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Exelon. Exelon Generation Company, LLC www.exeloncorp.com Byron Station NUdeaT 445o North German Church Road Byron, IL 61010-9794 August 3, 2010 LTR: BYRON 2010-0042 FILE: 1.10.0101 United States Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Byron Station, Unit 2 Facility Operating License No. NPF-66 NRC Docket No. STN50-455 SUBJECT: Byron Station Unit 2 90-Day Inservice Inspection Report for Interval 3, Period 2, (B2R15) The subject 90-Day Inservice inspection Report for the Byron Station Unit 2, Refueling Outage Fifteen (B2R15) is being submitted pursuant to the requirements of Article IWA-6000, "Records and Reports" of Section XI, "Rules for Inservice inspection of Nuclear Power Plant Components," of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code 200i Edition through the 2003 Addenda. The report covers the inservice inspections conducted prior to and during the Unit 2 Spring 2010 refueling outage. If there are any questions regarding this matter, please contact Dave Gudger, Regulatory Assurance Manager, at (815)-406-2800. Respectfully, Daniel J. Enright Site Vice President Byron Generating Station DJE/RGM,/TLH/cy Attachment: B2R15 Inservice Inspection Summary Report - Spring 2010 outage 404-7 1 kJ(v4

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Page 1: Byron, Unit 2, Submittal of 90-Day Inservice Inspection Report for … · 2012-12-03 · BYRON STATION UNIT 2 REFUELING OUTAGE 15 INSERVICE INSPECTION REPORT 1.1.0 INTRODUCTION Inservice

Exelon.Exelon Generation Company, LLC www.exeloncorp.comByron Station NUdeaT445o North German Church RoadByron, IL 61010-9794

August 3, 2010

LTR: BYRON 2010-0042FILE: 1.10.0101

United States Nuclear Regulatory CommissionATTN: Document Control DeskWashington, DC 20555-0001

Byron Station, Unit 2Facility Operating License No. NPF-66NRC Docket No. STN50-455

SUBJECT: Byron Station Unit 2 90-Day Inservice Inspection Report for Interval 3, Period 2,(B2R15)

The subject 90-Day Inservice inspection Report for the Byron Station Unit 2, Refueling Outage Fifteen(B2R15) is being submitted pursuant to the requirements of Article IWA-6000, "Records and Reports" ofSection XI, "Rules for Inservice inspection of Nuclear Power Plant Components," of the American Societyof Mechanical Engineers Boiler and Pressure Vessel Code 200i Edition through the 2003 Addenda. Thereport covers the inservice inspections conducted prior to and during the Unit 2 Spring 2010 refuelingoutage.

If there are any questions regarding this matter, please contact Dave Gudger, Regulatory AssuranceManager, at (815)-406-2800.

Respectfully,

Daniel J. EnrightSite Vice PresidentByron Generating Station

DJE/RGM,/TLH/cy

Attachment: B2R15 Inservice Inspection Summary Report - Spring 2010 outage

404-71kJ(v4

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BYRON Exelon..UNIT 2 Nuclear

B2R15Spring 2010 Outage

INSERVICE INSPECTIONSUMMARY REPORT

For Inspection Activitiesfrom

October 24, 2008to

May 8, 2010

Commercial Service DateAugust 21, 1987

Document Completion DateJuly 29, 2010

Exelon Generation Company (EGC, LLC)

4300 Winfield RdWarrenville, IL 60555

Byron Nuclear Power Station4450 North German Church Rd.

Byron, IL 61010.

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BYRON UNIT 2 Exelon.Nuclear

B2R15INSERVICE INSPECTION SUMMARY REPORT

SECTION SECTION DESCRIPTION PAGES

ICover Page 1

I ii ITable of Contents 1

1 1.0 Report Introduction 6

ISI - Weld / Component Listing 18ISI - Bolts, Pumps, and Valves Listing 1

Examination PSI - Weld / Component Listing 12.0 Summary PSI - Bolts, Pumps, and Valves Listing 2

Tables ISI - Pressure Tests 12ISI - Component Supports 9

ISI - Snubbers 11

1 3.0 IStatus of Examination Completion for the Program Plan 7

1 4.0 IForm NIS-I: Preservice and Inservice Examinations 5=3

1 5.0 lForm NIS-2: Repairs/ Modifications 49

I TOTAL PAGES IN REPORTI 171

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SECTION 1.0

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BYRON STATION UNIT 2 REFUELING OUTAGE 15INSERVICE INSPECTION REPORT

1.1.0 INTRODUCTION

Inservice inspections of American Society of Mechanical Engineers (ASME) Class 1,2, 3, CC, and MC components were conducted at Byron Station Unit 2 from October24, 2008 through May 8, 2010. The majority of these inspections were performedduring the fifteenth refueling outage (B2R15) from April 19 through May 8, 2010.

B2R1 5 is the first outage of the Second Period in the Third Inspection Interval.

The examinations were performed in compliance with the rules and regulations ofASME Section Xl 2001 Edition, through the 2003 Addenda, pursuant to therequirements of 10 CFR 50.55a.

See 1.7.0 of the introduction for a listing of referenced documents.

This summary report meets the requirements of ASME Code, IWA-6000 for theinspection of Class 1 and 2 components and piping. Class CC and MC componentsin the Containment Inservice Inspection (CISI) program are included whenexamination results require reporting as specified in 10 CFR 50.55a.

The Nondestructive Examination (NDE) Inservice Inspection (ISI) Program Plan forClass 1, 2, 3, CC, and MC components was developed in accordance with therequirements and intent of Section Xl Subsections IWA, IWB, IWC, IWD, IWE, IWFand IWL, 2001 Edition, through the 2003 Addenda.

In addition to the ASME Section Xl requirements of examination, certain NuclearRegulatory Commission (NRC) augmented ISI inspections and industry initiatives(NEI-03-08) were required. The Byron Station Unit 2 augmented ISI examinationrequirements include:

6 Class 1 pressure boundary examinations for leakage at nominal operatingpressure, in accordance with NRC Generic Letter 88-05;

* Class 1 Alloy 600 weld examinations in accordance with MRP-139, N-722, andN-729-1;

6 Class 2 and 3 pressure boundary examinations for leakage at nominal operatingpressure, in accordance with NUREG 0737.

* Examination of RCP Flywheels in accordance with Regulatory Guide 1.14.

* Class 1 examinations of non-isolable Reactor Coolant System branch lines forThermal Fatigue in accordance with MRP-146;

Specific requests for relief were developed and submitted for the NRC's reviewwhen the code and/or augmented requirement(s) were deemed to be impractical,results in excessive hardship, or an alternative examination method is determinedas more suitable for the particular component.

Section 1.0 Page 1 of 6

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BYRON STATION UNIT 2 REFUELING OUTAGE 15INSERVICE INSPECTION REPORT

1.1.1 Identification of Examination Requirements

The Section 7.0 of the ISI Program Plan contains the examination program tables.These tables are consistent with the tables found in Subsections IWB, IWC, IWD,IWE, IWF, and IWL-2500 of the ASME Code. The examination tables include thecorresponding code category, item number, and component/weld selection inconformance with examination requirements and intent of Section Xl.

For Class 1, 2, and certain non-class piping components, the requirements of RiskInformed Inservice Inspection (RI-ISI) are followed using EPRI TRI 12657 and Table1 of ASME Code Case N-578-1.

1.1.2 Identification of Exempted Components

ASME Class 1, 2, and 3 components, or parts of components, that are not includedin the examination tables and that are exempt from examination, as specified inSection Xl Paragraphs IWB, IWC, and IWD-1200, and Tables IWB-2500-1, IWC-2500-1, and IWD-2500-1, are identified in the NDE Program Plan in conjunction withtechnical justification(s) for exempting the component/system.

Class 1 or 2 piping welds exempted by IWB and IWC-1200 are not included in theRI-ISI program. Previous selection and examination exemptions identified in TablesIWB and IWC-2500-1 for Examination Categories B-F, B-J, C-F-i, and C-F-2, arenot allowed under the requirements of the RI-ISI program. With the adoption of RI-ISI, welds evaluated as Risk Category 6 or 7 are not subject to examination.

1.1.3 Implementation of the ISI Program

Exelon Nuclear, or its designee, examined ASME components utilizing the followingmethods: MT, PT, UT, VT-1, VT-2, and VT-3. The components examined complywith the ISI Program Schedule, Byron Station Technical Specifications, and/orcomply with the ASME Section Xl Repair/Replacement Program.

Personnel certified in nondestructive examination are qualified in accordance withANSI/ASNT CP-1 89, 1995 Edition and ASME Section Xl, 2001 Edition through 2003Addenda including December 2003 Erratum.

All personnel performing ASME Section Xl ultrasonic examinations are qualified tothe requirements of ASME Section Xl Appendix VII.

The NDE procedures were developed and qualified in-conformance with ASMESection V and XI as applicable.

All ISI NDE, including evaluation of flaw indications, were performed in accordancewith the requirements stipulated under Section XI IWA-2200. For componentsincorporated into the RI-ISI program, the guidance for the examination volume for agiven degradation mechanism is provided by the EPRI Topical Report while theguidance for the examination method is provided by Code Case N-578-1.

Section 1.0 Page 2 of 6

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BYRON STATION UNIT 2 REFUELING OUTAGE 15INSERVICE INSPECTION REPORT

1.1.4 Siginificant Activities During B2R15

During the refueling outage, the Alloy 600 welds were examined for PWSCC per therequirements specified in N-722:

" All reactor vessel bottom-mounted instrument penetrations were visuallyexamined for leakage Item 115.80 weldments.

" All reactor vessel hot leg safe-end welds were visually examined for leakage forItem B15.90 weldments.

" One Alloy 600 reactor vessel cold leg safe-end weld was visually examined forleakage for Item B15.95 weldments.

" The steam generator primary channel head drains were visually examined forleakage for Item B15.120 weldments.

The reactor vessel head exterior surface was visually examined for evidence ofleakage per the requirements specified in N-729-1 Note (4) for Item B4.1 0components. One repaired reactor head penetration was examined with surfaceand volumetric methods per Item B4.20 and the approved relief request 13R-16.

All weld overlays on the pressurizer safe-end welds were volumetrically examined.This examination complies with the requirements specified in MRP-139 for CategoryF welds and ASME Appendix Q Paragraph Q-4300(a). Use of Appendix Q wasaddressed in relief request 13R-08.

1.1.5 ASME Section Xl Code Cases

N-566-2 is incorporated into the current Byron Station ISI Program and was utilizedduring this fuel cycle.

The implementation of the risk-informed program as described in relief request 13R-02 utilized N-578-1 during this Inspection Interval.

For Repair/Replacement activities, code cases are identified on the applicable FormNIS-2.

1.1.6 Witness and Verification of Examination

The inservice inspections were witnessed and/or verified by Authorized NuclearInservice Inspectors (ANII) associated with Hartford Steam Boiler CT of Hartford,Connecticut, Chicago Branch, at 2443 Warrenville Rd., Suite 500, Lisle, Illinois60532.

1.1.7 Corrective Measures

A surface examination revealed two indications located in the fusion zone betweentwo weld beads of an attachment weld on the 12" SI pipe to the flued headPenetration P-66 closure. The weld is identified in the Inservice Inspection Programas 2SI04B-1 2/C02 and was examined as Observation 15-203 in the outage. The

Section 1.0 Page 3 of 6

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BYRON STATION UNIT 2 REFUELING OUTAGE 15INSERVICE INSPECTION REPORT

weld was selected under ASME Section Xl Class 2 Examination Category C-C; ItemC3.20. The indications were described in Issue Report 01057786 and OE 31183.

The indications were near the weld toe on the flued head side of the fillet weld. Theindications followed the interface between the beads while being removed and werethus classified as lack of fusion. The areas of the indications were blended and theindications were completely removed.

Additional examinations were performed on other attachment welds of similarmaterials and service per the requirements of ASME XI IWC-2430. Welds2RH01 BA-1 2/C03 and 2SI05BA-8/C02 were examined as Observations 15-223 and15-221 respectively. The additional examinations were acceptable and no othercode related actions are required.

1.2.0 EXAMINATION SUMMARIES

The following section lists the summaries of examinations performed during therefueling cycle. Refer to Section 2.0 for each summary table for information or forspecific tests and examinations conducted during this term.

Welds & Components Summaries

Inservice Inspection - Weld / Component ListingInservice Inspection - Bolts, Pumps, and Valves ListingPreservice Inspection - Weld / Component ListingPreservice Inspection - Bolts, Pumps, and Valves Listing

* System Pressure Test Summaries

• Component Support Examination Summary

* Component Snubber Test Summary

1.3.0 UNIT 2 EXAMINATION COMPLETION STATUS

A summary table of the examination status of Class 1 and 2 components iscontained in Section 3.0.

1.4.0 FORM NIS-1 DATA SHEETS

ASME Form NIS-1 were filed during the cycle for Unit 2. See Section 4.0 for thereports.

1.5.0 FORM NIS-2 DATA SHEETS

ASME Form NIS-2 were filed during the cycle for Unit 2. See Section 5.0 for thereports.

Section 1.0 Page 4 of 6

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BYRON STATION UNIT 2 REFUELING OUTAGE 15INSERVICE INSPECTION REPORT

1.6.0 CONTAINMENT ISI PROGRAM

No reportable conditions were identified for Class CC and Class MC componentsduring this fuel cycle.

1.7.0 REFERENCED DOCUMENTS

1.7.1 Code of Federal Regulations, Title 10 Energv

Part 50: Domestic Licensing of Production and Utilization Facilities.

50.55a: Codes and Standards.

1.7.2 American Society of Mechanical Engineers Boiler and Pressure Vessel Code

Section V: Nondestructive Examination, 2001 Edition, through 2003 Addenda.Section XI: Rules for Inservice Inspection of Nuclear Power Plant Components,2001 Edition, through 2003 Addenda.

IWA-2200: Examination Methods.

IWA-6000: Records and Reports.IWB, IWC: and IWD-1 200, Components Exempt from Examination.IWB, IWC: and IWD-2500, Examination and Pressure Test Requirements.IWC-2430: Additional Examinations.IWC-3512: Standards for Examination Category C-C, Welded Attachments forVessels, Piping, Pumps, and Valves.Appendix I1: Owner's Reports for Inservice Inspections.

Form NIS-1: Owners Report for Inservice Inspections.Form NIS-2: Owners Report for Repairs or Replacements.

Appendix VII: Qualification of Nondestructive Examination Personnel forUltrasonic Examination.

Code Case N-504-3: Alternative Rules for Repair of Classes 1, 2, and 3 AusteniticStainless Steel Piping.Code Case N-566-2: Corrective Action for Leakage Identified at Bolted Connections.Code Case N-578-1: Risk-Informed Requirements for Class 1, 2, or 3 Piping,Method B.

Code Case N-722: Additional Examinations for PWR Pressure Retaining Welds inClass 1 Components Fabricated With Alloy 600/82/182 Materials.Code Case N-729-1: Alternative Examination Requirements for PWR ReactorVessel Upper Heads With Nozzles Having Pressure-Retaining Partial-PenetrationWelds.

Section 1.0 Page 5 of

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BYRON STATION UNIT 2 REFUELING OUTAGE 15INSERVICE INSPECTION REPORT

Nonmandatory Appendix Q: Weld Overlay Repair of Class 1, 2, and 3 AusteniticStainless Steel Piping Weldments (2004 Edition, through 2005 Addenda). AppendixQ was required for the installation of the weld overlays using Code Case N-504-3.

Section Q-4300: Inservice Inspection.

1.7.3 American National Standards Institute / American Society for Nondestructive Testing

ANSI/ASNT CP-1 89:1995 Edition, Standard for Qualification and Certification ofNondestructive Testing Personnel.

1.7.4 Miscellaneous NRC Documents

Generic Letter 88-05: Boric Acid Corrosion of Carbon Steel Reactor PressureBoundary Components in PWR Plants.

NUREG 0737: Clarification of TMI Action Plan Requirements.

Regulatory Guide RG 1.14: Reactor Coolant Pump Flywheel Integrity.

1.7.5 Electric Power Research Institute

Material Reliability Program: Primary System Piping Butt Weld Inspection andEvaluation Guideline (MRP-1 39) Revision 1, December 2008.Material Reliability Program: Management of Thermal Fatigue in Normally StagnantNon-Isolable Reactor Coolant System Branch Lines (MRP-1 46), June 2005.

Topical Report TR1 12657: Revision B-A, Revised Risk-Informed InserviceInspection Procedure, December 1999.

1.7.6 Nuclear Energy Institute

NEI 03-08: Guideline for the Management of Materials Issues.

1.7.7 Byron Station Documents

Relief Request 13R-02: Alternate Risk-Informed Selection and Examination Criteriafor Category B-F, B-J, C-F-1, and C-F-2 Pressure Retaining Piping Welds.

Relief Request 13R-08: Alternative Requirements of Structural Weld Overlays(SWOLs) of the Pressurizer Surge, Spray, Safety and Relief Nozzles, DissimilarWelds including the SWOLs of the Safe-End to Pipe, Reducer and Elbow Welds onPressurizer Surge, Spray, Safety and Relief Nozzles.

Relief Request 13R-1 6: Alternate Examination Frequency under ASME Code CaseN-729-1 for Reactor Vessel Head Penetration Welds.

Issue Report 01057786: Recordable Indications Discovered During ISI Examination.

1.7.8 Institute of Nuclear Power Operations

0E31183: Unacceptable Surface Indications on a Safety Injection Flued HeadPenetration Weld.

Section 1.0 Page 6 of 6

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SECTION 2.0

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7/29/2010 Exelin.,Byron Station Unit 2

B2R15 ISI Outage Report

Weld / Component Outage Summary

SYSTEM: Chemical & Volume Control System (CV)

Section Xl TComponent ID Line e:Nuber Relief Technical . code Acual Resul'ts

Cat' Description Requests Notes. Coverage .d Exam

Comments

R-A R1.11 2CVA3B-21W-70 2CVA3B-2 13R-02 89.40 VT-2 NRI

Pipe - Elbow 13T-01

13T-02

OBS 15-005

R-A R1.11 2CVA3B-2/W-71 2CVA3B-2 13R-02 B9.40 VT-2 NRI

Elbow - Pipe 13T-01

13T-02.

OBS 15-006

R-A R1.11 2CVA3B-2/W-72 2CVA3B-2 13R-02 89.40 VT-2 NRI

Pipe - Elbow 13T-01

13T-02

OBS 15-007

R-A RI.11 2CVA3B-2/W-73 2CVA3B-2 13R-02 89.40 VT-2 NRI

Elbow - Pipe 13T-01

13T-02

OBS 15-008

R-A R1.1 1 2CVA3B-2/W-80 2CVA3B-2 13R-02 B9.40 VT-2 NRI

Pipe - Elbow 13T-01

13T-02

OBS 15-009

R-A R1.11 2CVA3B-2/W-81 2CVA3B-2 13R-02 89.40 VT-2 NRI

Elbow - Pipe 13T-01

13T-02

OBS 15-010

R-A R1.11 2CVA5AA-2/W-06 2CVA5AA-2 13R-02 B9.40 VT-2 NRI

Pipe - Elbow 13T-01,

13T-02

OBS 15-011

R-A R1.11 2CVA5AA-2/W-07 2CVA5AA-2 13R-02 B9.40 VT-2 NRI

Elbow - Pipe 13T-01

13T-02

OBS 15-012

R-A R1.11 2CVA6AA-2/W-04 2CVA6AA-2 13R-02 89.40 VT-2 NRI

Pipe - Elbow 13T-01

13T-02

OBS 15-013

R-A R1.1 1 2CVA6AA-2/W-05 2CVA6AA-2 13R-02 89.40 VT-2 NRI

Elbow - Pipe 13T-0113T-02

OBS 15-014

R-A R1.11 2CVA7AA-2/W-06 2CVA7AA-2 13R-02 89.40 VT-2 NRI

Pipe - Elbow 13T-01

13T-02

OBS 15-050

1

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7/29/2010 Exel mn..Byron Station Unit 2

B2R15 ISI Outage Report

Weld / Component Outage Summary

SYSTEM: Chemical & Volume Control System (CV)

Section XI, Compoonent ID LineNumber Relief 'Technical Code ]- r tua[' ResultsCat. Description Requests Notes' Coverage7 Exam'.

Comments'

R-A R1.11 2CVA7AA-2/W-07 2CVA7AA-2 13R-02 B9.40 VT-2 NRIElbow - Pipe 13t-01

13T-02OBS 15-051

R-A RI.11 2CVA7AA-2/W-08 2CVA7AA-2 13R-02 B9.40 VT-2 NRIPipe - Elbow 13T-01

13T-02OBS 15-052

2

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B2R15 ISI Outage Report

Weld / Component Outage Summary

SYSTEM: Feedwater System (FW)

Section Xl 0Component ID , Line Number, Relief. >Technical Code. 1,.• Actuai ResultsCa. Description -.Reiet k!ote s. Cvrg Exam

Comments .

R-A R1.11 2FW03DA-16/CO1 2FW03DA-16 13R-02 C5.51 100 UT NRI

R1.18 Valve-Pipe 13T-01

13T-02

OBS 15-102

R-A R1.11 2FW03DA-16/C02 2FW03DA-16 13R-02 C5.51 100 UT GEOMR1.18 Pipe - Penetration 13T-01

13T-02

OBS 15-103ID Geometry 3600 Intermittent.

R-A R1.11 2FW81BA-6/C07 2FW81BA-6 13R-02 C5.51 99 UT NRI

R1.18 Pipe-Tee 13T-01

13T-02

OBS 15-104Coverage reduced due to adjacent branch connection on tee side.

R-A R1.1l 2FW87CA-6/CO1 2FW87CA-6 13R-02 C5.51 99 UT NRI

R1.18 Reducer-Tee 13T-01

13T-02

OBS 15-105Coverage reduced due to adjacent branch connection on tee side.

R-A R1.11 2FW87CA-6/C02 2FW87CA-6 13R-02 C5.51 98 UT GEOM

R1.18 Tee-Pipe 13T-01

13T-02

OBS 15-106ID Geometry 3600 Intermittent. Coverage reduced due to adjacent branch connection on tee side.

R-A R1.11 2FW87CA-6/C03 2FW87CA-6 13R-02 C5.51 100 UT GEOMR1.18 Pipe - Penetration 13T-01

13T-02

OBS 15-107ID Geometry 3600 Intermittent.

C-C C3.20 2FW87CA-6/C04 2FW87CA-6 100 MT NRIClosure Plate 2PC-100

OBS 15-108

3

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7/29/2010 ExeI4 n,nByron Station Unit 2

B2R15 ISI Outage Report

Weld / Component Outage Summary

SYSTEM: Pressurizer (PZR)ýSection XI Component ID Line Number . :rRie -Technica[* Cd cua eut

Cat. Description j,,,' Requests,,-,, Notes., Coverage Exam

Comments

B-B B2.11 2RY-01-S/PC-05 2RY-01-S .96 UT NRIShell - Upper Head

OBS 15-128Scanning obstructed by 4 welded insulation pads.

B-B B2.12 2RY-01-S/PL-04 2RY-01-S 100 UT NRIUpper Longitudinal Weld

OBS 15-129

B-D B3.110 2RY-01-S/PN-02 2RY-01-S 13R-12 62 UT NRISpray Nozzle

OBS 15-131Limited examination due to nozzle to vessel configuration.

B-D 83.120 2RY-01-S/PN-02-NIR 2RY-01-S UT NRISpray Nozzle Inner Radius

OBS 15-133

B-D B3.110 2RY-01-S/PN-03 2RY-01-S 13R-12 66 UT NRIPORV Nozzle

OBS 15-136Limited examination due to nozzle to vessel configuration.

B-D B3.120 2RY-01-S/PN-03-NIR 2RY-01-S UT NRIRelief Nozzle Inner Radius

OBS 15-136

B-D 83.120 2RY-01-S/PN-05-NIR 2RY-01-S UT NRIRelief Nozzle Inner Radius

OBS 15-139

B-D B3.110 2RY-01-S/PN-06Relief Nozzle

2RY-01-S 13R-12 66 UT NRI

OBS 15-140Limited examination due to nozzle to vessel configuration.

B-D B3.120 2RY-01-S/PN-06-NIR 2RY-01-SRelief Nozzle Inner Radius

OBS 15-142

UT NRI

4

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7/29/2010ExIn~Exelon.

Byron Station Unit 2B2R15 ISI Outage Report

Weld Component Outage Summary

SYSTEM: Reactor Coolant System (RC)

~Setin I ChionntlDbf~r L neNib6iýbe,ýt Relief" ~T4echmic'all '+~eý':' ,. ., 46t4aLýl, Resu tsippequestion Notes , oveage Exam

ýComments'

R-A R1.20 2RC01AA-29/J06 2RC01AA-29 13R-02. B9.40 VT-2 NRISOL - Thermowell 13T-01

13T-02OBS 15-015

R-A R1.15 2RC-01-R/RPVS-A F1 2RC-01-R 13R-02 B5.10 BMV NRIB15.90 RPV Nozzle Safe-End HL Loop D 13T-01

13T-02OBS 15-185Hot Leg Bare Metal exam per N-722 requirements. See WO#01 182316.

R-A R1.15 2RC-01-R/RPVS-D F1 2RC-01-R 13R-02 B5.10 BMV NRIB15.90 RPV Nozzle Safe-End HL Loop C 13T-01

13T-02OBS 15-186Hot Leg Bare Metal exam per N-722 requirements. See WO#01 182316.

R-A R1.15 2RC-01-R/RPVS-E F1 2RC-01-R 13R-02 B5.10 BMV NRIB15.90 RPV Nozzle Safe-End HL Loop B 13T-01

13T-02OBS 15-187Hot Leg Bare Metal exam per N-722 requirements. See WO#01 182316.

R-A R1.15 2RC-01-R/RPVS-F F1 2RC-01-R 13R-02 B5.10 VT-2 NRIB15.95 RPV Nozzle Safe-End CL Loop B 13T-01

13T-02OBS 15-225Bare Metal exam per N-722 requirements. See WO#01300973.

R-A R1.15 2RC-01-R/RPVS-H F1 2RC-01-R 13R-02 85.10 BMV NRIB15.90 RPV Nozzle Safe-End HL Loop A - 13T-01

13T-02OBS 15-188Hot Leg Bare Metal exam per N-722 requirements. See WO#01 182316.

R-A R1.20 2RC03AA-27.5/JO2A 2RC03AA-27.5 13R-02 B9.40 VT-2 NRISOL - Thermowell 13T-01

13T-02OBS 15-016

R-A R1.20 2RC03AA-27.5/J04 2RC03AA-27.5 13R-02 B9.40 VT-2 NRISOL - Thermowell 13T-01

13T-02OBS 15-017

R-A R1.20 2RC13AA-2/W-01 2RC13AA-2 13R-02 B9.40 VT-2 NRISOL - Pipe 13T-01

13T-02OBS 15-026

R-A R1.20 2RC13AA-2/W-02 2RC13AA-2 13R-02 B9.40 VT-2 NRIPipe - Tee 13T-01

13T-02OBS 15-027

5

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7/29/2010 Exelen.Byron Station Unit 2

B2R15 ISI Outage Report

Weld / Component Outage Summary

SYSTEM: Reactor Coolant System (RC)

Section XI Component iD) Line Number,, -. Relief -. :Technicai Code Actual Results,]rCat. Descrption Requests'- Notes 0Coveage Exam

Comments"-

R-A R1.20 2RC13AA-2/W-03 2RC13AA-2 13R-02- B9.40 VT-2 NRITee - Reducer 13T-01

13T-02

OBS 15-028

R-A R1.20 2RC13AA-2/W-04 2RC13AA-2 13R-02 B9.40 VT-2 NRITee - Pipe 13T-01

13T-02

OBS 15-029

R-A R1.20 2RC13AA-2/W-05 2RC13AA-2 13R-02 B9.40 VT-2 NRI

Pipe - Valve 13T-01

13T-02

OBS 15-030

R-A R1.20 2RC13AB-2/W-01 2RC13AB-2 13R-02 B9.40 VT-2 NRISOL - Pipe 13T-01

13T-02

OBS 15-031

R-A R1.20 2RC13AC-2/W-01 2RC13AC-2 13R-02 B9.40 VT-2 NRISOL - Pipe 13T-01

13T-02

OBS 15-032

R-A R1.20 2RC13AD-2/W-01 2RC13AD-2 13R-02 B9.40 VT-2 NRI

SOL - Pipe 13T-01

13T-02OBS 15-033

R-A R1.11 2RC14AA-2/W-01 2RC14AA-2 13R-02 89.40 VT-2 NRISOL - Pipe 13T-01

13T-02

OBS 15-036

R-A R1.11 2RC14AA-21W-01A 2RC14AA-2 13R-02 89.40 VT-2 NRIPipe - Tee 13T-01

13T-02OBS 15-037

R-A R1.11 2RC14AA-2/W-01B 2RC14AA-2 13R-02 89.40 VT-2 NRITee - Reducer 13T-01

13T-02

OBS 15-038

R-A R1.11 2RC14AA-2/W-01C 2RC14AA-2 13R-02 B9.40 VT-2 NRITee - Pipe 13T-01

13T-02

OBS 15-039

R-A R1.11 2RC14AA-2/W-02 2RC14AA-2 13R-02 B9.40 VT-2 NRIPipe - Elbow 13T-01

13T-02

OBS 15-040

6

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7/29/2010 Exelon.Byron Station Unit 2

B2R15 ISI Outage Report

Weld / Component Outage Summary

SYSTEM: Reactor Coolant System (RC)

,Secton* XI Cohiponent, D Line Number•,, , -," Relief -,Technicai Code I 'Actual , ResultsactKK :~euss'.~o~~ Coverage ,Exam ~

IComments ~ ...- 4•.. . . •• " .. ... "

R-A R1.11 2RC14AA-2/W-03 2RC14AA-2 13R-02 B9.40 VT-2 NRI

Elbow - Pipe 13T-01

13T-02

OBS 15-041

R-A R1.11 2RC14AA-2/W-04 2RC14AA-2 13R-02 B9.40 VT-2 NRI

Pipe - Elbow 13T-01

13T-02

OBS 15-042

R-A R1.11 2RC14AA-2/W-05 2RC14AA-2 13R-02 B9.40 VT-2 NRI

Elbow - Pipe 13T-01

13T-02

OBS 15-043

R-A R1.11 2RC14AA-2/W-06 2RC14AA-2 13R-02 B9.40 VT-2 NRIPipe - Valve 13T-01

13T-02

OBS 15-044

R-A R1.11 2RC14AA-2/W-07 2RC14AA-2 13R-02 B9.40 VT-2 NRI

Valve - Pipe 13T-01

13T-02

OBS 15-045

R-A R1.11 2RC14AA-2/W-08 2RC14AA-2 13R-02 89.40 VT-2 NRIPipe - Tee 13T-01

13T-02

OBS 15-046

R-A R1.11 2RC14AA-2/W-09 2RC14AA-2 13R-02 89.40 VT-2 NRI

Tee - Reducer 13T-01

13T-02

OBS 15-047

R-A R1.11 2RC14AA-2/W-10 2RC14AA-2 13R-02 89.40 VT-2 NRI

Tee - Pipe 13T-01

13T-02

OBS 15-048

R-A R1.11 2RC14AA-2/W-11 2RC14AA-2 13R-02 89.40 VT-2 NRI

Pipe - Valve 13T-01

13T-02

OBS 15-049

R-A R1.11 2RC16AA-2/W-03 2RC16AA-2 13R-02 B9.40 VT-2 NRI

Valve - Pipe 13T-01

13T-02

OBS 15-053

R-A R1.11 2RC16AA-2/W-04 2RC16AA-2 13R-02 89.40 VT-2 NRI

Pipe - Elbow 13T-0113T-02

OBS 15-054

7

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7/29/2010Ex I nByron Station Unit 2

B2R15 ISI Outage Report

Weld / Component Outage Summary

SYSTEM: Reactor Coolant System (RC)

Section XI Component ID .. Line Number, F- : Relief 'Technicai Code - - Actual Results

' Cat. Description Re'qesti ' "- Notes Coverage Exam

Comments-

R-A R1.11 2RC16AA-2/W-05 2RC16AA-2 13R-02 89.40 VT-2 NRI

Elbow - Pipe 13T-01

13T-02

OBS 15-055

R-A R1.11 2RC16AA-2/W-06 2RC16AA-2 13R-02 B9.40 VT-2 NRI

Pipe - Elbow 13T-01

13T-02

OBS 15-056

R-A R1.11 2RC16AA-2/W-07 2RC16AA-2 13R-02 B9.40 VT-2 NRI

Elbow - Pipe 13T-0113T-02

OBS 15-057

R-A R1.11 2RC16AB-2/W-04 2RC16AB-2 13R-02 B9.40 VT-2 NRIPipe - Elbow 13T-01

13T-02

OBS 15-058

R-A R1.11 2RC16AB-2/W-05 2RC16AB-2 13R-02 89.40 VT-2 NRI

S"Elbow - Pipe 13T-01

13T-02

OBS 15-059

R-A R1.20 2RC16AC-2/W-08 2RC16AC-2 13R-02 B9.40 VT-2 NRI

Pipe - SOL 13T-01

13T-02

OBS 15-024

R-A R1.20 2RC16AD-2/W-01 2RC16AD-2 13R-02 89.40 VT-2 NRI

Valve - Pipe 13T-01

13T-02

OBS 15-025

R-A R1.20 2RC22AA-1.5/W-01 2RC22AA-1.5 13R-02 B9.40 VT-2 NRI

SOL - Pipe 13T-01

13T-02

OBS 15-020

R-A R1.20 2RC22AA-1.5/W-05 2RC22AA-1.5 13R-02 89.40 VT-2 NRI

Elbow - Pipe 13T-01

13T-02

OBS 15-021

R-A R1,20 2RC22AC-1.5/W-01 2RC22AC-1.5 13R-02 89.40 VT-2 NRI

SOL - Pipe 13T-01

13T-02

OBS 15-022

R-A R1.20 2RC22AC-1.5/W-06 2RC22AC-1.5 13R-02 B9.40 VT-2 NRI

Pipe - Tee 13T-01

13T-02

OBS 15-023

8

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7/29/2010 Exelon.Byron Station Unit 2

B2R15 ISI Outage Report

Weld / Component Outage Summary

SYSTEM: Reactor Coolant System (RC)

Seciion XI. component ID Line Number. .," Relief ,.; Technicai Code ActuaI: Results'Cat. Description Reluests . oiýýt Ex'COverage Exam

Comments

R-A R1.20 2RC22AD-1.5/W-01 2RC22AD-1.5 13R-02 B9.40 VT-2 NRISOLL- Pipe 13T-01

13T-02OBS 15-018

R-A R1.20 2RC22AD-1.5/W-08 2RC22AD-1.5 13R-02 B9.40 VT-2 NRIPipe - Tee 13T-01

13T-02OBS 15-019

R-A R1.20 2RC26A-2/W-01 2RC26A-2 13R-02 B9.40 VT-2 NRISOL - Pipe 13T-01

13T-02OBS 15-034

R-A R1.20 2RC26A-2/W-02 2RC26A-2 13R-02 B9.40 VT-2 NRIPipe - Valve 13T-01

13T-02OBS 15-035

N/A N/A 2RC28A-3/Zone 1 2RC28A-3 91 UT NRIElbow - SOL VT-2 NRI

OBS 15-212Volumetric and bare metal visual per MRP-146.Scanning obstructed due to elbow to branch configuration.

R-A R1.11 2RC30AA-1.5/W-01 2RC30AA-1.5 13R-02 B9.40 VT-2 NRIValve - Reducer 13T-01

13T-02OBS 15-079

R-A R1.20 2RC35AA-6/J02 2RC35AA-6 13R-02 B9.11 100 UT NRIPipe - Elbow 13T-01

13T-02OBS 15-199ID Geometry 360' Intermittent seen below recording levels.

R-A R1.20 2RC35AA-6/J03 2RC35AA-6 13R-02 139.11 100 UT NRIElbow - Pipe 13T-01

13T-02OBS 15-200ID Geometry 3600 Intermittent seen below recording levels.

R-A R1.11 2RC35AA-6/J04 2RC35AA-6 13R-02 B9.11 100 UT NRIPipe - Elbow 13T-01

13T-02OBS 15-201ID Geometry 3600 Intermittent seen below recording levels.

R-A R1.11 2RC35AA-6/J05 2RC35AA-6 13R-02 B9.11 100 UT NRIElbow - Pipe 13T-01

13T-02OBS 15-202ID Geometry 3600 Intermittent seen below recording levels.

9

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7/29/2010 Exelon,nByron Station Unit 2

B2R15 ISI Outage Report

Weld / Component Outage Summary

SYSTEM: Reactor Coolant System (RC)

Section Xl Component iD,, Line Nume Relief Tehia oe Actual, Results'Cat Requests , otes• Coverage Exam

Cdmmbnts'

N/A N/A 2RC37A-3/Zone 2 2RC37A-3 91 UT NRI

Elbow - SOL VT-2 NRI

OBS 15-213Volumetric and bare metal visual per MRP-146.Scanning obstructed due to elbow to branch configuration.

10

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7/29/2010 Exeloin.Byron Station Unit 2

B2R15 ISI Outage Report

Weld / Component Outage Summary

SYSTEM: Residual Heat Removal System (RH)

Section Xl component ID Line Numbeer. Re ie ef Technica[ Code-. j Actual ]ResultsC at. Description .. .. , , . t " Requests, . Notes CoVerage Exam,

Commentsý

C-C C3.20 2RH01BA-12/C03 2RH01BA-12 100 PT NRI

Closure Plate.2PC-68OBS 15-223WO# 01330140. Additional examination for OBS 15-203.

C-C C3.20 2RH02AA-8/C47 2RH02AA-8 100 PT INDClosure Plate 2AB-37

OBS 15-1811/16" Rounded Indication on penetration plate 0.25" from weld toe. Acceptable per procedure. Ref. RIR B2R15-PT-010.

11

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7/29/2010 Exelon.Byron Station Unit 2

B2R15 ISl Outage Report

Weld / Component Outage Summary

SYSTEM: Reactor Pressure Vessel (RPV)

Sýection XiL component'iD 1ine. Number, , iReief I•, ehnica ;'l Cde Actal ResultS.

S Cat. pesriptio'n Requests ',,Notes C oerage Exam

Comments',

N/A B15.80 2RC-01-R/RPV BMI 2RC-01-R 100 VE NRI

RPV Bottom Mounted Instruments

OBS 15-217Detailed examination of head surface and annular area of the penetrations. Ref. WO 01019896

B-E B4.20 2RC-01-R/RPV HEAD 2RC-01-R 13R-16 100 UT. RIPEN

RPV Head Penetrations J-Weld 13R-18 100 PT NRI

OBS 15-218Examination per N-729-1 requirements. Penetration 68 only. See WO#01 186189. Indication classified as fabrication flaw from repairweldingin B2R13. No change in flaw seen in this examination.

B-E B4.10 2RC-01-R/RPV HEAD 2RC-01-R 100 BMV NRISURFRPV Head Penetrations

OBS 15-219Detailed examination of head surface and annular area of the penetrations. Ref. WO 01181363

B-N-1 B13.10 2RC-01-R/RPV 2RC-01-R VT-3 NRIINTERIORRPV Interior Surfaces

OBS 15-220Debris found reference IR 01061204. All other conditions acceptable.

12

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7/29/2010 Exel mn.Byron Station Unit 2

B2R15 ISI Outage Report

Weld / Component Outage Summary

SYSTEM: Reactor Coolant System (RY)

Section Xl Component ID. ... Line Nuimber,- Relief ,. Technical -- Code ,,Acualct Results

Cat. IDescription Requests Notes coverageExam

Comments .

R-A R1.11 2RY01B-6/J28 2RY01B-6 13R-02 B9.11 100 UT NRIElbow - Pipe 13T-01

13T-02OBS 15-156ID Geometry 3600 Intermittent seen below recording levels.

R-A R1.11 2RY01B-6/J29 2RY01B-6 13R-02 B9.11 100 UT NRIPipe - Elbow 13T-01

13T-02OBS 15-157ID Geometry 360' Intermittent seen below recording levels.

R-A R1.11 2RY01B-6/J30 2RY01B-6 13R-02 89.11 100 UT NRIElbow - Reducer 13T-01

13T-02OBS 15-158ID Geometry 360' Intermittent seen below recording levels.

N/A N/A 2RY01C-4/J01S 2RY01C-4 13R-08 100 UT NRIReducer - Spray Nozzle Overlay

OBS 15-159Reexamination per Appendix Q requirements.

N/A N/A 2RY-01-S/PN-01-F1S 2RY-01-S 13R-08 100 UT NRISurge Nozzle-Safe End Overlay

OBS 15-130Reexamination per Appendix Q and MRP-139 Category F requirements.

N/A N/A 2RY-01-S/PN-02-F2S 2RY-01-S 13R-08 100 UT NRISpray Nozzle-Safe End Overlay

OBS 15-132Reexamination per Appendix Q and MRP-139 Category F requirements.

N/A N/A 2RY-01 -S/PN-03-F3S 2RY-01-S 13R-08 100 UT NRIPORV Nozzle-Safe End Overlay

OBS 15-135Reexamination per Appendix Q and MRP-139 Category F requirements.

N/A N/A 2RY-01-S/PN-04-F4S 2RY-01-S 13R-08 UT NRISafety A Nozzle-Safe End Overlay

OBS 15-137Reexamination per Appendix Q and MRP-139 Category F requirements.99.4% coverage in circ. direction and 99.2% in axial direction due to 2 laminar indications seen in the B2R13 baseline examination.

N/A N/A 2RY-01-S/PN-05-F5S 2RY-01-S 13R-08 UT NRISafety B Nozzle-Safe End Overlay

OBS 15-138Reexamination per Appendix Q and MRP-139 Category F requirements.98.2% coverage in circ. direction and 98.3% in axial direction due to 1 laminar indication seen in the B2R13 baseline examination.

N/A N/A 2RY-01-S/PN-06-F6S 2RY-01-S 13R-08 UT NRISafety C Nozzle-Safe End Overlay

OBS 15-141Reexamination per Appendix Q and MRP-139 Category F requirements.92.5% coverage in circ. direction and 90.9% in axial direction due to laminar indications seen in the B2R13 baseline examination.

13

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7/29/2010 - xIn~Exelen..

Byron Station Unit 2B2R15 ISI Outage Report

Weld / Component Outage Summary

SYSTEM: Reactor Coolant System (RY)

,•Section I •,ComonentlD- o .. LiieNumber, , Relef &' ..Techncal -• Code hpActual',, ResultsJrca. Descriptin , , .Requests Notes. Coverage:' Exam

N/A N/A 2RY02A-6/J01S 2RY02A-6 13R-08 UT NRI

PORV Nozzle - Elbow Overlay

OBS 15-171Reexamination per Appendix Q requirements.98.2% coverage in circ. direction and 98.4% in axial direction due to 1 laminar indication seen in the 82R13 baseline examination.

N/A N/A 2RY03AA-6/J01S 2RY03AA-6 13R-08 100 UT NRI

Safety A Nozzle-Safe End - Elbow Overlay

OBS 15-160Reexamination per Appendix Q requirements.

N/A N/A 2RY03AB-6/J01S 2RY03AB-6 13R-08 UT NRI

Safety B Nozzle-Safe End - Elbow Overlay

OBS 15-164Reexamination per Appendix Q requirements.100% coverage in circ. direction and 99.1% in axial direction due to adjacent elbow configuration.

N/A N/A 2RY03AC-6/J01S 2RY03AC-6 13R-08 UT NRI

Safety C Nozzle-Safe End - Elbow Overlay

OBS 15-168Reexamination per Appendix 0 requirements.99.6% coverage in circ. direction and 99.8% in axial direction due to laminar indications seen in the B2R13 baseline examination.

N/A N/A 2RY11A-14/J01S 2RY11A-14 13R-08 100 UT NRI

Surge Nozzle Safe End - Pipe Overlay

OBS 15-144Reexamination per Appendix 0 requirements.

R-A R1.11 2RY18A-2/W-01 2RY18A-2 13R-02 B9.40 VT-2 NRI

Valve - Pipe 13T-01

13T-02

OBS 15-001

R-A R1.11 2RY18A-2/W-02 2RY18A-2 13R-02 B9.40 VT-2 NRI

Pipe - Elbow 13T-01

13T-02

OBS 15-002

R-A R1.11 2RY18A-2/W-03 2RY18A-2 13R-02 B9,40 VT-2 NRI

Elbow - Pipe 13T-01

13T-02

OBS 15-003

R-A R1.11 2RY18A-2/W-04 2RY18A-2 13R-02 B9.40 VT-2 NRI

Pipe - WOL 13T-01

13T-02

OBS 15-004

14

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7/29/2010 Exelkn.Byron Station Unit 2

B2R15 ISI Outage Report

Weld / Component Outage Summary

SYSTEM: Steam Generator (SG)

Section Xl. Component ID . Line Number Relief, -Techia al, oCde I Actual• ,,IResults.,Cat. Descripti on . Requests, !; Notes• d :Coverage Exam.

Comments '

B15.120 2RC-01-BA/DRAIN 2RC-01-BA VT-2 NRI

SG Channel Head Drain

OBS 15-211Bare Metal exam per N-722 requirements. See WO#1 182319.

B15.120 2RC-01-BB/DRAIN 2RC-01-BB VT-2 NRI

SG Channel Head Drain

OBS 15-214Bare Metal exam per N-722 requirements. See WO#1 182320.

B15.120 2RC-01-BC/DRAIN 2RC-01-BC VT-2 NRI

SG Channel Head Drain

OBS 15-215Bare Metal exam per N-722 requirements. See WO#1 182321.

B15.120 2RC-01-BD/DRAIN 2RC-01-BD VT-2 NRISG Channel Head Drain

OBS 15-216Bare Metal exam per N-722 requirements. See WO#1 182317.

15

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7/29/2010 Exelkn..Byron Station Unit 2

B2R15 ISI Outage Report

Weld / Component Outage Summary

SYSTEM: Safety Injection System (SI)

WSktion XI Cociiipqbhen ID~ ~ Line Nimb'ler 7Rei ef Tech~nical 064oce Actual iResults

SD~sti~pin~ Reque i sts Notes, Coverage' Exam~c~meisr.

B-K B10.20 2SI03DA-2/W-08A

Closure Plate 2RB-61

2SI03DA-2 NA 100 PT IND

OBS 15-2041/16" Rounded Indication on penetration plate 0.2" from weld toe. Acceptable per procedure. Ref. RIR B2R15-PT-004.

C-C C3.20 2SI04B-12/C02

Closure Plate 2PC-66

2SI04B-12 100 PT

PT

RI

RI

PT RIPT NRI

OBS 15-203One 0.1" rounded, one 1.3" linear, and one 2.4" linear indications. The linear indications are rejectable per procedure. Ref: IR01057786. The indications were reexamined twice after minor surface conditioning.Linear indications removed by blending and the areas were reexamined.Additional examinations performed on 15-221 and 15-223.

C-C C3.20 2SI05BA-8/C02 2SI05BA-8 100 PT NRI

Closure Plate 2PC-50

OBS 15-221WO# 01330141. Additional examination for OBS 15-203.

R-A R1.11 2SI08HA-2/W-01 2SI08HA-2 13R-02 B9.40 VT-2 NRIReducer - Coupling 13T-01

13T-02

OBS 15-060

R-A R1.11 2SI08HA-2/W-02 2SI08HA-2 13R-02 B9.40 VT-2 NRICoupling - Pipe 13T-01

13T-02

OBS 15-061

R-A R1.11 2SI08HA-2/W-03

Pipe - Flange

2SI08HA-2 13R-02

OBS 15-062

R-A R1.11 2SI08HA-2/W-04Flange - Pipe

2SI08HA-2 13R-02

OBS 15-063

R-A R1.11 2SI08HA-2/W-05Pipe - Coupling

OBS 15-064

2SI08HA-2 13R-02

B9.40

13T-01

13T-02

B9.4013T-01

13T-02

B9.4013T-01

13T-02

89.4013T-01

13T-02

B9.4013T-01

13T-02

VT-2

VT-2 NRI

NRI

VT-2 NRI

R-A R1.11

OBS 15-065

R-A R1.11

OBS 15-066

2SI08HA-2/W-06

Coupling - Reducer

2SI08JA-1.5/W-01Reducer - Pipe

2SI08HA-2 13R-02 VT-2 NRI

2SI08JA-1.5 13R-02 VT-2 NRI

16

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7/29/2010 Exelein.Byron Station Unit 2

B2R15 ISI Outage Report

Weld I Component Outage Summary

SYSTEM: Safety Injection System (SI)

Section Xl Component ID ,Line Number .Relief, 'Technical ,-Code Actual. Results'

Cat v Description Requests, Notes , Coverage Exam

Comments

R-A R1.11 2SI08JA-1.5/W-02 2SI08JA-1.5 13R-02 B9.40 VT-2 NRI

Pipe - Elbow 13T-01

13T-02

OBS 15-067

R-A R1.11 2SI08JA-1.5/W-03 2SI08JA-1.5 13R-02 89.40 VT-2 NRI

Elbow - Pipe 13T-01

13T-02

OBS 15-068

R-A R1.11 2SI08JA-1.5/W-04 2SI08JA-1.5 13R-02 B9.40 VT-2 NRI

Pipe - Elbow 13T-01

13T-02

OBS 15-069

R-A R1.11 2SI08JA-1.5/W-05 2SI08JA-1.5 13R-02 B9.40 VT-2 NRI

Elbow - Pipe 13T-01

13T-02

OBS 15-070

R-A R1.11 2SI08JA-1.5NW-05A 2SI08JA-1.5 13R-02 B9.40 VT-2 NRI

Pipe - Valve 13T-0113T-02

OBS 15-071

R-A R1.11 2SI08JA-1.5/W-05B 2SI08JA-1.5 13R-02 B9.40 VT-2 NRI

Valve - Pipe 13T-6113T-02

OBS 15-072

R-A R1.11 2SI08JA-1.5/W-06 2SI08JA-1.5 13R-02 19.40 VT-2 NRI

Pipe - Elbow 13T-01

13T-02

OBS 15-073

R-A R1.11 2SI08JA-1.5/W-07 2SI08JA-1.5 13R-02 89.40 VT-2 NRI

Elbow - Pipe 13T-01

13T-02

OBS 15-074

R-A R1.11 2SI08JA-1.5/W-10 2SI08JA-1.5 13R-02 89.40 VT-2 NRI

Pipe - Flange 13T-01

13T-02

OBS 15-075

R-A R1.11 2SI08JA-1.5/W-11 2SI08JA-1.5 13R-02 B9.40 VT-2 NRI

Flange - Pipe 13T-01

13T-02

OBS 15-076

R-A R1.11 2SI08JA-1.5/W-14 2SI08JA-1.5 13R-02 89.40 VT-2 NRI

Pipe - Coupling 13T-01

13T-02

OBS 15-077

17

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7/29/2010 Exelein.Byron Station Unit 2

B2R15 ISI Outage Report

Weld / Component Outage Summary

SYSTEM: Safety Injection System (SI)

Section Xl, ComponentiD! , ,Lne Number.. Relief Techical Code , Actual Resultsn,Cat. Description, Requests - Notes,, Coverage " Exam

Comme nts 'R-A R1.11 2SI08JA-1.5/W-15 2SI08JA-1.5 13R-02 B9.40 VT-2 NRI

Coupling - Pipe 13T-01

13T-02

OBS 15-078

18

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7/29/2010 Exelon,Byron Station Unit 2

B2R15 ISI Outage Report

Bolts, Pumps, and Valves Outage Summary

SYSTEM: Safety Injection System (SI)

CttmDescrption, Requests Notes Exami.

Commeýnts. -

B-G-2 B7.50 2SI08HA-2/FLG 1-8 VT-1 RI

Piping Flange Bolting

OBS 15-224Flange was disassembled for gasket replacement under WO 01179198. All studs and nuts were reused.

I

1

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7/29/2010 Exelon.Byron Station Unit 2

B2R15 ISl Outage Report

Weld / Component Outage Summary (Preservice Inspections)

SYSTEM: Safety Injection System (SI)

Section Xl Component ID "Line Number , Relief, Technical Code Required Actual Results.Cat. Item Description NRquests Notes • oCverage Exam Exam

Comments

NA NA 2SI18FC-2/W-01.02 2SI18FC-2 13R-02 B9.40 100 SURF PT NRIValve - Pipe 13T-01 VT-2 VT-2 NRI

13T-02Baseline examination Baseline exam of new socket weld W-4 under WO#01225344.

NA NA 2SI18FC-2/W-01A.01 2SI18FC-2 13R-02 B9.40 100 SURF PT NRIPipe - Coupling 13T-01 VT-2 VT-2 NRI

13T-02Baseline examination Baseline exam of new socket weld W-3A under WO#01225344.

NA NA 2SI18FC-2/W-O1B.01 2SI18FC-2 13R-02 B9.40 100 SURF PT NRICoupling - Pipe 13T-01 VT-2 VT-2 NRI

13T-02Baseline examination Baseline exam of new socket weld W-2 under WO#01225344.

1 7/29/2010

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7/29/2010Ex I In~Exelon,

Byron Station Unit 2

B2R15 ISI Outage Report

Detailed Inservice Inspection Bolts, Pumps, and Valves Listing (PSI)

SYSTEM: Reactor Coolant System (RY)

Section Xl, Component ID-, ei f Technical ActualT Results'Cat. Item Description WRequeSt&"Noes Exam

Cohmments

B-G-2 B7.50 2RY03BC-6/FLG 1-12 VT-1 NRI

Piping Flange Bolting

Baseline exam for 2RY8010C replacement under WO#01 178737.

B-G-2 B7.50 2RY76A-2/FLG 1-8 VT-1 NRI

Piping Flange Bolting

Baseline exam for flange bolting replacement under WO#01 180530.

1 7/29/2010

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7/29/2010 Exelei n.Byron Station Unit 2

B2R15 IS Outage Report

Detailed Inservice Inspection Bolts, Pumps, and Valves Listing (PSI)

SYSTEM: Steam Generator (SG)

S component ID : Relef; Technical Actuale Results

Cat. Item IDescription -. RuesNos, Exa

Comments

B-G-2 B7.30 2RC-01-BA/BLT 1-32 VT-1 NRISG Manway Studs and Nuts

Baseline exam for Cold Leg Bolt #13 replacement. WO#01199605.

2 7/29/2010

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7/29/2010 Exelkn..Byron Station Unit 2

B2R15 ISI Outage Report

Pressure Test Outage Summary

SYSTEM: Auxiliary Feedwater System (AF)Section Xl Component ID . .' , . Rehef, Techncal Actual, Results"'I

Cat.' Item RequeSts Notes Exam

Comments. '.

C-H C7.10 2-AF-2-1 13T-04 VT-2 NRI

C-H C7.10 2-AF-2-2 13T-04 VT-2 NRI

1 7/29/2010

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7/29/2010 Exelon.Byron Station Unit 2

B2R15 ISI Outage Report

Pressure Test Outage Summary

SYSTEM: Containment Spray System (CS)

j.Sction.Xi Component ID., "eif Techia ~At~j esulti,Cat. Item " iequests': N-tes Exam

Comnments -

C-H C7.10 2-CS-2-1 13T-04 VT-2 NRI

C-H C7.10 2-CS-2-2 13T-04 VT-2 NRI

2 7/29/2010

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7/29/2010 Exelkn.Byron Station Unit 2

B2R15 ISI Outage Report

Pressure Test Outage Summary

SYSTEM: Chemical & Volume Control System (CV)

Section X'I Component ID A Relief,ý41'Techinical Actual ResultsCat. Item - Requests Notes Exam

Comments

C-H C7.10 2-CV-2-1 13T-04 VT-2 NRI

C-H C7.10 2-CV-2-10 13T-04 VT-2 NRI

C-H C7.10 2-CV-2-2 13T-04 VT-2 NRI

C-H C7.10 2-CV-2-3 13T-04 VT-2 NRI

C-H C7.10 2-CV-2-4 13T-04 VT-2 NRI

C-H C7.10 2-CV-2-5 13T-04 VT-2 NRI

C-H C7.10 2-CV-2-6 13T-04 VT-2 NRI

C-H C7.10 2-CV-2-7 13T-04 VT-2 NRI

3 7/29/2010

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7/29/2010 Exeln.,Byron Station Unit 2

B2R15 ISI Outage Report

Pressure Test Outage Summary.

SYSTEM: Fuel Pool Cooling System (FC)

Srestion XICompbnenti••D .e•m .. . -equ Techniote .. ual Rgesult

Cat., Itemn ýR -que-sts ~Notes ~ Exani

Coiimmets'

C-H C7.10 2-FC-2-1 13T-04 VT-2 NRI

4 7/29/2010

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7129/2010 Exelan..Byron Station Unit 2

B2R15 ISI Outage Report

Pressure Test Outage Summary

SYSTEM: Feedwater System (FW)SeciohXI ornonetlDK -~ReieL~TeI~nca~ :A~tijI Resu'lts,

'Cat. -Item Reeest Noe~ xam~

Comments

C-H C7.10 2-FW-2-2 13T-04 VT-2 NRI

5 7/29/2010

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7/29/2010 Exelon.Byron Station Unit 2

B2R15 ISI Outage Report

Pressure Test Outage Summary

SYSTEM: Main Steam System (MS)

Section xI Component ID Relief. Technical ctua•A i Results

'Cat. Item Requests Notei :Exam

Comments

C-H C7.10 2-MS-2-1 13T-04 VT-2 NRI

C-H C7.10 2-MS-2-2 13T-04 VT-2 NRI

6 7/29/2010

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7/29/2010 Exelon.Byron Station Unit 2

B2R15 ISl Outage Report

Pressure Test Outage Summary

SYSTEM: Off Gas System (OG)

Section X1 i 1Component ID : Relief Technca Actual Results..Cat.' item Requests E MNotes4 Eam,

ComHments

C-H 07.10 2-OG-2-1 13T-04 VT-2 NRI

7 7/29/2010

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7/29/2010 Exelkn.Byron Station Unit 2

B2R15 ISI Outage Report

Pressure Test Outage Summary

SYSTEM: Process Sampling System (PS)

Section Xl. Component ID' "i ,-jiefjechnical Actual Results*Cat IeRequeist 9 otes Exam

Comments'

C-H C7.10 2-PS-2-3 13T-04 VT-2 NRI

C-H C7.10 2-PS-2-4 13TZ04 VT-2 NRI

C-H C7.10 2-PS-2-5 13T-04 VT-2 NRI

C-H C7.10 2-PS-2-6 13T-04 VT-2 NRI

8 7/29/2010

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7/29/2010 Exelmn.Byron Station Unit 2

B2R15 ISI Outage Report

Pressure Test Outage Summary

SYSTEM: Reactor Coolant System (RC)

..Section Xl AComp'onent ID ,. Relief 'TechniCal,.•-c. Results

Cat. Item Requests Notes Ex, am

Comments

B-P B15.10 2-RC-1-1 13T-04 VT-2 NRI

9 7/29/2010

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7/29/2010 Exelkn.,Byron Station Unit 2

B2R15 ISI Outage Report

Pressure Test Outage Summary

SYSTEM: Residual Heat Removal System (RH)

Section xIComponent ID. '•.. r " R elief. Technical Actual Results/ Cat. Item . ... ... ,,, :: . . , .. .. . - ;- ]Requests,, ,,Notes - . .Exam I

Ciomments

C-H C7.10 2-RH-2-1 13T-04 VT-2 NRI

C-H C7.10 2-RH-2-2 13T-04 VT-2 NRI

C-H C7.10 2-RH-2-3 13T-04 VT-2 NRI

C-H C7.10 2-RH-2-6 13T-04 VT-2 NRI

10 7/29/2010

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7/29/2010 Exelon.Byron Station Unit 2

B2R15 ISl Outage Report

Pressure Test Outage Summary

SYSTEM: Safety Injection System (SI)

Section XI Component ID,. .. " Reief 'Technical Actual Results.

Cat. Item..qess Notes Exam'

Comments

C-H C7.10 2-SI-2-1 13T-04 VT-2 NRI

C-H C7.10 2-SI-2-2 13T-04 VT-2 NRI

C-H C7.10 2-SI-2-3 13T-04 VT-2 NRI

C-H C7.10 2-SI-2-4 13T-04 VT-2 NRI

C-H C7.10 2-SI-2-5 13T-04 VT-2 NRI

C-H C7.10 2-SI-2-6 13T-04 VT-2 NRI

C-H C7.10 2-SI-2-7 13T-04 VT-2 NRI

11 7/29/2010

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7/29/2010 Exelon.Byron Station Unit 2

B2R15 ISI Outage Report

Pressure Test Outage Summary

SYSTEM: Essential Service Water System (SX)

Section -X C0omlonent ID .' -' Relief 'Technical Actual ResultsCat. Item "equests 'Notes Exam

Com m ents.

C-H C7.10 2-SX-2-1 13T-04 VT-2 NRI

C-H C7.10 2-SX-2-2 13T-04 VT-2 NRI

12 7/29/2010

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7/29/2010 E e~ nByron Station Unit 2

B2R15 ISI Outage Report

Component Support Outage Summary

SYSTEM: Containment Spray System (CS)

Section Xl" Component ID -' i. ne Number' Relief Technical A"ctual•. .Results

Cat. Item IDescription Requests Notes Exam

Comments

F-A F1.20 2CS02AA- 10/2CS03A007S 2CS02AA-10 VT-3 NRISNUBBER- SR

MINOR SURFACE RUST ON REAR BRACKET WELDS AND PIVOT PIN, NO DEGRADATION NOTED

F-A F1.20 2CS06AA-6/2CS06033A 2CS06AA-6 VT-3 NRIANCHOR

No indication detected

1

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7/29/2010 Exelon.Byron Station Unit 2

B2R15 ISl Outage Report

Component Support Outage Summary

SYSTEM: Chemical & Volume Control System (CV)

Section Xl jcomponent ID - o Lihe Number . Relief, Technicai A0U01-:- ResultsCat. Item oDescription Requests, Notes ,- •mComments

F-A F1.20 2CV05CB-6/2CV08007V

VARIABLE

ALL WELDS ARE PAINTED

F-A F1.20 2CV09A-4/2CV01A064X

SEISMIC

WELDS ARE PAINTED

F-A Fl1I0 2CV10DB-3/2CV02009S

SNUBBER

INSULATION REMOVED FOR EXAM

F-A F1.10 2CV45B-2/2CV22007X

SEISMIC

INSULATION REMOVED FOR EXAM

F-A F1.10 2CV45B-2/2CV22008X

SEISMIC

INSULATION REMOVED FOR EXAM

F-A F1.10 2CV45B-2/2CV22010X

SEISMIC

INSULATION REMOVED FOR EXAM

F-A F1.10 2CV45B-2/2CV22011X

SEISMIC

INSULATION REMOVED FOR EXAM

F-A F1.10 2CV45B-2/2CV22016A

ANCHOR

INSULATION REMOVED FOR EXAM

F-A F1.10 2CVA6AA-2/2CV09026S

SNUBBER

INSULATION REMOVED FOR EXAM

F-A F1.10 2CVA7AA-2/2CV25012S

SNUBBER

Insulation removed for exam.

F-A F1.10 2CVB7A-3/2CV06005X

SEISMIC

NONE

2CV05CB-6 VT-3 NRI

2CV09A-4 VT-3 NRI

2CV10DB-3 VT-3 NRISR

2CV45B-2

2CV45B-2

2CV45B-2

2CV45B-2

2CV45B-2

2CVA6AA-2

2CVA7AA-2

2CVB7A-3

VT-3

VT-3

VT-3

VT-3

VT-3

VT-3

NRI

NRI

NRI

NRI

NRI

NRI

SR

SRVT-3

VT-3

NRI

NRI

2

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7/29/2010 Exel in ,Byron Station Unit 2

B2R15 ISl Outage Report

Component Support Outage Summary

SYSTEM: Feedwater System (FW)Section ,XI., , I pm, 6m nent ID Ž,1,:_ •,•,,• ,, ,:,lineNumbe- ,,,,• ,•••.. K:• • .R.,ehe~f4 •,,Techniical: j,•,Actual ,.,, •Results,

Cat. IteM, .ielcrppflonl 7>:-, /iIqet8*oes!:Exrn

Commen s ' --

F-A F1.20 2FW03DA-16/2FW02016S 2FW03DA-16 VT-3 NRISNUBBER SR

F-A F1 .20 2FW03DA-16/2FW02020X 2FW03DA-16 VT-3 NRISEISMIC

NONE

F-A F1.20 2FW03DB- 16/2FW03017S 2FW03DB- 16 VT-3 NRISNUBBER SR

INSULATION REMOVED FOR EXAM

F-A F1 .20 2FW03DD-16/2FW05022S 2FW03DD-16 VT-3 NRISNUBBER SR

F-A F1.20 2FW81AA-6/2AF06038R 2FW81 AA-6 VT-3 NRIRIGID

NONE

F-A F1 .20 2FW81 BA-6/2AF06040V 2FW81 BA-6 VT-3 NRIVARIABLE

F-A F1 .20 2FW87CC-6/2FW08005S 2FW87CC-6 VT-3 NRISNUBBER SR

GRADING REMOVED FOR EXAM

3

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7/29/2010 Exelen.Byron Station Unit 2

B2R15 ISI Outage Report

Component Support Outage Summary

Main Steam System (MS)SYSTEM:

Section X1 Crpanen 'ID ' ' "" -V1 Lirei"Ndmberý ý( ''R~if .Tecnica ,Atl. lRe6ts 'Itcat, lIemf~ bescri~toV n9 RW 'No f xa j

F-A F1.20 2MS07AA-28/2MS01205X 2MS07AA-28 VT-3 NRI

SEISMIC

NONE

F-A F1.20 2MS07AC-28/2MS01 101S 2MS07AC-28 DBL VT-3 NRISNUBBER SR

* S/N# 13772 ($1) 3-7/8" - S/N# 13785 (S2) 3-5/8"

4

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7/29/2010 Exel mn..Byron Station Unit 2

B2R15 ISI Outage Report

Component Support Outage Summary

SYSTEM: Reactor Coolant System (RC)

Section XI ComponentlD" Line Number of!-o Relief Technical Actual ResultsCat. Item IDescription Requests Noes EamComments

F-A F1.10 2RC14AB-2/2CV15016V 2RC14AB-2 VT-3 NRIVARIABLE

F-A Fl.10 2RC14AD-2/2CV25019S 2RC14AD-2 VT-3 NRISNUBBER SR

Insulation removed for exam, snubber was removed for functional testing at time of exam. Pipe clamp and structural steelexamined.Snubber exam performed on report 2010-EPP-025.

F-A F1.10 2RC14AD-2/2CV25020S 2RC14AD-2 VT-3 NRISNUBBER SR

Insulation removed for exam, snubber was removed for functional testing at time of exam. Pipe clamp and structural steel examined.Snubber exam performed on report 201 0-EPP-023.

F-A F1.10 2RC14AD-2/2CV25024S 2RC14AD-2 VT-3 NRISNUBBER SR

Insulation removed for exam, snubber was removed for functional testing at time of exam. Pipe clamp and structural steel examined.Snubber exam performed on report 201 0-EPP-026.

F-A Fl.10 2RC22AA-1.5/2RC16001S 2RC22AA-1-1/2 VT-3 NRISNUBBER SR

INSULATION REMOVED FOR EXAM

5

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7/29/2010. Exelon.,Byron Station Unit 2

B2R15 ISI Outage Report

Component Support Outage Summary

SYSTEM: Residual Heat Removal System (RH)

Sepction XI.', Linee Number _ ; r Relief- Technical Ata0 ResultsCat Iem Description, Reuets Notes Exam

Com ments -

F-A F1.20 2RH01CA-16/2SI06259X 2RH01CA-16 VT-3 NRISEISMIC

No indication detected

6

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7/29/2010 ExeI n.Byron Station Unit 2

B2R15 ISI Outage Report

Component Support Outage Summary

SYSTEM: Reactor Coolant System (RY)

SectionXl , c0PornentD Line Numl*er Reliefi', Technical Actual ResultsIckrto e ., euests Nes Ea

Commentfs

F-A F1.40 2RY-01-S/SKT 2RY-01-S VT-3 NRI

PRESSURIZER SKIRT

F-A F1.10 2RY18A-2/2RY06114S 2RY18A-2 VT-3 NRISNUBBER SR

INSULATION REMOVED FOR EXAM

7

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7/2912010 Exelkn.Byron Station Unit 2

B2R15 ISI Outage Report

Component Support Outage Summary

Safety Injection System (SI)SYSTEM:

Section Xl ComponentlD .Cat. Item IDescription

Lin~e'Nme Rel ief~ , ehicl At'a esultsRque'sts, Notes Ea

Comments

F-A Fl.20 2SI04B-12/2RH02109X

SEISMIC

F-A Fl.20 2SI04B-12/2RHO211OX

SEISMIC

F-A Fl.10 2SI04D-8/2RH02020X

SEISMIC

F-A F1.20 2SI05CA-8/2SI01024X

SEISMIC

F-A Fl.20 2SI05CA-8/2SI01040X

SEISMIC

F-A F1.20 2SI06BA-24/2SI06260X

SEISMIC

No indication detected

2SI04B-l 2

2S10413-12

2SI04D-8

2SI05CA-8

2SI05CA-8

2SI06BA-24

VT-3

VT-3

VT-3

VT-3

VT-3

VT-3

NRI

NRI

NRI

NRI

NRI

NRI

F-A Fl.20 2SI06BA-24/2SI06261X 2SI06BA-24 VT-3 NRISEISMIC

No indication detected

F-A Fl.10 2SI08FA-3/2SI21014X 2SI08FA-3 VT-3 NRISEISMIC

F-A F1.10 2SI08HA-2/2SI25009X 2S108HA-2 VT-3 NRI

SEISMIC

8

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7/29/2010 ExelonIByron Station Unit 2

B2R15 ISI Outage Report

Component Support Outage Summary

SYSTEM: Essential Service Water System (SX)Section X mot 'ID Lne Number Relief 'r TechnicaIk Actual Results-'

A 'D sri~ji on Reques~ts , ots

C men s - ... , .

F-A F1.20 2SX06CA-14/2SX06009X 2SX06CA-14 VT-3 NRI.

SEISMIC

F-A F1.20 2SX06EC-10/2SX06023A 2SX06EC 10 VT-3 NRI

ANCHOR

INSIDE RCFC PLENIUM

F-A F1.20 2SX07EB-14/2SX09015X

SEISMIC2SX07EB- 14 VT-3 NRI

9

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Byron Station Outage B2R15

Snubber Outage Summary(Page 1 of 11)

SYSTEM: Auxiliary Feedwater System (AF)

!§cioin.X,)(. ',2CtnhjpnentID7 Li'~br Relif2' 'TechnicalY i-AtuaIl ResuIlts',

F-A F1.20 2FW87BC-3/2FW10001S 2FW87BC-3 VT-3 NRI

SNUBBER SR FT PASS

Note: Section Xl Category numbers N/A-ed are exempt from IWF-1220 and IWF-2500 tables

1

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.Byron Station Outage B2R15

Snubber Outage Summary(Page 2 of 11)

SYSTEM: Containment Spray System (CS)

Section Xl Component ID Line Number - Relief Technical Actual Results

Cat. Item IDescription Requests Notes Exam

Comments .

F-A F1.20 2CS02AB-1 0/2CS03B01 8S 2CS02AB-10 VT-3 NRISNUBBER SR FT PASS

Note: Section Xl Category numbers N/A-ed are exempt from IWF-1220 and IWF-2500 tables

2

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Byron Station Outage B2R15

Snubber Outage Summary(Page 3 of 11)

SYSTEM: Chemical & Volume Control System (CV)

setin L> C onent~~, Actual~C ~ [It );qk Dscription M Rqet Nt~

NA NA 2CV10B-3/2CV04002S 2CV10B-3 VT-3 NRISNUBBER SR FT PASS

NA NA 2CV10BL3/2CV04012S

SNUBBER

NA NA 2CV10CA-3/2CV22002S

SNUBBER

NA NA 2CV 1 5AC-3/4/2CV29002S

SNUBBER

NA NA 2CVB7BA-3/2CV23005SSNUBBER

2CV 10B-3

2CV 10CA-3

2CV15AC-3/4

2CVB7BA-3

VT-3

SR FT

VT-3

SR FT

NRIPASS

NRIPASS

VT-3 NRISR FT PASS

VT-3SR FT

NRIPASS

Note: Section Xl Category numbers N/A-ed are exempt from IWF-1220 and IWF-2500 tables

3

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Byron Station Outage B2R15

Snubber Outage Summary(Page 4 of 11)

SYSTEM: Feedwater System (FW)

Section Xl Component11) ,D Line Number Relief Technical ýj Actual, Results

S~~at.~ Itm 'ecito ~s otes, E"r xam,ý'

F-A F1.20 2FW03DA-16/2FW02012S 2FW03DA-16 VT-3 NRISNUBBER SR

F-A F1 .20 2FW87CC-6/2FW08005S 2FW87CC-6 VT-3 NRI

SNUBBER SR FT PASS

F-A F1 .20 2FW87CC-6/2FW08006S 2FW87CC-6 VT-3 NRI

SNUBBER SR FT PASS

Note: Section XI Category numbers N/A-ed are exempt from IWF-1220 and IWF-2500 tables

4.

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7/29/2010 Exelein.Byron Station Unit 2

Byron Station Outage B2R15

Snubber Outage Summary(Page 5 of 11)

SYSTEM: Main Steam System (MS)

Section Xl Component ID Line Number Technical Actual ResultsCat. Item Description Requests Notes Exam

Comments .

N/A SNUB 2MS01AC-32.75/2MS07006-S1 2MS01AC-32.75 DBL VT-3 NRISNUBBER SR FT PASS

N/A SNUB 2MS01AC-32.75/2MS07006-S2 2MS01AC-32.75 DBL VT-3 NRISNUBBER SR FT PASS

Note: Section XI Category numbers N/A-ed are exempt from IWF-1 220 and IWF-2500 tables

5

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7/29/2010ExIn

Byron Station Unit 2

Byron Station Outage B2R15

Snubber Outage Summary(Page 6 of 11)

SYSTEM: Reactor Coolant System (RC)

a c Item X C escrpb oiD~n' Requ•sts N-. . . . . . ... ot"-": "...........

rnmnts.

F-A F1.40 2RC01BA-2A/2RC01BA-A

SNUBBER

F-A F1.40 2RC01BA-2A/2RC01BA-B

SNUBBER

F-A F1.40 2RC01BB-2B/2RC01BB-A

SNUBBER

F-A F1.40 2RC01BB-2B/2RC01BB-B

SNUBBER

F-A F1.40 2RC01BC-2C/2RC01BC-ASNUBBER

SNUBBER

F-A F1.40 2RC01BC-2C/2RC01BC-B

SNUBBER

SNUBBER

F-A F1.40 2RC01BD-2D/2RC01BD-A

SNUBBER

F-A F1.40 2RC01BD-2D/2RCO1BD-B

SNUBBER

NA NA 2RC08AA-3/4/2RC1 6009SSNUBBER

F-A F1.10 2RC13AB-2/2CV15002S

SNUBBER

F-A F1.10 2RC14AD-2/2CV25019SSNUBBER

F-A F1.10 2RC14AD-2/2CV25020S

SNUBBER

F-A F1.10 2RC14AD-2/2CV25024SSNUBBER

F-A F1.10 2RC22AA-1.5/2RC16011SSNUBBER

F-A F1.10 2RC22AB-1.5/2RC17015SSNUBBER

2RC01 BA-2A

2RC01BA-2A

2RC01 BB-2B

2RC01 BB-2B

2RC01 BC-2C

2RC01 BC-2C

VT-3 NRISR

2RC01 BD-2D

2RC01BD-2D

2RC08AA-3/4

2RC13AB-2

2RC14AD-2

2RC14AD-2

2RC14AD-2

2RC22AA-1-1/2

2RC22AB-1-1/2

VT-3

SR

VT-3

SR FT

VT-3

SR

VT-3SR

FT

VT-3

SR

FT

VT-3

SR

VT-3

SR

VT-3SR FT

VT-3

SR FT

VT-3

SR FT

VT-3

SR FT

VT-3

SR FT

VT-3

SR FT

VT-3SR FT

NRI

NRI

PASS

NRI.

NRI

FAIL

NRI

PASS

NRI

NRI

NRIPASS

NRI

PASS

NRI

PASS

NRI"

PASS

NRIPASS

NRIPASS

NRIPASS

Note: Section XI Category numbers N/A-ed are exempt from IWF-1220 and IWF-2500 tables

6

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Byron Station Outage B2R15

Snubber Outage Summary(Page 7 of 11)

SYSTEM: Reactor Coolant System (RC)

Section XI Component ID Line Number - . Relief Technical Actual Results

Cat. Item Description - Requests,. Notes Exam

Comments ' .

NA NA 2RC48BB-1/2/2RC90B008S 2RC48BB-1/2 VT-3 NRISNUBBER SR FT PASS

Note: Section XI Category numbers N/A-ed are exempt from IWF-1220 and IWF-2500 tables

7

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Byron Station Outage B2R15

Snubber Outage Summary(Page 8 of 11)

SYSTEM: Residual Heat Removal System (RH)

Section XI lComponent ID Line Number . Relief Technical Actual, I-Results

Cat. Item Description Notequesis "ores', ýxam-

Comments

F-A F1.20 2RH02AA-8/2RH07003S 2RH02AA-8 VT-3 NRI

SNUBBER SR FT PASS

F-A F1.20 2RH02AA-8/2RH07012S 2RH02AA-8 VT-3 NRI

SNUBBER SR FT PASS

NA NA 2RH26AA-3/4/2RH02121S

SNUBBER

2RH26AA-3/4 VT-3 NRISR FT PASS

Note: Section X1 Category numbers N/A-ed are exempt from IWF-1220 and IWF-2500 tables

8

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Byron Station Outage B2R15

Snubber Outage Summary(Page'9 of 11)

SYSTEM: Reactor Coolant System (RY)

Section Xl Component ID Line Number Relief Technical :Actual ResultsCat. Item IDescription 4rr : Requests Notes Exar . .

CornmentsAl

N/A SNUB 2RY01B-6/2RY06025-S1 2RY01B-6 DBL VT-3 NRI

SNUBBER SR FT PASS

N/A SNUB 2RY01 B-6/2RY06025-S2 2RY01 B-6 DBL VT-3 NRI

SNUBBER SR FT PASS

F-A F1.10 2RY02B-3/2RY09077S 2RY02B-3 VT-3 NRI

SNUBBER SR FT PASS

NA NA 2RY34AB-1/2/2RC92002S 2RY34AB-1/2 VT-3 NRI

SNUBBER SR FT PASS

Note: Section XI Category numbers N/A-ed are exempt from IWF-1220 and IWF-2500 tables

9

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Byron Station Outage B2R15

Snubber Outage Summary(Page 10 of 11)

SYSTEM: Steam Generator Blowdown System (SD)

Section XI Component ID Line Number Relief Technicald Actual Results

Cat. Item IDescription Requests Notes Exam

Comments, ' ;

NA NA 2SD01CB-2/2SD01005S 2SD01CB-2 VT-3 NRI

SNUBBER SR FT PASS

Note: Section Xl Category numbers N/A-ed are exempt from IWF-1220 and IWF-2500 tables

10

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Byron Station Outage B2R15

Snubber Outage Summary(Page 11 of 11)

SYSTEM: Safety Inhection System (SI)

Section X I Component ID Line Number Technical Actual Results

Cat. Item IDescription Requests Notes Exam,

Comments

N/A SNUB 2SI05DC-6/2SI09014-S1 2SI05DC-6 DBL VT-3 NRI

SNUBBER SR FT PASS

N/A SNUB 2SI05DC-6/2SI09014-$2 2S105DC-6 DBL VT-3 NRI

SNUBBER SR FT PASS

Note: Section XI Category numbers N/A-ed are exempt from IWF-1220 and IWF-2500 tables

11

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SECTION 3.0

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(This report is used to verify that the periodic BYRON STATION UNIT 2 - 3RD INTERVAL ASME SECTION XI (The percentage requirements of Tables IWx-requirements of Tables IWx-2412-1 will be met by EXAMINATION STATUS REPORT 2412-1 apply to the Category and werethe interval schedule.) applied to each Item only when practical.)

# of Total # Exams Completed % Exams CompletedItem No. Comp Selected Mi Per 1 Max Min Per 2 Max Per 3 % Selected Period 1 Period 2 Period 3

Category B-A Non-Deferred ExamsB1.30 1 1 0 1 1 1 0 1 0 100.00% 100.00% 100.00% 100.00%B1.40 1 1 0 0 1 1 0 1 0 100.00% 0.00% 0.00% 0.00%Totals: 2 2 0 1 1 1 0 1 0 100.00% 50.00% 50.00% 50.00%

Category B-A Deferred Exams-B1.11 3 3 N/A 3 N/A N/A 0 N/A 0 100.00% 100.00% 100.00% 100.00%B1.21 2 2 N/A 1 N/A N/A 0 N/A 0 100.00% 50.00% 50.00% 50.00%Totals: 5 5 N/A 4 N/A N/A 0 N/A 0 100.00% 80.00% 80.00% 80.00%

1. (B1.11 & B1.21) Examination completion exceeds 50.00% for 1 st Period and 75.00% for this 2 nd Period. The examinations were performed at the beginning ofthe Inspection Interval as allowed by Relief Request 13R-01.

Category B-B Non-Deferred ExamsB2.11 2 2 0 0 1 1 1 1 0 100.00% 0.00% 50.00% 50.00%B2.12 2 2 0 0 1 1 1 1 0 100.00% 0.00% 50.00% 50.00%B2.40 4 1 0 1 1 1 0 1 0 25.00% 100.00% 100.00% 100.00%Totals: 8 5 1 1 2 2 2 2 0 62.50% 20.00% 65.00% 65.00%

1. (B2.40) Per Examination Category'B-B, Note 1, examinations may be limited to one vessel among a group of vessels performing a similar function.

Category B-D Non-Deferred ExamsB3.110 6 6 1 1 3 2 3 3 0 100.00% 16.67% 66.67% 66.67%B3.120 6 6 1 1 3 2 4 3 0 100.00% 16.67% 66.67% 66.67%B3.140 8 8 .2 4 4 0 0 2 0 100.00% 50.00% 50.00% 50.00%Totals: 20 20 4 6 10 4 7 9 0 100.00% 30.00% 65.00% 65.00%1. (B3.120 & B3.140) Per 10 CFR 50.55a(b)(2)(xxi)(A), Table IWB-2500-1 examination requirements, the provisions of Table IWB-2500-1, Examination Category

B-D, Item Numbers B3.120 and B3.140 in the 1998 Edition must be applied when using the 1999 Addenda through the latest edition and addenda.

Category B-D Deferred ExamsB3.90 8 8B3.100 8 8.

Totals: 16 16

N/A 8N/A 8

N/AN/A

N/A 0N/A 0

N/AN/A

00

100.00%100.00%

100.00%100.00%

100.00%100.00%

100.00%100.00%

N/A 16 N/A N/A 0 N/A 0 100.00% 100.00% 100.00% 100.00%

1. (B3.100) This Item Number requires a visual examination with enhanced magnification in lieu of volumetric examination, as allowed by Code Case N-648-1.

Section 3.0 Page 1 of 7

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(This report is used to verify that the periodic BYRON STATION UNIT 2 - 3RD INTERVAL ASME SECTION X1requirements of Tables IWx-2412-1 will be met by EXAMINATION STATUS REPORTthe interval schedule.)

# of Total # Exams CompletedItem No. Comp Selected Mi Per 1 Max Min Per 2 Max Per 3 %

(The percentage requirements of Tables JWx-2412-1 apply to the Category and wereapplied to each Item only when practical.)

I % Exams Completed

S elected Period 1 Period 2 Period 3

2. (B3.90 & B3.100) Per Examination Category B-D, Note 5, for PWR's in the second and successive inspection intervals, these examinations may be deferred tothe end of the interval provided no repair/replacement activities have been performed on the examination item, and no flaws or relevant conditions requiringsuccessive inspections in accordance with IWB-2420(b) are contained in the examination item.

3. (B3.90 & B3.100) Examination completion exceeds 50.00% for 1st Period and 75.00% for this 2 nd Period. The examination were performed at the beginning ofthe Inspection Interval as allowed by Relief Request 13R-01.

Category B-G-1 Deferred ExamsB6.10 3 3 N/A 3 N/A N/A 0 N/A 0 100.00% 100.00% 100.00% 100.00%B6.20 3 3 N/A 3 N/A N/A 0 N/A 0 100.00% 100.00% 100.00% 100.00%B6.40 1 1 N/A 0 N/A N/A 0 N/A 0 100.00% 0.00% 0.00% 0.00%B6.50 3 3 N/A 0 N/A N/A 0 N/A 0 100.00% 0.00% 0.00% 0.00%B6.170 1 1 N/A 0 N/A N/A 0 N/A 0 100.00% 0.00% 0.00% 0.00%B6.180 4 1 N/A 0 N/A N/A 0 N/A 0 25.00% 0.00% 0.00% 0.00%B6.190 4 0 N/A 0 N/A N/A 0 N/A 0 0.00% 0.00% 0.00% 0.00%B6.210 8 2 N/A 0 N/A N/A 0 N/A 0 25.00% 0.00% 0.00% 0.00%B6.220 8 0 N/A 0 N/A N/A 0 N/A 0 0.00% 0.00% 0.00% 0.00%B6.230 8 0 N/A 0 N/A N/A 0 N/A 0 0.00% 0.00% 0.00% 0.00%Totals: 43 14 N/A 6 N/A N/A 0 N/A 0 32.56% 42.86% '42.86% 42.86%

1. (B6.10 & B6.20 & B6.50) Single components representing one third of the 54 Reactor Vessel Closure Head Nuts, Closure Studs, and Closure Washers,Bushings. The examinations were performedat the beginning of the Inspection Interval as allowed by Relief Request 13R-01.

2. (B6.40) A single component representing all of the 54 Reactor Vessel Threads in Flange to be examined.3. (B6.170) A single component represents the five sets of CETC column nuts.4. (B6.180) Four components are tracked in the database, each representing one of the 24 Bolts on one of the four Reactor Coolant Pumps (96 total) as reported

in the ISI Program Plan. The volumetric examination of these components is limited to only one of the pumps per Examination Category B-G-1, Note 3 andExamination Category B-L-2, Note 1. Examination is required only once per inspection interval.

5. (B6.190) Four components are tracked in the database, each representing all 24 associated Flange Surfaces and Nuts, Bushings, and Washers for one of thefour Reactor Coolant Pumps (96 total) as reported in the ISI Program Plan. The visual examination of these components is limited to only one of the pumpsper Examination Category B-G-1, Note 3 and Examination Category B-L-2, Note 1. Also, per Examination Category B-G-1, Note 4 and Examination CategoryB-L-2, Note 2, examination is required only when a pump is disassembled for maintenance, repair, or volumetric examination or bolting is removed.Examination is required only once per inspection interval.

6. (B6.210) Eight components are tracked in the database, each representing all of the Bolts and associated Nuts, Bushings, and Washers and Flange Surfaceson one of the eight Reactor Coolant Valves as reported in the ISI Program Plan. The volumetric examination of these components is limited to only one of thevalves per Examination Category B-G-1, Note 3 and Examination Category B-M-2, Note 3. Examination is required only once per inspection interval.

Section 3.0 Page 2 of 7

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(This report is used to verify that the periodic BYRON STATION UNIT 2 - 3RD INTERVAL ASME SECTION XI (The percentage requirements of Tables lWx-requirements of Tables IWx-2412-1 will be met by EXAMINATION STATUS REPORT 2412-1 apply to the Category and werethe interval schedule.) I applied to each Item only when practical.)

# of Total # Exams Completed % Exams CompletedItem No. Comp Selected Mi Per I Max Min Per 2 Max Per 3 % Selected Period 1 Period 2 Period 3

7. (B6.220 & B6.230) Eight components are tracked in the database, each representing all of the Bolts and associated Nuts, Bushings, and Washers and FlangeSurfaces on one of the eight Reactor Coolant Valves as reported in the ISI Program Plan. The visual examination of these components is limited to only one ofthe valves per Examination Category B-G-1, Note 3 and Examination Category B-M-2, Note 3. Also, per Examination Category B-G-1, Note 4 and ExaminationCategory B-M-2, Note 2, examination is required only when a valve is disassembled for maintenance, repair, or volumetric examination or bolting is removed.Examination is required only once per inspection interval.

Category B-G-2 Deferred ExamsB7.10 2 1 N/A 0 N/A N/A 0 N/A 0 50.00% 0.00% 0.00% 0.00%B7.20 1 0 N/A. 0 N/A N/A 0 N/A 0 0.00% 0.00% 0.00% 0.00%B7.30 4 4 N/A 2 N/A N/A 0 N/A 0 100.00% 50.00% 50.00% 50.00%B7.50 20 5 N/A 3 N/A N/A 1 N/A 0 25.00% 60.00% 80.00% 80.00%B7.60 4 0 N/A 0 N/A N/A 0 N/A 0 0.00% 0.00% 0.00% 0.00%B7.70 26 1 N/A 1 N/A N/A 0 N/A 0 3.85% 100.00% 100.00% 100.00%Totals: 57 11 N/A 6 N/A N/A 1 N/A 0 19.30% 54.55% 63.64% 63.64%

1. (B7.10) Two components representing the CETC and RVLIS Clamp Bolts and associated Nuts as reported in the ISI Program Plan.2. (B7.20) A single component representing all 16 Pressurizer Manway Bolts and associated Nuts as reported in the ISI Program Plan.3. (B7.30) Four components are tracked in the database, each representing all 32 Bolts and associated Nuts for both Manways on each of the four Steam

Generator (128 total) as reported in the ISI Program Plan.4. (B7.50) Per Examination Category B-G-2, Note 3, examination is required only when a bolted connection is disassembled or bolting is removed. Also, per

Examination Category B-G-2, Note 3, examinations are limited to at least one bolted connection within each group of bolted connections that are similar indesign, size, function, and service. Examination is required only once per inspection interval within each bolted connection group.

5. (B7.60) Four components are tracked in the database, each representing all 36 Bolts and associated Nuts for one of the four Reactor Coolant Pumps (144total) as reported in the ISI Program Plan. Per Examination Category B-G-2, Note 2 and Examination Category B-L-2, Note 2, examination is required onlywhen a pump is disassembled for maintenance, repair, or volumetric examination or bolting is removed. Also, per Examination Category B-G-2, Note 2 andExamination Category B-L-2, Note 1, examinations are limited to at least one pump within each group of pump that are of the same size, design, manufacturingmethod, and function. Examination is required only once per inspection interval within each valve group.

6. (B7.70) Per Examination Category B-G-2, Note 2 and Examination Category B-M-2, Note 2, examination is required only when a valve is disassembled formaintenance, repair, or volumetric examination or bolting is removed. Also, per Examination Category B-G-2, Note 2 and Examination Category B-M-2, Note 3,examinations are limited to at least one valve within each group of valves that are of the same size, design, manufacturing method, and function. Examinationis required only once per inspection interval within each valve group.

Section 3.0 Page 3 of 7

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(This report is used to verify that the periodic BYRON STATION UNIT 2 - 3RD INTERVAL ASME SECTION Xl (The percentage requirements of Tables IWx-.requirements of Tables IWx-2412-1 will be met by EXAMINATION STATUS REPORT 2412-1 apply to the Category and werethe interval schedule.) I ........... .. ... ... .. applied to each Item only when practical.)

#of Total # Exams Comrleted % Exams CorpletedItem No. Comp Selected Min Per 1 Max Min Per 2 Max Per 3 % Selected Period 1 Period 2 Period 3

Category B-K Non-Deferred ExamsB10.10 2 2 0 0 1 1 0 1 0 100.00% 0.00% 00.00% 0.00%B10.20 8 3 1 1 1 1 1 1 0 37.50% 33.33% 66.67% 66.67%Totals: 10 5 1 1 2 2 1 2 0 50.00% 20.00% 40.00% 40.00%1. (B10.10) Per Examination Category B-K, Note 4, for multiple vessels of similar design, function and service, only one welded attachment of only one of the

multiple vessels shall be selected for examination. Conservatively, a welded attachment of each type of welded attachment of one of multiple vessels will beexamined.

2. (B10.20) Per Examination Category B-K, Note 5, for piping, pumps, and valves, a sample of 10% of the welded attachments associated with the componentsupports selected for examination under IWF-2510 shall be examined. This requirement is conservatively interpreted to mean that 10% of the total

Category B-L-2 Deferred ExamsB12.20 4 0 N/A

N/A00

N/AN/A

N/A 0 N/AN/A 0 N/A

0 0.00%0.00%

0.00% 0.00% 0.00%0.00% 0.00% 0.00%Totals: 4 0 0

1. (B12.20) The examination of pump casings is limited to only one of the pumps performing similar functions in the system per Examination Category B-L-2, Note1. Also, per Examination Category B-L-2, Note 2, examination is required only when a pump is disassembled for maintenance, repair, or volumetricexamination. Examination is required only once per inspection interval.

Category B-M-2 Deferred ExamsB12.50 37 2 N/A 2 N/A N/A 0 N/A 0 5.41% 100.00% 100.00% 100.00%Totals: 37 2 N/A 2 N/A N/A 0 N/A 0 5.41% 100.00% 100.00% 100.00%1. (B12.50) Per Examination Category B-M-2, Note 2, examination is required only when a valve is disassembled for maintenance, repair, or volumetric

examination. Also, per Examination Category B-M-2, Note 3, examinations are limited to at least one valve within each group of valves that are of the samesize, design, manufacturing method, and function. Examination is required only once per inspection interval within each valve group.

Category B-N-1 Non-Deferred ExamsB13.10 2 1 0 1 1 1 0 50.00% 100.00% 200.00%

50.00% 100.00% 200.00%200.00%200.00%Totals: 2 1 0 1 1 1 1 1 0

1. (B13.10) "% Completed" exceeds 100% since the vessel interior is selected for examination once each period (three times during the interval).

Section 3.0 Page 4 of 7

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I(This report is used to verify that the periodicrequirements of Tables IWx-2412-1 will be met by

BYRON STATION UNIT 2 - 3RD INTERVAL ASME SECTION XI (The percentage requirements of Tables IWx-

EXAMINATION STATUS REPORT 2412-1 apply to the Category and werethe interval schedule.) -. . . . . . . . I applied to each Item only when practical.)

# of Total # Exams Completed % Exams CompletedItem No. Comp Selected Min Per 1 Max Min Per 2 Max Per 3 % Selected Period 1 Period 2 Period 3

Category B-N-2 Deferred ExamsB13.50 1 1 N/A 1 N/A N/A 0 N/A 0 100.00% 100.00% 100.00% 100.00%B13.60 1 1 N/A 1 N/A N/A 0 N/A 0 100.00% 100.00% 100.00% 100.00%Totals: 2 2 N/A 2 N/A N/A 0 N/A 0 100.00% 100.00% 100.00% 100.00%

1. (B13.50 & B13.60) Examination completion exceeds 50.00% for 1st Period and 75.00% for this 2nd Period. The examination were performed at the beginning ofthe Inspection Interval as allowed by Relief Request 13R-01.

Category B-N-3 Deferred ExamsB13.70 1 1 N/A 1 N/A N/A 0 N/A 0 100.00% 100.00% 100.00% 100.00%Totals: 1 1 N/A 1 N/A N/A 0 N/A 0 100.00% 100.00% 100.00% 100.00%1. (B133.70) Examination completion exceeds 50.00% for 1 st Period and 75.00% for this 2 nd Period. The examination were performed at the beginning of the

Inspection Interval as allowed by Relief Request 13R-01.

Category B-O Deferred ExamsB14.10 5 5 N/A 2 N/A N/A 0 N/A 0 100.00% 40.00% 40.00% 40.00%Totals: 5 5 N/A 2 N/A N/A 0 N/A 0 100.00% 40.00% 40.00% 40.00%

1. (B134.10) 10% of the 45 CRD Housings (as reported in the ISI Program Plan) are required to be examined each interval per this Item Number. These 5components represent that 10% population.

Category B-P Non-Deferred ExamsB15.10 1 1 N/A 2 N/A N/A 1 N/A 0 100.00% 200.00% 300.00% 0.00%Totals: 1 1 N/A 2 N/A N/A 1 N/A 0 100.00% 200.00% 300.00% 0.00%1. (B135.10) "% Completed" exceeds 100% since Class 1 pressure tests are performed each refueling outage.2. (B15.10) One component representing the five systems in Class 1 as reported in the ISI Program Plan.

Category C-A Non-Deferred ExamsC1.10 14 3 1 1 1 1 0 1 0 21.43% 33.33% 33.33% 33.33%C1.20 6 1 0 0 1 1 0 1 0 16.67% 0.00% 0.00% 0.00%C1.30 4 1 0 1 1 1 0 1 0 25.00% 100.00% 100.00% 100.00%Totals: 24 5 1 2 2 1 0 1 0 20.83% 40.00% 40.00% 40.00%

1. (C1.104& C1.20) Per Examination Category C-A, Note 3, in the case of multiple vessels of similar design, size, and service, the required examinations may belimited to one vessel or distributed among the vessels.

Section 3.0 Page 5 of 7

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(This report is used to verify that the periodicrequirements of Tables (Wx-2412-1 will be met by

BYRON STATION UNIT 2 - 3RD INTERVAL ASME SECTION XIEXAMINATION STATUS REPORT

(The percentage requirements of Tables IWx-2412-1 apply to the Category and were

the interval schedule.) ..... .. . . . . . . . . I applied to each Item only when practical.)# of T Total # Exams Completed % Exams Completed

Item No. Comp Selected Mi Per 1 Max Min Per 2 Max Per 3 % Selected Period 1 Period 2 Period 3

Category C-B Non-Deferred ExamsC2.21 16 3 1 1 1 1 0 1 0 18.75% 33.33% 33.33% 33.33%C2.22 4 1 0 1 1 1 0 1 0 25.00% 100.00% 100.00% 100.00%Totals: 20 4 1 2 2 0 0 1 0 33.33% 50.00% 50.00% 50.00%

1. (C2.21 & C2.22) Per Examination Category C-B, Note 4, in the case of multiple vessels of similar design, size, and service, the required examinations may belimited to one vessel or distributed among the vessels.

2. (C2.21) Two welds per item for the Residual Heat Removal Heat Exchanger are exempted from examination with the adoption of ASME Code Case N-706 (ref:13T-08). The remaining welds in the items are for the four steam generators and are selected for examination under #1 above.

Category C-C Non-Deferred ExamsC3.10 2 1C3.20 76 8C3.30 20 2

02

0 11 4

1 03 31 0

151

000

50.00%10.53%10.00%

0.00% 0.00%12.50% 50.00%50.00% 50.00%18.18% 45.45%

0.00%50.00%50.00%45.45%

0 1 1Totals: 98 11 2 2 5 4 3 6 0 11.22%

1. (C3.10) Per Examination Category C-C, Note 4, for multiple vessels of similar design, function, and service, only one welded attachment of only one of themultiple vessels shall be selected for examination. Conservatively, a welded attachment of each type of welded attachment of one of multiple vessels will beexamined.

2. (C3.20 & C3.30) Per Examination Category C-C, Note 5, for piping, pumps, and valves, a sample of 10% of the welded attachments associated with thecomponent supports selected for examination under IWF-2510 shall be examined. This requirement is conservatively interpreted to mean that 10% of the totalClass 2 welded attachments shall be examined. The interpretation is consistent with the previous NRC condition on the use of Code Case N-509.

Category C-H Non-Deferred ExamsC7.10 49 49 N/A 49 N/A N/A 12 N/A 0 100.00% 100.00% 124.49%

100.00% 124.49%0.00%0.00%Totals: 49 49 N/A 49 WA N/A 12 N/A 0 100.00%

1. (C7.10) "% Completed" exceeds 100% since Class 2 pressure tests are performed each inspection period.2. (C7.10) Forty-nine components representing the twenty-nine systems/ in Class 2 as reported in the ISI Program Plan.

Section 3.0 Page 6 of 7

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(This report is used to verify that the periodicrequirements of Tables IWx-2412-1 will be met by

BYRON STATION UNIT 2 - 3RD INTERVAL ASME SECTIOEXAMINATION STATUS REPORT

N Xl (The percentage requirements of Tables lWx-2412-1 apply to the Category and were

tne interval scnedule.) . applied to each Item only wnen practical.)# of Total # Exams Com pleted % Exams Comnleted

Item No. I Comp Selected Min Per 1 Max Min Per 2 Max Per 3 % Selected Period 1 Period 2 Period 3

Category F-A Non-Deferred ExamsF1.10 467 120 20 31 60 29 18 59 0 25.70% 25.83% 40.83% 40.83%F1.20 659 109 18 25 54 30 23 56 0 16.54% 22.94% 44.04% 44.04%F1.30 370 41 7 9 20 12 9 21 0 11.08% 21.95% 43.90% 43.90%F1.40 70 32 6 6 16 10 1 18 0 45.71% 18.75% 21.88% 21.88%Totals: 1566 302 49 71 151 80 51 155 0 19.28% 23.51% 40.40% 40.40%

1. (F1.40) Per Examination Category F-A, Note 3, for multiple components other than piping within a system of similar design, function, and service, the supportsof only one of the multiple components are required to be examined.

2. (F1l.30 & F1.40) Class 3 components included in table. IWF-2410 completion percentage applies to entire Examination Category.

Category R-A Non-Socket Welds1 242 612 130 394 1364 1405 71 9

107

232

2320367

3019704

8 60 5

34 2-2 039 13

22969-1

100

00000

25.21%30.00%10.26%12.68%13.78%

37.70%51.28%25.71%77.78%34.54%

47.54%64.10%27.14%77.78%39.76%

47.54%64.10%27.14%77.78%39.76%Totals: 1807 249 40 86 124

1. (BER Welds) The # of Comp and # Selected include all BER welds which have been integrated into the RISI Program and are selected in accordance with theRisk Informed BER methodology.

Category R-A Socket Welds2 84 264 172 215 334 32

N/A 52N/A 42N/A 64

N/AN/AN/A

N/A 26N/A 21N/A 32

N/AN/AN/A

000

30.95%12.21%9.58%

200.00% 300.00%200.00% 300.00%200.00% 300.00%200.00% 300.00%

300.00%300.00%300.00%300.00%Totals: 590 79 N/A 158 N/A N/A 79 N/A 0 13.39%

1. Socket welds for Examination Category R-A piping structural elements are listed separately from butt welds because socket welds are selected for examinationin "each" refueling outage. Including socket welds in the # of Comp, Total Selected, and # Selected fields with the butt welds would misrepresent the %completed distributions for the remainder of the Examination Category. The "% Completed" exceeds 100% since they are examined each outage per ASMECode Case N-578-1, Table 1, footnote 12.

Section 3.0 Page 7 of 7

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SECTION 4.0

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7/29/2010 Exelon.Byron Station Unit 2

B2R15 ISI Outage Report

FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONSAs Required by the Provisions of the ASME Code Rules

(Page 1 of 53)

1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555(Name and Address of Owner)

2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010(Name and Address of Plant)

3. Plant Unit: 2 4. Owner Certificate Of Authorization (if required): N/A

5. Commercial Service Date: 08/22/87 6. National Board Number for Unit: N-200

7. Components Inspected: Auxiliary Feedwater System (AF)

Comp ponent or Manufacturer ManufacturerAppurtenance or Installer Serial No. Province No. Board No.

2-AF-2-1 Hunter Corporation N/A N/A N/A

2-AF-2-2 Hunter Corporation N/A N/A N/A

Note (1): Baseline Examination

Note (2): Snubber examined as a Component Support

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) informationin items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded atthe top of this form.

Computer Generated Form

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7/29/2010 Exel6n.Byron Station Unit 2

B2R15 ISI Outage Report

FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONSAs Required by the Provisions of the ASME Code Rules

(Page 2 of 53)

1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555(Name and Address of Owner)

2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010(Name and Address of Plant)

3. Plant Unit: 2 4. Owner Certificate Of Authorization (if required): N/A

5. Commercial Service Date: 08/22/87 6. National Board Number for Unit: N-200

7. Components Inspected: Auxiliary Feedwater System (AF)

Component or Manufacturer Manufacturer State or NationalAppurtenance or Installer Serial No. Province No. Board No.

2FW87BC- Pacific Scientific 12034 NA NA3/2FW10001S

Note (1): Baseline ExaminationNote (2): Snubber examined as a Component Support

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) informationin items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded atthe top of this form.

Computer Generated Form

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7/29/2010 Exelon.Byron Station Unit 2

B2R15 ISI Outage Report

FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONSAs Required by the Provisions of the ASME Code Rules

(Page 3 of 53)

1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555(Name and Address of Owner)

2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010(Name and Address of Plant)

3. Plant Unit: 2 4. Owner Certificate Of Authorization (if required): N/A

5. Commercial Service Date: 08/22/87 6. National Board Number for Unit: N-200

7. Components Inspected: Containment Spray System (CS)

Component or Manufacturer Manufacturer State or NationalAppurtenance or Installer Serial No. Province No. Board No.

2-CS-2-1 Hunter Corporation N/A N/A N/A

2-CS-2-2 Hunter Corporation N/A N/A N/A

Note (1): Baseline ExaminationNote (2): Snubber examined as a Component Support

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) informationin items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded atthe top of this form.

Computer Generated Form

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7/29/2010 Exelon.Byron Station Unit 2

B2R15 ISI Outage Report

FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONSAs Required by the Provisions of the ASME Code Rules

(Page 4 of 53)

1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555(Name and Address of Owner)

2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010(Name and Address of Plant)

3. Plant Unit: 2 4. Owner Certificate Of Authorization (if required): N/A

5. Commercial Service Date: 08/22/87 6. National Board Number for Unit: N-200

7. Components Inspected: Containment Spray System (CS)

Component or Manufacturer Manufacturer State or NationalAppurtenance or Installer Serial No. Province No. Board No.

2CS06AA- HUNTER N/A NA NA6/2CS06033A

Note (1): Baseline Examination

Note (2): Snubber examined as a Component Support

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) informationin items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded atthe top of this form.

Compter Generated Form

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7/29/2010 Exelkn.Byron Station Unit 2

B2R15 ISI Outage Report

FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONSAs Required by the Provisions of the ASME Code Rules

(Page 5 of 53)

1.

2.

3.

5.

7.

Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555(Name and Address of Owner)

Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010(Name and Address of Plant)

Plant Unit: 2 4. Owner Certificate Of Authorization (if required): N/A

Commercial Service Date: 08/22/87 6. National Board Number for Unit: N-200

Components Inspected: Containment Spray System (CS)

ManufacturerComponent or Manufacturer or Installer State or NationalAppurtenance or Installer Serial No. Province No. Board No.

2CS02AA- Pacific Scientific 16636 NA NA10/2CS03A007S

2CS02AB- Pacific Scientific 9178 NA NA10/2CS03B01 8S

2

Note (1): Baseline Examination

Note (2): Snubber examined as a Component Support

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) informationin items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded atthe top of this form.

Computer Generated Form

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7/29/2010 Exelon.Byron Station Unit 2

B2R15 ISI Outage Report

FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONSAs Required by the Provisions of the ASME Code Rules

(Page 6 of 53)

1.

2.

3.

5.

7.

Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555(Name and Address of Owner)

Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010(Name and Address of Plant)

Plant Unit: 2 4. Owner Certificate Of Authorization (if required): N/A

Commercial Service Date: 08/22/87 6. National Board Number for Unit: N-200

Components Inspected: Chemical & Volume Control System (CV)

Component or Manufacturer Manufacturer State or NationalAppurtenance or Installer or Installer Province No. Board No.

Serial No.2-CV-2-1 Hunter Corporation N/A N/A N/A

2-CV-2-1 0 Hunter Corporation N/A N/A N/A

2-CV-2-2 Hunter Corporation N/A N/A N/A

2-CV-2-3 Hunter Corporation N/A N/A N/A

2-CV-2-4 Hunter Corporation N/A N/A N/A

2-CV-2-5 Hunter Corporation N/A N/A N/A

,2-CV-2-6 Hunter Corporation N/A N/A N/A

2-CV-2-7 Hunter Corporation N/A N/A N/A

Note (1): Baseline Examination

Note (2): Snubber examined as a Component Support

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) informationin items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded atthe top of this form.

Computer Generated Form

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7/29/2010 Exelkn.Byron Station Unit 2

B2R15 ISl Outage Report

FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONSAs Required by the Provisions of the ASME Code Rules

(Page 7 of 53)

1.

2.

3.

5.

7.

Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555(Name and Address of Owner)

Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010(Name and Address of Plant)

Plant Unit: 2 4. Owner Certificate Of Authorization (if required): N/A

Commercial Service Date: 08/22/87 6. National Board Number for Unit: N-200

Components Inspected: Chemical & Volume Control System (CV)

Component or Manufacturer Manufacturer State or NationalAppurtenance or Installer Serial No. Province No. Board No.

2CV05CB- HUNTER N/A NA NA6/2CV08007V

2CV09A- HUNTER N/A NA NA4/2CV01AO64X

2CV45B-2/2CV22007X HUNTER N/A NA NA

2CV45B-2/2CV22008X HUNTER N/A NA NA

2CV45B-2/2CV2201 OX HUNTER N/A NA NA

2CV45B-2/2CV2201 1X HUNTER N/A NA NA

2CV45B-2/2CV22016A HUNTER N/A NA NA

2CVB7A-3/2CV06005X HUNTER N/A NA NA

Note (1): Baseline ExaminationNote (2): Snubber examined as a Component Support

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) informationin items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded atthe top of this form.

Computer Generated Form

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7/29/2010 Exelkn.Byron Station Unit 2

B2R15 ISI Outage Report

FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONSAs Required by the Provisions of the ASME Code Rules

(Page 8 of 53)

1.

2.

3.

5.

7.

Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555(Name and Address of Owner)

Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010(Name and Address of Plant)

Plant Unit: 2 4. Owner Certificate Of Authorization (if required): N/A

Commercial Service Date: 08/22/87 6. National Board Number for Unit: N-200

Components Inspected: Chemical & Volume Control System (CV)

Component or Manufacturer Manufacturer State or Nationalor InstallerSttorNinaAppurtenance or Installer Serial No. Province No. Board No.

2CVA3B-2/W-70 Hunter Corp. 2-CV-1-N5 NA NA

2CVA3B-2/W-71 Hunter Corp. 2-CV-1-N5 NA NA

2CVA3B-2/W-72 Hunter Corp. 2-CV-1-N5 NA NA

2CVA3B-2/W-73 Hunter Corp. 2-CV-1-N5 NA NA

2CVA3B-2/W-80 Hunter Corp. 2-CV-1-N5 NA NA

2CVA3B-2/W-81 Hunter Corp. 2-CV-1-N5 NA NA

2CVA5AA-2/W-06 Hunter Corp. 2-CV-1-N5 NA NA

2CVA5AA-2/W-07 Hunter Corp. 2-CV-1-N5 NA NA

2CVA6AA-2!W-04 Hunter Corp. 2-CV-1-N5 NA NA

2CVA6AA-2/W-05 Hunter Corp. 2-CV-1-N5 NA NA

2CVA7AA-2!W-06 Hunter Corp. 2-CV-1-N5 NA NA

2CVA7AA-2/W-07 Hunter Corp. 2-CV-1-N5 NA NA

Note (1): Baseline ExaminationNote (2): Snubber examined as a Component Support

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) informationin items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded atthe top of this form.

Computer Generated Form

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7/29/2010 Exelen.Byron Station Unit 2

B2R15 ISI Outage Report

FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONSAs Required by the Provisions of the ASME Code Rules

(Page 9 of 53)

1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555(Name and Address of Owner)

2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010(Name and Address of Plant)

3. Plant Unit: 2 4. Owner Certificate Of Authorization (if required): N/A

5. Commercial Service Date: 08/22/87 6. National Board Number for Unit: N-200

.7. Components Inspected: Chemical & Volume Control System (CV)

ManufacturerComponent or Manufacturer or Installer State or NationalAppurtenance or Installer Serial No. Province No. Board No.

2CVA7AA-2/W-08 Hunter Corp. 2-CV-1-N5 NA NA

Note (1): Baseline ExaminationNote (2): Snubber examined as a Component Support

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) informationin items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded atthe top of this form.

Computer Generated Form

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7/29/2010 Exeln.Byron Station Unit 2

B2R15 ISI Outage Report

FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONSAs Required by the Provisions of the ASME Code Rules

(Page 10 of 53)

1.

2.

3.

5.

7.

Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555(Name and Address of Owner)

Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010(Name and Address of Plant)

Plant Unit: 2 4. Owner Certificate Of Authorization (if required): N/A

Commercial Service Date: 08/22/87 6. National Board Number for Unit: N-200

Components Inspected: Chemical & Volume Control System (CV)

Component or Manufacturer Manufacturer State or NationalAppurtenance or Installer Serial No. Province No. Board No.

2CV1OB-3/2CV04002S Lisega 01615143/008 NA NA

2CV1OB-3/2CV04012S Lisega 02615163/012 NA NA

2CV1 OCA- Pacific Scientific 7738 NA NA3/2CV22002S

2CV1 0DB- Pacific Scientific 2184 NA NA3/2CV02009S

2CV1 5AC- Pacific Scientific 23855 NA NA3/4/2CV29002S

2CVA6AA- Pacific Scientific 4099 NA NA2/2CV09026S

2CVA7AA- Pacific Scientific 8084 NA NA2/2CV25012S

2CVB7BA- Pacific Scientific 1575 NA NA3/2CV23005S

2

2

2

Note (1): Baseline ExaminationNote (2): Snubber examined as a Component Support

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) informationin items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded atthe top of this form.

Computer Generated Form

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7129/2010 Exelin..Byron Station Unit 2

B2R15 ISI Outage Report

FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONSAs Required by the Provisions of the ASME Code Rules

(Page 11 of 53)

1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555(Name and Address of Owner)

2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010(Name and Address of Plant)

3. Plant Unit: 2 4. Owner Certificate Of Authorization (if required): N/A

5. Commercial Service Date: 08/22/87 6. National Board Number for Unit: N-200

7. Components Inspected: Fuel Pool Cooling System (FC)

Manufacturer SttorNinaComponent or Manufacturer or InstallerAppurtenance or Installer Serial No. Province No. Board No.

2-FC-2-1 Hunter Corporation N/A N/A N/A

Note (1): Baseline Examination

Note (2): Snubber examined as a Component Support

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) informationin items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded atthe top of this form.

Computer Generated Form

Page 86: Byron, Unit 2, Submittal of 90-Day Inservice Inspection Report for … · 2012-12-03 · BYRON STATION UNIT 2 REFUELING OUTAGE 15 INSERVICE INSPECTION REPORT 1.1.0 INTRODUCTION Inservice

7/29/2010 Exelon-Byron Station Unit 2

B2R15 ISI Outage Report

FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONSAs Required by the Provisions of the ASME Code Rules

(Page 12 of 53)

1.

2.

3.

Z5.

7.

Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555(Name and Address of Owner)

Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010(Name and Address of Plant)

Plant Unit: 2 4. Owner Certificate Of Authorization (if required): N/A

Commercial Service Date: 08/22/87 6. National Board Number for Unit: N-200

Components Inspected: Feedwater System (FW)

ManufacturerComponent or Manufacturer orMnnstaller State or NationalAppurtenance or Installer oSerial No. Province No. Board No.

2-FW-2-2 Hunter Corporation N/A N/A N/A

Note (1): Baseline Examination

Note (2): Snubber examined as a Component Support

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) informationin items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded atthe top of this form.

Computer Generated Form

Page 87: Byron, Unit 2, Submittal of 90-Day Inservice Inspection Report for … · 2012-12-03 · BYRON STATION UNIT 2 REFUELING OUTAGE 15 INSERVICE INSPECTION REPORT 1.1.0 INTRODUCTION Inservice

7/29/2010 _Exelon.Byron Station Unit 2

B2R15 ISI Outage Report

FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONSAs Required by the Provisions of the ASME Code Rules

(Page 13 of 53)

1.

2.

3.

5.

7.

Owner: Exelon Generation Company, (EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555(Name and Address of Owner)

Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010(Name and Address of Plant)

Plant Unit: 2 4. Owner Certificate Of Authorization (if required): N/A

Commercial Service Date: 08/22/87 6. National Board Number for Unit: N-200

Components Inspected: Feedwater System (FW)

Component or Manufacturer Manufacturer State or NationalAppurtenance or Installer or Installer Province No. Board No.

Serial No.2FW03DA- HUNTER N/A NA NA

1 6/2FW02020X

2FW81AA- HUNTER N/A NA NA6/2AF06038R

2FW81 BA- HUNTER N/A NA NA6/2AF06040V

Note (1): Baseline ExaminationNote (2): Snubber examined as a Component Support

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) informationin items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded atthe top of this form.

Computer Generated Form

Page 88: Byron, Unit 2, Submittal of 90-Day Inservice Inspection Report for … · 2012-12-03 · BYRON STATION UNIT 2 REFUELING OUTAGE 15 INSERVICE INSPECTION REPORT 1.1.0 INTRODUCTION Inservice

7/29/2010 • Exeln.Byron Station Unit 2

B2R15 ISI Outage Report

FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONSAs Required by the Provisions of the ASME Code Rules

(Page 14 of 53)

1.

2.

3.

5.

7.

Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555(Name and Address of Owner)

Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010(Name and Address of Plant)

Plant Unit: 2 4. Owner Certificate Of Authorization (if required): N/A

Commercial Service Date: 08/22/87 6. National Board Number for Unit: N-200

Components Inspected: Feedwater System (FW)

Component or Manufacturer Manufacturer State or NationalAppurtenance or Installer or Installer Province No. Board No.

Serial No.

2FW03DA-16/CO1 Hunter Corp. 2-FW-5-N5 NA NA

2FW03DA-1 6/C02 Hunter Corp. 2-FW-5-N5 NA NA

2FW81 BA-6/C07 Hunter Corp. 2-FW-5-N5 NA NA

2FW87CA-6/CO1- Hunter Corp. 2-FW-5-N5 NA NA

2FW87CA-6/C02 Hunter Corp. 2-FW-5-N5 NA NA

2FW87CA-6/C03 Hunter Corp. 2-FW-5-N5 NA NA

2FW87CA-6/C04 Hunter Corp. 2-FW-5-N5 NA NA

Note (1): Baseline Examination

Note (2): Snubber examined as a Component Support

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) informationin items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded atthe top of this form.

Computer Generated Form

Page 89: Byron, Unit 2, Submittal of 90-Day Inservice Inspection Report for … · 2012-12-03 · BYRON STATION UNIT 2 REFUELING OUTAGE 15 INSERVICE INSPECTION REPORT 1.1.0 INTRODUCTION Inservice

7/29/2010 Exelkn.Byron Station Unit 2

B2R15 ISI Outage Report

FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONSAs Required by the Provisions of the ASME Code Rules

(Page 15 of 53)

1.

2.

3.

5.

7.

Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555(Name and Address of Owner)

Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010(Name and Address of Plant)

Plant Unit: 2 4. Owner Certificate Of Authorization (if required): N/A

Commercial Service Date: 08/22/87 6. National Board Number for Unit: N-200

Components Inspected: Feedwater System (FW)

Component or Manufacturer Manufacturer State or NationalAppurtenance or Installer Serial No. Province No. Board No.

2FW03DA- Pacific Scientific 2565 NA NA16/2FW02012S

2FW03DA- Pacific Scientific 8270 NA NA16/2FW02016S

2FW03DB- Pacific Scientific .4794 NA NA16/2FW03017S

2FW03DD- Pacific Scientific 8201 NA NA16/2FW05022S

2FW87CC- Pacific Scientific 19389 NA NA6/2FW08005S

2FW87CC- Pacific Scientific 20613 NA NA6/2FW08006S

2

2

2

2

Note (1): Baseline Examination

Note (2): Snubber examined as a Component Support

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) informationin items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded atthe top of this form.

Computer Generated Form

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7/29/2010 Exelkn.Byron Station Unit 2

B2R15 ISI Outage Report

FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONSAs Required by the Provisions of the ASME Code Rules

(Page 16 of 53)

1.

2.

3.

5.

7.

Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555(Name and Address of Owner)

Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010(Name and Address of Plant)

Plant Unit: 2 4. Owner Certificate Of Authorization (if required): N/A

Commercial Service Date: 08/22/87 6. National Board Number for Unit: N-200

Components Inspected: Main Steam System (MS)

Component or Manufacturer Manufacturer State or NationalAppurtenance or Installer Serial No. Province No. Board No.

2-MS-2-1 Hunter Corporation N/A N/A N/A

2-MS-2-2 Hunter Corporation N/A N/A N/A

Note (1): Baseline Examination

Note (2): Snubber examined as a Component Support

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) informationin items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded atthe top of this form.

Computer Generated Form

Page 91: Byron, Unit 2, Submittal of 90-Day Inservice Inspection Report for … · 2012-12-03 · BYRON STATION UNIT 2 REFUELING OUTAGE 15 INSERVICE INSPECTION REPORT 1.1.0 INTRODUCTION Inservice

7/29/2010 Exelon.Byron Station Unit 2

B2R15 ISI Outage Report

FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONSAs Required by the Provisions of the ASME Code Rules

(Page 17 of 53)

1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555(Name and Address of Owner)

2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010(Name and Address of Plant)

3. Plant Unit: 2 4. Owner Certificate Of Authorization (if required): N/A

5. Commercial Service Date: 08/22/87 6. National Board Number for Unit: N-200

7. Components Inspected: Main Steam System (MS)

Component or Manufacturer Manufacturer State or NationalAppurtenance or Installer Serial No. Province No. Board No.

2MS07AA- HUNTER N/A NA NA28/2MS01 205X

2MS07AC- PACIFIC SCIENTIFIC 13785/113772 NA NA28/2MS01 101S

Note (1): Baseline ExaminationNote (2): Snubber examined as a Component Support

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) informationin items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded atthe top of this form.

Computer Generated Form

Page 92: Byron, Unit 2, Submittal of 90-Day Inservice Inspection Report for … · 2012-12-03 · BYRON STATION UNIT 2 REFUELING OUTAGE 15 INSERVICE INSPECTION REPORT 1.1.0 INTRODUCTION Inservice

7/2912010 Exelkn.Byron Station Unit 2

B2R15 ISl Outage Report

FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONSAs Required by the Provisions of the ASME Code Rules

(Page 18 of 53)

1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road; Warrenville, Illinois 60555(Name and Address of Owner),

2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010(Name and Address of Plant)

3. Plant Unit: 2 4. Owner Certificate Of Authorization (if required): N/A

5. Commercial Service Date: 08/22/87 6. National Board Number for Unit: N-200.

7. Components Inspected: Main Steam System (MS)

ManufacturerComponent or Manufacturer or Installer State or NationalAppurtenance or Installer Serial No. Province No. Board No.

2MS01 AC- Pacific Scientific 10537 NA NA32.75/2MS07006-S1

2MS01 AC- Pacific Scientific 10536 NA NA32.75/2MS07006-S2

Note (1): Baseline Examination

Note (2): Snubber examined as a Component Support

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) informationin items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded atthe top of this form.

Computer Generated Form

Page 93: Byron, Unit 2, Submittal of 90-Day Inservice Inspection Report for … · 2012-12-03 · BYRON STATION UNIT 2 REFUELING OUTAGE 15 INSERVICE INSPECTION REPORT 1.1.0 INTRODUCTION Inservice

7/29/2010 ExeleknByron Station Unit 2

B2R15 ISI Outage Report

FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONSAs Required by the Provisions of the ASME Code Rules

(Page 19 of 53)

1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555(Name and Address of Owner)

2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010(Name and Address of Plant)

3. Plant Unit: 2 4. Owner Certificate Of Authorization (if required): N/A

5. Commercial Service Date: 08/22/87 6. National Board Number for Unit: N-200

7. Components Inspected: Off Gas System (OG)

Component or Manufacturer Manufacturer State or NationalAppurtenance or Installer or Installer Province No. Board No.Serial No.

2-OG-2-1 Hunter Corporation N/A N/A N/A

Note (1): Baseline Examination

Note (2): Snubber examined as a Component Support

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) informationin items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded atthe top of this form.

Computer Generated Form

Page 94: Byron, Unit 2, Submittal of 90-Day Inservice Inspection Report for … · 2012-12-03 · BYRON STATION UNIT 2 REFUELING OUTAGE 15 INSERVICE INSPECTION REPORT 1.1.0 INTRODUCTION Inservice

7/29/2010 Exelon..Byron Station Unit 2

B2R15 ISl Outage Report

FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONSAs Required by the Provisions of the ASME Code Rules

(Page 20 of 53)

1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555(Name and Address of Owner)

2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010(Name and Address of Plant)

3. Plant Unit: 2 4. Owner Certificate Of Authorization (if required): N/A

5. Commercial Service Date: 08/22/87 6. National Board Number for Unit: N-200

7. Components Inspected: Process Sampling System (PS)

Component or Manufacturer Manufactureror Installer State or NationalAppurtenance or Installer Serial No. Province No. Board No.

2-PS-2-3 Hunter Corporation N/A N/A N/A

2-PS-2-4 Hunter Corporation N/A N/A N/A

2-PS-2-5 Hunter Corporation N/A N/A N/A

2-PS-2-6 Hunter Corporation N/A N/A N/A

Note (1): Baseline Examination

Note (2): Snubber examined as a Component Support

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) informationin items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded atthe top of this form.

Computer Generated Form

Page 95: Byron, Unit 2, Submittal of 90-Day Inservice Inspection Report for … · 2012-12-03 · BYRON STATION UNIT 2 REFUELING OUTAGE 15 INSERVICE INSPECTION REPORT 1.1.0 INTRODUCTION Inservice

7/29/2010 Exelkn.Byron Station Unit 2

B2R15 ISI Outage Report

FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONSAs Required by the Provisions of the ASME Code Rules

(Page 21 of 53)

1.

2.

3.

5.

7.

Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555(Name and Address of Owner)

Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010(Name and Address of Plant)

Plant Unit: 2 4. Owner Certificate Of Authorization (if required): N/A

Commercial Service Date: 08/22/87 6. National Board Number for Unit: N-200

Components Inspected: Pressurizer (PZR)

Component or Manufacturer Manufacturer State or NationalAppurtenance or Installer Serial No. Province No. Board No.

2RY-01-S/PC-05 Westinghouse Corp. 1741 U-201441 W13582

2RY-01 -S/PL-04 Westinghouse Corp. 1741 U-201441 W 13582

2RY-01-S/PN-02 Westinghouse Corp. 1741 U-201441 W13582

2RY-01-S/PN-02-NIR Westinghouse Corp. 1741 U-201441 Wi 3582

2RY-01 -S/PN-03 Westinghouse Corp. 1741 U-201441 W 13582

2RY-01-S/PN-03-NIR Westinghouse Corp. 1741 U-201441 W 13582

2RY-01-S/PN-05-NIR Westinghouse Corp. 1741 U-201441 W13582

2RY-01-S/PN-06 Westinghouse Corp. 1741 U-201441 W13582

2RY-01 -S/PN-06-NIR Westinghouse Corp. 1741 U-201441 W 13582

Note (1): Baseline Examination

Note (2): Snubber examined as a Component Support

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) informationin items 1 through 6 of this report is included on each sheet, an'd (3) each sheet is numbered and the number of sheets is recorded at

the top of this form:

Computer Generated Form

Page 96: Byron, Unit 2, Submittal of 90-Day Inservice Inspection Report for … · 2012-12-03 · BYRON STATION UNIT 2 REFUELING OUTAGE 15 INSERVICE INSPECTION REPORT 1.1.0 INTRODUCTION Inservice

7/29/2010 Exelon.Byron Station Unit 2

B2R15 ISI Outage Report

FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONSAs Required by the Provisions of the ASME Code Rules

(Page 22 of 53)

1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555(Name and Address of Owner)

2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010(Name and Address of Plant)

3. Plant Unit: 2 4. Owner Certificate Of Authorization (if required): N/A

5. Commercial Service Date: 08/22/87 6. National Board Number for Unit: N-200

7. Components Inspected: Reactor Coolant System (RC)

Component or Manufacturer Manufacturer State or NationalAppurtenance or Installer Serial No. Province No. Board No.

2-RC-1-1 Hunter Corporation N/A N/A N/A

Note (1): Baseline ExaminationNote (2): Snubber examined as a Component Support

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) informationin items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded atthe top of this form.

Computer Generated Form

Page 97: Byron, Unit 2, Submittal of 90-Day Inservice Inspection Report for … · 2012-12-03 · BYRON STATION UNIT 2 REFUELING OUTAGE 15 INSERVICE INSPECTION REPORT 1.1.0 INTRODUCTION Inservice

7/29/2010 Exekon.Byron Station Unit 2

B2R15 ISI Outage Report

FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONSAs Required by the Provisions of the ASME Code Rules

(Page 23 of 53)

1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555(Name and Address of Owner)

2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010(Name and Address of Plant)

3. Plant Unit: 2 4. Owner Certificate Of Authorization (if required): N/A

5. Commercial Service Date: 08/22/87 6. National Board Number for Unit: N-200

7. Components Inspected: Reactor Coolant System (RC)

Component or Manufacturer Manufacturer State or NationalAppurtenance or Installer Serial No. Province No. Board No.

2RC14AB- HUNTER N/A NA NA2/2CV15016V

Note (1): Baseline Examination

Note (2): Snubber examined as a Component Support

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) informationin items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded atthe top of this form.

Computer Generated Form

Page 98: Byron, Unit 2, Submittal of 90-Day Inservice Inspection Report for … · 2012-12-03 · BYRON STATION UNIT 2 REFUELING OUTAGE 15 INSERVICE INSPECTION REPORT 1.1.0 INTRODUCTION Inservice

7/29/2010 Exeln.Byron Station Unit 2

B2R15 ISI Outage Report

FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONSAs Required by the Provisions of the ASME Code Rules

(Page 24 of 53)

1.

2.

3.

5.

7.

Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555(Name and Address of Owner)

Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010(Name and Address of Plant)

Plant Unit: 2 4. Owner Certificate Of Authorization (if required): N/A

Commercial Service Date: 08/22/87 6. National Board Number for Unit: N-200

Components Inspected: Reactor Coolant System (RC)

Component or Manufacturer Manufacturer State or NationalAppurtenance or Installer Serial No. Province No. Board No.

2RC01AA-29/J06 Hunter Corp. 2-RC-1-N5 NA NA

2RC-01-R/RPVS-A F1 Westinghouse Corp. 640-0012-51 B-09062 N-200

2RC-01 -R/RPVS-D F1 Westinghouse Corp. 640-0012-51 B-09062 N-200

2RC-01-R/RPVS-E F1 Westinghouse Corp. 640-0012-51 B-09062 N-200

2RC-01 -R/RPVS-F F1 Westinghouse Corp. 640-0012-51 B-09062 N-200

2RC-01 -R/RPVS-H F1 Westinghouse Corp. 640-0012-51 B-09062 N-200

2RC03AA-27.5/JO2A Hunter Corp. 2-RC-1-N5 NA NA

2RC03AA-27.5/J04 Hunter Corp. 2-RC-1 -N5 NA NA

2RC13AA-2/W-01 Hunter Corp. 2-RC-1 -N5 NA NA

2RC13AA-2/W-02 Hunter Corp. 2-RC-1 -N5 NA NA

2RC13AA-2/W-03 Hunter Corp. 2-RC-1-N5 NA NA

2RC13AA-2/W-04 Hunter Corp. 2-RC-1 -N5 NA NA

Note (1): Baseline Examination

Note (2): Snubber examined as a Component Support

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) informationin items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded atthe top of this form.

Computer Generated Form

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7/2912010 Exelon.Byron Station Unit 2

B2R15 ISI Outage Report

FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONSAs Required by the Provisions of the ASME Code Rules

(Page 25 of 53)

1.

2.

3.

5.

7.

Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555(Name and Address of Owner)

Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010(Name and Address of Plant)

Plant Unit: 2 4. Owner Certificate Of Authorization (if required): N/A

Commercial Service Date: 08/22/87 6. National Board Number for Unit: N-200

Components Inspected: Reactor Coolant System (RC)

Component or Manufacturer Manufacturer State or NationalAppurtenance or Installer Serial No. Province No. Board No.

2RC13AA-2/W-05 Hunter Corp. 2-RC-1 -N5 NA NA

2RC13AB-2/W-01 Hunter Corp. 2-RC-1-N5 NA NA

2RC13AC-2/W-01 Hunter Corp. 2-RC-1-N5 NA NA

2RC13AD-2/W-01 Hunter Corp. 2-RC-1-N5 NA NA

2RC14AA-2/W-01 Hunter Corp. 2-RC-1-N5 NA NA

2RC14AA-2/W-01A Hunter Corp. 2-RC-1 -N5 NA NA

2RC14AA-2/W-01B Hunter Corp. 2-RC-1-N5 NA NA

2RC14AA-2/W-01C Hunter Corp. 2-RC-1 -N5 NA NA

2RC14AA-2/W-02 Hunter Corp. 2-RC-1 -N5 NA NA

2RC14AA-2/W-03 Hunter Corp. 2-RC-1-N5 NA NA

2RC14AA-2/W-04 Hunter Corp. 2-RC-1-N5 NA NA

2RC14AA-2/W-05 Hunter Corp. 2-RC-1 -N5 NA NA

Note (1): Baseline Examination

Note (2): Snubber examined as a Component Support

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) informationin items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded atthe top of this form.

Computer Generated Form

Page 100: Byron, Unit 2, Submittal of 90-Day Inservice Inspection Report for … · 2012-12-03 · BYRON STATION UNIT 2 REFUELING OUTAGE 15 INSERVICE INSPECTION REPORT 1.1.0 INTRODUCTION Inservice

7/29/2010 Exelkn.Byron Station Unit 2

B2R15 ISI Outage Report

FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONSAs Required by the Provisions of the ASME Code Rules

(Page 26 of 53)

1.

2.

3.

5.

7.

Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555(Name and Address of Owner)

Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010(Name and Address of Plant)

Plant Unit: 2 4. Owner Certificate Of Authorization (if required): N/A

Commercial Service Date: 08/22/87 6. National Board Number for Unit: N-200

Components Inspected: Reactor Coolant System (RC)

Component or Manufacturer Manufacturer State or NationalAppurtenance or Installer Serial No. Province No. Board No.

2RC14AA-2/W-06 Hunter Corp. 2-RC-1-N5 NA NA

2RC14AA-2/W-07 Hunter Corp. 2-RC-1 -N5 NA NA

2RC14AA-2/W-08 Hunter Corp. 2-RC-1 -N5 NA NA

2RC14AA-2/W-09 Hunter Corp. 2-RC-1-N5 NA NA

2RC14AA-2/W-10 Hunter Corp. 2-RC-1-N5 NA NA

2RC14AA-2/W-11 Hunter Corp. 2-RC-1 -N5 NA NA

2RC16AA-2/W-03 Hunter Corp. 2-RC-1 -N5 NA NA

2RC16AA-2/W-04 Hunter Corp. 2-RC-1 -N5 NA NA

2RC16AA-2/W-05 Hunter Corp. 2-RC-1 -N5 NA NA

2RC16AA-2/W-06 Hunter Corp. 2-RC-1-N5 NA NA

2RC16AA-2/W-07 Hunter Corp. 2-RC-1-N5 NA NA

2RC16AB-2/W-04 Hunter Corp. 2-RC-1 -N5 NA NA

Note (1): Baseline Examination

Note (2): Snubber examined as a Component Support

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) informationin items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded atthe top of this form.

Computer Generated Form

Page 101: Byron, Unit 2, Submittal of 90-Day Inservice Inspection Report for … · 2012-12-03 · BYRON STATION UNIT 2 REFUELING OUTAGE 15 INSERVICE INSPECTION REPORT 1.1.0 INTRODUCTION Inservice

7/29/2010 Exelon.Byron Station Unit 2

B2R15 ISI Outage Report

FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONSAs Required by the Provisions of the ASME Code Rules

(Page 27 of 53)

1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555(Name and Address of Owner)

2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010(Name and Address of Plant)

3. Plant Unit: 2 4. Owner Certificate Of Authorization (if required): N/A

5. Commercial Service Date: 08/22/87 6. National Board Number for Unit: N-200

7. Components Inspected: Reactor Coolant System (RC)

ManufacturerComponent or Manufacturer or Installer State or NationalAppurtenance or Installer Serial No. Province No. Board No.

2RC16AB-2/W-05 Hunter Corp. 2-RC-1-N5 NA NA

2RC16AC-2/W-08 Hunter Corp. 2-RC-1-N5 NA NA-

2RC16AD-2/W-01 Hunter Corp. 2-RC-I.-N5 NA NA

2RC22AA-1.5/W-01 Hunter Corp. 2-RC-1-N5 NA NA

2RC22AA-1 .5/W-O Hunter Corp. 2-RC-1 -N5 NA NA

2RC22AC-1.5/W-01 Hunter Corp. 2-RC-1 -N5 NA NA

2RC22AC-1.5/W-06 Hunter Corp. 2-RC-1 -N5 NA NA

2RC22AD-1.5/W-01 Hunter Corp. 2-RC-1 -N5 NA NA

2RC22AD-1 .5/W-08 Hunter Corp. 2-RC-1 -N5 NA NA

2RC26A-2/W-01 Hunter Corp. 2-RC-1-N5 NA NA

2RC26A-2/W-02 Hunter Corp. 2-RC-1-N5 NA NA

2RC28A-3/Zone 1 Hunter Corp. 2-RC-1 -N5 NA NA

Note (1): Baseline Examination

Note (2): Snubber examined as a Component Support

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) informationin items 1 through 6 of this report is included on each sheet and (3) each sheet is numbered and the number of sheets is recorded atthe top of this form.

Computer Generated Form

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7/29/2010 Exelkn.Byron Station Unit 2

B2R15 ISI Outage Report

FORM NIS-1 OWNER'S-REPORT FOR INSERVICE INSPECTIONSAs Required by the Provisions of the ASME Code Rules

(Page 28 of 53)

1.

2.

3.

5.

7.

Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555(Name and Address of Owner)

Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010(Name and Address of Plant)

Plant Unit: 2 4. Owner Certificate Of Authorization (if required): N/A

Commercial Service Date: 08/22/87 6. National Board Number for Unit: N-200

Components Inspected: Reactor Coolant System (RC)

Component or Manufacturer Manufacturer State or NationalAppurtenance or Installer Serial No. Province No. Board No.

2RC30AA-1.5/W-01 Hunter Corp. 2-RC-1-N5 NA NA

2RC35AA-6/J02 Hunter Corp. 2-RC-1 -N5 NA NA

2RC35AA-6/J03 Hunter Corp. 2-RC-1 -N5 NA NA

2RC35AA-6/J04 Hunter Corp. 2-RC-1 -N5 NA NA

2RC35AA-6/J05 Hunter Corp. 2-RC-1-N5 NA NA

2RC37A-3/Zone 2 Hunter Corp. 2-RC-1-N5 NA NA

Note (1): Baseline ExaminationNote (2): Snubber examined as a Component Support

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) informationin items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded atthe top of this form.

Computer Generated Form

Page 103: Byron, Unit 2, Submittal of 90-Day Inservice Inspection Report for … · 2012-12-03 · BYRON STATION UNIT 2 REFUELING OUTAGE 15 INSERVICE INSPECTION REPORT 1.1.0 INTRODUCTION Inservice

7/29/2010 Exelrn..Byron Station Unit 2

B2R15 ISI Outage Report

FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONSAs Required by the Provisions of the ASME Code Rules

(Page 29 of 53)

1.

2.

3.

5.

7.

Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555(Name and Address of Owner)

Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010(Name and Address of Plant)

Plant Unit: 2 4. Owner Certificate Of Authorization (if required): N/A

Commercial Service Date: 08/22/87 6. National Board Number for Unit: N-200

Components Inspected: Reactor Coolant System (RC)

Component or Manufacturer Manufacturer State or NationalAppurtenance or Installer Serial No. Province No. Board No.

2RC01 BA- Boeing 27 NA NA2A/2RC01 BA-A

2RC01 BA- Boeing 35 NA NA2A/2RC01 BA-B

2RC01BB- Boeing 9 NA NA2B/2RC01 BB-A

2RC01BB- Boeing 15 NA NA2B/2RC01 BB-B

2RC01 BC- Boeing 19 NA NA2C/2RC01 BC-A

2RC01 BC- Boeing 7 NA NA2C/2RC01 BC-B

2RC01BD- Boeing 5 NA NA2D/2RC01 BD-A

2RC01 BD- Boeing 31 NA NA2D/2RC01BD-B

2RC08AA- Pacific Scientific 14672 NA NA3/4/2RC16009S

2RC13AB- Pacific Scientific 8034 NA NA2/2CV1 5002S

2RC14AD- Pacific Scientific 3105 NA NA 22/2CV25019S

2RC14AD- Pacific Scientific 17595 NA NA

2/2CV25020S

Note (1): Baseline Examination

Note (2): Snubber examined as a Component Support

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) informationin items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded atthe top of this form.

Computer Generated Form

Page 104: Byron, Unit 2, Submittal of 90-Day Inservice Inspection Report for … · 2012-12-03 · BYRON STATION UNIT 2 REFUELING OUTAGE 15 INSERVICE INSPECTION REPORT 1.1.0 INTRODUCTION Inservice

7/29/2010 Exelon.Byron Station Unit 2

B2R15 ISI Outage Report

FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONSAs Required by the Provisions of the ASME Code Rules

(Page 30 of 53)

1.

2.

3.

5.

7.

Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555(Name and Address of Owner)

Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010(Name and Address of Plant)

Plant Unit: 2 4. Owner Certificate Of Authorization (if required): N/A

Commercial Service Date: 08/22/87 6. National Board Number for Unit: N-200

Components Inspected: Reactor Coolant System (RC)

Component or Manufacturer Manufacturer State or NationalAppurtenance or Installer Serial No. Province No. Board No.

2RC14AD- Pacific Scientific 8040 NA NA2/2CV25024S

2RC22AA- Pacific Scientific 12848 NA NA1.5/2RC16001S

2RC22AA- Pacific Scientific 2928 NA NA1.5/2RC16011S

2RC22AB- Pacific Scientific 9917 NA NA1.5/2RC17015S

2RC48BB- Pacific Scientific 3134 NA NA1/2/2RC90B008S

2

2

Note (1): Baseline Examination

Note (2): Snubber examined as a Component Support

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) informationin items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded atthe top of this form.

Computer Generated Form

Page 105: Byron, Unit 2, Submittal of 90-Day Inservice Inspection Report for … · 2012-12-03 · BYRON STATION UNIT 2 REFUELING OUTAGE 15 INSERVICE INSPECTION REPORT 1.1.0 INTRODUCTION Inservice

7/29/2010 Exelkn.Byron Station Unit 2

B2R15 ISI Outage Report

FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONSAs Required by the Provisions of the ASME Code Rules

(Page 31 of 53)

1. Owner: Exelon Generation Company,(EGC,LLC),.4300 Winfield Road, Warrenville, Illinois 60555(Name and Address of Owner)

2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010(Name and Address of Plant)

3. Plant Unit: 2 4. Owner Certificate Of Authorization (if required): N/A

5. Commercial Service Date: 08/22/87 6. National Board Number for Unit: N-200

7. Components Inspected: Residual Heat Removal System (RH)

Component or Manufacturer Manufactureror Installer State or National

Appurtenance or Installer Serial No. Province No. Board No.

2-RH-2-1 Hunter Corporation N/A N/A N/A

2-RH-2-2 Hunter Corporation N/A N/A N/A

2-RH-2-3 Hunter Corporation N/A. N/A N/A

2-RH-2-6 Hunter Corporation N/A N/A N/A

Note (1): Baseline ExaminationNote (2): Snubber examined as a Component Support

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) informationin items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded atthe top of this form.

Computer Generated Form

Page 106: Byron, Unit 2, Submittal of 90-Day Inservice Inspection Report for … · 2012-12-03 · BYRON STATION UNIT 2 REFUELING OUTAGE 15 INSERVICE INSPECTION REPORT 1.1.0 INTRODUCTION Inservice

7/29/2010 Exelon.Byron Station Unit 2

B2R15 ISI Outage Report

FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONSAs Required by the Provisions of the ASME Code Rules

(Page 32 of 53)

1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555(Name and Address of Owner)

2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010(Name and Address of Plant)

3. Plant Unit: 2 4. Owner Certificate Of Authorization (if required): N/A

5. Commercial Service Date: 08/22/87 6. National Board Number for Unit: N-200

7. Components Inspected: Residual Heat Removal System (RH)

ManufacturerComponent or Manufacturer or Installer State or NationalAppurtenance or Installer Serial No. Province No. Board No.

2RH01CA- HUNTER N/A NA N/A16/2S106259X

Note (1): Baseline Examination

Note (2): Snubber examined as a Component Support

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) informationin items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded atthe top of this form.

Computer Generated Form

Page 107: Byron, Unit 2, Submittal of 90-Day Inservice Inspection Report for … · 2012-12-03 · BYRON STATION UNIT 2 REFUELING OUTAGE 15 INSERVICE INSPECTION REPORT 1.1.0 INTRODUCTION Inservice

7/29/2010 Exelon.Byron Station Unit 2

B2R15 ISI Outage Report

FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONSAs Required by the Provisions of the ASME Code'Rules

(Page 33 of 53)

1.

2.

3.

5.

7.

Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555(Name and Address of Owner)

Plant: Byron Nuclear Power Station, 4450 North German Church'Road, Byron, Illinois 61010(Name and Address of Plant)

Plant Unit: 2 4. Owner Certificate Of Authorization (if required): N/A

Commercial Service Date: 08/22/87 6. National Board Number for Unit: N-200

Components Inspected: Residual Heat Removal System (RH)

Component or Manufacturer Manufacturer State or NationalAppurtenance or Installer Serial No. Province No. Board No.

2RH01BA-12/C03 Hunter Corp. 2-RH-2-N5 NA NA

2RH02AA-8/C47 Hunter Corp. 2-RH-2-N5 NA NA

Note (1): Baseline Examination

Note (2): Snubber examined as a Component Support

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) informationin items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded atthe top of this form.

Computer Generated Form

Page 108: Byron, Unit 2, Submittal of 90-Day Inservice Inspection Report for … · 2012-12-03 · BYRON STATION UNIT 2 REFUELING OUTAGE 15 INSERVICE INSPECTION REPORT 1.1.0 INTRODUCTION Inservice

7/29/2010 Exelon.Byron Station Unit 2

B2R15 ISI Outage Report

FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONSAs Required by the Provisions of the ASME Code Rules

(Page 34 of 53)

1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555(Name and Address of Owner)

2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010(Name and Address of Plant)

3. Plant Unit: 2 4. Owner Certificate Of Authorization (if required): N/A

5. Commercial Service Date: 08/22/87 6. National Board Number for Unit: N-200

7. Components Inspected: Residual Heat Removal System (RH)

ManufacturerComponent or Manufacturer or Installer State or NationalAppurtenance or Installer Serial No. Province No. Board No.

2RH02AA- Pacific Scientific 12105 NA NA8/2RH07003S

2RH02AA- Pacific Scientific 15103 NA NA8/2RH07012S

2RH26AA- Pacific Scientific 8077 NA NA3/4/2RH02121 S

Note (1): Baseline Examination

Note (2): Snubber examined as a Component Support

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) informationin items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded atthe top of this form.

Computer Generated Form

Page 109: Byron, Unit 2, Submittal of 90-Day Inservice Inspection Report for … · 2012-12-03 · BYRON STATION UNIT 2 REFUELING OUTAGE 15 INSERVICE INSPECTION REPORT 1.1.0 INTRODUCTION Inservice

7/29/2010~Exekrn.

Byron Station Unit'2B2R15 ISI Outage Report

FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONSAs Required by the Provisions of the ASME Code Rules

(Page 35 of 53)

1.

2.

3.

5.

7.

Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555(Name and Address of Owner)

Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010(Name and Address of Plant)

Plant Unit: 2 4. Owner Certificate Of Authorization (if required): N/A

Commercial Service Date: 08/22/87 6. National Board Number for Unit: 'N-200

Components Inspected: Reactor Pressure Vessel (RPV)

Component or Manufacturer Manufacturer State or Nationalor Installer SttorNtnaAppurtenance or Installer Serial No. Province No. Board No.

2RC-01-R/RPV BMI Westinghouse Corp. 640-0012-51 B-09062 N-200

2RC-01 -R/RPV HEAD Westinghouse Corp. 640-0012-52 B-09062 N-200PEN

2RC-01 -R/RPV HEAD Westinghouse Corp. 640-0012-52 B-09062 N-200SURF

2RC-01 -R/RPV Westinghouse Corp. 640-0012-51 B-09062 N-200INTERIOR

Note (1): Baseline Examination

Note (2): Snubber examined as a Component Support

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) informationin items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded atthe top of this form.

Computer Generated Form

Page 110: Byron, Unit 2, Submittal of 90-Day Inservice Inspection Report for … · 2012-12-03 · BYRON STATION UNIT 2 REFUELING OUTAGE 15 INSERVICE INSPECTION REPORT 1.1.0 INTRODUCTION Inservice

7/29/2010 Exelkn.Byron Station Unit 2

B2R15 ISI Outage Report

FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONSAs Required by the Provisions of the ASME Code Rules

(Page 36 of 53)

1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555(Name and Address of Owner)

2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010(Name and Address of Plant)

3. Plant Unit: 2 4. Owner Certificate Of Authorization (if required): N/A

5. Commercial Service Date: 08/22/87 6. National Board Number for Unit: N-200

7. Components Inspected: Reactor Coolant System (RY)

Component or Manufacturer Manufacturer State or NationalAppurtenance or Installer Serial No. Province No. Board No.

2RY03BC-6/FLG 1-12 Hunter Corp. 2-RC-1-N5 NA NA

2RY76A-2/FLG 1-8 Hunter Corp. 2-RC-1 -N5 NA NA

1

1

Note (1): Baseline Examination

Note (2): Snubber examined as a Component Support

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) informationin items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded atthe top of this form.

Computer Generated Form

Page 111: Byron, Unit 2, Submittal of 90-Day Inservice Inspection Report for … · 2012-12-03 · BYRON STATION UNIT 2 REFUELING OUTAGE 15 INSERVICE INSPECTION REPORT 1.1.0 INTRODUCTION Inservice

7/29/2010 Exelkn-Byron Station Unit 2

B2R15 ISI Outage Report

FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONSAs Required by the Provisions of the.ASME Code Rules

(Page 37 of 53)

1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555(Name and Address of Owner)

2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010(Name and Address of Plant)

3. Plant Unit: 2 4. Owner Certificate Of Authorization (if required): N/A

5. Commercial Service Date: 08/22/87 6. National Board Number for Unit: N-200

7. Components Inspected: Reactor Coolant System (RY)

Component or Manufacturer Manufacturer State or NationalAppurtenance or Installer Serial No. Province No. Board No.

2RY-01-S/SKT HUNTER N/A NA NA

Note (1): Baseline Examination

Note (2): Snubber examined as a Component Support

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) informationin items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded atthe top of this form.

Computer Generated Form

Page 112: Byron, Unit 2, Submittal of 90-Day Inservice Inspection Report for … · 2012-12-03 · BYRON STATION UNIT 2 REFUELING OUTAGE 15 INSERVICE INSPECTION REPORT 1.1.0 INTRODUCTION Inservice

7/29/2010 Exelon.Byron Station Unit 2

B2R15 ISI Outage Report

FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONSAs Required by the Provisions of the ASME Code Rules

(Page 38 of 53)

1.

2.

3.

5.

7.

Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555(Name and Address of Owner)

Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010(Name and Address of Plant)

Plant Unit: 2 4. Owner Certificate Of Authorization (if required): N/A

Commercial Service Date: 08/22/87 6. National Board Number for Unit: N-200

Components Inspected: Reactor Coolant System (RY)

Component or Manufacturer Manufacturer State or NationalAppurtenance or Installer Serial No. Province No. Board No.

2RY01B-6/J28 Hunter Corp. 2-RC-1 -N5 NA NA

2RY01 B-6/J29 Hunter Corp. 2-RC-1 -N5 NA NA

2RY01B-6/J30 Hunter Corp. 2-RC-1-N5 NA NA

2RY01C-4/J01S Westinghouse Corp. 2-RC-1-N5 NA NA

2RY-01 -S/PN-01 -FlS Westinghouse Corp. 1741 U-201441 W 13582

2RY-01-S/PN-02-F2S Westinghouse Corp. 1741 U-201441 W13582

2RY-01 -S/PN-03-IF3S Westinghouse Corp. 1741 U-201441 W 13582

2RY-01 -S/PN-04-F4S Westinghouse Corp. 1.741 U-201441 W 13582

2RY-01-S/PN-05-F5S Westinghouse Corp. 1741 U-201441 W13582

2RY-01 -S/PN-06-F6S Westinghouse Corp. 1741 U-201441 W 13582

2RY02A-6/JO1 S Westinghouse Corp. 2-RC-1 -N5 NA NA

2RY03AA-6/JO1 S Westinghouse Corp. 2-RC-1 -N5 NA NA

Note (1): Baseline Examination

Note (2): Snubber examined as a Component Support

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) informationin items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded atthe top of this form.

Computer Generated Form

Page 113: Byron, Unit 2, Submittal of 90-Day Inservice Inspection Report for … · 2012-12-03 · BYRON STATION UNIT 2 REFUELING OUTAGE 15 INSERVICE INSPECTION REPORT 1.1.0 INTRODUCTION Inservice

7/29/2010 Exelmn.Byron Station Unit 2

B2R15 ISI Outage Report

FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONSAs Required by the Provisions of the ASME Code Rules

(Page 39 of 53)

1.

2.

3.

5.

7.

Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555(Name and Address of Owner)

Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010(Name and Address of Plant)

Plant Unit: 2 4. Owner Certificate Of Authorization (if required): N/A

Commercial Service Date: 08/22/87 6. National Board Number for Unit: N-200

Components Inspected: Reactor Coolant System (RY)

Component or Manufacturer Manufacturer State or NationalAppurtenance or Installer Serial No. Province No. Board No.

2RY03AB-6/JO1 S Westinghouse Corp. 2-RC-1 -N5 NA NA

2RY03AC-6/JO1S Westinghouse Corp. 2-RC-1-N5 NA NA

2RY11A-14/JO1S Hunter Corp. 2-RC-1-N5 NA NA

2RY1 8A-2/W-01 Hunter Corp. 2-RC-1 -N5 NA NA

2RY1 8A-2/W-02 Hunter Corp. 2-RC-1 -N5 NA NA

2RY1 8A-2/W-03 Hunter Corp. 2-RC-1-N5 NA NA

2RY18A-2/W-04 Hunter Corp. 2-RC-1 -N5 NA NA

Note (1): Baseline Examination

Note (2): Snubber examined as a Component Support

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) informationin items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded atthe top of this form.

Computer Generated Form

Page 114: Byron, Unit 2, Submittal of 90-Day Inservice Inspection Report for … · 2012-12-03 · BYRON STATION UNIT 2 REFUELING OUTAGE 15 INSERVICE INSPECTION REPORT 1.1.0 INTRODUCTION Inservice

7/29/2010 Exekon.Byron Station Unit 2

B2R15 ISl Outage Report

FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONSAs Required by the Provisions of the ASME Code Rules

(Page 40 of 53)

1.

2.

3.

5.

7.

Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555(Name and Address of Owner)

Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010(Name and Address of Plant)

Plant Unit: 2 4. Owner Certificate Of Authorization (if required): N/A

Commercial Service Date: 08/22/87 6. National Board Number for Unit: N-200

Components Inspected: Reactor Coolant System (RY)

Component or Manufacturer Manufactureror Installer State or National

Appurtenance or Installer Serial No. Province No. Board No.

2RY01 B-6/2RY06025- Pacific Scientific 9655 NA NAS1

2RY01 B-6/2RY06025- Pacific Scientific 9558 NA NAS2

2RY02B-3/2RY09077S Hunter Corp. 23126 NA NA

2RY1 8A-2/2RY06114S Pacific Scientific 4356 NA NA

2RY34AB- Pacific Scientific 27591 NA NA1/2/2RC92002S

2

Note (1): Baseline Examination

Note (2): Snubber examined as a Component Support

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

computer Generated Form

Page 115: Byron, Unit 2, Submittal of 90-Day Inservice Inspection Report for … · 2012-12-03 · BYRON STATION UNIT 2 REFUELING OUTAGE 15 INSERVICE INSPECTION REPORT 1.1.0 INTRODUCTION Inservice

7/29/2010 Exelmn.Byron Station Unit 2

B2R15 ISI Outage Report

FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONSAs Required by the Provisions of the ASME Code Rules

(Page 41 of 53)

1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555(Name and Address of Owner)

2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010(Name and Address of Plant)

3. Plant Unit: 2 4. Owner Certificate Of Authorization (if required): N/A

5. Commercial Service Date: 08/22/87 6. National Board Number for Unit: N-200

7. Components Inspected: Steam Generator Blowdown System (SD)

Component or Manufacturer Manufacturer State or NationalAppurtenance or Installer or Installer Province No. Board No.Serial No.

2SDO1 CB- Lisega 03615873/010 NA NA2/2SD01 005S

Note (1): Baseline Examination

Note (2): Snubber examined as a Component Support

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) informationin items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded atthe top of this form.

Computer Generated Form

Page 116: Byron, Unit 2, Submittal of 90-Day Inservice Inspection Report for … · 2012-12-03 · BYRON STATION UNIT 2 REFUELING OUTAGE 15 INSERVICE INSPECTION REPORT 1.1.0 INTRODUCTION Inservice

7/2912010 Exelon.Byron Station Unit 2

B2R15 ISI Outage Report

FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONSAs Required by the Provisions of the ASME Code Rules

(Page 42 of 53)

1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555(Name and Address of Owner)

2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010(Name and Address of Plant)

3. Plant Unit: 2 4. Owner Certificate Of Authorization (if required): N/A

5. Commercial Service Date: 08/22/87 6. National Board Number for Unit: N-200

7. Components Inspected: Steam Generator (SG)

ManufacturerComponent or Manufacturer or Installer State or NationalAppurtenance or Installer Serial No. Province No. Board No.

2RC-01 -BNBLT 1-32 Westinghouse Corp. 2095 U-201435 15 1

Note (1): Baseline Examination

Note (2): Snubber examined as a Component Support

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) informationin items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded atthe top of this form.

Computer Generated Form

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7/29/2010 Exelon.Byron Station Unit 2

B2R15 IS[ Outage Report

FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONSAs Required by the Provisions of the ASME Code Rules

(Page 43 of 53)

1.

2.

3.

5.

7.

Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555(Name and Address of Owner)

Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010(Name and Address of Plant)

Plant Unit: 2 4. Owner Certificate Of Authorization (if required): N/A

Commercial Service Date: 08/22/87 6. National Board Number for Unit: N-200

Components Inspected: Steam Generator (SG)

ManufacturerComponent or Manufacturer or Installer State or NationalAppurtenance or Installer Serial No. Province No. Board No.

2RC-01 -BA/DRAIN Westinghouse Corp. 2095 U-201435 15

2RC-01-BB/DRAIN Westinghouse Corp. 2096 U-201436 16

2RC-01 -BC/DRAIN Westinghouse Corp. 2097 U-201437 17

2RC-01-BD/DRAIN Westinghouse Corp. 2098 U-201438 18

Note (1): Baseline Examination

Note (2): Snubber examined as a Component Support

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) informationin items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded atthe top of this form.

Computer Generated Form

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B2R15 ISI Outage Report

FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONSAs Required by the Provisions of the ASME Code Rules

(Page 44 of 53)

1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555(Name and Address of Owner)

2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010(Name and Address of Plant)

3. Plant Unit: 2 4. Owner Certificate Of Authorization (if required): N/A

5. Commercial Service Date: 08/22/87 6. National Board Number for Unit: N-200

7. Components Inspected: Safety Injection System (SI)

Component or Manufacturer Manufacturer State or NationalAppurtenance or Installer or Installer Province No. Board No.Serial No.

2SI08HA-2IFLG 1-8 Hunter Corp. 2-SI-i -N5 NA NA

Note (1): Baseline Examination

Note (2): Snubber examined as a Component Support

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) informationin items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded atthe top of this form.

computer Generated Form

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7/29/2010 Exelon.Byron Station Unit 2

B2R15 ISI Outage Report

FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONSAs Required by the Provisions of the ASME Code Rules

(Page 45 of 53)

1.

2.

3.

5.

7.

Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555(Name and Address of Owner)

Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010(Name and Address of Plant)

Plant Unit: 2 4. Owner Certificate Of Authorization (if required): N/A

Commercial Service Date: 08/22/87 6. National Board Number for Unit: N-200

Components Inspected: Safety Injection System (SI)

Component or Manufacturer Manufacturer State or NationalAppurtenance or Installer Serial No. Province No. Board No.

2-SI-2-1 Hunter Corporation N/A N/A N/A

2-SI-2-2 Hunter Corporation N/A N/A N/A

2-SI-2-3 Hunter Corporation N/A N/A N/A

2-SI-2-4 Hunter Corporation N/A N/A N/A

2-SI-2-5 Hunter Corporation N/A N/A N/A

2-SI-2-6 Hunter Corporation N/A N/A N/A

2-SI-2-7 Hunter Corporation N/A N/A N/A

Note (1):'Baseline Examination

Note (2): Snubber examined as a Component Support

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) informationin items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded atthe top of this form.

Computer Generated Form

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7/29/2010 Exelkn.Byron Station Unit 2

B2R15 ISI Outage Report

FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONSAs Required by the Provisions of the ASME Code Rules

(Page 46 of 53)

1.

2.

3.

5.

7.

Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555(Name and Address of Owner)

Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010(Name and Address of Plant)

Plant Unit: 2 4. Owner Certificate Of Authorization (if required): N/A

Commercial Service Date: 08/22/87 6. National Board Number for Unit: N-200

Components Inspected: Safety Injection System (SI)

Component or Manufacturer Manufacturer State or NationalAppurtenance or Installer Serial No. Province No. Board No.

2SI04B- HUNTER N/A NA NA12/2RH02109X

2SI04B- HUNTER N/A NA NA12/2RH021 1OX

2SI04D-8/2RH02020X HUNTER N/A NA NA

2SI05CA-8/2SI01024X 'HUNTER N/A NA NA

2SI05CA-8/2S101040X HUNTER N/A NA NA

2SI06BA- HUNTER N/A NA NA24/2SI06260X

2SI06BA- HUNTER N/A NA NA24/2SI06261 X

2SI08FA-3/2SI21014X HUNTER N/A NA NA

2SI08HA-2/2SI25009X HUNTER N/A NA NA

Note (1): Baseline Examination

Note (2): Snubber examined as a Component Support

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) informationin items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded atthe top of this form.

Computer Generated Form

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7/29/2010 Exelon.Byron Station Unit 2

B2R15 ISI Outage Report

FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONSAs Required by the Provisions of the ASME Code Rules

(Page 47 of 53)

1.

2.

3.

5.

7.

Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555(Name and Address of Owner)

Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010(Name and Address of Plant)

Plant Unit: 2 4. Owner Certificate Of Authorization (if required): N/A

Commercial Service Date: 08/22/87 6. National Board Number for Unit: N-200

Components Inspected: Safety Injection System (SI)

Component or Manufacturer Manufacturer 'State or NationalAppurtenance or Installer Serial No. Province No. Board No.

2SI03DA-2/W-08A Hunter Corp. 2-SI-1-N5 NA NA

2SI04B-12/C02 Hunter Corp. 2-SI-2-N5 NA NA

2SI05BA-8/C02 Hunter Corp. 2-SI-2-N5 NA NA

2SI08HA-2/W-01 H~unter Corp. 2-S1-1-N5 NA NA

2SI08HA-2/W-02 Hunter Corp. 2-S1-1-N5 NA NA

2SI08HA-2/W-03 Hunter Corp. 2-SI-1 -N5 NA NA

2SI08HA-2/W-04 Hunter Corp. 2-S1-1-N5 NA NA

2SI08HA-2/W-05 Hunter Corp. 2-S1-1-N5 NA NA

2SI08HA-2/W-06 Hunter Corp. 2-SI-1-N5 NA NA

2SI08JA-1.5/W-01 Hunter Corp. 2-SI-1-N5 NA NA

2SI08JA-1.5/W-02 Hunter Corp. 2-S1-1-N5 NA NA

2SI08JA-1.5/W-03 Hunter Corp. 2-SI-1-N5 NA NA

Note (1): Baseline Examination

Note (2): Snubber examined as a Component Support

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) informationin items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded atthe top of this form.

Computer Generated Form

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7/29/2010 Exelkn.Byron Station Unit 2

B2R15 ISI Outage Report

FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONSAs Required by the Provisions of the ASME Code Rules

(Page 48 of 53)

1.

2.

3.

5.

7.

Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555(Name and Address of Owner)

Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010(Name and Address of Plant)

Plant Unit: 2 4. Owner Certificate Of Authorization (if required): N/A

Commercial Service Date: 08/22/87 6. National Board Number for Unit: N-200

Components Inspected: Safety Injection System (SI)

ManufacturerComponent or Manufacturer Mansturer State or NationalAppurtenance or Installer or Installer Province No. Board No.

Serial No.

2SI08JA-1.5/W-04 Hunter Corp. 2-S1-1-N5 NA NA

2SI08JA-1.5/W-05 Hunter Corp. 2-SI-1-N5 NA NA

2SI08JA-1.5/W-05A Hunter Corp. 2-SI-1 -N5 NA NA

2SI08JA-1.5/W-05B Hunter Corp. 2-S1-1-N5 NA NA

2SI08JA-1.5/W-06 Hunter Corp. 2-SI-1 -N5 NA NA

2SI08JA-1.5/W-07 Hunter Corp. 2-SI-1 -N5 NA NA

2SI08JA-1.5/W-10 Hunter Corp. 2-S1-1-N5 NA NA

2SI08JA-1.5/W-14 Hunter Corp. 2-S1-1-N5 NA NA

2SI08JA-1.5/W-14 Hunter Corp. 2-S1-1-N5 NA NA

2SI108JA-1.5/W-15 Hunter Corp. 2-S1-1-N5 NA NA

2SI18FC-2/W-01.02 Exelon.Corp. 2-SI-1-N5 NA NA

2SI18FC-2/W-O1A.Oi Exelon.Corp. 2-SI-1-N5 NA NA

Note (1): Baseline Examination

Note (2): Snubber examined as a Component Support

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) informationin items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded atthe top of this form.

Computer Generated Form

1

1

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7/29/2010 Exelrn.Byron Station Unit 2

B2R15 ISI Outage Report

FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONSAs Required by the Provisions of the ASME Code Rules

(Page 49 of 53)

1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555(Nariie and Address of Owner)

2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010(Name and Address of Plant)

3. Plant Unit: 2 4. Owner Certificate Of Authorization (if required): N/A

5. Commercial Service Date: 08/22/87 6. National Board Number for Unit: N-200

7. Components Inspected: Safety Injection System (SI)

ManufacturerComponent or Manufacturer or Installer State or NationalAppurtenance or Installer Serial No. Province No. Board No.

2SI18FC-2/W-01B.01 Exelon Corp. 2-SI-1-N5 NA NA1

Note (1): Baseline Examination

Note (2): Snubber examined as a Component Support

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) informationin items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded atthe top of this form.

Computer Generated Form

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7/29/2010 Exelomn.Byron Station Unit 2

B2R15 ISI Outage Report

FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONSAs Required by the Provisions of the ASME Code Rules

(Page 50 of 53)

1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555(Name and Address of Owner)

2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010(Name and Address of Plant)

3. Plant Unit: 2 4. Owner Certificate Of Authorization (if required): N/A

5. Commercial Service Date: 08/22/87 6. National Board Number for Unit: N-200

7. Components Inspected: Safety Injection System (SI)

Component or Manufacturer Manufacturer State or NationalAppurtenance or Installer or Installer Province No. Board No.

Serial No.

2SI05DC-6/2SI09014- Pacific Scientific 20565 NA NA$1

2SI05DC-6/2SI09014- Pacific Scientific 20555 NA NAS2

Note (1): Baseline Examination

Note (2): Snubber examined as a Component Support

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) informationin items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded atthe top of this form.

Computer Generated Form

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7/29/2010 Exelkn.Byron Station Unit 2

B2R15 ISI Outage Report

FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONSAs Required by the Provisions of the ASME Code Rules

(Page 51 of 53).

1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555(Name and Address of Owner)

2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010(Name and Address of Plant)

3. Plant Unit: 2 4. Owner Certificate Of Authorization (if required): N/A

5. Commercial Service Date: 08/22/87 6. National Board Number for Unit: N-200

7. Components Inspected: Essential Service Water System (SX)

Component or Manufacturer Manufacturer State or NationalAppurtenance or Installer or Installer Province No. Board No.Serial No.

2-SX-2-1 Hunter Corporation N/A N/A N/A

2-SX-2-2 Hunter Corporation N/A N/A N/A

Note (1): Baseline Examination

Note (2): Snubber examined as a Component Support

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) informationin items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded atthe top of this form.

Computer Generated Form

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7/29/2010 Exelkn.Byron Station Unit 2

B2R15 ISI Outage Report

FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONSAs Required by the Provisions of the ASME Code Rules

(Page52 of 53)

1.

2.

3.

5.

7.

Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555(Name and Address of Owner)

Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010(Name and Address of Plant)

Plant Unit: 2- 4. Owner Certificate Of Authorization (if required): N/A

Commercial Service Date: 08/22/87 6. National Board Number for Unit: N-200

Components Inspected: Essential Service Water System (SX)

Component or Manufacturer Manufacturer State or NationalAppurtenance or Installer Serial No. Province No. Board No.

.2SX06CA- HUNTER N/A NA NA14/2SX06009X

2SX06EC- HUNTER N/A NA NA10/2SX06023A

2SX07EB- HUNTER N/A NA NA14/2SX09015X

Note (1): Baseline Examination

Note (2): Snubber examined as a Component Support

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) informationin items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded atthe top of this form.

Computer Generated Form

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7/29/2010Exe nByron Station Unit 2

B2R15 ISI Outage Report

FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONSAs Required by the Provisions of the ASME Code Rules

(Page 53 of 53)(BACK)

8. Examination Dates: 10/24/08 to 05/08/10

9. Inspection Period Identification: First Insoection Period

10. Inspection Interval Identification: Third Inspection Interval

11. Applicable Edition of Section Xl: 2001 Addenda 2003

12. Date / Revision of Inspection Plan: 08/15/09 4

13. Abstract of Examinations and Test. Include a list of examinations and tests and a statement concerning status

of work required for the Inspection Plan.Refer to the Outage Summary Report and ISI Program Plan

14. Abstract of Results of Examinations and Tests.

Refer to the Outage Summary Report

15. Abstract of Corrective Measures.Refer to the Outage Summary Report

We certify that a) the statements made in this report are correct, b) the examinations and tests meet theInspection Plan as required by the ASME Code, Section XI, and c) corrective measures taken conform to therules of the ASME Code, Section XI.

Certificate of Authorization No. (if applicable): N/A Expiration Date: N/A

Date: (. /:2 9 Signed for:Exelon Generation CompanyBy:

CERTIFICATE OF INSERVICE INSPECTION

1, the undersigned, holding a valid commission issued by the National Board of Boiler and PressureVessel Inspectors and the State or Province of Illinois and employedby HSB CT of Hartford CT. have inspected the components described in thisOwner's Report during the period 1A/24/0& to as1o81io, and state that to the best of myknowledge and belief, the Owner has performed examinations and tests 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, tests, and corrective measures described in thisOwner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any mannerfor any personal injury or property damage or a loss of any kind arising from or connected with thisinspection.

Inspectors Signature

Commissions: ILL-1254 Date: f,•e f ,20

National Board, State, Province, and Endorsements

Computer Generated Form

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SECTION 5.0

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DOCUMENT NO.: 2.2

FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTSAs Required by the Provisions of the ASME Code Section Xi

1. Owner Exelon Nuclear Date 4-26-10Name

4300 Winfield Road, Warrenville, IL Sheet 1 of IAddress

2. Plant Byron Nuclear Power Station Unit 02Name

4450 N. German Church Road, Byron, IL Work Order No. 00488016-01Address Repair Organization, P.O. No., Job No., etc.

3. Work Performed by Shaw/Stone &Webster Type Code Symbol Stamp Not ApplicableName Authorization No. Not Applicable

36400 S. Essex Road, Wilmington, IL 60481 Expiration Date Not ApplicableAddress

4. Identification of System CHEMICAL & VOLUME CONTROL (CV)

5. (a) Applicable Construction Code ASME Section III 19 74 Edition, S74 Addenda, 1644 Rev. 7,1651, 1682, 1683,1685, 1686, 1728, 1729, 1734, N-108, N-180 Code Case

(b) Applicable Edition of Section XI Used for Repair/Replacement Activity 2001 Edition / 2003 Addenda(c) Section XI Code Case(s) NONE

6. Identification of Components

ASMECorrected, Code

National Removed, or StampedName of Name of Manufacturer Board Other Year Installed (Yes or No)

Component Manufacturer Serial No. No. Identification Built

Snubber PacificPSA - 1/4 Scientific 23855 N/A 2CV29002S 1982 Removed YES

Snubber, Lisega LISEGA 30900553/008 N/A 2CV29002S 2009 Installed NO301856 RF1 (CAT ID# 1396543-1)

7. Description of Work REPLACED SNUBBER

8. Test Conducted: Hydrostatic [] Pneumatic E] Nominal Operating Pressure El_psi Test Temp.

Exempt ElOFVT-3 Other 0 Pressure

Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 81/2 in. x 11 in., (2)information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the numberof sheets is recorded at the top of this form.

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FORM NIS-2 (Back)

9. Remarks WO# 00488016-01Applicable Manufacturers Data Reports to be attached 9

CERTIFICATE OF COMPLIANCEI 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 Not ApplicableCertificate of Authorization No. Not ApplicableSigned __________ •Date 6__/___, 20 10

( Owner's Designee, Title

CERTIFICATE OF INSERVICE INSPECTIONI, the undersigned, holding a valid commission issued by the National Board of Boiler and PressureVessel Inspectors and the State or Province of Illinois and employed by HSB CTof Hartford, CT have inspeted the components described in this Owner's Report during the period

to , , and state that to the best of my knowledge and belief,te- Owner has performed Aexaminations and taken corrective measures described in this Owner'sReport 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 orimplied, concerning the examinations and corrective measures described in this Owner's Report.Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personalinjury or property dama. e or a loss of any kind arising from or connected with this inspection.

Commissions ,'11- -A'f 9f Inspector's Signature National Board, State Province, and Endorsements

Date: ,20 10

(Final)

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DOCUMENT NO.: 2.2

FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTSAs Required by the Provisions of the ASME Code Section XI

1. Owner Exelon Nuclear Date 4-26-10Name

4300 Winfield Road, Warrenville, IL Sheet 1 of 1Address

2. Plant Byron Nuclear Power Station Unit 02Name

4450 N. German Church Road, Byron, IL Work Order No. 00488060-01Address Repair Organization, P.O. No., Job No., etc.

3. Work Performed by Shaw/Stone & Webster Type Code Symbol Stamp Not ApplicableName Authorization No. Not Applicable

36400 S. Essex Road, Wilmington, IL 60481 Expiration Date Not ApplicableAddress

4. Identification of System REACTOR COOLING (RC)

5. (a) Applicable Construction Code ASME Section III 19 74 Edition, S74 Addenda, 1644 Rev. 7,1651, 1682, 1683, 1685, 1686, 1728,1729, 1734, N-108, N-180 Code Case

(b) Applicable Edition of Section Xl Used for Repair/Replacement Activity 2001 Edition / 2003 Addenda(c) Section XI Code Case(s) NONE

6. Identification of Components

ASMECorrected, Code

National Removed, or StampedName of Name of Manufacturer Board Other Year Installed (Yes or No)

Component Manufacturer Serial No. No. Identification BuiltSnubber Pacific

PSA - 1/2 Scientific 2829 N/A 2RC1601 S. 1980 Removed YESSnubber, Lisega LISEGA 30900553/004 N/A 2RC16011S 2009 Installed NO

301856 RF2 (CAT ID# 1033720-1)

7. Description of Work REPLACED SNUBBER

8. Test Conducted: Hydrostatic r]VT-3 Other Z Pr

Pneumatic C]ressure

Nominal Operating Pressure C1psi Test Temp.

Exempt 0]OF

Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8½ in. x 11 in., (2)information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the numberof sheets is recorded at the top of this form.

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FORM NIS-2 (Back)

9. Remarks WO# 00488060-01Applicable Manufacturer's Data Reports to be attached tC•

CERTIFICATE OF COMPLIANCEI 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 Not Applicable

Certificate of Authorization No. Not ApplicableSigned _ _ _ _ _ _ __ ___Date 1,20 10

r Owner's Designee, Title

CERTIFICATE OF INSERVICE INSPECTIONI, the undersigned, holding a valid commission issued by the National Board of Boiler and PressureVessel Inspectors and the State or Province of Illinois and employed by HSB CT.of -,artford, CT have ipsp9cted the components described in this Owner's Report during the period

to ,and state that to the best of my knowledge and belief,th0e dwner has performed 6xaminations and taken corrective measures described in this Owner'sReport 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 orimplied, concerning the examinations and corrective measures described in this Owner's Report.Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personalinjury or property dgmage or a loss of any kind arising from or connected with this inspection.c,46 Ae1' Commissions ,jZ'/,10(5"'1

Inspector's Signature

Date: 4e• z, 1!f' ,20 106-V

National Board, State Province, and Endorsements

(Final)

@

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( DOCUMENT NO.: 2.2 I

FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTSAs Required by the Provisions of the ASME Code Section XI

1. Owner Exelon Nuclear Date 4-24-10

2.

Name4300 Winfield Road, Warrenville, IL

AddressPlant Byron Nuclear Power Station

Name4450 N. German Church Road, Byron, IL

Address

Sheet I of 1

Unit 02

Work Order No. 00488066-01Repair Organization, P.O. No., Job No., etc.

3. Work Performed by Shaw/Stone & WebsterName

36400 S. Essex Road, Wilmington, IL 60481Address

Type Code Symbol Stamp Not ApFAuthorization No. Not ApplicableExpiration Date Not Applicable

ilicable

4. Identification of System REACTOR COOLING (RC)

5. (a) Applicable Construction Code ASME Section III 19 74 Edition, S74 Addenda,1651, 1682,1683, 1685, 1686, 1728, 1729, 1734, N-108, N-8a0 Code Case

1644 Rev. 7,

(b) Applicable Edition of Section XI Used for Repair/Replacement Activity(c) Section Xl Code Case(s) NONE

6. Identification of Components

2001 Edition / 2003 Addenda

ASME

Corrected, CodeNational Removed, or Stamped

Name of Name of Manufacturer Board Other Year Installed (Yes or No)Component Manufacturer Serial No. No. Identification Built

Snubber, PacificPSA - 1/2 Scientific 9917 N/A 2RC17015S 1981 Removed YES

Snubber, Lisega LISEGA 30900553/003 N/A 2RC17015S 2009 Installed NO301856 RF2 (CAT ID# 1033720-1)

7. Description of Work REPLACED SNUBBER

8. Test Conducted: Hydrostatic 0] Pneumatic C] Nominal Operating Pressure 0l Exempt 01OFVT-3 Other 0 Pressure psi Test Temp.

Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 81/2 in. x 11 in., (2)information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the numberof sheets is recorded at the top of this form.

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FORM NIS-2 (Back)

9. Remarks WO# 00488066-01Applicable Manufacturer's Data Reports to be attached

CERTIFICATE OF COMPLIANCEI 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 Not ApplicableCertificate of Authorization No. Not ApplicableSigned ___ ,_ _ _ _,.., _ Date L", . 20 10

rl

r o Owner's Designee, Title

CERTIFICATE OF INSERVICE INSPECTIONI, the undersigned, holding a valid commission issued by the National Board of Boiler and PressureVessel Inspectors and the State or Province of Illinois and employed by HSB CT

of Larford, CT have inppe ted the components described in this Owner's Report during the period

4Z' to g,/•.-'-- " , and state that to the best of my knowledge and belief,

th(ed wner has perform dd- e/aminations and taken corrective measures described in this Owner'sReport 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 measures described in this Owner's Report.

Furthermore,, neither the Inspector nor his employer shall be liable in any manner for any personalinjury or da;mge or a loss of any kind arising from or connected with this inspection.

9d Commissions &Zi- / ".'4Inspector's Signature National Board, State Province, and Endorsements

Date: a.e4W",, .,20 10Or

(Final)

I

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DOCUMENT NO.: 3A REV. NO.: 0

FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITYAs Required by the Provisions of the ASME Code Section XI

1. Owner Exelon Nuclear Date 2-6-09Name

4300 Winfield Road, Warrenville, IL Sheet 1 of 1Address

2. Plant Byron Nuclear Power Station Unit 02Name

4450 N. German Church Road, Byron, IL Work Order No. 00553426-01Address Repair Organization, P.O. No., Job No., etc.

3. Work Performed by Byron Mechanical Type Code Symbol Stamp Not ApplicableMaintenance

Name Authorization No. Not Applicable4450 N. German Church Road, Byron, IL Expiration Date Not Applicable

Address

4. Identification of System CV CHEMICAL AND VOLUME CONTROL

5. (a) Applicable Construction Code ASME Section ill 19 74 Edition, W76 Addenda, N/A Code Case(b) Applicable Edition of Section XI Used for Repair/Replacement Activity:. 2001 Editloni2003 Addenda(c) Section Xl Code Case(s) N/A

6. Identification of Components

ASMECorrected, Code

National Removed, or StampedName of Name of Manufacturer Board Other Year Installed (Yes or No)

Component Manufacturer Serial No. No. Identification BuiltBOLT, CLOSURE STOCK K29 2CV01 FB

EQUIP. N/A 1978 REMOVED NO

BOLT, CLOSURE NOVA MACH. HT# 144C N/A 2CV01FB 2006 INSTALLED NOSA-453 GR. 660 PROD. N/A CI# 1019317-1 206_NSALED N

7. Description of Work REPLACED FILTER COVER BOLTING

8. Test Conducted: Hydrostatic El Pneumatic C Norr

Other 0 Pressure _ psi

tinal Operating Pressure ElTest Temp. _

Exempt 0

Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8½ in. x 11in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numberedand the number of sheets is recorded at the top of this form.

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FORM NIS-2 (Back)

9. Remarks WO# 00553426-01Applicable Manufacturers Data Reports to be attached

Original bolting documentation is not available. Condition entered in the Exelon Corrective Action Program.

IR# 00322037

Component was built in 1978

CERTIFICATE OF COMPLIANCEI 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 Not ApplicableCertificate of Authorization No. Not ApplicableSigned X,?- Z Date 3 20 09

CERTIFICATE OF INSERVICE INSPECTIONI, the undersigned, holding a valid commission issued by the National Board of Boiler and PressureVessel Inspectors and the State or Province of Illinois and employed by HSB CTof farord, CT have i speced the components described in this Owner's Report during the period

'I 4-2100 to 4, and state that to the best of my knowledge and belief,the owner has performed examinations and taken corrective measures described in this Owner'sReport 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 orimplied, concerning the examinations and corrective measures described in this Owner's Report.Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personalinjury or propery damage or a loss of any kind arising from or connected with this inspection.Q14, ý .- , Commissions . tsq/ -/ f5'

D

Inspector's Signature

Date: A&OK e 20 09

National Board, State Province, and Endorsements

@

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DOCUMENT NO.: 5.2 REV. NO.: 0 IFORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS

As Required by the Provisions of the ASME Code Section Xl1. Owner Exelon Nuclear Date 4-24-10

2.

Name4300 Winfield Road, Warrenville, IL

AddressPlant Byron Nuclear Power Station

Name4450 N. German Church Road, Byron, IL

Address

Sheet 1 of

Unit 02

Work Order No. 01042618-01Repair Organization, P.O. No., Job No., etc.

3. Work Performed by Shaw/Stone & WebsterName

36400 S. Essex Road, Wilmington, IL 60481

Type Code Symbol Stamp Not ApAuthorization No. Not ApplicableExpiration Date Not Applicable

plicable

Address

4. Identification of System Si - SAFETY INJECTION

5. (a) Applicable Construction Code ASME Section III 19 74 Edition, S74 Addenda, 1644 Rev. 7,1651, 1682, 1683, 1685, 1686, 1728, 1729, 1734, N-108, N-180 Code Case

(b) Applicable Edition of Section Xl Used for Repair/Replacement Activity 2001 Edition / 2003 Addenda(c) Section XI Code Case(s) NONE

6. Identification of Components

ASMECorrected, Code

National Removed, or StampedName of Name of Manufacturer Board Other Year Installed (Yes or No)

Component Manufacturer Serial No. No. Identification BuiltSnubber, Pacific 20565 N/A 2SI09014S1 1986 Removed YESPSA - 3 Scientific

Snubber, Pacific 10581 N/A 2SI09014S1 1982 Installed YESPSA -3 Scientific

7. Description of Work REPLACED SNUBBER

8. Test Conducted: Hydrostatic El Pneumatic E] Nominal Operating Pressure [I Exempt E0

VT-3 Other Z Pressure psi Test Temp.

Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8½ in. x 11 in., (2)information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the numberof sheets is recorded at the top of this form.

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FORM NIS-2 (Back)

9. Remarks WO# 01042618-01Applicable Manufacturer's Data Reports to be attached 'VIEW

CERTIFICATE OF COMPLIANCEI 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 Not ApplicableCertificate of Authorization No. Not ApIlIcableSigned /E e a.,," Date "-// ,20 10

. ... "" __ Owner's Designee, Title

CERTIFICATE OF INSERVICE INSPECTIONI, the undersigned, holding a valid commission issued by the National Board of Boiler and PressureVessel Inspectors and the State or Province of Illinois and employed by HSB CTof .Hafford, CT have inspected the components described in this Owner's Report during the period4•.7_ to * and state that to the best of my knowledge and belief,the Owner has performed examinations and taken corrective measures described in this Owner'sReport 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 orimplied, concerning the examinations and corrective measures described in this Owner's Report.Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personalinjury or property dama e or a loss of any kind arising from or connected with this inspection.

az = ;W Commissions /1Z" -/"/ýy&ý" Inspector's Signature

Date: ,gffee /'ý/ ,20 10

National Board, State Province, and Endorsements

(Final)

I

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DOCUMENT NO.: 4A REV. NO.: 077 I

FORM NIS-2 OWNER'S REPORT FOR REPAIR/IEPLACEMENT ACTIVITYAs Required by the Provisions of the ASME Code Section XI

1. Owner Exelon Nuclear Date 5-7-10Name

4300 Winfield Road, Warrenville, IL Sheet 1 of 1Address

2. Plant Byron Nuclear Power Station Unit 02Name

4450 N. German Church Road, Byron, IL Work Order No. 1052501-01Address Repair Organization. P.O. No., Job No., etc.

3. Work Performed by Byron Mechanical Type Code Symbol Stamp Not ApplicableMaintenance

Name Authorization No. Not Applicable4450 N. German Church Road, Byron, IL Expiration Date Not Applicable

Address

4. Identification of System VO - Primary Containment Purge

5. (a) Applicable Construction Code ASME Section III 19 71 Edition, W73 Addenda, 1682 Code Case(b) Applicable Edition of Section XI Used for Repair/Replacement Activity: 2001 Edition/2003 Addenda(c) Section Xl Code Case(s) NONE

6. Identification of Components

ASMECorrected, Code

National Removed, or StampedName of Name of Manufacturer Board Other Year Installed (Yes or No)

Component Manufacturer Serial No. No. Identification BuiltEQUALIZATIONVALVE JAMESBURY NC17016-02E N/A 2VO5000A 1975 REMOVED YES

EQUALIZATION TRENTEC EQ-2-7M021-4 N/A CAT ID #1420998-1 2008 INSTALLED YESDEVICE TRENTEC __-2-7M021-4 N/A UTC# 0002837371

A I ~ .L I J. I

7. Description of Work REPLACED EQUALIZATION VALVE W/ EQUALIZATION DEVICE PER EC#360246

8. Test Conducted: Hydrostatic [I Pneumatic [] Nominal Operating Pressure Elpsi Test Temp.

Exempt ElOFVT-3 Other 0 Pressure

Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 81/ in. x 11in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numberedand the number of sheets is recorded at the top of this form.

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FORM NIS-2 (Back)

9. Remarks 1052501-01Applicable Manufacturer's Data Reports to be attached

CERTIFICATE OF COMPLIANCEI 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 Not ApplicableCertificate of Authorization No. Not Applicable

Signed X - Date 20 10v • .•Owner's Designee, Title

CERTIFICATE OF INSERVICE INSPECTIONI, the undersigned, holding a valid commission issued by the National Board of Boiler and PressureVessel Inspectors and the State or Province of Illinois and employed by HSB CTof Hartford, CT have i psp9cted the components described in this Owner's Report during the period

,,IVA/fr - to 4AI700//p , and state that to the best of my knowledge and belief,t&e 6wner has performed eam 'inations and taken corrective measures described in this OwnersReport 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 orimplied, concerning the examinations and corrective measures described in this Owners Report.Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personalinjury or property.darnage or a loss of any kind arising from or connected with this ins ection.

__ WeCommissions l'l-,/ 1157R Inspector's Signature National Board, State Province, and Endorsements

Date: • I4 .. ,20 10

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DOCUMENT NO.: 4A REV. NO.: 0

FORM NIS-2 OWNER'S REPORT FOR REPAIRIREPLACEMENT ACTIVITYAs Required by the Provisions of the ASME Code Section XI

I Owner Exelon Nuclear Date 5-6-10Name

4300 Winfield Road, Warrenville, IL Sheet 1 of 1Address

2. Plant Byron Nuclear Power Station Unit 02Name

4480 N. German Church Road, Byron, IL Work Order No. 1052501-03Address Repair Organization, P.O. No., Job No., etc.

3. Work Performed by Byron Mechanical Type Code Symbol Stamp Not ApplicableMaintenance

Name Authorization No. Not Applicable4450 N. German Church Road, Byron, IL Expiration Date Not Applicable

Address

4. identification of System VQ - Primary Containment Purge

5. (a) Applicable Construction Code ASME Section Ill 19 71 Edition, W73 Addenda, 1682 Code Case(b) Applicable Edition of Section XI Used for Repair/Replacement Activity: 2001 EditionI2003 Addenda(c) Section Xl Code Case(s) NONE

6. Identification of Components

ASMECorrected, Code

National Removed, or StampedName of Name of Manufacturer Board Other Year Installed (Yes or No)

Component Manufacturer Serial No. No. Identification BuiltEQUALIZATIONVALVE JAMESBURY Valve Body S/N: N/A 2VQ5000B 1975 REMOVED YESVALVE NC-0149-03-AA

EQUALIZATION TRENTEC EQ-2-7M021-6 N/A CAT 113142099"1 2008 INSTALLED YESDEVICE UTC# 0002817047

7. Description of Work Replaced Equalization Valve W/ Equalization Device per EC# 360246

8. Test Conducted: Hydrostatic [I Pr

VT-3 Other 0 Pressure

teumatic 5 Nominal Operating Pressure El Exempt C0

OFpsi Test Temp.

Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 81/2 in. x 11in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numberedand the number of sheets is recorded at the top of this form.

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FORM NIS-2 (Back)

9. Remarks 1052501-03 -IFApplicable Manufacturer's Data Reports to be attached

CERTIFICATE OF COMPLIANCEI 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 Not ApplicableCertificate of Authorization No. Not ApplicableSigned Date 7--Z.. ,20 10

er or ers Designee, Title

CERTIFICATE OF INSERVICE INSPECTIONI, the undersigned, holding a valid commission issued by the National Board of Boiler and PressureVessel Inspectors and the State or Province of Illinois and employed by HSB CTof Hartford, CT have inspected the components described in this Owner's Report during the period

to , , and state that to the best of my knowledge and belief,the Owner has perform&J exarminations and taken corrective measures described in this Owner'sReport 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 orimplied, concerning the examinations and corrective measures described in this Owner's Report.Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personalinjury or prop or a loss of any kind arising from or connected with this inspection.

Commissions /L '.41 Inspector's Signature National Board, State Province, and Endorsements

Date: -2 A-3 20 10r" if

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DOCUMENT NO.: 4A REV. NO.: 0

FORM NIS-2 OWNER'S REPORT FOR REPAIRIREPLACEMENT ACTIVITYAs Required by the Provisions of the ASME Code Section Xi

1. Owner Exelon Nuclear Date 5-10-10Name

4300 Winfield Road, Warrenville, IL Sheet 1 of 1Address

2. Plant Byron Nuclear Power Station Unit 02Name

4450 N. German Church Road, Byron, IL Work Order No. 1052501-04Address Repair Organization, P.O. No., Job No., etc.

3. Work Performed by Byron Mechanical Type Code Symbol Stamp Not ApplicableMaintenance

Name Authorization No. Not Applicable4450 N. German Church Road, Byron, IL Expiration Date Not Applicable

Address

4. Identification of System VO - Primary Containment Purge

5. (a) Applicable Construction Code ASME Section III 19 71 Edition, W73 Addenda, 1682 Code Case(b) Applicable Edition of Section XI Used for Repair/Replacement Activity: 2001 Editlon/2003 Addenda(c) Section XI Code Case(s) NONE

6. Identification of Components

ASMECorrected, Code

National Removed, or Stamped'Name of Name of Manufacturer Board Other Year Installed (Yes or No)

Component Manufacturer Serial No. No. Identification BuiltEQUALIZATIONVALVE JAMESBURY NC17016-O2AL N/A 2VQ5001A 1975 REMOVED YES

EQUALIZATION TRENTEC EQ-2-7M021-5 N/A CAT ID #1420998 2008 INSTALLED YESDEVICE UTC# 0002837372 208 NTALD E

7. Description of Work REPLACED EQUALIZATION VALVE W/ EQUALIZATION DEVICE PER EC# 360246

8. Test Conducted: Hydrostatic E] Pr

VT-3 Other 0 Pressure

ieumatic E] Nominal Operating Pressure 0-psi Test Temp.

Exempt E0

Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 81 in. x 11in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numberedand the number of sheets is recorded at the top of this form.

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FORM NIS-2 (Back)

9. Remarks 1052501-04Applicable Manufacturer's Data Reports to be attached

CERTIFICATE OF COMPLIANCEI 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 Not ApplicableCertificate of AuthoriatloNod Not ApplicableSigned C",6 Date 2-02- 20 10

Owner's Designee, Title

CERTIFICATE OF INSERVICE INSPECTIONI, the undersigned, holding a valid commission issued by the National Board of Boiler and PressureVessel Inspectors and the State or Province of Illinois and employed by HSB CTof Hartprd, CT have ippcted the components described in this Owner's Report during the periodZ'e•w r to , and state that to the best of my knowledge and belief,th6 Oner has performed e~aminatlons and taken corrective measures described in this Owner'sReport 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 orimplied, concerning the examinations and corrective measures described in this Owner's Report.Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personalinjury or property damage or a loss of any kind arising from or connected with this inspection.

Commissions /I.2-'an/Inspector's Signature

Date: a" , . 20 10

National Board, State Province, and Endorsements

'I

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DOCUMENT NO.: 4A REV. NO.: 0

FORM NIS-2 OWNER'S REPORT FOR REPAIRIREPLACEMENT ACTIVITYAs Required by the Provisions of the ASME Code Section XI

1. Owner Exelon Nuclear Date 5-10-10Name

4300 Winfield Road, Warrenville, IL Sheet 1 of 1Address

2. Plant Byron Nuclear Power Station Unit 02Name

4450 N. German Church Road, Byron, IL Work Order No. 1052501-05Address Repair Organization, P.O. No., Job No., etc.

3. Work Performed by Byron Mechanical Type Code Symbol Stamp Not ApplicableMaintenance

Name Authorization No. Not Applicable4450 N. German Church Road, Byron, IL Expiration Date Not Applicable

Address

4. Identification of System VO - Primary Containment Purge

5. (a) Applicable Construction Code ASME Section 1ii 19 71 Edition, W73 Addenda, 1682 Code Case(b) Applicable Edition of Section XI Used for Repair/Replacement Activity:. 2001 Editioni2003 Addenda(c) Section XI Code Case(s) NONE

6. Identification of Components

ASMECorrected, Code

National Removed, or StampedName of Name of Manufacturer Board Other Year Installed (Yes or No)

Component Manufacturer Serial No. No. Identification BuiltEQUALIZATIONVALVE JAMESBURY NC17016-02AD N/A 2VQ5001B 1975 REMOVED YES

EQUALIZATION TRENTEC EQ-2-7M021-3 N/A CAT ID #1420998 2008 INSTALLED YESDEVICE TRENTEC EQ-2-7M021-3 N/A UTC# 0002837370 2008 INSTALLED YE

7. Description of Work REPLACE EQUALIZATION VALVE W/ EQUALIZATION DEVICE PER EC# 360246

8. Test Conducted: Hydrostatic C3 Pneumatic E] Nominal Operating Pressure Cl Exempt ElOFVT-3 Other 0 Pressure psi Test Temp.

Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 81/½ in. x 11in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numberedand the number of sheets is recorded at the top of this form.

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FORM NIS-2 (Back)

9. Remarks 1052501-05Applicable Manufacturers Data Reports to be attached

CERTIFICATE OF COMPLIANCEI 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 Not ApplicableCertificate of Authorization No. Not ApplicableSigned Date 7- &-._ , 20 10

(!±eroOwner's Designee, Tite

CERTIFICATE OF INSERVICE INSPECTIONI, the undersigned, holding a valid commission issued by the National Board of Boiler and PressureVessel Inspectors and the State or Province of Illinois and employed by HSB CTof Hartf~ord, CT have inspected the components described in this Owner's Report during the period

to, and state that to the best of my knowledge and belief,tAOwvnar has performed e'xaminations and taken corrective measures described in this Owner'sReport 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 orimplied, concerning the examinations and corrective measures described in this Owner's Report.Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personalinjury or properjy damage or a loss of any kind arising from or connected with this inspection.

Commissions //Z -1(_'V

I

Dae Inspetors SignatureDate: f A. ,20 10

National Board, State Province, and Endorsements

j

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DOCUMENT NO.: 13.1 REV. NO.: 0

FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITYAs Required by the Provisions of the ASME Code Section Xl

1. Owner Exelon Nuclear Date 4-30-10Name

4300 Winfleld Road, Warrenville, IL Sheet 1 of 1Address

2. Plant Byron Nuclear Power Station Unit 02Name

4450 N. German Church Road, Byron, IL Work Order No. 01176166-03Address Repair Organization, P.O. No., Job No., etc.

3. Work Performed by Shaw/Stone & Webster Type Code Symbol Stamp Not ApplicableName Authorization No. Not Applicable

36400 S. Essex Road, Wilmington, IL 60481 Expiration Date Not ApplicableAddress

4. Identification of System PRIMARY CONTAINMENT VENTILATION (VP)

5. (a) Applicable Construction Code ASME Sec. III Piping 19 74 Edition, S75 Addenda, N/A Code Case(a) Applicable Construction Code ASME Sec. III Cooler 19 74 Edition, S76 Addenda, 1695-1 Code Case(b) Applicable Edition of Section XI Used for Repair/Replacement Activity 2001 Edition / 2003 Addenda(c) Section XI Code Case(s) NONE

6. Identification of Components

ASMECorrected, Code

National Removed, or StampedName of Name of Manufacturer Board Other Year Installed (Yes or No)

Component Manufacturer Serial No. No. Identification Built

HEAD BOLT, 1/2 2VP01AC13x 4 W, SA449 CARRIER HT# 18474 N/A SX-RH-5 1978 Removed NO13_x_4___,___44 ___Bolt# 20 & 21

HT# 2VP01AC,Screw, Hex, 1/a" x NOVA HT#-RH-5ACUS Y06420 N/A SX-RH-5 2008 Installed NO4 1/2", SA1931B7 MACHINE Bolt# 20 & 21

CID# 1396320-1

7. Description of Work INSTALLED NEW WATERBOX HEAD BOLTING

8. Test Conducted: Hydrostatic E] Pneumatic F] Norr

Other 0 Pressure _ _ psi

iinal Operating Pressure CTest Temp.

Exempt Z

Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 81/2 in. x 11 in., (2)information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and thenumber of sheets is recorded at the top of this form.

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FORM NIS-2 (Back)

-I9. Remarks WO# 01177789-01

Applicable Manufacturers Data Reports to be attached

CERTIFICATE OF COMPLIANCEI 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 Not ApplicableCertificate of Authorization No. Not ApplicableSigned Date C, 20 10

(! Owner's Designee, Title

CERTIFICATE OF INSERVICE INSPECTIONI, the undersigned, holding a valid commission issued by the National Board of Boiler and PressureVessel Inspectors and the State or Province of Illinois and employed by HSB CTof Hartford, CT have inspected the components described in this Owner's Report during the period

to ________ , and state that to the best of my knowledge and belief,

t Owner has performed examinations and taken corrective measures described in this Owner'sReport 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 orimplied, concerning the examinations and corrective measures described in this Owner's Report.Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personalinjury or property damage or a loss of any kind arising from or connected with this inspection.

Commissions /z-/. j-q'/Inspector's Signature

Date: <•d/ (, 20 10National Board, State Province, and Endorsements

(Final)

I

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DOCUMENT NO.: 13.1 REV. NO.: 0

FORM NIS-2 OWNER'S REPORT FOR REPAIRIREPLACEMENT ACTIVITYAs Required by the Provisions of the ASME Code Section XI

1. Owner Exelon Nuclear Date 5-1-10Name

4300 Winfield Road, Warrenville, IL Sheet 1 of 1Address

2. Plant Byron Nuclear Power Station Unit 02Name

4480 N. German Church Road, Byron, IL Work Order No. 01177789-01Address Repair Organization. P.O. No., Job No., etc.

3. Work Performed by Shaw/Stone & Webster Type Code Symbol Stamp Not ApplicableName Authorization No. Not Applicable

36400 S. Essex Road, Wilmington, IL 60481 Expiration Date Not ApplicableAddress

4. Identification of System PRIMARY CONTAINMENT VENTILATION (VP)

5. (a) Applicable Construction Code ASME Sec. III Piping 19 74 Edition, S75 Addenda, N/A Code Case(a) Applicable Construction Code ASME Sec. III Cooler 19 74 Edition, S76 Addenda, 1695-1 Code Case(b) Applicable Edition of Section XI Used for Repair/Replacement Activity 2001 Edition / 2003 Addenda(c) Section XI Code Case(s) NONE

6. Identification of Components

ASMECorrected, Code

National Removed, or StampedName of Name of Manufacturer Board Other Year Installed (Yes or No)

Component Manufacturer Serial No. No. Identification Built

HEAD BOLT, 1/2" Cooler S/N# 2VP01AB,x 4 W, SA449 CARRIER 7862 N/A SX-LH-5, 1978 Removed NO

Bolt# 72VPO1AB,

Screw, Hex, 1/2 x NOVA HT# SX-LH-5, 2010 Installed NO4 /A-, SA193/B7 MACHINE US Y06420 N/A St7

CAT ID# 46596-1

7. Description of WorkLEFT BANK

INSTALLED NEW COOLER HEAD BOLT

8. Test Conducted: Hydrostatic C0 Pneumatic C] Norr

Other C3 Pressure 100 psi

iinal Operating Pressure IN Exempt C0

Test Temp. 68 OF

Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8½ in. x 11 in., (2)information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and thenumber of sheets is recorded at the top of this form.

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FORM NIS-2 (Back)

9. Remarks WO# 01177789-01Applicable Manufacturer's Data Reports to be attached

Bolt acceptable per Technical Evaluation 97-014

CERTIFICATE OF COMPLIANCEI certify that the statements made in the report are correct and this conforms to the requirements of the ASME

Code, Section Xl.Type Code Symbol Stamp Not ApplicableCertificate of Authorization No. Not ApplicableSigned Date -7-ZZ. ,20 10

CERTIFICATE OF INSERVICE INSPECTIONI, the undersigned, holding a valid commission issued by the National Board of Boiler and PressureVessel Inspectors and the State or Province of Illinois and employed by HSB CTof . H tford, CT have inspected the components described in this Owner's Report during the period

to ,and state that to the best of my knowledge and belief,the )wner has performled efxaminations and taken corrective measures described in this Owner'sReport 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 orimplied, concerning the examinations and corrective measures described in this Owner's Report.Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personalinjury or propertydamage or a loss of any kind arising from or connected with this inspection.

Commissions Arz - ,kFi. Inspector's Signature

Date: .,20 10

National Board, State Province, and Endorsements

(Final)

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DOCUMENT NO.: 13.1 REV. NO.: 0

FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITYAs Required by the Provisions of the ASME Code Section XI

1. Owner Exelon Nuclear Date 5-1-10Name

4300 Winfield Road, Warrenville, IL Sheet 1 of 1Address

2. Plant Byron Nuclear Power Station Unit 02Name

4450 N. German Church Road, Byron, IL Work Order No. 01177789-15Address Repair Organization, P.O. No., Job No., etc.

3. Work Performed by ShawlStone & Webster Type Code Symbol Stamp Not ApplicableName Authorization No. Not Applicable

36400 S. Essex Road, Wilmington, IL 60481 Expiration Date Not ApplicableAddress

4. Identification of System PRIMARY CONTAINMENT VENTILATION (VP)

5. (a) Applicable Construction Code ASME Sec. III Piping 19 74 Edition, S75 Addenda, N/A Code Case(a) Applicable Construction Code ASME Sec. III Cooler 19 74 Edition, S76 Addenda, 1695-1 Code Case(b) Applicable Edition of Section XI Used for Repair/Replacement Activity 2001 Edition / 2003 Addenda(c) Section XI Code Case(s) NONE

6. Identification of Components

ASMECorrected, Code

National Removed, or StampedName of Name of Manufacturer Board Other Year Installed (Yes or No)

Component Manufacturer Serial No. No. Identification Built2VP01AB,

HEAD BOLT, 2 CARRIER Cooer S/N# N/A SX-RH-5 1978 Removed NOx 4 /", SA449 7865406-1 Bolt# 7, 10, 24,

25, 48, 53, 54, 632VP01AB,

Screw, Hex, Wx NOVA HT# SX-RH-54Scre, HA193IB7 MACHINE US Y06420 N/A Bolt# 7, 10, 24, 2010 Installed NO

25, 48, 53, 54, 63CID# 46596-1

7. Description of WorkRIGHT BANK

INSTALLED NEW COOLER HEAD BOLTING

8. Test Conducted: Hydrostatic C0 Pneumatic 0] Nominal Operating Pressure 0 Exempt E0

Other 0 Pressure 100 psi Test Temp. 68 °F

Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8½ in. x 11 in., (2)information in items I through 6 on this report is included on each sheet, and (3) each sheet is numbered and thenumber of sheets is recorded at the top of this form.

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FORM NIS-2 (Back)

9. Remarks WO# 01177789-15 ;12UApplicable Manufacturer's Data Reports to be attached

Bolt acceptable per Technical Evaluation 97-01.4

CERTIFICATE OF COMPLIANCEI certify that the statements made in the report are correct and this conforms to the requirements of the ASME

Code, Section XA.Type Code Symbol Stamp Not ApplicableCertificate of Authorizatio o. Not ApplicableSigned _. /Q F Date 7-Z.. , 20 10

(•yr Owner's Designee, Title

CERTIFICATE OF INSERVICE INSPECTIONI, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure

Vessel Inspectors and the State or Province of IllInois and employed by HSB CT Al

of Ha ord, CT havep spected the components described in this Owner's Report during the period

to 71.,01,0 , and state that to the best of my knowledge and belief,

the 6wner has perfored examinations and taken corrective measures described in this Owner's

Report in accordance with the requirements of the ASME Code, Section Xl.By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or

implied, concerning the examinations and corrective measures described in this Owner's Report.Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal

injury or property d piage or a loss of any kind arising from or connected with this inspection.

Commissions /'1 ./,.i"Inspector's Signature

Date: , 20 10

National Board, State Province, and Endorsements

(Final

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DOCUMENT NO.: 7.2 REV. NO.: 0

FORM NIS-2 OWNER'S REPORT FOR REPAIRIREPLACEMENT ACTIVITYAs Required by the Provisions of the ASME Code Section Xl

Owner Exelon Nuclear Date 4/30/10Name

4300 Wlnfleld Road, Warrenville, IL Sheet 1 of 1Address

2. Plant Byron Nuclear Power Station Unit 02Name

4450 N. German Church Road, Byron, IL Work Order No. 01177830-01Address Repair Organization, P.O. No., Job No., etc.

3. Work Performed by Shaw/Stone & Webster Type Code Symbol Stamp Not ApplicableName Authorization No. Not Applicable

36400 S. Essex Road, Wilmington, IL 60481 Expiration Date Not ApplicableAddress

4. Identification of System WO (CHILLED WATER)

5. (a) Applicable Construction Code ASME Section III 19 74 Edition, S76 Addenda, N/A Code Case(b) Applicable Edition of Section XI Used for Repair/Replacement Activity 2001 Edition / 2003 Addenda(c) Section X1 Code Case(s) NONE

6. Identification of Components

ASMECorrected, Code

National Removed, or StampedName of Name of Manufacturer Board Other Year Installed (Yes or No)

Component Manufacturer Serial No. No. Identification Built

STUD AndersonSTUD____Geewo MK#: HG-2 N/A 2WO007B 1979 REMOVED NOGreenwood

STUD Nova Ht# 250832 N/A 2WO007BCAT ID # 37096-1 '4 INSTALLED NO

NUT Anderson MK#: HG-1 N/A 2WO007B 1979 REMOVED NOGreenwood

NUT Nova Ht# 251919 N/A 2WA 007B INSTALLED NO_________ _________ _________CAT I D # 37033-1 A~~ISALD N

7. Description of Work INSTALLED STUDS AND NUTS

8. Test Conducted: Hydrostatic [I Pn

Other E] Pressure

eumatic [j Nominal Operating Pressure El

psi Test Temp.

Exempt 59OF

Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 81/2 in. x 11 in., (2)information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the numberof sheets is recorded at the top of this form.

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FORM NIS-2 (Back)

9. Remarks W.O. 01177830-01Applicable Manutacturers Data Reports to be attached

CERTIFICATE OF COMPLIANCEI 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 Not ApplicableCertificate of Authorization No. Not ApplicableSigned Date .20 10

" - -- Owner's Designee, Title

CERTIFICATE OF INSERVICE INSPECTION1, the undersigned, holding a valid commission issued by the National Board of Boiler and PressureVessel Inspectors and the State or Province of Illinois and employed by HSB CTof Hlrtfd, CT have isp ted the components described in this Owner's Report during the period

ý411", to , and state that to the best of my knowledge and belief,the Owner has performed eiaminations and taken corrective measures described in this Owner'sReport 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 orimplied, concerning the examinations and corrective measures described in this Owner's Report.Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personalinjury or property damage or a loss of any kind arising from or connected with this inspection.61•21.4 Zy' l Commissions Aý r/ -,/W 5 'I"

Insectr: Signatur ,0e 1 National Board, State Province, and Endorsements

Date: Q&rý/ 20 10

(Final)

(Al

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DOCUMENT NO.: 6A REV. NO.: 0

FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITYAs Required by the Provisions of the ASME Code Section Xl

1. Owner Exelon Nuclear Date 04/26110Name

4300 Winfield Road, Warrenville, IL Sheet 1 of 1Address

2. Plant Byron Nuclear Power Station Unit 02Name

4450 N. German Church Road, Byron, IL Work Order No. 01177875-01Address Repair Organization, P.O. No., Job No., etc.

3. Work Performed by Byron Mechanical Type Code Symbol Stamp Not ApplicableMaintenance

Name; Authorization No. Not Applicable4450 N. German Church Road, Byron, IL Expiration Date Not Applicable

Address

4. Identification of System CV CHEMICAL AND VOLUME CONTROL

5. (a) Applicable Construction Code ASME Section III 19 71 Edition, W72 Addenda, N/A Code Case(b) Applicable Edition of Section XI Used for Repair/Replacement Activity, 2001 Editioni2003 Addenda(c) Section XI Code Case(s) N/A

6. Identification of Components

ASMECorrected, Code

National Removed, or StampedName of Name of Manufacturer Board Other Year Installed (Yes or No)

Component Manufacturer Serial No. No. Identification BuiltVALVE SEAL984TRWELD KEROTEST ADF6-14 9854 THRU 2CV8480A 1976 Corrected NO

WELD____ ______ ______ 9857 ____ _____

7. Description of Work Re-installed seal weld between cover and body

8. Test Conducted: Hydrostatic El Pn

Other F1 Pressure

eumatic El Nominal Operating Pressure El__psi Test Temp. _

Exempt 0

Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 81/2 in. x 11in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numberedand the number of sheets is recorded at the top of this form.

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FORM NIS-2 (Back)

9. Remarks WO# 01177875-01 "Applicable Manufacturer's Data Reports to be attached

CERTIFICATE OF COMPLIANCEI 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 Not ApplicableCertificate A Authorization No. Not Applicable

Signed (J A 'AJ A.,4A , g& )d /AJDWA3I1-- Date .- 20 10Owner or Owner's Designee, Title

CERTIFICATE OF INSERVICE INSPECTIONI, the undersigned, holding a valid commission issued by the National Board of Boiler and PressureVessel Inspectors and the State or Province of Illinois and employed by HSB CTof Hartford, CT have i spected the components described in this Owner's Report during the period

tO to .,ýg , and state that to the best of my knowledge and belief,'h6 Owner has performerd•6xaminations and taken corrective measures described in this OwnersReport 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 measures described in this Owner's Report.Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personalinjury or property damap or a loss of any kind arising from or connected with this inspection.

___ ,___________Commissions 1Z1-/L.E5(4 . Inspector's Signature National Board, State Province, and Endorsements

Date: .... , . ,20 Wl,#

r ,

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DOCUMENT NO.: 3.2 REV. NO.: 0

FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITYAs Required by the Provisions of the ASME Code Section XI

1. Owner Exelon Nuclear Date 04/14/10Name

4300 WInfield Road, Warrenville, IL Sheet 1 of 1Address

2. Plant Byron Nuclear Power Station Unit 02Name

4450 N. German Church Road, Byron, IL Work Order No. 01177885-01/02Address Repair Organization, P.O. No., Job No., etc.

3. Work Performed by Shaw/Stone & Webster Type Code Symbol Stamp Not ApplicableName Authorization No. Not Applicable

36400 S. Essex Road, Wilmington, IL 60481 Expiration Date Not ApplicableAddress

4. Identification of System SI

5. (a) Applicable Construction Code ASME Section III 19 71 Edition, W172 Addenda, Code Case(b) Applicable Edition of Section XI Used for Repair/Replacement Activity 2001 Edition / 2003 Addenda(c) Section XI Code Case(s) NONE

6. Identification of Components

ASMECorrected, Code

National Removed, or StampedName of Name of Manufacturer Board Other Year Installed (Yes or No)

Component Manufacturer Serial No. No. Identification Built

VALVE, RELIEF CROSBY VALVE N56902-00-0015 N/A 2SI8856A 1976 Removed YES_____ _____ & GAGE __ _ _ _ ___ _ _ _ ___ _ _ __ _ _ _ _

VALVE, RELIEF CROSBY VALVE N56902-00-0016 N/A 2SI8856A 1973 Installed YESVALV, RLIE & GAGE N590-0-01 CAT ID 27740-1 1973 _nstalle YES

7. Description of Work REPLACE RELIEF VALE 2SI8856A PER PM PROGRAM

8. Test Conducted: Hydrostatic C] Pneumatic C] Norn

Other C1 Pressure 181 psi

iinal Operating Pressure 0 Exempt C0

Test Temp. 86 OF

Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8½ in. x 11 in., (2)information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the numberof sheets is recorded at the top of this form.

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FORM NIS-2 (Back)

9. Remarks 01177885-01/02 ,Applicable Manufacturers Data Reports to be attached

CERTIFICATE OF COMPLIANCEI 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 Not Applicable

Certificate ,uthoriz • Not Applicable

Signed .- _"_"_._OR _____,_121" ý Date :"-,Q,7 20 10

Owner or Owner's Designee, Title

CERTIFICATE OF INSERVICE INSPECTIONI, the undersigned, holding a valid commission issued by the National Board of Boiler and PressureVessel Inspectors and the State or Province of Illinois and employed by HSB CTýof HartfTord, CT have insp cted the components described in this Owners Report during the period

to ,and state that to the best of my knowledge and belief,

tK(eOner has performedlxaminations and taken corrective measures described in this Owner'sReport 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 orimplied, concerning the examinations and corrective measures described in this Owner's Report.Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personalinjury or property damage or a loss of any kind arising from or connected with this inspection.

---•t-- Commissions AZ - /"yInspector's Signature 9" •l National Board, State Province, and Endorsements

Date: 20••62 '

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DOCUMENT NO.: 3.2 REV. NO.: 0

FORM NIS-2 OWNER'S REPORT FOR REPAIRIREPLACEMENT ACTIVITYAs Required by the Provisions of the ASME Code Section XI

1. Owner Exelon NuclearName

4300 Winfield Road, Warrenville, ILAddress

2. Plant Byron Nuclear Power StationName

.4450 N. German Church Road, Byron, ILAddress

3. Work Performed by Shaw/Stone & WebsterName

36400 S. Essex Road, Wilmington, IL 60481Address

Date 4-25-10

Sheet 1 of 1

Unit 02

Work Order No. 01178701-01/02Repair Organization, P.O. No., Job No., etc.

Type Code Symbol Stamp Not ApplicableAuthorzation No. Not ApplicableExpiration Date Not Applicable

4. Identification of System CV - CHEMICAL VOLUME CONTROL

5. (a) Applicable Construction Code ASME Section III 19 71 Edition, W72 Addenda, 1649 Code Case(b) Applicable Edition of Section Xl Used for Repair/Replacement Activity 2001 Edition / 2003 Addenda(c) Section XI Code Case(s) NONE

6. Identification of Components

7. Description of Work REPLACED RELIEF VALVE 2CV8121 PER PM PROGRAM

8. Test Conducted: Hydrostatic [] Pneumatic [] Norr

Other 0 Pressure 49 psi

iinai Operating Pressure 0 Exempt [I

Test Temp. 71 °F

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

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FORM NIS-2 (Back)

9. Remarks 01178701-01/02Applicable Manufacturer's Data Reports to be attached

Valve pre-tested / evaluated on WO# 1178701-02

CERTIFICATE OF COMPLIANCEI 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 Not ApplicableCertificate of Authogzation No. Not ApplicableSigned Date -. , 20 10

er Owner's Designee, Title

CERTIFICATE OF INSERVICE INSPECTIONI, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure

Vessel Inspectors and the State or Province of Illinois rand employed by HSB CT

of Hartford, CT have inspected the components described in this Owner's Report during the period

to , , and state that to the best of my knowledge and belief,

the 0•ner 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 orimplied, concerning the examinations and corrective measures described in this Owner's Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal

injury or property d-age or a loss of any kind arising from or connected with this inspection.

Commissions /1/z- 1",vC" Inspector's Signature

Date: . , .Afj, , . ,20 10

National Board, State Province, and Endorsements

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DOCUMENT NO.: 3.2 REV. NO.: 0

FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITYAs Required by the Provisions of the ASME Code Section XI

1. Owner Exelon Nuclear Date 4-27-10Name

4300 Winfield Road, Warrenville, IL Sheet 1 of 1Address

2. Plant Byron Nuclear Power Station Unit 01Name

4450 N. German Church Road, Byron, IL Work Order No. 01178705-01/02Address Repair Oraization, P.O. No., Job No., etc.

3. Work Performed by Shaw/Stone & Webster Type Code Symbol Stamp Not ApplicableName Authorization No. Not Applicable

36400 S. Essex Road, Wilmington, IL 60481 Expiration Date Not ApplicableAddress

4. Identification of System CC (COMPONENT COOLING)

5. (a) Applicable Construction Code ASME Section III 19 71 Edition, S/72 Addenda, _Code Case(b) Applicable Edition of Section XI Used for Repair/Replacement Activity 2001 Edition / 2003 Addenda(c) Section XI Code Case(s) NONE

6. Identification of Components

ASMECorrected, Code

National Removed, or StampedName of Name of Manufacturer Board Other Year Installed (Yes or No)

Component Manufacturer Serial No. No. Identification Built

RELIEF VALVE CROSBY VALVE 5N2CC9427 1975 Removed YES2CC9427 & GAGE CO. N56895-00-0009 N/A

RELIEF VALVE CROSBY VALVE 2CC94272CC9427 & GAGE CO N56895-00-0004 N/A CAT ID 1442884-1 1973 Installed YES

7. Description of Work REPLACE RELIEF VALVE 2CC9427

8. Test Conducted: Hydrostatic [I Pr

Other El Pressure

aeumatic 0 Nominal Operating Pressure 0 Exempt 0122.5 psi Test Temp. 72 OF

Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8½ in. x 11 in., (2)information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the numberof sheets is recorded at the top of this form.

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FORM NIS-2 (Back)

9. Remarks WO 01178705-01/02Applicable Manufacturers Data Reports to be attached

- CERTIFICATE OF COMPLIANCEI certify that the statements made in the report are correct and this conforms to the requirements of the ASME

Code, Section Xl.Type Code Symbol Stamp Not ApplicableCertificate of, uthorization No. Not ApplicableSigned I "-, a/ AJiL4 k IQa &2Oq.1A,)M(V .. Date -.,,2 20 10

.w

Ownefor Owner's Designee. Title

CERTIFICATE OF INSERVICE INSPECTIONI, the undersigned, holding a valid commission issued by the National Board of Boiler and PressureVessel Inspectors and the State or Province of Illinois and employed by HSB CTof Hartford, CT have inspected the components described in this Owner's Report during the period

/,c4gggac to 'd,,edA , and state that to the best of my knowledge and belief,the Owner has performed examinations and taken corrective measures described in this Owner'sReport 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 orimplied, concerning the examinations and corrective measures described in this Owner's Report.Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personalinjury or property dapmage or a loss of any kind arising from or connected with this inspection.

ed• Commissions /L- ,IJ'•./Inspector's Signature

Date: 9 .A f, 20 le

National Board, State Province, and Endorsements

(Final)

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DOCUMENT NO.: 6A REV. NO.: 0

FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITYAs Required by the Provisions of the ASME Code Section Xl

1. Owner Exelon Nuclear Date 4-29-10Name

4300 Winfield Road, Warrenville, IL Sheet 1 of 1Address

2. Plant Byron Nuclear Power Station Unit 02Name

4450 N. German Church Road, Byron, IL Work Order No. 01178734-01Address Repair Organization, P.O. No., Job No., etc.

3. Work Performed by Byron Mechanical Type Code Symbol Stamp Not ApplicableMaintenance

Name Authorization No. Not Applicable4450 N. German Church Road, Byron, IL Expiration Date Not Applicable

Address

4. Identification of System CV CHEMICAL AND VOLUME CONTROL

5. (a) Applicable Construction Code ASME Section III 19 71 Edition, W72 Addenda, N/A Code Case(b) Applicable Edition of Section XI Used for Repair/Replacement Activity: 2001 Edition/2003 Addenda(c) Section XI Code Case(s) N/A

6. Identification of Components

ASMECorrected, Code

National Removed, or StampedName of Name of Manufacturer Board Other Year Installed (Yes or No)

Component Manufacturer Serial No. No. Identification BuiltVALVE SEALWELD KEROTEST N01 -21 9536 2CV8368C 1976 REMOVED NO

VALVE SEAL KEROTEST N01 -21 9536 2CV8368C 1976 INSTALLED NOWELD __ _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _ _ _ _ _

7. Description of Work REMOVE / REWELD VALVE SEAL WELD (COVER TO BODY)

8. Test Conducted: Hydrostatic C] Pneumatic 0] Nominal Operating Pressure 0 Exempt C0

Other E] Pressure 950 psi Test Temp. 110 OF

Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 81/2 in. x 11in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numberedand the number of sheets is recorded at the top of this form.

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FORM NIS-2 (Back)

9. Remarks WO# 01178734-01Applicable Manufacturer's Data Reports to be attached

CERTIFICATE OF COMPLIANCEI 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 Not Applicable

Certificate of Authorization No. Not Applicable

Signed _.- Z Date .- Z- ,20 10Owner or er's Designee, Title

CERTIFICATE OF INSERVICE INSPECTION

I, the undersigned, holding a valid commission issued by the National Board of Boiler and PressureVessel Inspectors and the State or Province of Illinois and employed by HSB CT

of H-artrd, CT have sp cted the components described in this Owner's Report during the period

to _________ , and state that to the best of my knowledge and belief,

the O4ner has performed examinations and taken corrective measures described in this Owner'sReport 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 orimplied, concerning the examinations and corrective measures described in this Owner's Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal

injury or property damane or a loss of any kind arising from or connected with this inspection.

_________________Commissions //Zt - 'Z5F Inspector's Signature National Board, State Province, and Endorsements

Date: ,20 10

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DOCUMENT NO.: 4.2 REV. NO.: 0-_I

FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITYAs Required by the Provisions of the ASME Code Section Xi

1. Owner Exelon Nuclear Date 4/24/10Name

4300 Winfield Road, Warrenville, IL Sheet 1 of 1Address

2. Plant Byron Nuclear Power Station Unit 01Name

4450 N. German Church Road, Byron, IL Work Order No. 01178737-01/02Address Repair Organization, P.O. No., Job No., etc.

3. Work Performed by Shaw/Stone & Webster Type Code Symbol Stamp Not ApplicableName Authorization No. Not Applicable

36400 S. Essex Road, Wilmington, IL 60481 Expiration Date Not ApplIcableAddress

4. Identification of System RY - REACTOR COOLANT

5. (a) Applicable Construction Code ASME Section III 1971 Edition, W72 Addenda, 1501 & 1649 Code Case(b) Applicable Edition of Section Xl Used for Repair/Replacement Activity 2001 Edition / 2003 Addenda(c) Section Xl Code Case(s) NONE

6. Identification of Components

ASMECorrected, Code

National Removed, or StampedName of Name of Manufacturer Board Other Year Installed (Yes or No)

Component Manufacturer Serial No. No. Identification Built

VALVE, RELIEF CROSBY VALVE N56964-00-0111 N/A 2RY801OC 1993 REMOVED YES

VALVE, RELIEF CROSBY VALVE N56964-00-0049 N/A 1 RY8010C 1976 INSTALLED YESCat ID 1402762-1 1976 INSTALLED YES

7. Description of Work REPLACED RELIEF VALVE PER PM PROGRAM

8. Test Conducted: Hydrostatic C] Pneumatic C] Norm

Other El Pressure 2229 psi

inal Operating Pressure 0 Exempt C0

Test Temp. 651 °F

Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 81/2 in. x 11 in., (2)information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the numberof sheets is recorded at the top of this form.

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FORM NIS-2 (Back)

9. Remarks 01178737-01/02 tApplicable Manufacturer's Data Reports to be attached

CERTIFICATE OF COMPLIANCEI 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 Not ApplicableCertificate of Authorin ation No. Not ApplicableSigned - Date ,20 10

er Owner's Designee, Title

CERTIFICATE OF INSERVICE INSPECTIONI, the undersigned, holding a valid commission issued by the National Board of Boiler and PressureVessel Inspectors and the State or Province of Illinois and employed by HSB CT

of Has ford, CT have in pec ed the components described in this Owner's Report during the period:X to sCa' - 4 ,e , and state that to the best of my knowledge and belief,tKe Owner has performed examinations and taken corrective measures described in this OwnersReport 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 orimplied, concerning the examinations and corrective measures described in this Owners Report.Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personalinjury or property dargag or a loss of any kind arising from or connected with this inspection.

____•_ _•_•f______Commissions /A',( -

.. Inspectr's Signature National Board, State Province, and Endorsements

Date: (df, ,20 1001-

(Final)

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DOCUMENT NO.: 2-1 REV. NO.: 0

FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITYAs Required by the Provisions of the ASME Code Section XI

1. Owner Exelon Nuclear Date 5-4-10Name

4300 Wlnfleld Road, Warrenville, IL Sheet 1 of IAddress

2. Plant Byron Nuclear Power Station Unit 2Name

4460 N. German Church Road, Byron, IL Work Order No. 01180527-02Address- Repair Organization, P.O. No., Job No., etc.

3. Work Performed by Byron Mechanical Type Code Symbol Stamp Not ApplicableMaintenance

Name Authorization No. Not Applicable4460 N. German Church Road, Byron, IL Expiration Date Not Applicable

Address

4. Identification of System RC-Reactor Coolant

5. (a) Applicable Construction Code ASME Section III 19 74 Edition, S/75 Addenda, N/A Code Case(b) Applicable Edition of Section XI Used for Repair/Replacement Activity: 2001 EdItIonI2003 Addenda(c) Section XI Code Case(s) N/A

6. Identification of Components

ASMECorrected, Code

National Removed, or StampedName of Name of Manufacturer Board Other Year Installed (Yes or No)

Component Manufacturer Serial No. No. Identification Built

Studs Bethlehem Heat Code: W-77 on(Qty. 2)3/4"-10, Steel Corp. LIFU N/A 2RC23AB-3/4 1981 Removed NoSA 193 Gr. BIB Oriainal Const.

Studs Com Ed UTC Nbr: MJ-77(Qty. 2)31V-10, 0002039994 WO 9M9e70e43-01SA 193 Gr. B7 Ht. Code: N/A under DCP to install 1999 Removed No

____ __ _____ support 2RC02009G

Studs Nova Machine HT #3001306 MJ-77 on(Qty. 4) 34-i-10, Prod. Trace Code N/A 2RC23AB-3/4" 2009 Installed NoSA 193 Gr. B7 .. 3T22 Cat Id# 37094-1

Nuts Bethlehem Heat Code: MJ-77 on(Oty. 2) 3/40-I0, Steel Corp. LICJ N/A 2RC23AB-3/4" 1981 Removed No

SA 194 Gr. 4 Orlginal Const.Nuts Corn Ed UTC Nbr. MJ-77

(Oty. 2) 3/4-10, 000204623 WO 990070543-01SA 194 Gr. 2H Ht. Code: JNC N/A under DCP to Install 1999 Removed No

_ support 2RC02009G

Nuts Nova Machine HT# 241436 MJ-77 on X(Oty. 4) 314-"-0, Prod. N/A 2RC23AB-3/4" 2008 Installed NoSA 194 Gr. 2H _ Cat Id# 1394886-1 1 - - I

7. Description of Work Replaced worn flange bolting.

8. Test Conducted: Hydrostatic [I Pneumatic 0 Nor

VT-1 Other 0 Pressure _ _ psi

iinal Operating Pressure [I Exempt ED

Test Temp. °_OF

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

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FORM NIS-2 (Back)

9. Remarks WO# 01180527-02 '•NApplicaole Manufacturers 0a5a Repons to De attacned

CERTIFICATE OF COMPLIANCEI certify that the statements made in the report are correct and this conforms to the requirements of the ASME

Code, Section Xl.Type Code Symbol Stamp Not ApplicableCertificate of Authorization No. Not ApplicableSigned g-- Date 7-/ ,20 10

Owns or Owner's Designee, litle

CERTIFICATE OF INSERVICE INSPECTIONI, the undersigned, holding a valid commission issued by the National Board of Boiler and PressureVessel Inspectors and the State or Province of Illinois and employed by HSB CT

Of A~ar2rd, CT havesected the components described in this Owner's Report during the period"yf 1Ato aA//v , and state that to the best of my knowledge and belief,

16 Owner has performed xaminations 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 orimplied, concerning the examinations and corrective measures described in this Owner's Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal

injury or property dama• or a loss of any kind arising from or connected with this inspection.

___ Commissions i/LL40 -/e Inspector's Signature

Date: -Q g X ,20 10National Board, State Province, and Endorsements

ý JAI

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DOCUMENT NO.: 3A REV. NO.: 0

FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITYAs Required by the Provisions of the ASME Code Section Xl

1. Owner Exelon Nuclear Date 01///oName I f

4300 Winfleld Road, Warrenville, IL Sheet 1 of IAddress

2. Plant Byron Nuclear Power Station Unit 02Name

4450 N. German Church Road, Byron, IL Work Order No. 01180530-01Address Repair Organization, P.O. No., Job No., etc.

3. Work Performed by Byron Mechanical Type Code Symbol Stamp Not ApplicableMaintenance

Name Authorization No. Not Applicable4450 N. German Church Road, Byron, IL Expiration Date Not Applicable

Address

4. Identification of System RC REACTOR COOLANT

5. (a) Applicable Construction Code ASME Section III 19 74 Edition, S75 Addenda, N/A Code Case(b) Applicable Edition of Section XI Used for Repair/Replacement Activity: 2001 Editlon/2003 Addenda(c) Section Xl Code Case(s) N/A

6. Identification of Components

ASMECorrected, Code

National Removed, or StampedName of Name of Manufacturer Board Other Year Installed (Yes or No)

Component Manufacturer Serial No. No. Identification BuiltSTUD Bethlehem HT# 8087874. 2RC76A 1981 REMOVED NO

Steel HT Code LIEK N/A_1981___REMOVEDNOTHREADED ROD Nova Machine HT# 75262621 N/A CAT ID# 44337-1 2006 INSTALLED NO

Products HT CD 281C N/A 2006 INSALLD NNUT Bethlehem HT# 65589 N/A 2RC76A

Steel HT Code LIBP N/A_1981 REMOVED NO

NUT Nova Machine HT# Q2280A- t CAT ID# 30520-1Products N/A 2007 INSTALLED NO

7. Description of Work REPLACE FLANGE STUDS AND NUTS.

8. Test Conducted: Hydrostatic [] Pneumatic [] Nominal Operating Pressure [] Exempt 0"

Other C] Pressure psi Test Temp.

Note: Supplemental sheets in form of lists, sketches, or drawingsmay be used, provided (1) size is 81/2 in. x 11in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numberedand the number of sheets is recorded at the top of this form.

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FORM NIS-2 (Back)

9. Remarks WO# 01180530-01~ppiicable manuiacturer s uai 1leporrs to be auacnieu v

CERTIFICATE OF COMPLIANCEI 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 Not Applicable

Certificate of Autorization No. Not ApplicableSigned 7- " z'p Date &/// ,20 /

6" •'C(: Owners Designee, Title .F

CERTIFICATE OF INSERVICE INSPECTIONI, the undersigned, holding a valid commission issued by the National Board of Boiler and PressureVessel Inspectors and the State or Province of Illinois and employed by HSB CTof Hytford, CT have inspcted the components described in this Owner's Report during the period

4// to /n ,dstate that to the best of my knowledge and belief,te 6wner has performed e•aminations and taken corrective measures described in this Owner'sReport 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 orimplied, concerning the examinations and corrective measures described in this Owner's Report.Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personalinjury or property damage or a loss of any kind arising from or connected with this inspection.

Commissions /zz/- .0-ý'4Inspector's Signature

Date: 9! // 20 . .

National Board, State Province, and Endorsements

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ý DOCUMENT NO.: 3.2 REV. NO.: 0 1

F DOCUMENT NO.: 3.2 REV.NO.: 0

FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITYAs Required by the Provisions of the ASME Code Section Xl

1. Owner Exelon Nuclear Date Z-'513O

2.

Name4300 WInfleld Road, Warrenville, IL

AddressPlant Byron Nuclear Power Station

Name4450 N. German Church Road, Byron, IL

Address

Sheet 1 of 1

Unit 02

Work Order No. 01199605-01Repair Organization, P.O. No., Job No., etc.

3. Work Performed by Shaw/Stone & WebsterName

36400 S. Essex Road. Wllmlnaton. IL 60481

Type Code Symbol Stamp Not ApAuthorization No. Not ApplicableExpiration Date Not Applicable

pllcable

Address

4. Identification of System RC

5. (a) Applicable Construction Code ASME Section 1II 19 71 Edition, $72* Addenda, ** Code Case(b) Applicable Edition of Section XI Used for Repair/Replacement Activity 2001 Edition / 2003 Addenda(c) Section XI Code Case(s) NONE

6. Identification of Components

ASMECorrected, Code

National Removed, or StampedName of Name of Manufacturer Board Other Year Installed (Yes or No)

Component Manufacturer Serial No. No. Identification BuiltBolt, Primary Ht Code: J940 2RC01BA/MJ149BManway, 1.875" x Nova Machine Ht#: 2M34637 N/A Bolt # 13 2004 Removed No7.500(

Bolt, Primary Ht Code: J940 2RCO1BA/MJ149BManway, 1.875" x Nova Machine Ht#: 2M34637 N/A Bolt # 13 2005 Installed No7500,"

7. Description of Work Replaced Primary Manway Bolt

8. Test Conducted: Hydrostatic [3 Pn

Other E] Pressure

eumatic 0 Nominal Operating Pressure El Exempt 0OFpsi Test Temp.

Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8V2 in. x 11 in., (2)information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the numberof sheets is recorded at the top of this form.

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FORM NIS-2 (Back)

9. Remarks WO# 01199605-01Applicable Manufacturer's Data Reports to be attached

W74 for NB-2331(D), NB2332(A)(2), NB-4334, 4334.1& 4334.2, NB-4335.1, NB-4335.2, & NB-4335.3

1355, 1493-1, 1484,1528

CERTIFICATE OF COMPLIANCEI certify that the statements made in the report are correct and this conforms to the requirements of the ASME

Code, Section Xl.Type Code Symbol Stamp Not ApplicableCertificate of Authorization No. Not ApplicableSigned , ,5z1,4 zl C ob., Date ,/7 ,20 10

a~mer or Owneres Designee, Title

CERTIFICATE OF INSERVICE INSPECTIONI, the undersigned, holding a valid commission issued by the National Board of Boiler and PressureVessel Inspectors and the State or Province of Illinois and employed by HSB CTof Ha!3!ord, CT have ipsp~cted the components described in'this Owner's Report during the period

_'to ., , and state that to the best of my knowledge and belief,tle Owner has performed examinations and taken corrective measures described in this Owner'sReport 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 orimplied, concerning the examinations and corrective measures described in this Owner's Report.Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personalinjury or a loss of any kind arising from or connected with this inspection._______________Commissions &/. /AX_''ae Inspector's Signature National Board, State Province, and Endorsements

Date: ( f, /)--o ,,20 10

(Final)

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DOCUMENT NO.: 2.2 REV. NO.: 0

FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITYAs Required by the Provisions of the ASME Code Section XI

1. Owner Exelon Nuclear Date 5/1/10Name

4300 Winfield Road, Warrenville, IL Sheet 1 of 1Address

2. Plant Byron Nuclear Power Station Unit 02Name

4450 N. German Church Road, Byron, IL Work Order No. 01199606-02Address Repair Organization, P.O. No., Job No., etc.

3. Work Performed by Westinghouse Electric Co. Type Code Symbol Stamp Not ApplicableName Authorization No. Not Applicable

PO Box 158, Madison, PA 15663 Expiration Date Not ApplIcableAddress

4. Identification of System REACTOR COOLANT (RC)

5. (a) Applicable Construction Code ASME Section III 19 71 Edition, S72/W74 * Addenda, ** Code Case(b) Applicable Edition of Section Xl Used for Repair/Replacement Activity 2001 Edition / 2003 Addenda(c) Section XI Code Case(s) NONE

6. Identification of Components

ASMECorrected, Code

National Removed, or StampedName of Name of Manufacturer Board Other Year Installed (Yes or No)

Component Manufacturer Serial No. No. Identification BuiltHT# 2RC01BB

Mechanical Tube NX3188HK NA S/N 2096 2002 Installed NOPlug Westinghouse Lot 11 Row 7

CAT ID 45093 Col. 7

7. Description of Work INSTALL MECHANICAL TUBE PLUGS IN THE 2B SG.

8. Test Conducted: Hydrostatic (I

Other El Pr

Pneumatic E] Nominal Operating Pressure [] Ex(

psi Test Temp. n/a

9mpt0

OFessure n/a

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

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FORM NIS-2 (Back)

9. Remarks 01199606-02Applicable Manufacturer's Data Reports to be attached

W74 for NB-2331(D), NB-2332(A)(2), NB-4332, NB-4334, 4334.1& 4332.2, NB-4335, NB-4335.1, NB-4335.2. & NB-4335.3

_6

** 1355, 1493-1, 1484, 1528, NB-4643

Mechanical tube plugs fabricated to ASME Section III 1989 Edition No Addenda with Code Case N-474-1.

CERTIFICATE OF COMPLIANCEI 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 Not ApplicableCertificate of Authoriz ti No. Not ApplicableSigned _ __ __ __Date (/ ,20 10

Owner or/Swners Designee, Title

CERTIFICATE OF INSERVICE INSPECTIONI, the undersigned, holding a valid commission issued by the National Board of Boiler and PressureVessel Inspectors and the State or Province of Illinois and employed by HSB CTof laro•rd, CT have in pec: d the components described in this Owners Report during the period

.?// h P to -7./,0 / , and state that to the best of my knowledge and belief,the Oner has perform id exdminations and taken corrective measures described in this Owner'sReport 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 orimplied, concerning the examinations and corrective measures described in this Owner's Report.Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personalinjury or prperty damage or'ass of any kind arising from or connected with this inspection.

a~zwm;ý01 IelrCommissions

4.

Inspector's Signature

Date: 20 10

National Board, State Province, and Endorsements

(Final)

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DOCUMENT NO.: 3.1 REV. NO.: 0

FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITYAs Required by the Provisions of the ASME Code Section XI

1. Owner Exelon Nuclear Date 4-29-10Name

4300 Winfield Road, Warrenville, IL Sheet 1 of 1Address

2. Plant Byron Nuclear Power Station Unit 02Name

4450 N. German Church Road, Byron, IL Work Order No. 01212449-01Address Repair Organization, P.O. No., Job No., etc.

3. Work Performed by Shaw/Stone & Webster Type Code Symbol Stamp Not ApplicableName Authorization No. Not Applicable

36400 S. Essex Road, Wilmington, IL 60481 Expiration Date Not ApplicableAddress

4. Identification of System MS (MAIN STEAM)

5. (a) Applicable Construction Code ASME Section 1II 19 74 Edition, na Addenda, Code Case(b) Applicable Edition of Section XI Used for Repair/Replacement Activity 2001 Edition / 2003 Addenda(c) Section XI Code Case(s) NONE

6. Identification of Components

ASMECorrected, Code

National Removed, or StampedName of Name of Manufacturer Board Other Year Installed (Yes or No)

Component Manufacturer Serial No. No. Identification Built

SAFETY VALVE, 6", DRESSER BU01479 N/A 2MS013C 1978 Removed YES1500# INDUSTRIES

SAFETY VALVE. 6", DRESSER 2MS013C1500# !INDUSTRIES DA27376 N/A 2009 installed YES______ _ INDUSTRIE Cat ID 1442243-1

STUD, 1-3/8" TEXAS BOLT TRACE#LR7 N/A 2MS013C 1981 REMOVED NOSA193 B7 HT# 8898128

( STUD, 1-3/8" NOVA TRACE #SA193 B7 MACHINE E382 N/A 2MS013C 2002 INSTALLED NO

HT#13853 CAT ID 37106-1NUT, 1-3/8 TEXAS BOLT TRACE#LRB N/A 2MS013C 1981 REMOVED NOSA194 2H HT# 2D9355

TRACE#NUT, 1-3/8 NOVA 438C N/A 2MS013C 2007 INSTALLED NOSA194 2H MACHINE HT# CAT ID 1394991 -1

11557520

7. Description of Work REPLACE RELIEF VALVE / REPLACED ONE STUD AND TWO (2) NUTS

Test Conducted: Hydrostatic [I Pn

Other El Pressure

eumatic [] Nominal Operating Pressure 0 Exempt El949.68 psi Test Temp. 651.78 OF

Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 81/2 in. x 11 in., (2)information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the numberof sheets is recorded at the top of this form.

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FORM NIS-2 (Back)

9. Remarks 01212454-01Applicable Manufacturer's Data Reports to be attached

CERTIFICATE OF COMPLIANCEI certify that the statements made in the report are correct and this conforms to the requirements of the ASME

Code, Section Xl.Type Code Symbol Stamp Not ApplicableCertificate o uthorizat)on No. Not ApplicableSigned !V =.4L( UA. ) /6.I.2 OWi'A&iAA'Y"9- Date ,Ž./ ,20 10

Owner-or Owner's Designee, Title

CERTIFICATE OF INSERVICE INSPECTIONI, the undersigned, holding a valid commission issued by the National Board of Boiler and PressureVessel Inspectors and the State or Province of Illinois and employed by HSB CTof Hartford, CT have insp cted the components described in this Owner's Report during the period

.to { , and state that to the best of my knowledge and belief,t~e O3wner has perforrned ex~aminations and taken corrective measures described in this OwnersReport 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 orimplied, concerning the examinations and corrective measures described in this Owner's Report.Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personalinjury or properdarnaj or a loss of any kind arising from or connected with this inspection.

Commissions //1/- l "/54Inspector's Signature

Date: •-el ,20 10National Board, State Province, and Endorsements

(Final)

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DOCUMENT NO.: 3.1 REV. NO.: 0

FORM NIS-2 OWNER'S REPORT FOR REPAIRIREPLACEMENT ACTIVITYAs Required by the Provisions of the ASME Code Section Xl

Owner Exelon Nuclear Date 4/29/10Name

4300 Winfield Road, Warrenville, IL Sheet 1 of 1Address

2. Plant Byron Nuclear Power Station Unit 01Name

4450 N. German Church Road, Byron, IL Work Order No. 01212462-01Address Repair Organization, P.O. No., Job No., etc.

3. Work Performed by Shaw/Stone & Webster Type Code Symbol Stamp Not ApplicableName Authorization No. Not Applicable

36400 S. Essex Road, Wilmington, IL 60481 Expiration Date Not ApplicableAddress

4. Identification of System MS (MAIN STEAM)

5. (a) Applicable Construction Code ASME Section III 19 74 Edition, na Addenda, Code Case(b) Applicable Edition of Section XI Used for Repair/Replacement Activity 2001 Edition / 2003 Addenda(c) Section Xl Code Case(s) NONE

6. Identification of Components

ASMECorrected, Code

National Removed, or StampedName of Name of Manufacturer Board Other Year Installed (Yes or No)

Component Manufacturer Serial No. No. Identification Built

SAFETY VALVE, 6",11500#

DRESSERINDUSTRIES BU01487 N/A 2MS015C 1978 Removed YES

SAFETY VALVE, 6", DRESSER 2MS01 5C11500# INDUSTRIES DA27375 N/A 2009 Installed YES______ _____ ______ ___ _ _____ Cat ID 1442238-1 _____

7. Description of Work REPLACE RELIEF VALVE

8. Test Conducted: Hydrostatic E] Pn

Other [] Pressure

eumatic [] Non"

949.68 psi

iinal Operating Pressure 0 Exempt [I

Test Temp. 651.78 OF

Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 81/2 in. x 11 in., (2)information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the numberof sheets is recorded at the top of this form.

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FORM NOS-2 (Back)

9. Remarks 01212452-01Applicable Manufacturer's Data Reports to be attached

CERTIFICATE OF COMPLIANCEI 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 Not ApplicableCertificate of4uthorization No. Not ApplicableSigned r -, &J"A 1A I e &.OoefVl/ A' Date A , 20 10

Owner or Owner's Designee, Title

CERTIFICATE OF INSERVICE INSPECTIONI, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure

Vessel Inspectors and the State or Province of Illinois and employed by HSB CT

of Hartford, CT have ipsppcted the components described in this Owner's Report during the period

a 7T/ _ to ,=/ , and state that to the best of my knowledge and belief,

Ge wner has performled dS/aminations and taken corrective measures described in this Owner'sReport 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 measures described in this Owner's Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal

injury or property dama e or a loss of any kind arising from or connected with this inspection.

Commissions 'z,./,- "/W, Inspector's Signature

Date: 1/.20 ,wre //6

National Board, State Province, and Endorsements

, 20 XWXO 9j2 A001

(Final)

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FORM NVR-1 REPORT OF REPAIR C3 REPLACEMENT Q3OF NUCLEAR PRESSURE RELIEF DEVICES

1. Work performed by: NWS Technologlee, LLC131 Venture Boulevard, Spartanburg.

Purchase Order 0SC 29306

458731

2. Work performed for Exelon Corporation, Byron Nuclar Station

3/4. Owner - name, address and Identification of nuclear power plant Exelon Corporation,Byron Nuclear Station 4450 N. German Church Road Byron IL 61010A

5. a: Repaired pressure relief device: Main Steam Eb: Name of manufacturer Consolidated / Dresserc: Identifying nos.

~afety Valve

3707R(MMp)

DA27375(mfWs S"N

n/a steam(NWe (senim) (size)

2009(yr.buiRt)

d: Construction Code: ASME Section III 197,(nerresed"Wivi/don) (edili

6. ASME Code Section Xl applicable for Inservice Inspection:

7. ASME Code Section Xl used for repairs, replacements:

8. Construction Code used for repairs, replacements:

4 n/a n/a) (addenda) (Cods Cases(s))

2001(edmon)2001

(ed9on)1974

(edftn)

2003(&*WW*)

2003(addendla)

n/a(addenda)

2(Cod. Class)

n/a(Code Case(s))

n/a(Code Case(s))

n/a(Code Case(s))

9. Design responsibiliftis: n/a10. Opening pressure: 1205 psig

Set-pressure adjustment made at NW'S Technologies, LLC using steam

(a 11. Description of work (Indude name and denrng number o replaoment pars): Disassembled, cleaned, inspected.lapped nozzle & passivated seat area, lapl and pre-oxidized the X750 disc, load tested the spring,

A -- * ýft @Rai atooassen'10180. towullau Vý11 W;WW1 W ai I

1Z. RIemarKs: Nvv- I reveler 41 1u-w. Nou i W • ,!' 'CEATIFICATE OF COMPLIANCE

I, Cesar V. Sierra certify that to the best of my knowledge and belief the statements made in thisreport are correct and the repair, modification or replacement of the pressure relief devices described aboveconforms to Section Xl of the ASME Code and the National Board Inspection Code "VRW and "NR" rules.National Board Certificate of Authorization No. 632 to use the "VR" stamp expires April 3, 2012.

Napn I Board Certificate of Authorization No. 81 to use th "NRO Stam expires April 9, 2012.NWS Technologies, LLC .Manger, CIA

Date Repair Organization T" I. . . . . ..

CERTIFICATE OF INSPECTIONI, Charles, F. Toegel Jr. holding a valid commission issued by The National Board of Boiler and PressureVessel Inspectors and certificate of competency issued by the jurisdiction of North Carolina and employedby Hartford Steam Boiler of CT of Hartford, CT have inspected the repair, modificationor replacement described In this report on f.A& Zo ip and state that to the best of my knowledge and belief,

this repair, modification or replacement has been completed In accordance with Section XI of the of the ASME

Code and the National Board Inspection Code 'VR" and "NR" rules.By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied,

concerning this repair, modification or replacement described In this reporL Futhernore, neither the undersigned

nor my employe" shall be liable in any manner for any personal injury, property damage or loss of any kindarising from or connectrm~ h s inspctx

S/jhf1 D 1~~ NO 0 462,A, N, INO17

19 ~35-4-5

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NWS Work Pitochnologe I

Valve Serial Number DA27375

rogression & Hold Point Checklist

POo. 458731 NWS Traveler # 10-.3

This block to be signed after Indicating hold points and prior to

AlmfloThis traveler has been reviewed and approved for use by:NWS QA-.C• S~a [f Wa

Construction Code: ASME Section: III Edition: 74 Addenda: nra CodeCase: n/aRepair Code: ASME Section: XI Edition: 2001 Addenda: 2003 CedeCase: n/a

This traeler has been reviewed aiff approved for use by-

This traveler has been reviewed and approved for use by:NWM (H,.SM ANI - ChadnTol

Work Step NMS NM QA NW8 NW AmiQA Witness ANt VItness

_ Hold Date/IniL Hold Datedlnlt.

This Is a new valve.

1. Receipt Inspection

2. Full disassembly (NWS-R-3 rev 7)3. Component inaspect n! _

4. Rea (Section XI) components Exenon Attachment s re / a5. Replace (Section Xl components (Exelon Attachment 5 reo'd) 7L of/ & LP- I" .'//* 7 , 0G. Lap and oxidize doe X750 disc (NWYS--2 Revt 0)

7. Lap and peaelvate nozzle seet (NWS-f.3 Rev 0).

S. Inspect Spring I Load Test Spring

9. Valve assembly

10. Set blowdown rings

11. Steam set-pressure certification testing (NWS-T-62 rev 1)

12. Steam seat thtness test.

13. Tighten compression screw locknut & torque seal '

14. Loclcwire, and seat ring pins and cap illwlZip A#15. Final Inspection LO~

16. Completion of Form NVR-1 1 f)( 10

.17. Apply name plate I___.

@

This block to be signed after completion of work:

This traveler has been reviewed and accepted by:

This traveler has been reviewed and accepted by:

N UaN r

1 ir I 5415

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NWS Cereificate of Conformancetechnologiesi of work performed for

131 Venture Boulevard ExelonSpartmnburg, SC 29306 Byron Nuclear StationPh: 864-587-7001 Purchase Order # 458731Fx: 864-587-9005

Valve Identification

Valve SIN: DA27375 Model Number. 3707R Main Steam

Set-Pressure: 1205 Dsic Valve OEM: Dresser NWS Traveler # 10-63Job Summary

This was a new valve which had not been installed at site.Repair. The valve was repaired under the NWS VR/NR programs. The X750 disc waslapped and oxidized disc prior to reuse. The nozzle seat was passivated after lapping.The spring was load tested with satisfactory results. Wear areas were cleaned asnecessary. All wear areas and contact points were lubricated prior to assembly.Initial Test* The valve was allowed to thermally stabilize at a holding pressure of -1000psig. A total of four lifts were done. No adjustments were required. The final two liftswere within the required as-left BYRON acceptance range of +1% of set-pressure.Final Seat Tightness Testing: Following set-pressure certification, system pressurewas maintained at 90%. No moisture was detected on a cold bar placed in the vicinityof the seats.All work was done by NWS personnel. An NWS test supervisor was present during alltesting. An HSB of CT reviewed documentation, witnessed nameplate installation, andcompleted an NVR-1 form.The valve was cleaned, sealed and packaged for return shipment.

Set-Pressure Certification Lifts (1193 to 1217 psig)Lift Date Time Set- Inlet Body Spring Ambient

Number Pressure Flange Can(PSIG) (°F) (°F) (°F) (LF)

63-0-3 4/7/10 10:25 1214 443 265 141 12463-0-4 4/7/10 10:32 1206 442 268 142 123

We certify that all work performed was in compliance with the referenced PO and othercorrespondence, NWS QA System Manual Rev. 4, NWS VR Program Rev. 7, NWS NRProgram Rev. 6, NWS Procedures and the documents referenced therein. All required testsand inspections have been performed and the results accepted. Documentation supporting thisCertificate of Conformance is available for review as applicable.

NWS Job Coordinator J1LP.uAlLZAP#-T.P.Nederostek - V.P. Operatlons'

Date: V / ?g /Id

Date: .gIjfjjQNWS Quality

- (;I" 1

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DOCUMENT NO.: 3.1 REV. NO.: 0

FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITYAs Required by the Provisions of the ASME Code Section Xl

1. Owner Exelon NuclearName

4300 Winfleld Road, Warrenville, IL

IDate 4/29/1 0

Sheet 1 of 1

2.Address

Plant Byron Nuclear Power StationName

4450 N. German Church Road, Byron, ILAddress

Unit 02

Work Order No. 01212454-01Repair Organization, P.O. No., Job No., etc.

3. Work Performed by Shaw/Stone & WebsterName

36400 S. Essex Road, Wilmington, IL 60481Address

Type Code Symbol Stamp Not ApAuthorization No. Not ApplicableExpiration Date Not Applicable

plicable

4. Identification of System MS (MAIN STEAM)

5. (a) Applicable Construction Code ASME Section Ill 19 74 Edition, na Addenda, Code Case(b) Applicable Edition of Section XI Used for Repair/Replacement Activity 2001 Edition / 2003 Addenda(c) Section Xi Code Case(s) NONE

6. Identification of Components

ASMECorrected, Code

National Removed, or StampedName of Name of Manufacturer Board Other Year Installed (Yes or No)

Component Manufacturer Serial No. No. Identification Built

SAFETY VALVE, 6", DRESSER BU01495 N/A 2MS017C1500# INDUSTRIES 1978 Removed YES

SAFETY VALVE, 6", DRESSER 2MS01 7C1500# INDUSTRIES BR09609 N/A 1977 Installed YES____ ___ ____ __ ____ ___ __ _ ___ ____ ___ ___ Cat ID 1439913-1

7. Description of Work -REPLACE RELIEF VALVE

8. Test Conducted: Hydrostatic E] Pn

Other 0 Pressure

eumatic E] Nominal Operating Pressure 0 Exempt 01949.68 psi Test Temp. 651.78 °F

Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 81/ in. x 11 in., (2)information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the numberof sheets is recorded at the top of this form.

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FORM NIS-2 (Back)

9. Remarks 01212454-01Applicable Manufacturer's Data Reports to be attached

CERTIFICATE OF COMPLIANCEI certify that the statements made in the report are correct and this conforms to the requirements of the ASME

Code, Section Xl.

Type Code Symbol Stamp Not Applicable

Certificate of Authorization No. Not Applicable

Signed CtUV, A .•C•WL W/• er''•4 (100I011YAMLO,- Date 4-P 20 10Owner'or Owner's Designee, Title

CERTIFICATE OF INSERVICE INSPECTION

I, the undersigned, holding a valid commission issued by the National Board of Boiler and PressureVessel Inspectors and the State or Province of Illinois and employed by HSB CT

of Hartford, CT have insp cted the components described in this Owner's Report during the period

to Yo,, a , and state that to the best of my knowledge and belief,

the Owner has perform d 12xaminations 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 measures described in this Owner's Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal

injury or property damage or a loss of any kind arising from or connected with this inspection.

541# ,4' Commissions I//- /,f#"4'Inspector's Signature National Board, State Province, and Endorsements

Date: 20 10

(Final)

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FORM NVR-1 REPORT OF REPAIR tO REPLACEMENTOF NUCLEAR PRESSURE RELIEF DEVICES

E3

1. Work performed by: NWS Technologies, LLC Purchase OrderS131 Venture Boulevard, Spartanbura, SC 29306

454204

2. Work performed for Exelon Corporation, Byron Nuclear Station

3/4. Owner - name, address and identification of nuclear power plant ExelByron Nuclear Station 4450 N. German Church Road Byron, IL 61010

on Corporation,

5. a: Repaired pressure relief device: Main Steam Safety Valveb: Name of manufacturer Consolidated I Dresserc: Identifying nos.

3707R BRO!i|ffdft

d: Construction Code: ASME Section III(naes/dodMsm)

409SM)

n/a steam so(N W (siawos) (stze)

77(Yr.buiU)

2(code Class)

1974 n/a n/a(adRkm) (addwna) (Cods Case*(*))

6. ASME Code Section XI applicable for inservice inspection:

7. ASME Code Section Xl used for repairs, replacements:

8. Construction Code used for repairs, replacements:

2001

2001(edin)

1974(scdfln)

2003 r/a(addenda) (Code Case())

2003 n/a(addenda) (Cods Case(s))

n/a n/a(addenda) (Code Case(s))

9. Design responsibilities: n/a10. Opening pressure: 1176 psigSet-pressure adjustment made at NWS Technologies, LLC using steam

11. Description of work (include nuns and denufvtg numier of mploS•mtns parl): Disassembled, cleaned, inspected,lapped nozzle & passivated seat area, lapped and pre-oxidized the X750 disc, load tested the spring,

J ~ ~ ~ ~ ~ - -- &.a.. W"Aaf 0... ... d4.him ,.0i aboomas55uIIU. %.WuImuI ýU'J 211 @ i U5I

0% 0 .6- LnAM 0 4 A-PA Nft nOrM re lacedI . 011#0 C

I_ CERTIFICATE OF COMPLIANCI

I, Cesar V. Sierra certify that to the best of my knowledge and belief the statements made in thisreport are correct and the repair, modification or replacement of the pressure relief devices described aboveconforms to Section Xl of the ASME Code and the National Board Inspection Code "V1R" and "NR" rules.National Board Certificate of Authorization No. 632 to use the "VR0 stamp expires April 3, 2012.Natoa rd Certificate of Authorization No. 81 se the N stap expires April 9, 2012.

Rechnologies•e LIC o TManager, QADats Repair organizatin Au" Irepnefd"v Tmel

CERTiFICATE OF INSPECTIONI, Charles F. Toogel Jr. holding a valid commission issued by The National Board of Boiler and PressureVessel Inspectors and certificate of competency Issued by the jurisdiction of North Carolina and employedby Hartford Steam Boiler of CT of Hartford, CT have inspected the repair, modification

or replacement described in this report on V ?M/I4 . r'oand state that to the best of my knowledge and belief,

this repair, modification or replacement has been completed in accordance with Section Xl of the of the ASME

Code and the National Board Inspection Code "VR and "NR" rules.

By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied,

concerning this repair, modification or replacement described in this report. Futhermore, neither the undersigned

nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind

arising from or conn is ins :,/ ';A, N. I__O 07

1~3 55

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NWS Work Pt

Valve Serw Nume. BROR096

rogression & Hold Point Checklist

PM. 4411 rev I NWS Traveler 0 1046

This block to be sgned altr Indic,*ng hold points end prior to woo

This traele has been reviewed anid approved for use by: %ý == -- 4

Construction Code: ASME Section: III Edition 74 Addenda: n/a CodeCase: N__Repair Code: ASME Section: Xl Edition: 2001 Addenda: 250 CodeCase N

This bveler has bee reviewed and approved for use by: I I 'L

This traveler has been reviewed and approved for use by: &af.-4 vwv/.9,#7d4,j V.1..0 441 ' .- HS S)AN F- Ch .,r IG W .O", _ _.-M A

work Step NV, f NV OA NYS NMS ANIQ1A Whies P"I WtivesHold OatilnIt. Hold DatefLnit.

Valve had been tetied at site. Sent to NWS for refurb and st-eam issur certification.1. Recelpt Inspein_

2. Full dsassembly (NW A-R-3 rev 7)

3. Component inspection4. Repair (Sectiont X) components (Exelon Atschmnent 5 re.,d) ,5. Replece (Section XI) components (Exelan Afttamenwt 5 reqd) - M

.. Lap and oxidize the X750 disc (NWS-I-2 Rev 0)

7. Lap and pmatvalve nozzle seat (NW84-3 Rev 0)

8. Inspect Spring I Load Test Sprng

9. Valve assembly

10. Set blowdown rtngs

11. Steam se-pre,,se certtication tesft (NW.S-T-82 rev 1) __,,//__/

12. Steem seat tightness testl _______

13. Tlighten compression screw locknut & torque seal

14. Lockwre and seal ring pins and cap

15. Final Inspection

IS. Completion of Form NVR-110117. Appl nameplate

@

This block to be signed after completion of work*

This traveler has been reviewed and accepted by:

This traveler has been reviewed and accepted by:

(Ilol / lQua 4... M ANIJ,

1 ~ .3 ~i ~i *<

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NWS Certificate of Conformancetechnologies of work performed for

131 Venture Boulevard ExelonSpartanburg, SC 29308 Byron Nuclear StationPh: 864-587-7001Fx: 864"587-9005 Purchase Order # 454204

Valve IdentificationValve S/N: BR09609 Model Number 3707R Main Steam

Set-Pressure: 1175 "sia Valve OEM: Dresser NWS Traveler # 10-66

Job SummaryAs-found testing had been done at site.Repair: The valve was repaired under the NWS VR/NR programs. The X750 disc waslapped and oxidized disc prior to reuse. The nozzle seat was passivated after lapping.The spring was load tested with satisfactory results. Wear areas were cleaned asnecessary. All wear areas and contact points were lubricated prior to assembly.Initial Test: The valve was allowed to thermally stabilize at a holding pressure of -1000psig. A total of three lifts were done. No adjustments were required. The final two liftswere within the required as-left BYRON acceptance range of +1% of set-pressure.Final Seat Tightness Testing: Following set-pressure certification, system pressurewas maintained at 90%. No moisture was detected on a cold bar placed in the vicinityof the seats.All work was done by NWS personnel. An NWS test supervisor was present during alltesting. An HSB of CT reviewed documentation, witnessed steam certification testing,nameplate installation, and completed an NVR-1 form.The valve was cleaned, sealed and packaged for return shipment.

Set-Pressure Certification Lifts (1164 to 1186 psig)Lift Date Time Set- Inlet Body Spring Ambient

Number Pressure Flange Can_(PSIG) (°FO°F) (OF) (TF)

66-0-21B 4/6/10 12:23 1179 469 248 144 11466-0-3B 4/6/10 12:28 1 1178 1 469 249 144 114

We certify that all work performed was in compliance with the referenced PO and othercorrespondence, NWS QA System Manual Rev. 4, NWS VR Program Rev. 7, NWS NRProgram Rev. 6, NWS Procedures and the documents referenced therein. All required testsand inspections have been performed and the results accepted. Documentation supporting thisCertificate of Conformance is available for review as applicable.

NWS Job Coordinator: Date: q•_/_•_/0

NWS Quality Assurance: Date: 0(/_P_/P

3 1Z :3 -

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DOCUMENT NO.: 3A REV. NO.: 0

FORM NIS-2 OWNER'S REPORT FOR REPAIRIREPLACEMENT ACTIVITYAs Required by the Provisions of the ASME Code Section XI

1. Owner Exelon Nuclear Date 4/26/10Name

4300 Winfield Road, Warrenville, IL Sheet 1 of 1Address

2. Plant Byron Nuclear Power Station Unit 2Name

4450 N. German Church Road, Byron, IL Work Order No. 01213643-01Address Repair Organization, P.O. No., Job No., etc.

3. Work Performed by Byron Mechanical Type Code Symbol Stamp Not ApplicableMaintenance

Name Authorization No. Not Applicable4450 N. German Church Road, Byron, IL Expiration Date Not Applicable

Address

4. Identification of System CV - CHEMICAL VOLUME CONTROL

5. (a) Applicable Construction Code ASME Section 1II 19 71 Edition, S72 Addenda, 1540-1 Code Case(b) Applicable Edition of Section XI Used for Repair/Replacement Activity: 2001 Editlor/2003 Addenda(c) Section Xl Code Case(s) None

6. Identification of Components

ASMECorrected, Code

National Removed, or StampedName of Name of Manufacturer Board Other Year Installed (Yes or No)

Component Manufacturer Serial No. No. Identification Built

Diaphragm Valve ITT Grinnell 74-1658-25-4 N/A 2CV8399 1976 Removed Yes

Valve Bonnet ITT Viv. 74-1658-13-2 N/A 2CV8399 1976 Installed YesGRINNELL Cat ID# 38640-1

7. Description of Work REMOVED BONNET ASSEBONNET ASSEMBLY (INCLUDING DIAPHRAGM).

MBLY FROM OLD VALVE AND REPLACE WITH NEW

8. Test Conducted: Hydrostatic E] Pneumatic [] Norn

Other E] Pressure 35 psi

iinal Operating Pressure 0 Exempt ElTest Temp. 148 OF

Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8½2 in. x 11in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numberedand the number of sheets is recorded at the top of this form.

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FORM NIS-2 (Back)

9. RemarksApplicable Manufacturer's Data Reports to be attached

UTILIZED BONNET ASSEMBLY AND DIAPHRAGM FROM VAVLE (CAT ID# 38640-1)

CERTIFICATE OF COMPLIANCEI 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 Not Applicable

Certificate of.Huthorization No. Not Applicable

Signed (w - WA , A M C o0A /fAJA7O)/Q Date 5"- 17 ,20 10Owner or Owner's Designee, Title

CERTIFICATE OF INSERVICE INSPECTIONI, the undersigned, holding a valid commission issued by the National Board of Boiler and PressureVessel Inspectors and the State or Province of Illinois - and employed by HSB CTof Hartford, CT have ins cted the components described in this Owner's Report during the period

to ,and state that to the best of my knowledge and belief,tl~eOwner has performed /examinations and taken corrective measures described in this Owner'sReport 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 orimplied, concerning the examinations and corrective measures described in this Owners Report.Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personalinjury or propertyamagor a loss of any kind arising from or connected with this inspe.Ction.

Commissions /l" - ,,/01Inspectors SignatureU - - -

a tInspectos SignatureDate: -?f /' f

4F

National Board, State Province, and Endorsements

20 , /,0191,4lel

a--'I-r

@

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DOCUMENT NO.: 6A REV. NO.: 0

FORM NIS-2 OWNER'S REPORT FOR REPAIRIREPLACEMENT ACTIVITYAs Required by the Provisions of the ASME Code Section XI

1. Owner Exelon Nuclear Date 4/28/10Name

4300 Winfield Road, Warrenville, IL Sheet 1 of 2Address

2. Plant Byron Nuclear Power Station Unit 02Name

4450 N. German Church Road, Byron, IL Work Order No. 01225344-01Address Repair Organization, P.O. No., Job No., etc.

3. Work Performed by Byron Mechanical Type Code Symbol Stamp Not ApplicableMaintenance

Name Authorization No. Not Applicable4450 N. German Church Road, Byron, IL Expiration Date Not Applicable

Address

4. Identification of System SI Safety Injection

5. (a) Applicable Construction Code - Pipe ASME Sect 1II 19 74 Edition, S75 Addenda, N/A Code Case(a) Applicable Construction Code - Valve ASME Sect III 19 74 Edition, S76 Addenda, N/A Code Case(b) Applicable Edition of Section XI Used for Repair/Replacement Activity: 2001 Edition/2003 Addenda(c) Section XI Code Case(s) NONE

6. Identification of Components

ASMECorrected, Code

National Removed, or StampedName of Name of Manufacturer Board Other Year.. Installed (Yes or No)

Component Manufacturer Serial No. No. Identification Built2SI881 9C

Valve Kerotest US6-24 21,428 CI# 32726-1 1978 Removed Yes

Valve Kerotest US7-111 21,453 2SI8819C 1978 Installed YesCI# 32726-1CONSOLIDATED 2I518FC-2" 2006 Removed NOPIPE SCH.160 POWER SUPPLY HT# 505112 N/A CI# 32352-1

PIPE SCH.160 CONSOLIDATED ,T 2SI18FC-2"POWER SUPPLY HT# 505112 N/A CI# 32352-1 2010 Installed NO

COUPLING TIOGA PIPE HT# HRV N/A 2SI18FC326 2008 Removed NOCI# 39261 -1

COUPLING Guyon Alloys, Ht. Code: CJW N/A 2SI18FC-2" 1982 Installed NOInc. CI# 39261-1 1982 Installed NOORIFICE Consolidated 2S5118FC-2"ORFC osfdtd HT# 2082ANEI N/A 2S1F-" 2008 Removed NOFLANGE Power Supply N CAT# 1230885-1

STANDARD Joliet Valves HT# D2283 N/A 2SI18FC-2" 1984 Installed NOFLANGE Inc. HTID2283 N/A Cat Id# 30443-1 1

7. Description of Work REPLACE VALVE, PIPE & FLANGE (PER EC 375527)

Replace flange bolting and orifice plate on 2SI06MC per EC 375527,

8. Test Conducted: Hydrostatic [I Pneumatic [] Nominal Operating Pressure 0 Exempt [-

Other 0J Pressure 0865/ Q)615 psi Test Temp. 87/ N/A OF(1) Class-2 portion, 0 Class-1 portion

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

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FORM NIS-2 (Back)

9. Remarks WO# 01225344-01 "4Applicable Manufacturers Data Reports to be attached

CERTIFICATE OF COMPLIANCEI 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 Not Applicable

Certificate of Authorization No. Not Applicable

Signed e-i - Date - ,20 10r Owner's Designee, Title

CERTIFICATE OF INSERVICE INSPECTION

I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure

Vessel Inspectors and the State or Province of Illinois and employed by HSB CT

of Hartford, CT have inspe ted the components described in this Owner's Report during the period

,, to , and state that to the best of my knowledge and belief,the wner has perfo fminations 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 measures described in this Owner's Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal

injury or property damrne or a loss of any kind arising from or connected with this inspection.

Q 4.* ' -t~ Commissions _, _ __ - __1"0V

'Y -Inspector's Signature National Board, State Province, and Endorsements

Date: / 10

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FORM NIS-2 SUPPLEMENTAL SHEET

1. Owner Exelon Nuclear Date 4/28/10

2.

3.

Name4300 Winfield Road, Warrenville, IL

AddressPlant Byron Nuclear Power Station

Name4450 N. German Church Road, Byron, IL

Address

Work Performed by Byron MechanicalMaintenance

Name,4450 N. German Church Road, Byron, IL

Address

Sheet 2 of 2

Unit 2

Work Order No. 01225344-01Repair Organization, P.O. No., Job No., etc.

Type Code Symbol Stamp Not Applicable

Authorization No.Expiration Date

Not ApplicableNot Applicable

4. Identification of System CC - Component Cooler

5. (a) Applicable Construction Code: Piping ASME Sect III 19 74 Ed, S/75 Ad, None Code CaseApplicable Construction Code: Valve ASME Sect 1II 19 74 Ed, S/76 Ad, None Code Case

(b) Applicable Edition of Section XI Utilized for Repairs or Replacement Components 2001 Ed/2003 Ad(c) Section XI Code Cases used, None.

6. Identification of Components Repaired or Replaced and Replacement Components

ASMECorrected, Code

National Removed, or StampedName of Name of Manufacturer Board Other Year Installed (Yes or No)

Component Manufacturer Serial No. No. Identification Built

Pipe Sch. 160 Guyon Alloys Mk.# 749803 N/A 2SI18FC-2 1982 Removed NoMRA # 5962

Orifice Plate Hunter Corp. Ht. # K51292 N/A 2SI06MC 1981 Removed No

Orifice Plate Energy Steel Ht # 877945 N/A 2SI06MC 2010 Installed NoMIC# T25975 Cat/ld: 1443150-1

Flange Studs Hunter Corp. Mk.# LIEH N/A 2SI06MC 1981 Removed NoQty. 8 (MJ-48A)

Flange Studs Nova Machine HT# 7526262 N/A 2SI06MC 2006 Installed NoOty. 8 Prod. TC# 147F Cat/ID: 44337-1

Flange Nuts Nova Machine Mk. #LISP N/A 2SI06MCQty. 16 Products (MJ-48A)

Flange Nuts Nova Machine HT# 02280A N/A 2SI06MCQty. 16 Prod. Cat/Id: 30520-1

(Final)

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DOCUMENT NO.: 3-1 REV. NO.: 0

FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITYAs Required by the Provisions of the ASME Code Section XI

1. Owner Exelon Nuclear Date 4-26-10

2.

3.

Name4300 Winfield Road, Warrenville, IL

AddressPlant Byron Nuclear Power Station

Name4450 N. German Church Road, Byron, IL

Address

Work Performed by Byron MechanicalMaintenance

Name4450 N. German Church Road, Byron, IL

Address

Sheet 1 of

Unit 2

1

Work Order No. 01225561-01Repair Organization, P.O. No., Job No., etc.

Type Code Symbol Stamp Not Applicable

Authorization No.Expiration Date

Not ApplicableNot Applicable

4. Identification of System SI - Safety Injection

5. (a) Applicable Construction Code ASME Section III 19 71 Edition, W/72 Addenda, 1553-1 Code Case1649 (nuts)

(b) Applicable Edition of Section XI Used for Repair/Replacement Activity: 2001 Editlon/2003 Addenda(c) Section XI Code Case(s) None

6. Identification of Componentst4. a I Ign

ASMECorrected, Code

National Removed, or StampedName of Name of Manufacturer Board Other Year Installed (Yes or No)

Comoonent Manufacturer Serial No. No. Identification Built

Disc for 6" Swing McWilliams S/N: 2075 W10992 EPN: 2SI8818C 1976 Removed NoCheck Valve. FORGE CO. HT # 65800 (Valve) ID: 6C88 1976 Removed No

Disc for 6" Swing IONICS, INC RP-2000 N/A EPN: 2SI8818C 2001 Installed NoCheck Valve. ID: 6C88 2001 _nstalled No

9 9 4 9

I * 4 I I S I

9 4 4 9 9 4 9

9 1 ~ 9 9 4 9

______________ L I .1. & I .1. 1

7. Description of Work Replaced the check valve disc

8. Test Conducted: Hydrostatic [I Pneumatic 0] Noff

Other E0 Pressure n/a psi

inal Operating Pressure 0l Exempt Z

Test Temp. n/a OF

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

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FORM NIS-2 (Back) alýý9. Remarks Reference WO 01225561-01.

Applicable Manufacturer's Data Reports to be attached

CERTIFICATE OF COMPLIANCEI 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 Not Applicable

Certificate of uthorization No. Not Applicable

Signed (Aja¾A C. eMA A IM AXW--l, Date "-lI ,20 /Owner or Owner's Designee, Title

CERTIFICATE OF INSERVICE INSPECTIONI, the undersigned, holding a valid commission issued by the National Board of Boiler and PressureVessel Inspectors and the State or Province of Illinois rand employed by HSB CT

of Hartford, CT have nspcted the components described in this Owner's Report during the period

607eje to ,and state that to the best of my knowledge and belief,

th wner has p examinations and taken corrective measures described in this Owner'sReport 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 orimplied, concerning the examinations and corrective measures described in this Owner's Report.Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personalinjury or propertydajn age or a loss of any kind arising from or connected with this inspection.

Commissions /Zzi - /ab'(Inspector's Signature

Date: • 20 'National Board, State Province, and Endorsements

(Final)

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I DOCUMENT NO.: 5.2 I

FORM NIS-2 OWNER'S REPORT FOR REPAIRIREPLACEMENT ACTIVITYAs Required by the Provisions of the ASME Code Section XI

1. Owner Exelon NuclearName

4300 Wlnfleld Road, Warrenville, IL

Date 4/25/10

Sheet 1 of 1

2.Address

Plant Byron Nuclear Power StationName

4450 N. German Church Road, Byron, ILAddress

Unit 02

Work Order No. 01232858-01Repair Organization, P.O. No., Job No., etc.

3. Work Performed by Shaw/Stone & WebsterName

36400 S. Essex Road, Wilmington, IL 60481

Type Code Symbol Stamp Not ApAuthorization No. Not ApplicableExpiration Date Not Applicable

plicable

Address

4. Identification of System SI - SAFETY INJECTION

5. (a) Applicable Construction Code ASME Section 1II 19 74 Edition, S75 Addenda, NONE Code Case(b) Applicable Edition of Section XI Used for Repair/Replacement Activity 2001 Edition / 2003 Addenda(c) Section Xl Code Case(s) NONE

6. Identification of Components

ASMECorrected, Code

National Removed, or StampedName of Name of Manufacturer Board Other Year Installed (Yes or No)

Component Manufacturer Serial No. No. Identification Built

BONNET NUT VITCO N2 N/A 2SI8816D 1978 Removed NO

HT# 532670BONNET NUT NOVA MACHINE TRACE# E578 N/A 2SI8816D 2002 Installed NOPRODUCTS CAT ID 37057-1

4 4. 4 4 4 4 4.

4 4. 4 .4 4 .4 4.

4 4. 4 4 4 4 4.

4 4. 4 .4 4 .4 4.

7. Description of Work REPLACE DAMAGED BONNET NUT

8. Test Conducted: Hydrostatic C] Pn

Other E5 Pressure

eumatic C] Nominal Operating Pressure 51psi Test Temp.

Exempt [

OF

Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 812 in. x 11 in., (2)information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the numberof sheets is recorded at the top of this form.

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FORM NIS-2 (Back)

9. Remarks Replacement per WO 01232858-01Applicable Manufacturers Data Reports to be attached

CERTIFICATE OF COMPLIANCE

I 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 Not Applicable

Certificate of Authorization No. Not Applicable

Signed Date 6 - 20 10OnrsDesignee, Tite

CERTIFICATE OF INSERVICE INSPECTION

I, the undersigned, holding a valid commission issued by the National Board of Boiler and PressureVessel Inspectors and the State or Province of Illinois and employed by HSB CT

of Hartford, CT have inspe ted the components described in this Owner's Report during the period

to ,and state that to the best of my knowledge and belief,

thfe cfwner has performed efaminations and taken corrective measures described in this Owner'sReport 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 orimplied, concerning the examinations and corrective measures described in this Owner's Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personalinjury or property damage or a loss of any kind arising from or connected with this inspection.

_____ ____ ____ ___Commissions el -/1-445Inspector's Signature National Board, State Province, and Endorsements

Date: ,& 7 20 10

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DOCUMENT NO.: 5.1 REV. NO.: 0

FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITYAs Required by the Provisions of the ASME Code Section XI

1. Owner Exelon Nuclear Date 4-27-10Name

4300 WInfield Road, Warrenville, IL Sheet 1 of 1Address

2. Plant Byron Nuclear Power Station Unit 01Name

4450 N. German Church Road, Byron, IL Work Order No. 01241053-01Address Repair Organization, P.O. No., Job No., etc.

3. Work Performed by Shaw/Stone & Webster Type Code Symbol Stamp Not ApplicableName Authorization No. Not Applicable

36400 S. Essex Road, Wilmington, IL 60481 Expiration Date Not ApplicableAddress

4. Identification of System SI - Safety Injection

5. (a) Applicable Construction Code ASME Section II1 19 74 Edition, S75 Addenda, None Code Case(b) Applicable Edition of Section Xl Used for Repair/Replacement Activity 2001 Edition / 2003 Addenda(c) Section XI Code Case(s) NONE

6. Identification of Components

ASMECorrected, Code

National Removed, or StampedName of Name of Manufacturer Board Other Year Installed (Yes or No)

Component Manufacturer Serial No. No. Identification Built

PIPE, 2" SCH 160 SANDVIK INC. HT# 745223 N/A 2SI18EB-2" 1977 Removed NO

ALLOYELBOW, 90", 6000# STAINLESS MK# P1 N/A 2SI18EB-2" 1977 Removed NO

PRODUCTS HT# 74188

PIPE, 2" SCH 160 CONSOLIDATED HT# 505112N N/A 2SI18EB-2OPOWER Cat ID 32352-1

ELBOW, 90°, 6000# ALLOY TRACE# PJ N/A 1977 INSTALLED NOSTAINLESS A91 -00363 Cat ID 26875-1

COUPLING, 2", 6000# AMCO FITTINGS HT# EEX N/A 2SI18EB-2" INSTALLED NOCO. Cat ID 26943-1

7. Description of Work INSTALLED PIPING (APPROX. 7 FT.) AND FITTINGS (2 ELBOWS & 1 COUPLING)

8. Test Conducted: Hydrostatic [] Pr

Other E] Pressureieumatic [] Nominal Operating Pressure Z Exempt El

865 psi Test Temp. 87 OF

Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 81/2 in. x 11 in., (2)information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the numberof sheets is recorded at the top of this form.

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FORM NIS-2 (Back)

9. Remarks 01241053-01.Applicable Manufacturer's Data Reports to be attached 14

CERTIFICATE OF COMPLIANCEI 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 Not ApplicableCertificate of Authorization No. Not ApplicableSigned " Date Z - ,20 10

Owner's Designee. Title

CERTIFICATE OF INSERVICE INSPECTIONI, the undersigned, holding a valid commission issued by the National Board of Boiler and PressureVessel Inspectors and the State or Province of Illinois and employed by HSB CTof Hartford, CT have 17pcted the components described in this Owner's Report during the period

.Y// 7 to I,"r I , and state that to the best of my knowledge and belief,the 0rner has perform~d examinations and taken corrective measures described in this Owner'sReport 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 orimplied, concerning the examinations and corrective measures described in this Owner's Report.Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personalinjury or property dacnap or a loss of any kind arising from or connected with this inspection.

Commissions '/1/. - /I1W

I

............... |

Inspector's Signature

Date: , 20 10

National Board, State Province, and Endorsements

(Final)

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DOCUMENT NO.: 5.1 REV. NO.: 0

FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITYAs Required by the Provisions of the ASME Code Section Xl

1. Owner Exelon Nuclear Date 4-27-10Name

4300 Winfield Road, Warrenville, IL Sheet 1 of 1Address

2. Plant Byron Nuclear Power Station Unit 01Name

4450 N. German Church Road, Byron, IL Work Order No. 01241053-08Address Repair Organization, P.O. No., Job No., etc.

3. Work Performed by Shaw/Stone & Webster Type Code Symbol Stamp Not ApplicableName Authorization No. Not Applicable

36400 S. Essex Road, Wilmington, IL 60481 Expiration Date Not ApplicableAddress

4. Identification of System Si (SAFETY INJECTION)

5. (a) Applicable Construction Code ASME Section III 19 74 Edition, S75 Addenda, N/A Code Case(b) Applicable Edition of Section XI Used for Repair/Replacement Activity 2001 Edition / 2003 Addenda(c) Section XI Code Case(s) NONE

6. Identification of Components

ASMECorrected, Code

National Removed, or StampedName of Name of Manufacturer Board Other Year Installed (Yes or No)

Component Manufacturer Serial No. No. Identification BuiltSTRAP, PIPEGUIDE WE HUNTER N/A N/A 2SI17038X 1984 Installed NOGUIDE WELDS

7. Description of Work MODIFIED PIPE SUPPORT 2SI17038X PER EC# 375526

8. Test Conducted: Hydrostatic E] Pneumatic [] Nominal Operating Pressure [I Exempt (]OFVT-3 Other Z Pressure psi Test Temp.

Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 81/2 in. x 11 in., (2)information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the numberof sheets is recorded at the top of this form.

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FORM NIS-2 (Back)

9. Remarks 01241053-08Applicable Manufacturers Data Reports to be attached

CERTIFICATE OF COMPLIANCEI 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 Not Applicable

Certificate of Authori•To No. Not Applicable

Signed Date 20 10&r~rOwneres Designee, Tidle

CERTIFICATE OF INSERVICE INSPECTIONI, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure

Vessel Inspectors and the State or Province of Illinois and employed by HSB CT

of Hartford, CT have ins7ected the components described in this Owners Report during the period

to , and state that to the best of my knowledge and belief,the-'wner has performed/examinations and taken corrective measures described in this Owner's

Report in accordance with the requirements of the ASME Code, Section Xl.

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

implied, concerning the examinations and corrective measures described in this Owner's Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal

injury or property damage or a loss of any kind arising from or connected with this inspection.

Commissions /ZzInspector's Signature

Date: . . ,20 10

National Board, State Province, and Endorsements

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DOCUMENT NO.: 4A REV. NO.: 0

FORM NIS-2 OWNER'S REPORT FOR REPAIRIREPLACEMENT ACTIVITYAs Required by the Provisions of the ASME Code Section XI

1 Owner Exelon Nuclear Date 5-2-10Name

4300 Winfleld Road, Warrenville, IL Sheet 1 of 2Address

2. Plant Byron Nuclear Power Station Unit 02Name

4450 N. German Church Road, Byron, IL Work Order No. 01279020-01Address Repair Organization, P.O. No., Job No., etc.

3. Work Performed by Byron Mechanical Type Code Symbol Stamp Not ApplicableMaintenance

Name Authorization No. Not Applicable4450 N. German Church Road, Byron, IL Expiration Date Not Applicable

Address

4. Identification of System RC REACTOR COOLANT

5. (a) Applicable Construction Code - Valves Sect. III 19 74 Edition, S76 Addenda, N-141(1 3) Code Case(a) Applicable Construction Code - Pipe Sect-. IU 19 74 Edition, S75 Addenda, N/A Code Case(b) Applicable Edition of Section XI Used for Repair/Replacement Activity. 2001 Editlon/2003 Addenda(c) Section XI Code Case(s) N/A

6. Identification of Components

ASMECorrected, Code

National Removed, or StampedName of Name of Manufacturer Board Other Year Installed (Yes or No)

Component Manufacturer Serial No. No. Identification BuiltPIPE 1/2"SCHED. 10 Unidentified HT# 462521 N/A 2RC31DB 1992 REMOVED NO

PIPE 1/2' Consolidated HT #8207J N/A 2RC31 B & 2 ISCHED.160 Power Supply 2RC31C 2000 INSTALLED NO

TEE Unidentified HT# KR N/A 2RC31B & 1992 REMOVED NO2RC31 EA 1992 REMOED_ NConsolidated 2RC31B &TEE Power Supply Lot#44050 N/A 2RC31C 2010 INSTALLED NO

ELBOW Unidentified HT Code #PP N/A 2RC31B 1992 REMOVED NO

ELBOW Guyon Alloys HT Code# PP N/A 2RC31B 1982 INSTALLED NOInc. NO

7. Description of Work REPLACED REACTOR HEADREMOVED / REINSTALLED PIPE SUPPORT WELDS

VENT VALVES AND PIPING, REPLACED U-BOLT &

8. Test Conducted: Hydrostatic [- Pr

VT-3 Other C] Pressure

eumatlc C] Non'

2244 psi

ninal Operating Pressure 0 Exempt [I

Test Temp. 557 OF

Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 81h in. x 11in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numberedand the number of sheets is recorded at the top of this form.

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FORM NIS-2 (Back)

9. Remarks WO# 01279020-01Applicable Manufacturer's Data Reports to be attached

CAT ID# 41641-1 consists of 2 Solenoid Valves, 2 reducers, 2(1/2") nipples, 1(1")

CERTIFICATE OF COMPLIANCEI certify that the statements made in the report are correct and this conforms to the requirements of the ASME

Code, Section Xl.

Type Code Symbol Stamp Not ApplicableCertificate of Authorization No. Not ApplicableSigned ______Date 2-- ,20 10

Q~or Owner's Designee, Title

CERTIFICATE OF INSERVICE INSPECTIONI, the undersigned, holding a valid commission issued by the National Board of Boiler and PressureVessel Inspectors and the State or Province of Illinois and employed by HSB CTof Hartford, CT have inspected the components described in this Owner's Report during the period

to 74,,, ... ,and state that to the best of my knowledge and belief,the Owner has performed examinations and taken corrective measures described in this Owner'sReport 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 orimplied, concerning the examinations and corrective measures described in this Owner's Report.Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personalinjury or property dAmage or a loss of any kind arising from or connected with this inspection.

ele-ý-Ae Commissions //ZI- AfS.Inspector's Signature

Date: , ,20 10

National Board, State Province, and Endorsements

t44

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FORM NIS-2 SUPPLEMENTAL SHEET

1. Owner Exelon Nuclear Date 5-2-10

2.

3.

Name4300 Winfield Road, Warrenville, IL

AddressPlant Byron Nuclear Power Station

Name4450 N. German Church Road, Byron, IL

Address

Work Performed by Byron MechanicalMaintenance

Name4450 N. German Church Road, Byron, IL

Address

Sheet 2 of 2

Unit 02

Work Order No. 01279020-01Repair Organization, P.O. No., Job No., etc.

Type Code Symbol Stamp Not Applicable

Authorization No.Expiration Date

Not ApplicableNot Applicable

4. Identification of System RC REACTOR COOLANT

5. (a) Applicable Construction Code - Valves Sect IlI 19 74 Edition, S76 Addenda, N-141(1773) Code Case(a) Applicable Construction Code - Pipe Sect. III 19 74 Edition, S75 Addenda, N/A Code Case(b) Applicable Edition of Section XI Utilized for Repairs or Replacement Components 2001 Ed/2003 Ad(c) Section Xl Code Cases used, N/A

6. Identification of Components Repaired or Replaced and Replacement Components

ASMECorrected, Code

National Removed, or StampedName of Name of Manufacturer Board Other Year Installed (Yes or No)

Component Manufacturer Serial No. No. Identification BuiltSOLENOID VALCOR S/N# 44 N/A 2RC014A 1992 REMOVED YES

VALVE ENGINEERING 4SOLENOID VALCOR S/N# 45 N/A 2RC014C 1992 REMOVED YES

VALVE ENGINEERINGSOLENOID VALCOR S/N# 42 N/A 2RC014B 1992 REMOVED YES

VALVE ENGINEERINGSOLENOID VALCOR S/N# 52 N/A 2RC014D 1997 REMOVED YES

VALVE ENGINEERINGSOLENOID VALCOR VLV ASSY SN# 4 2RC014A & C

VALVE ENGINEERING 2RC014A SN# 7 N/A UTC #2837690 2009 INSTALLED YESWELDED ASSY 2RC014C SN# 8 CAT# 41641-1

SOLENOID VALCOR VLV ASSY SN# 3 2RC014B & DVALVE ENGINEERING 2RC014B SN# 5 N/A UTC #2039040 1998 INSTALLED YES

WELDED ASSY 2RC014D SN# 6 CAT# 41641-1 __

INSERT 1 X 1/2" Unidentified 4C3414 N/A 2RC014A 1992 REMOVED NO

U-BOLT Unidentified HT# 8868763 N/A 2RC99012X 1992 REMOVED NO

U-BOLT BERGEN - N/A N/A 2RC99012X 2007 INSTALLED NOPOWER CAT# 42291-1

PIPE SUPPORT Exelon N/A N/A 2RC99013XSTRAP WELDS 1998 REMOVED NOPIPE SUPPORT Exelon N/A N/A 2RC99013XSTRAP WELDS ___2010 INSTALLED NQPIPE SUPPORT Exelon N/A N/A 2RC99014XSTRAP WELDS 1 1_99__I REMOVED NQPIPE SUPPORT Exelon N/A N/A 2RC99014XSTRAP WELDS 2I10 _____N/A _ N/ INSTALLED NO

(Final)

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I DOCUMENT NO.: 5.2

FORM NIS-2 OWNER'S REPORT FOR REPAIRIREPLACEMENT ACTIVITYAs Required by the Provisions of the ASME Code Section XI

1. Owner Exelon NuclearName

4300 Winfield Road, Warrenville, IL

Date 4-25-10

Sheet 1 of 1

2.Address

Plant Byron Nuclear Power StationName

4450 N. German Church Road, Byron, ILAddress

Unit 02

Work Order No. 01329864-01Repair Organization, P.O. No., Job No., etc.

3. Work Performed by Shaw/Stone & WebsterName

36400 S. Essex Road, Wilmington, IL 60481Address

Type Code Symbol Stamp Not ApAuthorization No. Not ApplicableExpiration Date Not Applicable

pilcable

4. Identification of System PRIMARY CONTAINMENT ISOLATION

5. (a) Applicable Construction Code - Weld ASME Sect III 19 74 Edition, S75 Addenda, Code Case5. (a) Applicable Construction Code - Penn ASME Sect III 197.•4 Edition, S76 Addenda, Code Case

(b) Applicable Edition of Section XI Used for Repair/Replacement Activity 2001 Edition / 2003 Addenda(c) Section XI Code Case(s) NONE

6. Identification of Components

ASMECorrected, Code

National Removed, or StampedName of Name of Manufacturer Board Other Year Installed (Yes or No)

Component Manufacturer Serial No. No. Identification Built

Penetration# EnergyProducts 802165-5C N/A 2PC066M 1978 Corrected NoGroup

7. Description of Work METAL REMOVAL OF A DEFECT PER EC# 379830

8. Test Conducted: Hydrostatic [] Pn

Other 0 Pressure

eumatic E3 Nominal Operating Pressure Cpsi Test Temp.

Exempt 0OF

Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 81/2 in. x 11 in., (2)information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the numberof sheets is recorded at the top of this form.

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FORM NIIS-2 (Back)

9. Remarks WO# 01329864-01Applicable Manufacturer's Data Reports to be attached

CERTIFICATE OF COMPLIANCEI certify that the statements made in the report are correct and this conforms to the requirements of the ASME

Code, Section Xl.Type Code Symbol Stamp Not ApplicableCertificate of Authorization No. Not ApplicableSigned ,Date C -/t 20 10

One) or Owneves Designee, Title

CERTIFICATE OF INSERVICE INSPECTIONI, the undersigned, holding a valid commission issued by the National Board of Boiler and PressureVessel Inspectors and the State or Province of Illinois rand employed by HSB CT

of Hartford, CT have ispeted the components described in this Owner's Report during the period,.to ____/// _ , and state that to the best of my knowledge and belief,

the OWner has performed examinations and taken corrective measures described in this Owner'sReport in accordance with the requirements of the ASME Code, Section X1.By signing this certificate neither the Inspector nor his employer makes any warranty, expressed orimplied, concerning the examinations and corrective measures described in this Owner's Report.Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personalinjury or property damae or a loss of any kind arising from or connected with this inspection.

Commissions /Z1%- ,5;604

'3

Aý Inspector's Signature National Board, State Province, and Endorsements

Date: al ! //20 10

(Final)

41(.

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DOCUMENT NO.: 2A REV. NO.: 0

FORM NIS-2 OWNER'S REPORT FOR REPAIRIREPLACEMENT ACTIVITYAs Required by the Provisions of the ASME Code Section Xl

1. Owner Exelon Nuclear Date 5/3/10Name

4300 Winfield Road, Warrenville, IL Sheet 1 of 1Address

2. Plant Byron Nuclear Power Station Unit 02Name

4480 N. German Church Road, Byron, IL Work Order No. 1332152-01Address Repair Organization, P.O. No., Job No., etc.

3. Work Performed by Byron Mechanical Type Code Symbol Stamp Not ApplicableMaintenance

Name Authorization No. Not Applicable4450 N. German Church Road, Byron, IL Expiration Date Not Applicable

Address

4. Identification of System RC - REACTOR VESSEL

5. (a) Applicable Construction Code ASME Section III 19 71 Edition, Sf73 Addenda, N/A Code Case(b) Applicable Edition of Section XI Used for Repair/Replacement Activity. 2001 Edltlon/2003 Addenda(c) Section Xl Code Case(s)

6. Identification of Components

ASMECorrected, Code

National Removed, or StampedName of Name of Manufacturer Board Other Year Installed (Yes or No)

Component Manufacturer Serial No. No. Identification BuiltReactor Closure McINNES HT#214444 N/A 2RC01R 1975 CORRECTED NO

Stud #11 STEEL HT#214444 N/A 2R0R_7 CORRETED_ N

7. Description of Work MODIFY/TRIMAPPROXIMATELY 5' PER EC 379850

REACTOR VESSEL CLOSURE STUD (HEAD STUD #11)I

I

8. Test Conducted: Hydrostatic 0] Pn

Other 0 Pressure

eumatic 0 Nominal Operating Pressure C0

psi Test Temp.

Exempt 10OF

Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 81h in. x 11in., (2) information in items I through 6 on this report is included on each sheet, and (3) each sheet is numberedand the number of sheets is recorded at the top of this form.

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FORM NIS-2 (Back)

9. Remarks WO#1332152-01Appucabie manuracturers Data Reports to be auacnea

CERTIFICATE OF COMPLIANCEI certify that the statements made in the report are correct and this conforms to the requirements of the ASME

Code, Section Xl.Type Code Symbol Stamp Not ApplicableCertificate ot.uthorization No. Not ApplicableSigned IJAAIA (a-. Ia 1 , im uWA4/RA)A1'r' Date = - 21, 20 10

Owner or Owner's Designee, Title

CERTIFICATE OF INSERVICE INSPECTION1, the undersigned, holding a valid commission issued by the National Board of Boiler and PressureVessel Inspectors and the State or Province of Illinois and employed by HSB CTof Hartford, CT have inspected the components described in this Owner's Report during the period4-3p-MO to a. .3,P. O' , and state that to the best of my knowledge and belief,the Owner has performed examinations and taken corrective measures described in this Owner'sReport 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 orimplied, concerning the examinations and corrective measures described in this Owner's Report.Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personalinjury or property damrage or a loss of any kind arising from or connected with this inspection.

____Commissions __Z__-_J._ __/

Inspector's Signature National Board, State Province, and Endorsements

Date: 140' 20 1PJIF

(Final

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DOCUMENT NO.: 2A REV. NO.: 0

FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTSAs Required by the Provisions of the ASME Code Section Xi

1. Owner Exelon Nuclear Date 5-5-10Name

4300 Winfield Road, Warrenville, IL Sheet 1 of 1Address

2. Plant Byron Nuclear Power Station Unit 02Name

4450 N. German Church Road, Byron, IL Work Order No. 01335437-08Address Repair Organization, P.O. No., Job No., etc.

3. Work Performed by Byron Mechanical Type Code Symbol Stamp Not ApplicableMaintenance

Name Authorization No. Not Applicable4450 N. German Church Road, Byron, IL 61010 Expiration Date Not Applicable

Address

4. Identification of System (RC) Reactor coolant

5. (a) Applicable Construction Code ASME Section III 19 74 Edition, S76 Addenda,Code Case

(b) Applicable Edition of Section XI Used for Repair/Replacement Activity 2001 Edition / 2003 Addenda(c) Section Xl Code Case(s) NONE

6. Identification of Components

ASMECorrected, Code

National Removed, or StampedName of Name of Manufacturer Board Other Year Installed (Yes or No)

Component Manufacturer Serial No. No. Identification Built

Snubber Control ITT Grinnell Snubber N/A 2RC01 BC-A 1979 Removed NOValve Assy (BOEING) S/N: 19 Snubber S/N: 19

Snubber Control ITT Grinnell Snubber N/A.Cat id:17296Valve Assy (BOEING) S/N: 4 UTC# 2038032

7. Description of Work REPLACED SNUBBER CONTROL VALVE ASSEMBLY

8. Test Conducted: Hydrostatic 0- Pn

VT-3 Other Z Pressure

eumatic C Norr

psi

iinal Operating Pressure [I Exempt [I

Test Temp. °_OF

Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8½ in. x 11 in., (2)information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the numberof sheets is recorded at the top of this form.

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FORM NIS-2 (Back)

9. Remarks WO# 01335437-08Applicable Manufacturers Data Reports to be attached

CONTROL VALVE ASSEMBLY TESTED ON WO# 1216985-01

CERTIFICATE OF COMPLIANCE

I 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 Not Applicable

Certificate of Authoriation No. Not Applicable

Signed If - Date C;-Z- ,20 10CtO er's Designee, "Tits

CERTIFICATE OF INSERVICE INSPECTION

I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure

Vessel Inspectors and the State or Province of Illinois rand employed by HSB CT

of Hartford, CT have inspeced the components described in this Owner's Report during the period

4.ýý - to _____,__ , and state that to the best of my knowledge and belief,tKe 6wner has performed examinations and taken corrective measures described in this Owner'sReport 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 orimplied, concerning the examinations and corrective measures described in this Owners Report.Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personalinjury or property damjge or a loss of any kind arising from or connected with this inspection.

__•_ _•._•__ Commissions 111- jj.4"/Inspector's Signature National Board, State Province, and Endorsements

Date: ,g , ,tf ,20 10#I -

(Final)

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DOCUMENT NO.: 4A REV. NO.: 0

FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITYAs Required by the Provisions of the ASME Code Section Xi

1. Owner Exelon Nuclear Date 5-6-10Name

4300 Winfield Road, Warrenville, IL Sheet 1 of 1Address

2. Plant Byron Nuclear Power Station Unit 02Name

4450 N. German Church Road, Byron, IL Work Order No. 01335438-01Address Repair Organization, P.O. No., Job No., etc.

3. Work Performed by Byron Mechanical Type Code Symbol Stamp Not ApplicableMaintenance

Name Authorization No. Not Applicable4450 N. German Church Road, Byron, IL Expiration Date Not Applicable

Address

4. Identification of System RC REACTOR COOLANT

5. (a) Applicable Construction Code ASME Section III 1974 Edition, Sf75 Addenda, 1644-4 Code Case(b) Applicable Edition of Section XI Used for Repair/Replacement Activity. 2001 Edition/2003 Addenda(c) Section XI Code Case(s) N/A

6. Identification of Components

ASMENational Corrected, Code

Name of Name of Manufacturer Board Other Year Removed, or StampedComponent Manufacturer Serial No. No. Identification Built Installed (Yes or No)

WELDED STUDS Teledyne Melt No. N/A 2RC01BC 1978 REMOVED NOBrown Eng. D5896 H-SG-109

THREADED Nova Machine HT# 230113 N/A CAT ID# 24979-1 2007 INSTALLED NOSTUD (4) Prod. HT_2013_/ C I24 - 07 NTL ___NO

NUTS Unidentified SA-194 Gr. 2H N/A 2RCOIBC 1988 REMOVED NOH-SG-109 188 RMVD N

NUTS (12) Nova Machine HT# 361170 N/A CAT ID# 37027-1 2007 INSTALLED - NOProd. __ _ _ _ __ _ _ ___ _ __ _ _ _ __ _ _

SLOTTED PLATE Unidentified Unidentified N/A 2RC01BCH-SG-109 1988 CORRECTED NO

7. Description of Work ALTERED SHIM PLATE AND INSTALLED BOLTS AND NUTS ON THE 2C STEAMGENERATOR UPPER LATERAL RESTRAINT, SOUTH EAST SHIM PACK PER EC# 380019

8. Test Conducted:

VT-3

Hydrostatic []

Other 0 Pressu

Pneumatic 0 Nominal Operating Pressure 0Jre psi Test Temp.

Exempt 0lOF

Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 81½ in. x 11in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numberedand the number of sheets is recorded at the top of this form.

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FORM NIS-2 (Back)

9. Remarks WO# 01335438-01 41Appiicaoie manufacturers Data Heporrs to De attacnea

CERTIFICATE OF COMPLIANCEI 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 Not ApplicableCertificate of Authori tion N Not AppIlcable

Signed Date 20 10--(!ý r Owner's Desk-tee, Tiffs

CERTIFICATE OF INSERVICE INSPECTION1, the undersigned, holding a valid commission issued by the National Board of Boiler and PressureVessel Inspectors and the State or Province of Illinois and employed by HSB CTof Haord CT have inspected the components described in this Owner's Report during the period

to .4 , and state that to the best of my knowledge and belief,Obwner has performred "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 orimplied, concerning the examinations and corrective measures described in this.Owner's Report.Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personalinjury or property damage or a loss of any kind arising from or connected with this inspection.

_________ _________Commissions ii ~Inspector's Signature National Board, State Province, and Endorsements

Date: • ,20 10

/4

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FORM NIS-2 OWNER'S REPORT FOR REPAIRIREPLACEMENT ACTIVITYAs Required by the Provisions of the ASME Code Section XI

1. Owner Exelon NuclearName

4300 Winfield Road, Warrenville, IL

Date 3-17-10

Sheet 1 of 1

2.Address

Plant Byron Nuclear Power StationName

4450 N. German Church Road, Byron, ILAddress

Unit 02

P.O. 00451499Repair Organization, P.O. No., Job No., etc.

3. Work Performed by NWS Technologlea, LLC131 Venture BoulevardSpartanburg, SC 29306

Address

Type Code Symbol Stamp NR/Authorization No. 81/632Expiration Date 4-9-12 / 4-3-12

VR

4. Identification of System REACTOR COOLANT (RY)

5. (a) Applicable Construction Code ASME Section III 19 71 Edition, W72 Addenda, None Code Case(b) Applicable Edition of Section XI Used for Repair/Replacement Activity 2001 Edition / 2003 Addenda(c) Section XI Code Case(s) NONE

6. Identification of Components

Name ofComoonent

Name ofManufacturer

ManufacturerSerial No.

NationalBoard

No.

Corrected,Removed, or

Installed

ASMECode

Stamped(Yes or No)Other

IdentificationYearBuilt

4. 4 4. I 4 1PRESSURIZERNOZZLE TYPERELIEF VALVE

(NOZZLE)

Crosby Valve& Gage Co.

VALVE S/N:N56964-00-0049 N/A

CAT ID#1402762-1

UTC# 27053941976 CORRECTED YES

7. Description of Work VENDOR - MACHINED NOZZLE TO RETORE SEAT STEP & TOP OF FLANGE TOTOP OF SEAT DIMENSION.

8. Test Conducted: Hydrostatic [I Pneumatic C] Nominal Operating Pressure 0] Exempt 0OFOther El Pressure psi Test Temp.

Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 81/2 in. x 11 in., (2)information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the numberof sheets is recorded at the top of this form.

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FORM NIS-2 (Back)

9. Remarks P.O. 00451499Applicable Manufacturer's Data Reports to be attached

CERTIFICATE OF COMPLIANCEI certify that the statements made in the report are correct and this conforms to the requirements of the ASME

Code, Section Xl.Type Code Symbol Stamp Not ApplicableCertificate of Authorizatio No. Not ApplicableSigned l Date 3-/' ,20 10

Owner's Designee, Tide

CERTIFICATE OF INSERVICE INSPECTIONI, the undersigned, holding a valid commission issued by the National Board of Boiler and PressureVessel Inspectors and the State or Province of Illinois and employed by HSB CTof H rtford, CT have*sp ed the components described in this Owner's Report during the period

47o t4o ,and state that to the best of my knowledge and belief,the Owner has performed examinations and taken corrective measures described in this Owner'sReport 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 orimplied, concerning the examinations and corrective measures described in this Owner's Report.Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personalinjury or property damage or a loss of any kind arising from or connected with this inspection.

Commissions ,/Ze- 141e-

9

Inspector's Signature

Date: % f'00'f6' , 20 10

National Board, State Province, and Endorsements

(Final)

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FORM NVR-1 REPORT OF REPAIR IM REPLACEMENT 03OF NUCLEAR PRESSURE RELIEF DEVICES

1. work performed by: NWS Technologies, LLC Purchase Order# 451499131 Venture Boulevard, Spartanburg, SC 29306

2. Work performed for Exelon Corporation, Byron Nuclear Station

3/4. Owner - name, address and identification of nuclear power plant Exelon Corporation,Byron Nuclear Station 4450 N. German Church Road Byron, IL 61010

5. a: Repaired pressure relief device: Pressurizer Safety Valveb: Name of manufacturer: Crosby Valve & Gage Co.c: Identifying nos.

HB-86-BP N56964-000004 n/a steam 6" 1976(type) (Wt's S/N) (NB#) (suVice) (size) (yr.built)

d: Construction Code: ASME Section III 1971 W72 n/a 1(namne/section/dslon) (edition) (addends) (Code Caes(s)) (Code Class)

6. ASME Code Section XI applicable for Inservice Inspection: 2001 2003 r/a(edmion) (addenda) (Code Case(s))

7. ASME Code Section Xl used for repairs, replacements: 2001 2003 n/a(edition) (addends) (Code Case(s))

8. Construction Code used for repairs, replacements: 1971 W72 n/a(edition) (addenda) (Code Case(s))

9. Design responsibilities: n/a

10. Opening pressure: 2460 psigSet-pressure adjustment made at NWS Technologies, LLC using steam

11. Description of work incude name and Identifying number of replacement pafts): As-found tested (CEAR 09-49),disassembled, inspected, cleaned, machined nozzle to restore seat step (CEAR 10-25), lapped seats,checked nozzle torque, lubricated, assembled. Certified set-pressureusing steam. Jacked and lapped torestore seat integrity. Final seat tightness and bellows/gasket integrity verified using gaseous nitrogen.

12. Remarks: NWS Traveler # 09-280. No parts were replaced.

CERTIFICATE OF COMPLIANCEI, Cesar V. Sierra -certify that to the best of my knowledge and belief the statements made in thisreport are correct and the repair, modification or replacement of the pressure relief devices described aboveconforms to Section XI of the ASME Code and the National Board Inspection Code "VR" and "NR" rules.National Board Certificate of Authorization No. 632 to use the "VR" stamp expires April 3, 2012.Natal Board Certificate of Authorization No. 81 tu, the "N stai I April 9, 2012.

I Date Repair Organization repmentatveoAMa Tite

CERTIFICATE OF INSPECTIONI, Charles F. Toegel Jr. holding a valid commission issued by The National Board of Boiler and PressureVessel Inspectors and certificate of competency issued by the jurisdiction of North Carolina and employedby Hartford Steam Boiler of CT of Hartford, CT have inspected the repair, modificationor replacement described in this report on 1?AfMZO1o and state that to the best of my knowledge and belief,this repair, modification or replacement has been completed in accordance with Section XI of the of the ASME

Code and the National Board Inspection Code "VR" and "NR" rules.By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied,concerning this repair, modification or replacement described in this report. Futhermore, neither the undersignednor my employer shall be liable in any manner for any personal injury, property damage or loss of any kindarising from or connected th ins ""

NoB#1A(r 07 3 Uo.)

I Dat6 =WT110q~~~n";!r"9m 'J 7 cormmssi4pl~ioldtindren4P) uid~&n.

i~~~h4~ ,/9 M~ 6L

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FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITYAs Required by the Provisions of the ASME Code Section XI

1. Owner Exelon NuclearName

4300 Winfield Road, Warrenville, IL

Date 3-11 -10

Sheet 1 of 1

2.

3.

AddressPlant Byron Nuclear Power Station

Name4450 N. German Church Road, Byron, IL

Address

Work Performed by Trentec4600 East Tech Drive

Cincinnati, Ohio 45245Address

Unit 02

P.O. 00454346Repair Organization, P.O. No., Job No., etc.

Type Code Symbol StampAuthorization No. N-2934Expiration Date 4-9-10

NPT

4. Identification of System Primary Containment Purge (VO)

5. (a) Applicable Construction Code ASME Section III 1971 Edition, W73Addenda, None Code Case(b) Applicable Edition of Section XI Used for Repair/Replacement Activity 2001 Edition I 2003 Addenda(c) Section XI Code Case(s) NONE

6. Identification of Components

ASMECorrected, Code

National Removed, or StampedName of Name of Manufacturer Board Other Year Installed (Yes or No)

Component Manufacturer Serial No. No. Identification BuiltEQUALIZING VALVE CAT ID#

DEVICE TRENTIC HT# 736368 N/A 1420998-1 2008 REMOVED NO(PIVOT SHAFT) LOT# 50132266 UTC#

PN: 7M021-100-7 0002817047EQUALIZING VALVE CAT ID#

DEVICE TRENTIC HT# 736366 N/A 1420998-1 2010 INSTALLED NO(PIVOT SHAFT) LOT# 50193578 UTC#

PN" 7M021-1f00-7 0002817047EQUALIZING VALVE CAT ID#

DEVICE NOVA HT# 533740 N/A 1420998-1 2008 REMOVED NO(HEX HEAD BOLT) LOT# 50150355 UTC#PN: 7M021-100-Q9 Q002917047

EQUALIZING VALVE CAT ID#DEVICE NOVA HT# CR533740 N/A 1420998-1 2010 INSTALLED NO

(HEX HEAD BOLT) LOT# 50194461 UTC#PN_ 7M__ 1-10 n-000o2517047

EQUALIZING VALVE CAT ID#DEVICE NOVA HT# Q9641 N/A 1420998-1 2008 REMOVED NO

(HEX NUT) LOT# 50150348 UTC#PN6 7M021-100-31 000__817 47

EQUALIZING VALVE CAT ID#DEVICE NOVA HT# 990200 N/A 1420998-1 2010 INSTALLED NO

(HEX NUT) LOT# 50150357 UTC#PNe 7MO21-100-31 I I 000I2817047

7. Description of Work VENDOR REPLACED PIVOT SHAFT AND BOLTING ON EQUALIZING DEVICEEQUALIZING DEVICE SIN: EQ-2-7M021-6

8. Test Conducted: Hydrostatic [I Pneumatic [D Nonm

Other E] Pressure 55.06 psi

linal Operating Pressure [I Exempt [I

Test Temp. 75 OF

Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 81/ in. x 11 in., (2)information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the numberof sheets is recorded at the top of this form.

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FORM NIS-2 (Back)

9. Remarks P.O. 00454346Applicable Manufacturer's Data Reports to be attached

CERTIFICATE OF COMPLIANCEI 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 Not ApplicableCertificate of Authorization No. Not ApplicableSigned ,_ _r__ __ _ __ __ __ _" _ /_ _ __-- Date , - 7 ,20 10

( 1ý9)Ownses Designee, Tid

CERTIFICATE OF INSERVICE INSPECTIONI, the undersigned, holding a valid commission issued by the National Board of Boiler and PressureVessel Inspectors and the State or Province of lilinols and employed by HSB CT

of Hartford, CT have inspected the components described in this Owner's Report during the period/gly/7n/•,• to 1114Z,/Z , and state that to the best of my knowledge and belief,

ttfe O(vner has performed examinations and taken corrective measures described in this Owner'sReport 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 orimplied, concerning the examinations and corrective measures described in this Owner's Report.Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personalinjury or property d~amae or a loss of any kind arising from or connected with this inspection.q _. 4 .0 Commissions Iw - I.'9

-inspector's Signature National Board, State Province, and Endorsements

Date: ;,Iý / ,20 10

(Final)

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ER-AA-330-009Revision 5

Page 33 of 39

ATTACHMENT 5Repair Specification

Page 1 of 2

Purchase Order 00454346 P.O. Rev O Date 12-14-09

Repair OrganizationTrentec

The following requirements shall be completed or imposed for the procurement of a"Repair Organization' performing ASME Section XI Repairs/Replacements to ASMEcomponents.1) Description of Work

P.O. Rev 0 Vendor to refurbish egualizlna device (S/N - EQ-2-7M021-6).(CAT ID# 1420998-1). UTC# 2817047.

Replace Pivot Shaft (Dwa. No. 7M021-100) Piece No. 7)

2) Applicable Repair CodeConstruction Code: ASME Section II11 Class-MC, Subsection NE, 1971Edition / Winter of 1973 AddendaRepair I Replacement Code: ASME Section XI1 Class-MC. 2001 Edition 12003Addenda

3) Program Requirements

E] Work shall be performed in accordance with an 'N* Certificate Program reviewedand accepted by Exelon Nuclear Assessment.

El Work shall be performed in accordance with a National Board "NR" CertificateProgram reviewed and accepted by Exelon Nuclear Assessment.

[] Work shall be performed in accordance with a Quality Assurance Programapproved by Exelon Nuclear Assessment and accepted by the ANII, with thefollowing additional program requirements:Completed work shall be certified to be in compliance with this Repair SpecificationandASME Section XI, 2001 Edition 2003 Addenda.

C1 Special process procedures shall be provided to the site for acceptance prior touse.

Completed documentation of work shall be submitted to the Repair/ReplacementEngineer.

4) ExaminationP.O. Rev 0 None

5) TestingP.O. Rev 0 Leakaqe Test

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ER-AA-330-009Revision 5

Page 33 of 39

P.O. Rev 06) Documentation

Vendor to suppv:1. Certificate of Conformance2. CMTR for Pivot Shaft - Piece No.7 (to be reviewed by ANIN

ASME NIS-2 Form to be completed by Exelon personnel.

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ER-AA-330-009Revision 5

Page 33 of 39

Initial Review.

P.O. Rev g Repair / Replacement Engineer:.

ANII Concurrence:

P.O. Rev Repair / Replacement Engineer:

ANII Concurrence:

P.O. Rev Repair / Replacement Engineer:

ANII Concurrence:

P.O. Rev Repair / Replacement Engineer:

ANII Concurrence:

P.O. Rev Repair / Replacement Engineer:

ANII Concurrence:

Date: /Z , I/.,Date: 1

Date:

Date:

Date:

Date:

Date:

Date:

Date:

Date:

Page 219: Byron, Unit 2, Submittal of 90-Day Inservice Inspection Report for … · 2012-12-03 · BYRON STATION UNIT 2 REFUELING OUTAGE 15 INSERVICE INSPECTION REPORT 1.1.0 INTRODUCTION Inservice

ER-AA-330-009Revision 5

Page 34 of 39ATTACHMENT 5

Repair SpecificationPage 2 of 2

7) Final Acceptance - All documentation shall be accepted by theRepair/Replacement Engineer prior to purchase order closeout.

8) RemarksVendor 'Trentec" replaced the Pivot Shaft. Hex Head Bolts and Hex Nuts.Vendor supplied the replacement Parts and oerformed a pressure test toverify leakage,

Final Review:

Repair / Replacement Engineer.ANII Review:

-4 4 ý Date: --17,-/Date:

A

Page 220: Byron, Unit 2, Submittal of 90-Day Inservice Inspection Report for … · 2012-12-03 · BYRON STATION UNIT 2 REFUELING OUTAGE 15 INSERVICE INSPECTION REPORT 1.1.0 INTRODUCTION Inservice

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Page 221: Byron, Unit 2, Submittal of 90-Day Inservice Inspection Report for … · 2012-12-03 · BYRON STATION UNIT 2 REFUELING OUTAGE 15 INSERVICE INSPECTION REPORT 1.1.0 INTRODUCTION Inservice

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