIPE-ELBOW B-K 810.20 1S1-21-09 1SIO3DA-2' PIPE-PENETRATION(1AB-061)

NOTE 4 VT-2 VT-2 NA!NOTE 4 VT-2 VT-2 NA!!2P-15 NOTE4100 SUP PT NP!Page 3-21 Bce kin.Braidwood Station Unit 1 A1R12 IS!Outage Report Section 3.1 Detailed Inservice Inspection Weld I Component Listing (Page 18 of 18)SYSTEM: Essential Service Water System (SX)lnsp C-C~ti~nxIjd~n~fier ection Comments C03.2O 1SX-11-SWO1 STANCHION~j Line Number I EPN 1SXO9BA-1O" WELDED TO ELBOW 1!i~tI2A-15NOTE 4 j~~e 100 Summary SUP E~MT Resu~~1 NPI Page 3-22 Ecekn.Braidwood Station Unit 1 A1Ri2 IS!Outage Report Section 3.1.1DetailedPreservice Inspection Weld I Component Listing (Page 1 of 1)SYSTEM:ReactorCoolant System (RY)SectionXI IS!Identifier I Line Number!EPN Description (Inspection Comments B-G-2B07.501PC-32-B41RY03BA-6~VT-i VT-l NP!FLANGEDCONNECTION (12 STUDS)Replacedinletflange studs on Valve S/N N56964-O0-Oi 09 to accommodateuseofhydranuts.Preservice VT-i performed under WO 773388.______________________________________

__________________________________

B-G-2 B07.S0 1PC-32-B5 1AY03BB-6~VT-iVT-i NP!FLANGEDCONNECTION (12 STUDS)Replaced inlet flange studs on Valve S/N N56964-OO-0054 to accommodate use of hydranuts.

Preservice VT-i performed under WO 793798._____________________________________

B-G-2 807.50 1PC-32-B6 1RY03BC-6~

VT-i VT-i NP!FLANGEDCONNECTION (12 STUDS)Replaced inlet flange studs on Valve S/N NS6964-O0-0i 10 to accommodate use ofhydranuts.Preservice VT-i performed under WO 781899.____________________________________

______________Page3-23 BceI~n.Braidwood Station Unit 1 AIRI2 IS!Outage Report Section 3.2 Detailed Inservice Inspection Component Support Listing (Page 1 of 9)SYSTEM:ContainmentSpray System (CS)Section Xl JISI Identifier Line Number I EPN Item j~~ription

[Inspection Comments F-A FO1.20 1CS03017X 1CS02AB-10~

NOTE 8 VT-3 NRI (1)StrutF-AF01.20 1CS03019V 1CSO2AB-10" NOTE 8 VT-3 NP!(1)VariableSpringCan As found Spring Can Setting: 1320#.Lower

Attachment:

Clamp, Rod, and Spring Can: (Direct Upper

Attachment:

Structural Attachment and Upper Rod Assy.(RemoteExamination 8'away)._______F-A FOl.20 1CSO3O21P 1CSO2AB-iO' NOTE 8 VT-3 NP!(1)Strut__________

________________________________

_______________F-AF01.20 1CSO3O88X 1CS10AA-6~

NOTE 8 VT-3 NA!Box__________________________________________________F-AF01.20 1CS03089A 1CS10AA-6~

NOTE 8 VT-3 NP!Anchor, integrally attached to pipe Component painted, no indication of distress.Page 3-24 Bcekn.Braidwood Station Unit 1 A1R12 IS!Outage Report Section 3.2 Detailed Inservice Inspection Component Support Listing (Page 2 of 9)SYSTEM: Chemical&Volume Control System (CV)SectionXI IS!Identifier Line Number!EPN Cat.Item DescriptionInspectionCommentsF-AF01.401CVO1PA1CVO1PA NOTE 8 VT-3 NA!1A CV PUMP, integrally attached to pump_______________________

___________

F-A F01.lO 1CV16012G1CVA7AB-2"NOTE 8 VT-3 NA!BoxF-AF01.10 1CV16014X 1CVA7AB-2~

NOTE 8 VT-3 NP!Box F-A FOlIO 1CV22006X ICV45B-2~NOTE 8 VT-3 NP!(1)Strut Note: Insulation removed for exam.Page3-25 Bcekn.Braidwood Station Unit 1 A1R12 ISI Outage Report Section 3.2 Detailed Inservice InspectionComponentSupport Listing (Page 3 of 9)SYSTEM:FeedwaterSystem (FW)Section XI IS!Identifier Cat.Item DescriptionInspectionCommentsF-AFOl.20 1 FWO40I SR (1)Strut F-A F01.20 IFWOSO18X 1FWO3DD-l6" NOTE 8 VT-3 NPI Box IFW03DC-16" NOTE 8 VT-3 NP!Page 3-26 Bcekn.BraidwoodStation Unit 1 A1R12 ISI Outage Report Section 3.2 DetailedInserviceInspection Component Support Listing (Page 4 of 9)SYSTEM: ReactorCoolantSystem (RC)Section XI IS!Identifier Line Number!EPN Cat.Item DescriptionInspectionComments F-A FOliO 1CVOSO14X_________(1)Strut F-A FOliO 1CVO9O61R Box F-A FOliO 1CVO9O71G U-BoltF-AF01.10 1CV12004V (1)Variable Spring Can As FoundSetting:460 lbs.________F-A FOliO 1CV13004R 1PC16AC-2~

Box F-A F0i.401RCO1BA1RCO1BA S.G A Insulation loosened/pulled back from upper lateral restraint inorderto perfrom examination.

F-A F01.401RCO1P1PCO1R REACTOR Perform in conjunction with MAP visual inspection of A and Ccoldlegs and B andDhot legs.F-A FOliO 1PCO2001V 1PC21AB-8' (1)VariableSpringCan NOTE 8 VT-3 NA!NOTE 8 VT-3 VT-3 NP!NA!NOTE 8 VT-3 NP!NOTE 8 VT-3 NP!1 PC36A-3~1PC14AC-2" 1 PCi 4AC-2"1 PCi 6AA-2"NOTE 8 NOTE 8 NOTE 8 NOTE 8 VT-3 VT-3 VT-3 VT-3 NA!NP!NA!NA!Page3-27 Ecekn.BraidwoodStation Unit 1 A1R12 ISI Outage Report Section 3.2 Detailed Inservice Inspection Component Support Listing (Page 5 of 9)SYSTEM: Residual Heat Removal System (RH)L~ctionXl~!Slldenfier

~J~ine Number!EPN J!ief~Pr gram 5ryjt8~InspectionComments F-A F01,20 1PC-068A 1PHO1BA-12" NOTE 8 VT-3 NA!Anchor, integrally attached to pipe Outside Containment Anchor, integrally attached to pipe VT-3 NA!Exam performed on 04/24/2006 was on the portion of the component located inside containment.

Exam performed on 02/16/2006 was on portion of component located outside the containment.

F-A FO1.20 1RHO4O14C lAH03AB-8~

NOTE 8 VT-3 NP!(2)Constant Spring Cans, IWA to pipe Spring can settings intolerance.

Size 17ConstantSupports (2"Cans"TrapezeType), Load 955#, T.T.=3", A.T.11/16"up.Remote examination performed (25away).Travel Setting acceptable.F-AF01.20 1RHO4O17G 1AHO3AB-8" NOTE 8 VT-3 NA!Box Remote examination performed (20'away).F-A FOl.20 1SI18O8SX 1AHO3AA-8" NOTE 8 VT-3 NP!(1)Strut Page 3-28 Bce k~nBraidwoodStation Unit 1 A1R12 IS!Outage Report Section 3.2 DetailedInserviceInspection Component Support Listing (Page 6 of 9)SYSTEM:ReactorCoolantSystem (RY)SectionXI IS!Identifier Cat.Item Description Line Number!EPN J Relief Program Notes Exam j~~ary Results Inspection CommentsF-AF01.40 1PYO1S 1PYO1S NOTE 8 VT-3 NP!All PZA_SupportsPage3-29 Ecek~Braidwood Station Unit 1 A1R12 IS!Outage Report Section 3.2 DetailedlnserviceInspectionComponentSupport Listing (Page 7 of 9)SYSTEM: SafetyInjectionSystem (SI)[Section XI IS!Identifier

[f~~em Description (Inspection CommentsF-AP01.10 1PB-061A_______Anchor,_integrally attached to pipeF-AF01.10 1PH02020R (2)Struts F-A FOliO 1RHO2O21R BoxF-AFO1.1O 1RH02072X_________(1)Strut F-A FOliO 1RHO2100X Box F-A FOliO 1SIO1O22X_____________

(1)Strut F-A FOliO 1SIO1O73X (1)Strut F-A F0i.20 1S!O3005C (1)ConstantSpringCan Actual Setting=5 1/2_______F-A FOliO 1SIO4O15R (1)Strut F-A FO1.20 1S!06098X (1)Strut,integrally attached to pipe F-A FOliO 1S!O9014R (2)Struts F-A FOliO 1S1O9036X Box F-A F01.iO 1S113104G U-BoltF-AF01.20 1S!l5002GBoxand StrutF-AF01.20 1SI15006R BoxF-AF01,20 lS!15008R (1)Strut F-A F01,20 1SI15O1OX (1)StrutF-AF01.20 iSIl5Ol5X BoxF-AF01.20 1SI18O24X Box-F-AP01.20 1SI18O5OX (1)Strut 1SIO3DA-Z' NOTE 8 VT-3 NP!1~O4D-8~NOTE 8 VT-3 NP!1SIO4D-8"NOTE 8 VT-3 NP!lSl04B-12~

NOTE 8VT-3 NP!1SIO4B-12" NOTE 8 VT-3 NP!1SlO5DA-6~

NOTE 8 VT-3 NP!NP!1S!O5DA-6" NOTE 8 VT-3 iSlO5cA-8' NOTE 8 VT-3 NP!1SIO5DB-6" NOTE 8 VT-3 NP!1SIO1B-24 NOTE 8 VT-3 NP!1SIO5DC-6' NOTE 8 VT-3 NP!1SIOSDC-6° NOTE 8 VT-3 NPI 1SI03DA-2~

NOTE 8 VT-3 NA!1 S!O2BA-6'NOTE 8 VT-3 NP!lS!l3BA-6~

NOTE 8 VT-3 NA!1Sl13C-6~NOTE 8 VT-3 NAI 1Sll3BA-6~

NOTE 8 VT-3 NP!1SI02BA-6~

NOTE 8 VT-3 NA!1Sl02A-8~NOTES VT-3 NA!1SIO2BA-6" NOTE 8 VT-3 NP!Page 3-30 Exek n.Braidwood Station Unit 1 A1R12 IS!Outage Report Section 3.2 DetailedInserviceInspectionComponentSupport Listing (Page 8 of 9)SYSTEM: Safety Injection System (SI)SectionXl IS!Identifier Description (Inspection Comments F-A F0l.2O 1S118060P Box F-A FOliO 1SI21O14G Box F-A FO1.10 1S121021A Anchor, integrally attached to_pipe________________

F-A FOliO 1S!21022X_____(1)Strut F-A F0l.l0 1S!23001G Box Box Support.1 Sl02BA-6~1 5108 FA-3~1 SIO8FA-3"1 S!O8E-3"1 SIO8FA-Y NOTE 8 NOTE 8 NOTE 8 NOTE 8 NOTE 8 VT-3 VT-3 VT-3 VT-3 VT-3 NP!

NA!NP!NA!NP!Page 3-31 Bcekn Braidwood Station Unit 1 A1R12 IS!Outage Report Section 3.2 Detailed Inservice InspectionComponentSupport Listing (Page 9 of 9)SYSTEM: Essential Service Water System (SX)[:: Insp F-A ion XI j~identifl~~

J~e Number!EPN ection Comments F0i.20 1SXO81O1X 1SXO9BA-iO" (1)Strut,integrally attached to pipe Program NOTE 8 Sum~IL~j VT-3 NPIPage3-32 Bcekn..BraidwoodStation Unit I A1R12 IS!Outage Report Section 3.3 Detailed lnservice Inspection Snubber Listing (Page 1 of 9)SYSTEM: Chemical&Volume Control System (CV)~S~ct Insp F-A It~iXl ection Corn FOliO~I~cien~fier ments iCV16009S Snubber Line Number I EP~:Iief IP~9ram1 1CVA7AB-2° I2P-14 Sry VT-3 Functional VT-3 Re~1 NRI NRI NA!Page3-33 Section 3.3 DetailedInserviceInspection Snubber Listing (Page 2 of 9)SYSTEM: Main Steam System (MS)Bcekn.BraidwoodStation Unit 1 A1R12 ISI Outage ReportInspectionCommentsF-AP01.20 1MSO1O79SSnubber,integrally attached to pipe F-A P01.20 1MSO1O8SSSnubber,integrally attached to pipe 1MSO7AD-28" l2A-14 VT-3 Functional VT-3 NP!NPI NP!F-A P01.20 1MSO1O92ASSnubber,integrally attached to pipe 1MSO7AB-28°

!2P-14 VT-3 Functional VT-3 NP!NP!NP!F-A P01.20 1MSO1O92BSSnubber,integrally attached to pipe 1MSO7AB-28" l2P-14 VT-3 Functional VT-3 NA!NA!NP!P-A P01.20 1MSO1O97.SSnubber,integrally attached to pipe1MS07AB-28"i2A-14 VT-3 Functional VT-3 NP!NP!NA!F-AP01.20 1MSO11O1AS Snubber, integrally attached to pipe 1MSO7AC-28" 12R-14 VT-3 Functional VT-3 NA!NP!NA!Serial Number: 1625 F-A P01.20 1MSO11O1BSSnubber,integrally attached to pipe1MSO7AC-28~!2R-14VT-3 NP!Functional IND.Functional NP!VT-3 NA!Snubber Serial Number 1534 failed to meet functional test acceptance criteria.Replaced by SerialNumber20006 under WO 899716-01 FunctionalSnubber,integrally attached to pipe VT-3 NA!Snubber functional and post-installation VT-3 Completed.

______F-AP01.20 1 MSO1 106S 1 MSO7AC-28~Snubber,integrally attached to pipe 12R-14 VT-3 NP!Functional NA!VT-3 NA!1MSO7AA-28' 12R-14 VT-3 NPIPage3-34 Ecekn.Braidwood Station Unit 1A1R12ISI Outage Report Section 3.3 DetailedInserviceInspection Snubber Listing SYSTEM:ReactorCoolant System (RC)SectionXl IS!Identifier

[Cat.Item Description (Inspection Comments P-AP01.101CV15O39AS Snubber Snubber functional and post-installationVT-3completed.

Snubber Functional

!ND.Functional NA!VT-3 NA!Snubber Serial Number3128failed to meet functional test acceptance criteria.Replaced by Serial Number 12538 under WO 914213-01.

Skewed pipeattachmentcomponent identfied during visual examination (post test VT-3)._______________________

F-AP01.101CV15O39BS 1RC14A8-2~

12R-14 Functional NP!Snubber VT-3 NP!Snubber functional and post-installation VT-3 completed.

Snubber VT-3 IND.Functional IND.Functional NP!VT-3 NP!Snubber Serial Number 8052 failed to meet functional test acceptance criteria.Replaced by Serial Number 14610 under WO 914213-01.Skewedpipeattachmentcomponent identfied durinq visual examination (post test VT-3).F-AP01.101CV25002S1PC14AD-2" 12R-14 VT-3 Snubber Functional VT-3 NA!NP!NRI P-A P01.10 1ACO1006S 1RC21AA-8' 12P-14 VT-3 NP!Snubber Functional NP!VT-3 NP!F-AP01.10 1RCO1007S 1PC21AA-8" 12R-14 VT-3 NP!Snubber Functional NP!VT-3 NP!F-AP01.40 1RCO1 BA-A S.G A l2R-14 VT-3 NP!SnubberF-AP01.40 IRC01BA-8 S.G A i2R-'14 VT-3 NRI SnubberF-AP01.40 1PCO1BB-A S.G B 12A-14 VT-3 NP!Snubber VT-3 NP!Serial Number 23.VT-3 performed for WO 98108541waspost maintenanceVT-3after replacement of 1PCO1BB-B snubber, Both snubbers are_supplied from a common reservoir.

F-A P01.40 1PCO1BB-B S.G B 12P-14 Functional NP!Snubber VT-3 NP!Snubber functional and post-installation VT-3 completed.

VT-3 IND.Snubber Functional VT-3 NA!Snubber (Serial Number 14)was identfiedasleaking fluidfromthepiston seal at power during the operating cycle prior to A1R12.Leakage quantified as 25 dpm on 04/2012006.Snubber was replaced by Serial Number 06underWO 98108541.(Page 3 of 9)1RC14AB-2" 12P-i4 Functional NP!VT-3 NP!VT-3 IND.Page3-35 Bcek~n Braidwood Station Unit 1 A1R12 IS!Outage Report (Page 4 of 9)Section 3.3 Detailed Inservice Inspection Snubber Listing SYSTEM: Reactor Coolant System (RC)(SI Identifier Description (Inspection CommentsF-AP01.40 1RCO1BC-A Snubber S.G C l2P-14 VT-3 NA!Functional NP!VT-3 NP!Serial Number 12.Snubber functional test and post maintenance VT-3 examination F-A P01.40 1PCO1BC-B S.CC12P-14 VT-3 NP!SnubberF-AP01.40 1PCO1BD-A S.G D 12R-14 VT-3 NP!SnubberF-AP01.40 1PCO1BD-B S,G C 12P-l4 VT-3 NP!Snubber F-AP01.101ACO2006AS 1AC21AB-8" 12P-14 VT-3 NA!Snubber Functional IND.Functional NA!VT-3 NP!Snubber (Serial Number 8666)failed to meet functional test acceptance criteria.Replaced by Serial Number 2S04 under WO 914208-01.

Functional Snubber VT-3 NA!Snubber functional and post-installation VT-3_completed.F-AP01.10 1PCO2006BS 1AC21AB-8'

!2A-l4 VT-3 NA!Snubber Functional NP!VT-3 NA!F-AP01.10 1PCO2007S 1PC21AB-8~

12A-14 VT-3 NA!Snubber Functional NP!VT-S NP!P-A P01.10 1PC16114S 1RC22AA-1.5~

12R-14 VT-3 NP!Snubber Functional NA!VT-3 NA!F-AP01.101RC16119S 1PC22AA-1.5~

12A-14 VT-3 NA!Snubber Functional NP!VT-3 NA!F-AP01.10 1RC17O52S 1PC22AB-1.5~

l2P-l4 VT-3 NA!Snubber Functional NA!VT-3 NP!P-A P01.10 1RC18O34AS 1PC22AC-1.5~

l2A-i4 VT-3 NA!Snubber Functional NA!VT-3 NP!Serial No.13044 P-A P01.10 1PC18034BS 1PC22AC-1.5~

12A-14 VT-3 NA!Snubber Functional NRI VT-3 NPI SN.13082SectionXI Cat.ItemPage3-36 Ecekn.Braidwood Station Unit 1 A1R12 IS!Outage Report Section 3.3 DetailedInserviceInspection Snubber Listing (Page 5 of 9)SYSTEM: Reactor Coolant System (RC)SectionXl IS!Identifier Cat.Item Description Inspection CommentsF-AP01.10 1RY06057S Snubber Snubber functional andpost-installationVT-3completed.

Snubber VT-3 Functional VT-3 NP!Snubber (Serial Number 329)wasreplacedwith Serial Number 13518 under WO 915045-01.F-AP01.10 1PYO6O91S 1PC26A-2~l2P-14 Functional NP!Snubber VT-S NP!Snubber (Serial Number 8609)performancewas identified as trending downward during Al All andwasreplaced with functionally testedsparesnubber (Serial Number9857)under WO 744327-01.

P-A P01.10 1RYO6153S 1PC24AB-4"

!2P-i4 VT-3 NP!Snubber Functional NA!VT-3 NP!1PC26A-2"I2P-14 Functional NP!VT-3 NP!Page 3-37 Exek;n, BraidwoodStationUnit 1 A1R12 IS!OutageReport Section 3.3 Detailed Inservice Inspection Snubber Listing (Page 6 of 9)SYSTEM:Residual Heat Removal System (RH)SectionXI IS!Identifier Item DescriptionInspectionCommentsF-AP01.10 1PHO2003S Snubber 1PHO1AB-12' 12R-14 VT-3 NP!Functional NP!VT-3 NP!F-AP01.10 1PHO2O13S Snubber 1PH0lAB-12~

!2P-14 VT-3 Functional VT-3 NA!NP!NP!P-A P01.10 1PHO2O59S Snubber 1AH0lAA-12~

l2R-14 VT-3 Functional NP!NP!VT-3 NP!P-A P01.20 1PHO8O15S1RHO2AB-8~l2P-14 VT-3 NP!Snubber Functional NP!______________________

___________________________

VT-3 NP!Page 3-38 Section 3.3 Detailed Inservice Inspection Snubber Listing (Page 7 of 9)SYSTEM: ReactorCoolantSystem (RY)BraidwoodStation Unit 1 A1R12 IS!Outage ReportSectionXI IS!Identifier

[~~1 j~escription (Inspection CommentsF-AP01,10 1PYO6O12S SnubberF-AP01.10 1PY06022S Snubber1AYO1B-6"12P-14 VT-3 Functional VT-3 NP!NA!NP!F-A P01.10 1PY06029S Snubber 1RYO1B-6"12R-i4 VT-3 Functional VT-3 NA!

NP!NP!P-A P01.10 1RYO6O33S Snubber lPYO1B-6~12P-14 VT-3 Functional VT-3 NP!NP!NP!P-A P01.10 1RY06034S Snubber lRYOlB-6~12P-14 VT-3 Functional VT-3 NP!

NP!NP!F-AP01.10 1RYO6O47S Snubber 1AY18A-2'12P-14 VT-3 Functional VT-3 NP!NP!NP!P-A P01.10 1RYO611OS Snubber lPYO1B-6~!2P-14 VT-3 Functional VT-3 NP!NP!

NP!F-AP01.10 1PYO6126S Snubber lPYOlAB-4~

!2R-14 VT-3 Functional VT-3 NP!NP!NP!P-A P01.10 1PYO9005S Snubber 1RYO2B-3'12R-14 VT-3 Functional VT-3 NP!NP!NA!P-A P01.10 1AYO9O77S Snubber 1PYO2B-3"12R-14 VT-3 Functional VT-3 NP!NP!NP!1RYO1AB-4" I2P-14 VT-3 NA!Functional NP!VT-3 NP!Page3-39 Exek: ii.BraidwoodStationUnit I A1R12 IS!Outage Report Section 3.3 Detailed Inservice Inspection Snubber Listing (Page 8 of 9)SYSTEM:SafetyInjectionSystem (SI)SectionXI IISI Identifier Line Number!EPN[~tem j~~ffiptionInspectionCommentsF-AP01.10 1PHO2O19S iSl04D-8~12P-14 VT-3 NP!Snubber Functional NP!__________________________

________________________

VT-3 NP!P-A P01.20 1AHO2O27S 1SI04C-8~!2P-14 VT-3 NP!Snubber Functional NP!____________________________________________________

_____VT-3 NP!F-AP01.10 1PHO2O66S 1SIA4B-8~!2P-14 VT-3 NP!Snubber Functional NA!____________________________________

VT-3 NP!P-A P01.10 1PHO2O67S 1SIO4D-8"!2P-14 VT-3 NP!Snubber Functional NP!______________________

__________________________

VT-3 NP!P-A P01.10 1PHO2O78S ISIA4B-8'12R-l4 VT-3 NP!Snubber Functional NP!__________________________________

VT-3 NP!F-AP01.10 1PHO2083S ISlA4B-8~12R-14 VT-3 NP!Snubber Functional NP!________________

_______________________________________

VT-3 NP!P-A P01.20 1PH02206S 1SlA4A-8~12P-14 VT-3 NP!Snubber Functional NP!_______________________________________

VT-3 NP!F-A NA 1SIO1003S 1Sl09BA-1O~

12P-14 VT-3 NP!Snubber Functional NP!______________________________________________________

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VT-3 NP!F-AP01.10 1SIO1O21S 1SIO5DA-6' 12R-14 VT-3 NP!Snubber Functional NP!__________________

___________VT-3 NP!F-AP01.201S!03003S 1SIO5CA-8" l2A-14 VT-3 NP!Snubber Functional NP!____________VT-3 NA!F-AP01.20 1SIO3006S 1Sl05CA-8~

I2P-14 VT-3 NP!Snubber Functional NA!____VT-3 NP!P-A P01.20 1S103007S 1SlO5CA-8~

12R-14 VT-3 NAI Snubber Functional NP!VT-3 NP!P-A P01.20 1S103009S 1SI05CA-8~

12P-14 VT-3 NA!Snubber Functional NA!VT-3 NAI P-A P01.10 1S103018S 1SIO5DD-6' l2A-l4 VT-3 NP!Snubber Functional NPI VT-3 NA!Page 3-40 Exekn.Braidwood Station Unit 1AlRi 2 IS!Outage Report Section 3.3 Detailed InserviceInspectionSnubber Listing (Page 9 of 9)SYSTEM: Safety Injection System (SI)SectionXI IS!Identifier Item~[f~ription (Inspection Comments P-A P01.10 1SIO3O24S SnubberF-AP01.10 1SIO4003S Snubber 1SIO9BB-iO" 12P-14 VT-3 Functional VT-2 NA!NPI NP!P-A P01.20 1S109004S Snubber 1S!05CB-8~

12P-14 VT-3 Functional VT-3 NP!NP!NA!F-AP01.20 iS!09009S Snubber 1SIO5CB-8°

!2R-14 VT-3 Functional VT-3 NP!NP!NP!P-A P01.10 1S109020S Snubber 1SIO9Bc-1O" l2R-14 VT-3 Functional VT-3 NA!NP!

NP!F-AP01.20 1S!O9043S Snubber lSIO5CB-8~

12R-14 VT-3 Functional VT-3 NP!NP!NP!F-AP01.20 1S!18049S Snubber 1SIO2BA-6"

!2P-14 VT-3 Functional VT-3 NP!NP!

NP!iSl09BD-1O~

12R-14 VT-3 NP!Functional NP!VT-3 NP!Page 3-41 Exek~n.BraidwoodStation Unit 1 A1Ri2 IS!Outage Report Section 3.3.1 Snubber Preservice Inspection Listing (Page 2 of 2)SYSTEM: ReactorCoolantSystem (RC)SectionXI IS!Identifier Line Number!EPN (Cat.Item Description Relief Request Program Notes Exam Summary Results)~spection CommentsF-AP01.101CV15O39AS 1RCl4AB-2~

12P-14 Functional NP!Snubber VT-3 NP!Snubber functional and post-installation VT-3 completed.

P-AP01.101CV15O39BS lPCi4AB-2~

l2P-14 Functional NP!Snubber VT-3 NP!Snubber functional andpost-installationVT-3completed.

P-A P01.40 1RCO1 88-B S.C B l2P-14 Functional NP!Snubber VT-3 NP!Snubber functional andpost-installationVT-3completed.

P-A P01.101PCO2006AS1RC21AB-8" l2R-14 Functional NP!Snubber VT-3 NP!Snubber functional andpost-installationVT-3completed.

P-A P01.10 1AYO6O57S 1RC26A-2"I2A-14Functional NP!Snubber VT-3 NP!Snubber functional andpost-installationVT-3completed.

P-A P01.10 1RYO6O91S 1PC26A-2~l2R-14 Functional NP!Snubber Snubber (Serial Number 8609)performance was identified as trendingdownwardduringAlAl 1and was replaced VT-3 with functiona NP!llytested sparesnubber(SerialNumber9857)under WO 744327-01.Page3-43 Exekn.BraidwoodStationUnit 1 A1R12 IS!Outage Report Section 3.4.1 DetailedInserviceInspectionPressureTestTest-Block Listing (Page 1 of 5)SYSTEM:ContainmentSpray System (CS)Section XI IS!Identifier

[Cat.Item Description (Inspection Comments C-H C07.1O AO1CS-000003-M04-O1A C07.30 40 Month Period ASME Section Xl pressure Test.C07.5O C07.70 Second period examination.

A number of minor packing leaks were identified (Information Only).___________________________

___________C-H CO7.1O AO1CS-000003-M04-O1B l2R-05 VT-2 ND.C07.3O 40 Month Period ASME Section XI pressure Test.!2R-1 3 CO7.5O CO7.70 Second period examination.

Nonactive boricacidieak atboltedconnection on Line 1CSO1AB-16'(reference IA284476and 291483).Gasket replacement performed under WO 697822.C-H CO7.iO AO1CS-000003-MO4-O1C 12P-05 VT-2 NP!CO7.3O 40 Month Period ASME Section Xl Pressure Test.The Test Pressure!2R-13 C07.70 shall be those pressures developed when the Spray Additive Tank is pressurized with the nitrogen blanket.UseSNOOPorUltraprobe to inspect nitrogen filledpiping,valvesandupper portion of Spray Additive Tankcontainingnitrogen blanket.Seco nd period examination.

l2P-05 NOTE13 VT-2 NP!l2R-13 Page 3-44 Bcekn.Braidwood Station Unit 1 Al Ri 2 IS!Outage Report Section 3.4.1 Detailed lnservice Inspection Pressure Test Test-Block Listing (Page 2 of 5)SYSTEM: Fuel PoolCoolingSystem(FC)

Section XI IS!Identifier

[~~~ltem Description

[Inspection Comments C-H C07.3O AO1FC-000001-M04-O1C C07.70 40 Month Period ASME Section Xl Pressure Test.Second period examination.

C-H CO7.3O AO1PC-000001-MO4-O1D

!2R-O5 NOTE13 VT-2 NA!CO7.7O 40 Month Period ASME Section Xl Pressure Test.12P-12!2P-13 Second period examination.

12R-05 NOTE13 VT-2 NP!12P-12 l2R-1 3 Page 3-45 ExeknBraidwoodStationUnit 1 AiRi2 IS!Outage Report Section 3.4.1 Detailed Inservice Inspection Pressure Test Test-Block Listing (Page 3 of 5)SYSTEM: Process Sampling System (PS)Section XI ils!Identifier

~InspectionComments C-H C07.3O AO1PS-000009-MO4-OlE l2P-05 NOTE13 VT-2 NA!C07.7O 40 Month Period ASME Section XI Pressure Test.12A-13 VT-2 NA!ReliefRequestl2P-47 submitted toaddressinaccessiblepiping.

Second period examination.

Initial review of May 2005 walk down revealed all sections of system were not examinedbyVT-2 method (Reference IA 338480).A subsequent risk evaluation was performed.

Access to 25 of piping could not beattainedduring second walk down in October 2005 (IA 387085), ReliefRequest!2P-47 submitted on 4/7/2006.Page 3-46 Bce1c~n.Braidwood Station Unit 1 A1R12 IS!Outage Report Section 3.4.1 Detailed Inservice Inspection Pressure Test Test-Block Listing (Page 4 of 5)SYSTEM: Safety Injection System (SI)SectionXI IS!Identifier

~DescriptionInspectionComments C-H C07.40 AO1SI-000005-M04-02H CO7.8O 10 Year Interval ASME Section Xl Pressure Test.Portion completed in AlA 12, the balance of the test block will beperformedduring Al P13.12R-05 NOTE13 VT-2 NPI 12R-12 NOTE17 12A-1 3Page3-47 Ecekn.Braidwood Station Unit 1 A1R12 IS!Outage Report Section 3.4.1 DetailedInserviceInspection PressureTestTest-Block Listing (Page 5 of 5)SYSTEM:PlantSystemsPressurizedDuringMode 3 (ZZ)Section XI!SI Identifier Cat.Item DescriptionInspectionComments B-P 815.10 AO1ZZ-000005-M04-O1A 815.20 Periodic (each refueling outage)ASME Section Xl Pressure Test&Generic Letter 88-05.815.30 815.50!2P-3O 815.60/70 12P-31 Class 1 system leakage test.NoRecordableIndications.InformationOnly (10):Leakagepast 1 PCO1 4 series head vent valve(referenceIA485050)

B-P 815.11 AO1ZZ-000005-MO4-02A

!2P-O5 NOTE13 VT-2 NP!815.21 10 Year Interval ASME Section XI Pressure Test.Freeze seal!2R-12 NOTE14 815.31 required for Line 1CV45B.l2P-l3 NOTE17 815.51!2R-30 815.61/71 I2P-3i Portion_completed_in_A1A12,_the_balance_of the_test_block_will_be_performed_during_Al P13.C-H CO7.2O AOl ZZ-000005-MO4-O2B l2R-05NOTE13VT-2 NA!CO7.4O 10 Year Interval ASME Section Xl Pressure Test.AllCodeClass 2!2P-12 NOTE17 Co7.8o Components insideContainment.VT-2 Visual Inspection of!2P-13 components outside of Missle Barrier may beperformedduring Mode 1 if conditions permit.Portion completed in AlP12,the balance of the test block will beperformedduring Al P13.C-H CO7.1O AOl ZZ-000078-MO4-03A l2P-05 NOTE13 VT-2 NP!CO7.3O 40 Month Period ASME Section Xl Pressure Test.All Code Class 2 12P-12 Co7.7o components inside containment.

VT-2 Visual Inspection of l2R-13 components outside Missle Barrier may beperformedduring Mode 1 if conditions permit.Class 2 and 3 systems examinedduringascending Mode 3 walk down.!2P-05NOTE13VT-2 10!2R-12 NOTE14!2R-l3 NOTE17Page3-48 Bce k;n,BraidwoodStationUnit 1 A1R12 IS!Outage Report Section 3.4.2 DetailedInserviceInspection Borated Bolting Listing (Page 1 of 5)SYSTEM: Chemical&Volume Control System (CV)Section Xl IS!Identifier Description C-H CO7.3O lA-C V-b P-2-1 (C-H)C07.40FLANGEDCONNECTION (8 STUDS)12P-l 3 C-H C07.1O 1CVO4AB (C-H)l2P-i2 VT-2 C07.2O1CVO4ABHX (28STUDS)!2P-13 NP!C-H CO7.3O 1CV-lO P-i-i (C-H)I2P-12 VT-2 IND.C07.4OFLANGEDCONNECTION (8 STUDS)!2R-13 VT-i NP!Evidenceofleakage(dry boric acid accumulation, (<1 Teaspoon)identhed at onestud.Component cleaned, VT-i Examination performed, with exception of minor surface rust no indication of degradation identhed.No evidence of leakage identifiedduringpostcleaningexamination.Reference Issue Report Number 496436 for identification of indication in theCorrectiveAction Program.B-P 815.50 PG-2546C-014 P-2-2 (B-P)!2R-12 VT-2 NP!815.51FLANGEDCONNECTION (4 STUDS)12P-13 C-H CO7.30 PG-2546C-O18 F-i-S (C-H)l2R-12 VT-2 NP!CO7.4OFLANGEDCONNECTION (4 STUDS)12R-13 C-H CO7.3O PG-2546C-O2O P-i-i (C-H)C07.4OFLANGEDCONNECTION (4 STUDS)l2P-12VT-2 NP!12R-l3 Evidence Of Dry Boric Acid at the packing oninstrumentvalves 1 CVO9OC and 1 CVO91 C which attaches to the flanges within this Borated Bolted Connection.

Not within the scope of boratedboltedconnections.

However components were cleaned and inspected with noidentifieddegradation.

Reference Issue Report Numbers 495158 and 495163 for identification of valvepackingleakage in the Corrective Action Program.C-H C07.3O PG-2546C-O41 P-i-i (C-H)12R-l2 VT-2 NP!CO7.4OFLANGEDCONNECTION (4 STUDS)!2P-l3 C-H CO7.30 PG-2546C-063 P-i-i (C-H)12P-l2 VT-2 NP!CO7.4OFLANGEDCONNECTION (4 STUDS)!2R-13 Evidence Of Dry Boric Acid at the packing oninstrumentvalves 1 CVO9OD and 1 CVO91Dwhich attaches to the flanges within this Borated Bolted Connection.

Not within the scope of boratedboltedconnections.

However components were cleaned and inspected with noidentifieddegradation.

Reference Issue Report Numbers 4951 6sand 495168 for identification of valvepackingleakage in the Corrective Action Program.C-H C07.3O PG-2546C-068 P-i (C-H)l2P-i2 VT-2 NP!C07.40FLANGEDCONNECTION (4 STUDS)12P-13 C-H C07.3O PG-2546C-076 P-1-3 (C-H)l2P-12 VT-2 NPI C07.4OFLANGEDCONNECTION (8 STUDS)12P-13 C-H C07.30 PG-2546C-083 PL-1-2 (C-H)l2P-l2 VT-2 NRI C07.4OFLANGEDCONNECTION (8STUDS)l2A-13 C-H C07.30 PG-2546C-089 FL-i-i (C-H)C07.40FLANGEDCONNECTION (8 STUDS)l2A-12 VT-2 NP!l2P-1 3EvidenceOf Dry Boric Acid at the packing oninstrumentvalves1CVO49Dand 1CVO5OD which attaches to the flanges within this Borated Bolted Connection.

Notwithinthe scope of borated bolted connections.

However components were cleaned and inspected with noidentifieddegradation.

Peference Issue Peport Numbers 495174 and 495185 for identification of valvepackingleakage in the Corrective Action Program.C-H C07.30 PG-2546C-090 F-i-i (C-H)l2P-12 VT-2 NPI C07.40FLANGEDCONNECTION (8 STUDS)12P-i3 B-P 816.50 PG-2546C-091 P-2-3 (8-P)12P-12 VT-2 NP!815.51FLANGEDCONNECTION (4 STUDS)l2A-13 C-H C07.30 PG-2546C-093 P-i (C-H)C07.4OFLANGEDCONNECTION (4 STUDS)12P-12 VT-2 NP!!2A-13 Inspection Comments 12P-12 VT-2 NP!Page3-49 Bcakn.BraidwoodStation Unit 1 A1R12 IS!Outage Report Section 3.4.2 Detailed Inservice Inspection Borated Bolting Listing (Page 2 of 5)SYSTEM: Chemical&Volume Control System (CV)SectionXI IS!Identifier Item Description

[nspection Comments B-P 815.50 PG-2546C-101 P-2-3 (B-P)815.51FLANGEDCONNECTION (4 STUDS)12P-13 C-H C07.30 PG-2546C-lllF-1-2(C-H) 12P-12 VT-2 NP!CO7.40FLANGEDCONNECTION (8STUDS)12P-l3EvidenceOf Dry Boric Acid at the packing oninstrumentvalves 1 CVO49A and 1 CVO5OA which attaches to the flanges within this Borated Bolted Connection.

Not within the scope of boratedboltedconnections.

However components werecleanedand inspected with no identif leddegradation.Reference IssueReportNumbers 495191 and 495195 for identification of valvepackingleakage in the Corrective Action_Program.

____________________________________________________________

!2R-12 VT-2 NP!Page3-50 E~fikfl Braidwood Station Unit 1 A1R12 IS!Outage Report Section 3.4.2 Detailed Inservice Inspection BoratedBoltingListing (Page 3 of 5)SYSTEM: Pressurizer (PZR)SectionXI IS!Identifier

[~~.__Item Description

[ispection Comments B-P 815.20 1PZP-O1-Bl (B-P)815.21 MANWAY BOLTING (16 TOTAL)I2R-12 VT-2 NP!!2R-13 Page 3-51 Exekn.Braidwood Station Unit 1 AiRi2 IS!Outage Report Section 3.4.2 Detailed Inservice Inspection BoratedBoltingListing (Page 4 of 5)SYSTEM: ReactorCoolantSystem (RC)SectionXl ISI Identifier

~Item Description (Inspection Comments B-P 815.50 1PC-i9-B3(B-P) 12P-12 VT-2 815.51FLANGEDCONNECTION(4STUDS) l2R-i3 B-P 815.50 1PC-2O-Bi (B-P)I2P-l2 VT-2 NP!815.51FLANGEDCONNECTION (4 STUDS)12P-13 B-P 815.501RC-23-Bi(B-P) 12R-b2 VT-2 NP!B15.51FLANGEDCONNECTION(4STUDS)______12P-13 B-P 815.50 IPC-27-Bl (B-P)12P-12 VT-2 NP!815.51FLANGEDCONNECTION (4STUDS)l2R-13 B-P 815.10 1RV-03-STUDS (01 TO54,B-P)12P-13 VT-2 NP!815.11 CLOSURE HEAD STUDS (54 TOTAL)12R-3l B-P Bi5.3O 1SG-O5-SGB-Oi (B-P)12P-13 VT-2 NA!815.31 PRIMARY MANWAY (20 STUDS)l2R-31 B-P 815.30 1SG-05-SGB-O2 (B-P)12R-13 VT-2 NP!815.31 PRIMARY MANWAY (20 STUDS)l2A-3l B-P 815.30 1SG-O6-SGB-O1 (B-P)!2P-13 VT-2 NA!815.31 PRIMARY MANWAY (20 STUDS)________12R-3l B-P 815.30 1SG-O6-SGB-O2 (B-P)12P-13 VT-2 NP!815.31 PRIMARY MANWAY (20 STUDS)12R-3l______B-P 815.30 1SG-O7-SGB-Oi (B-P)12P-13 VT-2 NP!815.31 PRIMARY MANWAY (20 STUDS)12R-31 Section Xl VT-i scheduledforA1P12.(IS!)____________________________

___________

B-P 815.30 1SG-07-SGB-02 (B-P)12A-13 VT-2 NA!B15.31 PRIMARY MANWAY (20 STUDS)12P-3l Section Xl VT-i scheduledforA1P12.(IS!)________________________B-P 815.30 1SG-08-SGB-Ol (B-P)I2P-l3 VT-2 NA!815.31 PRIMARY MANWAY (20 STUDS)12P-31 Section Xl VT-b scheduledforA1P12.(IS!)_______________

_____________B-P 815.30 1SG-O8-SGB-02 (B-P)l2P-13 VT-2 NA!815.31PRIMARYMANWAY (20 STUDS)l2P-3i Section XI VT-i scheduled forAlPl2.(ISI)_______________

_____NP!Page 3-52 Ecekn.Braidwood Station Unit 1 A1R12 IS!Outage Report Section 3.4.2 Detailed Inservice Inspection BoratedBoltingListing (Page 5 of 5)SYSTEM: Residual Heat Removal System (RH)Section XI Ils!Identifier

~(Inspection Comments C-H C07.30 1 RHO1 MB (C-H)C07.40 FLANGED CONNECTION (12 STUDS)C-H CO7.3O 1RH-02 F-i-i (C-H)C07.4O FLANGED CONNECTION (20 STUDS)l2R-12 12R-1 3 C-H CO7.30 C07.4O1AH-O2F-2-1 (C-H)FLANGED CONNECTION (20 STUDS)12R-12 12P-i3 VT-2 NP!C-H C07.3O CO7.4O 1PH-02 P-4 (C-H)FLANGED CONNECTION (8 STUDS)l2P-12 12A-13 VT-2 NP!C-H CO7.3O CO7.4O 1RH-03 P-2 (C-H)FLANGED CONNECTION (24 STUDS)!2R-12 12P-13 VT-2 NP!C-H CO7.3O CO7.4O 1PH-O5 F-i (C-H)FLANGED CONNECTION (24 STUDS)12P-12 12P-13 VT-2 NP!C-H C07.3O 1PH-OSP-2 (C-H)C07.4OFLANGEDCONNECTION (24 STUDS)C-H C07.3O 1RH-05 F-3-1 (C-H)CO7.4OFLANGEDCONNECTION (12 STUDS)l2R-12 VT-2 12R-i 3 12R-l 2 12P-13 VT-2 VT-i NP!IND.NA!Evidenceofleakage(dry boric acid accumulation, (Approx.1 Cup)identfied within the mechanicalconnection.Component cleaned, VT-iExaminationperformed, with exception of minor surface rust no indication of degradation identfied.

No evidence of leakage identifiedduringpostcleaningexamination.ReferenceIPNumber 477836 for identification of indication in theCorrectiveAction Program.Component was repaired (Bolting Retightened

/Petorqued) on04/13/2006under WO 911750.No evidence of leakage or degradation identifiedduringpost repair exam.C-H CO7.3O 1PH-06 P-i-i (C-H)12R-12 VT-2 NP!CO7.4OFLANGEDCONNECTION (12STUDS)12R-i3 C-H CO7.3O 1PH-O7 P-2-1 (C-H)l2R-i2 VT-2 NA!C07.4O FLANGED CONNECTION (20 STUDS)12R-13 C-H C07.3O 1PH-07 P-3-i(C-H)12P-12 VT-2 NP!C07.4O FLANGED CONNECTION (20 STUDS)12R-13 C-H CO7.7O 1PH6O6(C-H) 12R-12 VT-2 NP!C07.80 1RH606 VLV (4STUDS)l2P-13 12R-12 VT-2 NP!l2R-1 3 VT-2 NP!Page3-53

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