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#REDIRECT [[BYRON 2013-0100, 90-Day Inservice Inspection Report for Interval 3, Period 3, (B2R17)]]
{{Adams
| number = ML13217A093
| issue date = 07/29/2013
| title = 90-Day Inservice Inspection Report for Interval 3, Period 3, (B2R17)
| author name = Kearney F A
| author affiliation = Exelon Generation Co, LLC
| addressee name =
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000455
| license number = NPF-066
| contact person =
| case reference number = 1.10.0101, BYRON 2013-0100
| document type = Inservice/Preservice Inspection and Test Report, Letter
| page count = 184
}}
 
=Text=
{{#Wiki_filter:ArExelon Generation July 29, 2013 LTR: BYRON 2013-0100 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 Byron Generating Station 4450 North German Church Road Byron, IL 61010-9794 www.exeloncorp.com
 
==SUBJECT:==
Byron Station Unit 2 90-Day Inservice Inspection Report for Interval 3, Period 3, (B2R17)The subject 90- Day Inservice Inspection Report for the Byron Station Unit 2, Refueling Outage Seventeen (B2R17) 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 2001 Edition through the 2003 Addenda. The report covers the inservice inspections conducted prior to and during the Unit 2 Spring 2013 refueling outage.ithere are any questions regarding this matter, please contact Steve Gackstetter, Regulatory Assurance Manager, at (815)-406-2800.
Respectfully, Site Vice President Byron Generating Station FAK/RGM!LMZ/cy
 
==Attachment:==
 
B2R1 7 Inservice Inspection Sumrnary Report -Spring 2013 outage kc1 f.
Ad,,:i BYRON ANU.- Exelon Generation.
UNIT 2 B2R17 Spring 2013 Outage INSERVICE INSPECTION
 
==SUMMARY==
REPORT For Inspection Activities from October 10, 2011 to May 1, 2013 Commercial Service Date August 21, 1987 Document Completion Date July 29, 2013 Exelon Generation Company (EGC, LLC)4300 Winfield Rd Warrenville, IL 60555 Byron Nuclear Power Station 4450 North German Church Rd.Byron, IL 61010 AVEMW ExeLon Generation.
BYRON UNIT 2 B2R17 INSERVICE INSPECTION
 
==SUMMARY==
REPORT SECTION SECTION DESCRIPTION PAGES i lCover Page 1 ii ITable of Contents 1 1.0 IReport Introduction 6 2.1 ISI -Weld / Component Listing 16 Examination 2.2 PSI -Weld / Component Listing 3 2.0 Summary 2.3 PSI -Bolts, Pumps, and Valves Listing 1 2ary 2.4 ISI -Pressure Tests 13 2.5 ISI -Component Supports 9 2.6 ISI -Snubbers 9 3.0 Status of Examination Completion for the Program Plan 7 1 4.0 IForm NIS-i: Preservice and Inservice Examinations 52 5.0 Form N IS-2: Repairs / Modifications 65 TOTAL PAGES IN REPORTI 183 1 BYRON STATION UNIT 2 REFUELING OUTAGE 17 INSERVICE 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 October 10, 2011, through May 1, 2013. The majority of these inspections were performed during the seventeenth refueling outage (B2R137) from April 8 through May 1, 2013.B2R17 is the first outage of the Third Period in the Third Inspection Interval.The examinations were performed in compliance with the rules and regulations of ASME Section Xl (applicable edition and addenda), pursuant to the requirements of 10 CFR 50.55a.See Section 1.7.0 for a listing of referenced documents.
This summary report meets the requirements of ASME Code, IWA-6000 for the inspection of Class 1 and 2 components and piping. Class CC and MC components in the Containment Inservice Inspection (CISI) program are included when examination results require reporting as specified in 10 CFR 50.55a.The Nondestructive Examination (NDE) Inservice Inspection (ISI) Program Plan for Class 1, 2, 3, CC, and MC components was developed in accordance with the requirements and intent of Section Xl Subsections IWA, IWB, IWC, IWD, IWE, IWF and IWL, 2001 Edition, through the 2003 Addenda.In addition to the ASME Section Xl requirements of examination, certain Nuclear Regulatory Commission (NRC) augmented ISI inspections and industry initiatives (NEI-03-08) were required.
The Byron Station Unit 2 augmented ISI examination requirements include: a) Class 1 pressure boundary for leakage at nominal operating pressure, in accordance with N RC Generic Letter 88-05;b) Class 1 Alloy 600 weld examinations in accordance with N-722, N-729-1 and N-770-1;c) Class 2 and 3 pressure boundary for leakage at nominal operating pressure, in accordance with NUREG 0737.d) Class 1 examinations of non-isolable Reactor Coolant System branch lines for Thermal Fatigue in accordance with MRP-146;e) Examination of RCP Flywheels in accordance with Regulatory Guide 1.14.Note: Specific requests for relief were developed and submitted for NRC review when the code and/or augmented requirement(s) were deemed impractical, results in excessive hardship, or an alternative examination method is determined as more suitable for the particular component.
 
====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 Section Xl of the ASME Code. The examination tables include the corresponding code category, item number, and component/weld selection in conformance with examination requirements of Subsections IWA, IWB, IWC, IWD, IWE, IWF, and IWL.Section 1.0 Page 1 of 6 BYRON STATION UNIT 2 REFUELING OUTAGE 17 INSERVICE INSPECTION REPORT For Class 1, 2, and certain non-class piping components, the requirements of Risk Informed Inservice Inspection (RI-ISI) are followed using EPRI TR1 12657 and Table 1 of ASME Code Case N-578-1.Augmented examinations as specified by NRC and industry initiatives are included in these tables.1.1.2 Identification of Exempted Components ASME Class 1 and Class 2 components, or parts of components, that are not included in the examination tables and are exempt from examination, as specified in Section Xl Paragraphs IWB and IWC-1200, and Tables IWB-2500-1 and IWC-2500-1 are identified in the ISI Program Plan in conjunction with technical justification(s) for exempting the component or system.Class 1 or 2 piping welds exempted by IWB and IWC-1200 are not included in the RI-ISI program. Previous selection and examination exemptions identified in Tables IWB and IWC-2500-1 for the piping Examination Categories B-F, B-J, C-F-i, and C-F-2, are not incorporated into the RI-ISI program. With the adoption of RI-ISI, piping welds classified as Risk Category 6 or 7 are not subject to examination.
 
====1.1.3 Implementation====
 
of the ISI Program Exelon Nuclear, or its designee, visually examined ASME components utilizing the following test methods: VT-1, VT-2, and VT-3. The components examined comply with the ISI Program Schedule, Byron Station Technical Specifications, and/or comply with the ASME Section Xl Repair/Replacement Program.Certified personnel performed and evaluated visual examinations (i.e., VT-1, VT-2, and VT-3) of Class 1, 2, and 3 components, and supports.
Exelon Nuclear personnel certification procedures comply with the requirements of ANSI/ASNT CP-189, 1995 Edition and ASNT SNT-TC-1A, 1984 Edition.Certified personnel performed and evaluated all NDE. Personnel were certified to the requirements of the ASNT SNT-TC-1A, 1984 Edition. Additionally, ultrasonic examiners were certified in accordance with ANSI/ASNT CP-189, 1995 Edition. The NDE procedures were developed and certified in conformance with ASME Section V and Xl as applicable.
All ISI NDE, including evaluation of flaw indications, were performed in accordance with the requirements stipulated under Section Xl IWA-2200.
For components incorporated into the RI-ISI program, the guidance for the examination volume for a given degradation mechanism is provided by the EPRI Topical Report while the guidance for the examination method is provided by Code Case N-578-1. Augmented examinations are performed using the examination method specified in the governing regulatory or industry documents.
 
====1.1.4 Significant====
 
Activities During B2R17 The reactor vessel head exterior surface was visually examined for evidence of leakage per the requirements specified in N-729-1 Note (4) for Item B4.10 components.
One repaired reactor head penetration was examined with surface and volumetric methods per Item B4.20 and the approved relief request 13R-16.During the refueling outage, the Alloy 600 welds were examined for PWSCC per the requirements specified in N-722-1: Section 1.0 Page 2 of 6 BYRON STATION UNIT 2 REFUELING OUTAGE 17 INSERVICE INSPECTION REPORT" All reactor vessel bottom-mounted instrument penetrations were visually examined for leakage Item B15.80 weldments." The steam generator primary channel head drains were visually examined for leakage for Item B15.120 weldments.
A mechanical stress improvement process was performed on the reactor hot and cold leg nozzle safe-end welds. After the stress improvement process, the welds were volumetrically examined per the requirements specified in ASME Code Case N-770-1. With this application, the safe-end welds are now classified as Inspection Item D under N-770-1.1.1.5 ASME Section Xl Code Cases The implementation of the risk-informed program as described in relief request 13R-02 utilized N-578-1. For Repair/Replacement activities, code cases are identified on the applicable Form NIS-2.N-460 Alternative Examination Coverage for Class 1 and Class 2 Welds.N-508-3 Rotation of Serviced Snubbers and Pressure Relief Valves for the Purpose of Testing.N-513-2 Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping.N-566-2 Corrective Action for Leakage Identified at Bolted Connections.
N-597-2 Requirements for Analytical Evaluation of Pipe Wall Thinning.N-639 Alternative Calibration Block Material.N-648-1 Alternative Requirements for Inner Radius Examinations of Class 1 Reactor Vessel Nozzles.N-665 Alternative Requirements for Beam Angle Measurements Using Refracted Longitudinal Wave Search Units.N-685 Lighting Requirements for Surface Examination N-686-1 Alternative Requirements for Visual Examinations, VT-1, VT-2, and VT-3 N-695 Qualification Requirements for Dissimilar Metal Piping Welds.N-696 Qualification Requirements for Appendix VIII Piping Examinations Conducted From the Inside Surface.N-700 Alternative Rules for Selection of Classes 1, 2, and 3 Vessel Welded Attachments for Examination.
N-705 Evaluation Criteria for Temporary Acceptance of Degradation in Moderate Energy Class 2 or 3 Vessels and Tanks N-706 Alternative Examination Requirements of Table IWB-2500-1 and Table IWC-2500-1 for PWR Stainless Steel Residual and Regenerative Heat Exchangers N-753 Vision Tests Section 1.0 Page 3 of 6 BYRON STATION UNIT 2 REFUELING OUTAGE 17 INSERVICE INSPECTION REPORT 1.1.6 Witness and Verification of Examination The inservice inspections were witnessed and/or verified by the Authorized Nuclear Inservice Inspectors (ANII): Jeff Hendricks and Greg Feigel. These inspectors are associated with Hartford Steam Boiler CT of Harford, Connecticut, Chicago Branch, at 2443 Warrenville Rd., Suite 500, Lisle, Illinois 60532.1.2.0 EXAMINATION SUMMARIES The following section lists the summaries of examinations performed during the refueling cycle. Refer to Section 2.0 for each summary table for information or for specific tests and examinations conducted during this term.Welds & Components Summaries Inservice Inspection
-Weld / Component Listing Preservice Inspection
-Weld / Component Listing Preservice 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 is contained 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 the reports.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 the reports.1.6.0 CONTAINMENT ISI PROGRAM No reportable conditions were identified for Class CC and Class MC components during this fuel cycle.1.7.0 REFERENCED DOCUMENTS 1.7.1 Code of Federal Regulations, Title 10 Energy 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 Xl, Rules for Inservice Inspection of Nuclear Power Plant Components, 2001 Edition, through 2003 Addenda Section 1.0 Page 4 of 6 BYRON STATION UNIT 2 REFUELING OUTAGE 17 INSERVICE INSPECTION REPORT Subsection IWA: General Requirements Subsection IWB: Requirements for Class 1 Components Subsection IWC: Requirements for Class 2 Components Subsection IWD: Requirements for Class 3 Components Subsection IWE: Requirements for Class MC/Class CC Metallic Liners Components Subsection IWF: Requirements for Class 1, 2, 3, and MC Component Supports Subsection IWL: Requirements for Class CC Concrete Components a) IWA-2200 Examination Methods b) IWA-6000:
Records and Reports c) IWB, and IWC-1200, Components Exempt from Examination d) IWB, IWC, IWE, IWF, and IWL-2500, Examination and Pressure Test Requirements 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-722-1: Additional Examinations for PWR Pressure Retaining Welds in Class 1 Components Fabricated With Alloy 600/82/182 Materials.
Code Case N-729-1: Alternative Examination Requirements for PWR Reactor Vessel Upper Heads With Nozzles Having Pressure-Retaining Partial-Penetration Welds.Code Case N-770-1: Alternative Examination Requirements and Acceptance Standards for Class 1 PWR Piping and Vessel Nozzle Butt Welds Fabricated with UNS N06082 or UNS W86182 Weld Filler Material With or Without Application of Listed Mitigation Activities.
Form NIS-1, Owners Report for Inservice Inspections.
Form NIS-2, Owners Report for Repairs or Replacements.
 
====1.7.3 American====
National Standards Institute
/ American Society for Nondestructive Testing ANSI/ASNT CP-189, 1995 Edition, Standard for Qualification and Certification of Nondestructive Testing Personnel.
 
====1.7.4 American====
Society for Nondestructive Testinq ASNT Recommended Practice No. SNT-TC-1A, 1984 Edition, Personnel Qualification and Certification in Nondestructive Testing.1.7.5 Miscellaneous NRC Documents Generic Letter 88-05, Boric Acid Corrosion of Carbon Steel Reactor Pressure Boundary Components in PWR Plants.NUREG 0737, Clarification of TMI Action Plan Requirements.
 
====1.7.6 Electric====
Power Research Institute Topical Report TR1 12657 Revision B-A, Revised Risk-Informed Inservice Inspection Procedure, December 1999.Section 1.0 Page 5 of 6 BYRON STATION UNIT 2 REFUELING OUTAGE 17 INSERVICE INSPECTION REPORT Materials Reliability Program: Management of Thermal Fatigue in Normally Stagnant Non-Isolable Reactor Coolant System Branch Lines (MRP-146, Revision 1), June 2011 1.7.7 Nuclear Energy Institute NEI 03-08, Guideline for the Management of Materials Issues.1.7.8 Byron Station Documents Relief Request 13R-02: Alternate Risk-Informed Selection and Examination Criteria for Category B-F, B-J, C-F- 1, and C-F-2 Pressure Retaining Piping Welds.Relief Request 13R-14: Alternative Requirements for the Repair of a Reactor Vessel Head Penetration In Accordance with 10 CFR 50.55a(a)(3)(i)
Relief Request 13R-1 6: Alternate Examination Frequency under ASME Code Case N-729-1 for Reactor Vessel Head Penetration Welds.Section 1.0 Page 6 of 6 7/25/2013 Exeleln -Byron Station Unit 2 B2R17 ISI Outage Report Weld / Component Outage Summary SYSTEM: Chemical & Volume Control System (CV)Section X: Com ponent ID L1"ine Number. Relief Technical Code Actual Results.I Cat. Description Requests Notes Coverage Exam Comments /~R-A R1.11 2CVA3B-2/W-70 2CVA3B-2 13R-02 B9.40 VT-2 NRI Pipe -Elbow 13T-01 13T-02 OBS 17-005 R-A R1.11 2CVA3B-2/W-71 2CVA3B-2 13R-02 B9.40 VT-2 NRI Elbow -Pipe 13T-01 13T-02 OBS 17-006 R-A R1.11 2CVA3B-2/W-72 2CVA3B-2 13R-02 B9.40 VT-2 NRI Pipe -Elbow 13T-01 13T-02 OBS 17-007 R-A R1.11 2CVA3B-2/W-73 2CVA3B-2 13R-02 B9.40 VT-2 NRI Elbow -Pipe 13T-01 13T-02 OBS 17-008 R-A R1.11 2CVA3B-2/W-80 2CVA3B-2 13R-02 B9.40 VT-2 NRI Pipe -Elbow 13T-01 13T-02 OBS 17-009 R-A R1.11 2CVA3B-2iW-81 2CVA3B-2 13R-02 B9.40 VT-2 NRI Elbow -Pipe 13T-01 13T-02 OBS 17-010 R-A R1.11 2CVA5AA-2/W-06 2CVA5AA-2 13R-02 89.40 VT-2 NRI Pipe -Elbow 13T-01 13T-02 OBS 17-011 R-A R1.11 2CVA5AA-2/W-07 2CVA5AA-2 13R-02 B9.40 VT-2 NRI Elbow -Pipe 13T-01 13T-02 OBS 17-012 R-A R1.11 2CVA6AA-2/W-04 2CVA6AA-2 13R-02 89.40 VT-2 NRI Pipe -Elbow 13T-01 13T-02 OBS 17-013 R-A R1.11 2CVA6AA-2/W-05 2CVA6AA-2 13R-02 89.40 VT-2 NRI Elbow -Pipe 13T-01 13T-02 OBS 17-014 R-A R1.11 2CVA7AA-2/W-06 2CVA7AA-2 13R-02 89.40 VT-2 NRI Pipe -Elbow 13T-01 13T-02 OBS 17-050 1 7/25/2013 Exe in., Byron Station Unit 2 B2R17 ISI Outage Report Weld / Component Outage Summary SYSTEM: Chemical & Volume Control System (CV)ectlon Xl,ýComponent 1D Line Number Relief Code. Actual Results.CatD"scription Requests: ,Notes ; ~ Coverage..
Exam.Comments-R-A R1.11 2CVA7AA-2/W-07 2CVA7AA-2 13R-02 19.40 VT-2 NRI Elbow -Pipe 13T-01 13T-02 OBS 17-051 R-A R1.11 2CVA7AA-2/W-08 2CVA7AA-2 13R-02 89.40 VT-2 NRI Pipe -Elbow 13T-01 13T-02 OBS 17-052 2 7/25/2013 Exeln ..............................
...~ .t t o ~ i Byron Station Unit 2 B2R17 ISI Outage Report Weld / Component Outage Summary SYSTEM: Feedwater System (FW)Section Xl, ComponetID
." Line Number Relief Technical C6 ..e Actual Results Cat. IDescription Requests.
Notes Coverage Exam Comments_
_ ._. ...R-A R1.11 2FW03DB-16/118 2FW03DB-16 13R-02 05.51 100 UT Nil R1.18 Pipe- Elbow 13T-01 13T-02 OBS 17-080 R-A R1.11 2FW03DB-16/C19 2FW03DB-16 13R-02 C5.51 100 UT NRI R1.18 Elbow-Pipe 13T-01 13T-02 OBS 17-081 R-A R1.11 2FW03DC-16/C21 2FW03DC-16 13R-02 C5.51 100 UT NRI R1.18 Pipe-Elbow 13T-01 13T-02 OBS 17-082 R-A R1.11 2FW03DC-16/C22 2FW03DC-16 13R-02 C5.51 100 UT NRI R1.18 Elbow-Pipe 13T-01 13T-02 OBS 17-083 Weld obstructed 11 "-17" CCW on downstream side due to non-removable support. Code coverage was not limited by the obstruction.
R-A R1.11 2FW87CA-6/C05 2FW87CA-6 13R-02 C5.51 100 UT NRI R1.18 Pipe-Pipe 13T-01 13T-02 OBS 17-125 R-A R1.11 2FW87CA-6/C06 2FW87CA-6 13R-02 C5.51 100 UT GEOM R1.18 Pipe-Elbow 13T-01 13T-02 OBS 17-126 ID Geometry at 0". Weld crown from 2" CCW to 2" CW ground flush to aid scanning across weld.R-A R1.11 2FW87CA-6/C07 2FW87CA-6 13R-02 C5.51 100 UT NRI R1.18 Elbow-Pipe 13T-01 13T-02 OBS 17-127 R-A R1.11 2FW87CA-6/C08 2FW87CA-6 13R-02 C5.51 100 UT NRI R1.18 Pipe-Elbow 13T-01 13T-02 OBS 17-128 R-A R1.11 2FW87CA-6/C09 2FW87CA-6 13R-02 C5.51 100 UT NRI R1.18 Elbow-Pipe 13T-01 13T-02 OBS 17-129 3 7/25/2013 Exeklnm Byron Station Unit 2 B2R17 ISI Outage Report Weld / Component Outage Summary SYSTEM: Reactor Coolant System (RC)Section XlL iComponentlD LineNurber Relief .Technical Cod ActuaL Results Cat. Description Requests.
Notes Coverage.
Exam Comments .., R-A R1.20 2RC01AA-29/JO1 2RC01AA-29 13R-02 B9.11 97 UT NRI Safe End -Pipe 13T-01 100 ET NRI 13T-02 OBS 17-132 Outlet Nozzle @ 338' Safe-End Weld. Post-MSIP automated UT and ET examination from ID surface. See WO 01480225 for reports.Scan obstructed by counterbore geometry.
Exam not credited for RI-ISI, see B2R16 for credited examination.
R-A R1.20 2RC01AA-29/J06 2RC01AA-29 13R-02 B9.40 VT-2 NRI SOL -Thermowell 13T-01 13T-02 OBS 17-015 R-A R1.20 2RC01AB-29/J01 2RC01AB-29 13R-02 B9.11 94 UT NRI Safe End -Pipe 13T-01 100 ET NRI 13T-02 OBS 17-133 Outlet Nozzle @ 2020 Safe-End Weld. Post-MSIP automated UT and ET examination from ID surface. See WO 01480225 for reports.Scan obstructed by counterbore geometry.
Exam not credited for RI-ISI, see B2R16 for credited examination.
R-A R1.20 2RC01AC-29/JO1 2RC01AC-29 13R-02 B9.11 98 UT NRI Safe End -Pipe 13T-01 100 ET NRI 13T-02 OBS 17-134 Outlet Nozzle @ 1580 Safe-End Weld. Post-MSIP automated UT and ET examination from ID surface. See WO 01480225 for reports.Scan obstructed by counterbore geometry.
Exam not credited for RI-ISI, see B2R16 for credited examination.
R-A R1.20 2RC01AD-29/JO1 2RC01AD-29 13R-02 B9.11 90 UT NRI Safe End -Pipe 13T-01 100 ET NRI 13T-02 OBS 17-135 Outlet Nozzle @ 220 Safe-End Weld. Post-MSIP automated UT and ET examination from ID surface. See WO 01480225 for reports.Scan obstructed by counterbore geometry (actual coverage:
90.28%). Exam not credited for RI-ISI, see B2R16 for credited examination.
R-A R1.15 2RC-01-R/RPVS-A F1 2RC-01-R 13R-02 85.10 100 UT NRI 815.90 RPV Nozzle Safe-End HL Loop D 13T-01 100 ET NRI A-2 13T-02 OBS 17-113 Outlet Nozzle @ 22' Safe-End Weld. Post-MSIP automated UT and ET examination from ID surface. Per N-722-1 Note(5) and N-770-1 Note(3), the UT examination is acceptable in lieu of the BMV. See WO 01480225 for reports.R-A R1.15 2RC-01-R/RPVS-B F1 2RC-01-R 13R-02 85.10 100 UT NRI B15.95 RPV Nozzle Safe-End CL Loop D 13T-01 100 ET NRI 13T-02 OBS 17-114 Inlet Nozzle @ 67' Safe-End Weld. Post-MSIP automated UT and ET examination from ID surface. Per N-722-1 Note(5) and N-770-1 Note(3), the UT examination is acceptable in lieu of the BMV. See WO 01480225 for reports.R-A R1.15 2RC-01-R/RPVS-C F1 2RC-01-R 13R-02 B5.10 100 UT NRI 815.95 RPV Nozzle Safe-End CL Loop C 13T-01 100 ET NRI 13T-02 OBS 17-115 Inlet Nozzle @ 1130 Safe-End Weld. Post-MSIP automated UT and ET examination from ID surface. Per N-722-1 Note(5) and N-770-1 Note(3), the UT examination is acceptable in lieu of the BMV. See WO 01480225 for reports.4 7/25/2013 Exekln,.Byron Station Unit 2 B2R17 ISI Outage Report Weld / Component Outage Summary SYSTEM: Reactor Coolant System (RC)Section Xl Component ID Number Relief Code I Actual e Results Cat.. Description Request Notes ..Coverage 1 Exam%, Comments ,.......,, R-A R1.15 2RC-01-R/RPVS-D F1 2RC-01-R B15.90 RPV Nozzle Safe-End HL Loop C A-2 13R-02 135.10 13T-01 13T-02 98 UT NRI 100 ET NRI OBS 17-116 Outlet Nozzle @ 1580 Safe-End Weld. Post-MSIP automated UT and ET examination from ID surface. Per N-722-1 Note(5) and N-770-1 Note(3), the UT examination is acceptable in lieu of the BMV. See WO 01480225 for reports.R-A R1.15 2RC-01-R/RPVS-E F1 2RC-01-R B15.90 RPV Nozzle Safe-End HL Loop B A-2 13R-02 135.10 13T-01 13T-02 100 100 UT NRI ET NRI OBS 17-117 Outlet Nozzle @ 2020 Safe-End Weld. Post-MSIP automated UT and ET examination from ID surface. Per N-722-1 Note(5) and N-770-1 Note(3), the UT examination is acceptable in lieu of the BMV. See WO 01480225 for reports.R-A R1.15 2RC-01-R/RPVS-F F1 2RC-01-R 815.95 RPV Nozzle Safe-End CL Loop B 13R-02 85.10 13T-01 13T-02 100 100 UT ET NRI NRI OBS 17-118 Inlet Nozzle @ 247- Safe-End Weld. Post-MSIP automated UT and ET examination from ID surface. Per N-722-1 Note(5) and N-770-1 Note(3), the UT examination is acceptable in lieu of the BMV. See WO 01480225 for reports.R-A R1.15 2RC-01-R/RPVS-G F1 2RC-01-R B15.95 RPV Nozzle Safe-End CL Loop A 13R-02 85.10 13T-01 13T-02 100 UT 100 ET NRI NRI OBS 17-119 Inlet Nozzle @ 2931 Safe-End Weld. Post-MSIP automated UT and ET examination from ID surface. Per N-722-1 Note(5) and N-770-1 Note(3), the UT examination is acceptable in lieu of the BMV. See WO 01480225 for reports.R-A R1.15 2RC-01-R/RPVS-H F1 2RC-01-R 615.90 RPV Nozzle Safe-End HL Loop A A-2 13R-02 85.10 13T-01 13T-02 100 UT NRI 100 ET NRI OBS 17-120 Outlet Nozzle @ 3380 Safe-End Weld. Post-MSIP automated UT and ET examination from ID surface. Per N-722-1 Note(5) and N-770-1 Note(3), the UT examination is acceptable in lieu of the BMV. See WO 01480225 for reports.R-A R1.20 2RC03AA-27.5/JO2A 2RC03AA-27.5 13R-02 B9.40 VT-2 NRI SOL -Thermowell 13T-01 13T-02 OBS 17-016 R-A R1.20 2RC03AA-27.5/J04 2RC03AA-27.5 13R-02 B9.40 VT-2 NRI SOL -Thermowell 13T-01 13T-02 OBS 17-017 R-A R1.20 2RC03AA-27.5/J12 2RC03AA-27.5 13R-02 69.11 91 UT NRI Elbow -Safe End 13T-01 100 ET NRI 13T-02 OBS 17-121 Inlet Nozzle @ 293' Safe-End Weld. Post-MSIP automated UT and ET examination from ID surface. See WO 01480225 for reports.Scan obstructed by counterbore geometry (actual coverage:
90.75%).5 7/25/2013 Exe k n.0 Byron Station Unit 2 B2R17 ISI Outage Report Weld / Component Outage Summary SYSTEM: Reactor Coolant System (RC)Sectl Xl "Component ID Line Number Relief Technical
.Actual Results.Cat-. -(scription Requests Note..Coverage4!":
Exam Comments .R-A R1.20 2RC03AB-27.5/J12 2RC03AB-27.5 13R-02 B9.11 95 UT NRI Elbow -Safe End 13T-01 100 ET NRI 13T-02 OBS 17-122 Inlet Nozzle @ 2470 Safe-End Weld. Post-MSIP automated UT and ET examination from ID surface. See WO 01480225 for reports.Scan obstructed by counterbore geometry.R-A R1.20 2RC03AC-27.5/J13 2RC03AC-27.5 13R-02 B9.11 96 UT NRI Elbow -Safe End 13T-01 100 ET NRI 13T-02 OBS 17-123 Inlet Nozzle @ 113' Safe-End Weld. Post-MSIP automated UT and ET examination from ID surface. See WO 01480225 for reports.Scan obstructed by counterbore geometry.R-A R1.20 2RC03AD-27.5/J12 2RC03AD-27.5 13R-02 B9.11 92 UT NRI Elbow -Safe End 13T-01 100 ET NRI 13T-02 OBS 17-124 Inlet Nozzle @ 670 Safe-End Weld. Post-MSIP automated UT and ET examination from ID surface. See WO 01480225 for reports.Scan obstructed by counterbore geometry.R-A R1.20 2RC13AA-2/W-01 2RC13AA-2 13R-02 B9.40 VT-2 NRI SOL- Pipe 13T-01 13T-02 OBS 17-026 R-A R1.20 2RC13AA-2/W-02 2RC13AA-2 13R-02 B9.40 VT-2 NRI Pipe -Tee 13T-01 13T-02 OBS 17-027 R-A R1.20 2RC13AA-2/W-03 2RC13AA-2 13R-02 B9.40 VT-2 NRI Tee -Reducer 13T-01 13T-02 OBS 17-028 R-A R1.20 2RC13AA-2/W-04 2RC13AA-2 13R-02 B9.40 VT-2 NRI Tee -Pipe 13T-01 13T-02 OBS 17-029 R-A R1.20 2RC13AA-2/W-05 2RC13AA-2 13R-02 89.40 VT-2 NRI Pipe -Valve 13T-01 13T-02 OBS 17-030 R-A R1.20 2RC13AB-2/W-01 2RC13AB-2 13R-02 B9.40 VT-2 NRI SOL -Pipe 13T-01 13T-02 OBS 17-031 R-A R1.20 2RC13AC-2/W-01 2RC13AC-2 13R-02 B9.40 VT-2 NRI SOL- Pipe 13T-01 13T-02 OBS 17-032 6 7/25/2013 Exehon-Byron Station Unit 2 B2R17 ISI Outage Report Weld / Component Outage Summary SYSTEM: Reactor Coolant System (RC)on- IXl:"'Component ID " 1Line Number Relief Technical Code., A:: 1ai, Results.Cat; Description Requests.
Notes Coverage Exam Comments..
R-A R1.20 2RC13AD-2/W-01 2RC13AD-2 13R-02 B9.40 VT-2 NRI SOL- Pipe 13T-01 13T-02 OBS 17-033 R-A R1.11 2RC14AA-2/W-01 2RC14AA-2 13R-02 B9.40 VT-2 NRI SOL -Pipe 13T-01 13T-02 OBS 17-036 R-A R1.11 2RC14AA-2/W-01A 2RC14AA-2 13R-02 69.40 VT-2 NRI Pipe -Tee 13T-01 13T-02 OBS 17-037 R-A R1.11 2RC14AA-2/W-01B 2RC14AA-2 13R-02 69.40 VT-2 NRI Tee -Reducer 13T-01 13T-02 OBS 17-038 R-A R1.11 2RC14AA-2/W-01C 2RC14AA-2 13R-02 B9.40 VT-2 NRI Tee -Pipe 13T-01 13T-02 OBS 17-039 R-A R1.11 2RC14AA-2/W-02 2RC14AA-2 13R-02 B9.40 VT-2 NRI Pipe -Elbow 13T-01 13T-02 OBS 17-040 R-A R1.11 2RC14AA-2/W-03 2RC14AA-2 13R-02 B9.40 VT-2 NRI Elbow -Pipe 13T-01 13T-02 OBS 17-041 R-A R1.11 2RC14AA-2/W-04 2RC14AA-2 13R-02 69.40 VT-2 NRI Pipe -Elbow 13T-01 13T-02 OBS 17-042 R-A R1.11 2RC14AA-2/W-05 2RC14AA-2 13R-02 B9.40 VT-2 NRI Elbow -Pipe 13T-01 13T-02 OBS 17-043 R-A R1.11 2RC14AA-2/W-06 2RC14AA-2 13R-02 69.40 VT-2 NRI Pipe -Valve 13T-01 13T-02 OBS 17-044 R-A R1.11 2RC14AA-2/W-07 2RC14AA-2 13R-02 B9.40 VT-2 NRI Valve -Pipe 13T-01 13T-02 OBS 17-045 7 7/25/2013 Exelk n.-Byron Station Unit 2 B2R17 ISI Outage Report Weld / Component Outage Summary SYSTEM: Reactor Coolant System (RC)Section Xl Component ID Li" Number Relief Technical Code. Actual.: Results. i Ct". Description'
:Requests Notes .Coverage Examn Comments R-A R1.11 2RC14AA-2/W-08 2RC14AA-2 13R-02 89.40 VT-2 NRI Pipe -Tee 13T-01 13T-02 OBS 17-046 R-A R1.11 2RC14AA-2/W-09 2RC14AA-2 13R-02 B9.40 VT-2 NRI Tee -Reducer 13T-01 13T-02 OBS 17-047 R-A R1.11 2RC14AA-2/W-10 2RC14AA-2 13R-02 B9.40 VT-2 NRI Tee -Pipe 13T-01 13T-02 OBS 17-048 R-A R1.11 2RC14AA-2/W-11 2RC14AA-2 13R-02 B9.40 VT-2 NRI Pipe -Valve 13T-01 13T-02 OBS 17-049 R-A R1.11 2RC16AA-2/W-03 2RC16AA-2 13R-02 B9.40 VT-2 NRI Valve -Pipe 13T-01 13T-02 OBS 17-053 R-A R1.11 2RC16AA-2/W-04 2RC16AA-2 13R-02 B9.40 VT-2 NRI Pipe -Elbow 13T-01 13T-02 OBS 17-054 R-A R1.11 2RC16AA-2/W-05 2RC16AA-2 13R-02 B9.40 VT-2 NRI Elbow -Pipe 13T-01 13T-02 OBS 17-055 R-A R1.11 2RC16AA-2/W-06 2RC16AA-2 13R-02 B9.40 VT-2 NRI Pipe -Elbow 13T-01 13T-02 OBS 17-056 R-A R1.11 2RC16AA-2/W-07 2RC16AA-2 13R-02 B9.40 VT-2 NRI Elbow -Pipe 13T-01 13T-02 OBS 17-057 R-A R1.11 2RC16AB-2/W-04 2RC16AB-2 13R-02 B9.40 VT-2 NRI Pipe -Elbow 13T-01 13T-02 OBS 17-058 R-A R1.11 2RC16AB-2/W-05 2RC16AB-2 13R-02 B9.40 VT-2 NRI Elbow -Pipe 13T-01 13T-02 OBS 17-059 8 7125/2013 Exe. ...Byron Station Unit 2 B2R17 ISI Outage Report Weld / Component Outage Summary SYSTEM: Reactor Coolant System (RC)bComponent ID RefLine Number Rle Technical Code :tuai Results.Cat. Description Requests Notes.. Coverage, Exam R-A R1.20 2RC16AC-2/W-08 2RC16AC-2 13R-02 B9.40 VT-2 NRI Pipe -SOL 13T-01 13T-02 OBS 17-024 R-A R1.20 2RC16AD-2/W-01 2RC16AD-2 13R-02 B9.40 VT-2 NRI Valve -Pipe 13T-01 13T-02 OBS 17-025 R-A R1.11 2RC21AA-8/J05 2RC21AA-8 13R-02 B9.11 100 UT NRI Pipe -Elbow 13T-01 13T-02 OBS 17-086 ID Geometry seen below recording levels.R-A R1.11 2RC21AA-8/J06 2RC21AA-8 13R-02 B9.11 100 UT NRI Elbow -Pipe 13T-01 13T-02 OBS 17-087 ID Geometry seen below recording levels.R-A R1.11 2RC21AB-8/J07 2RC21AB-8 13R-02 B9.11 100 UT NRI Pipe -Elbow 13T-01 13T-02 OBS 17-090 R-A R1.11 2RC21AB-8/J08 2RC21AB-8 13R-02 B9.11 100 UT NRI Elbow -Pipe 13T-01 13T-02 OBS 17-091 R-A R1.11 2RC21AB-8/J09 2RC21AB-8 13R-02 B9.11 100 UT NRI Pipe -Elbow 13T-01 13T-02 OBS 17-092 R-A R1.11 2RC21AB-8/J10 2RC21AB-8 13R-02 B9.11 100 UT NRI Elbow -Pipe 13T-01 13T-02 OBS 17-093 R-A R1.20 2RC22AA-1.5/W-01 2RC22AA-1.5 13R-02 69.40 VT-2 NRI SOL- Pipe 13T-01 13T-02 OBS 17-020 R-A R1.20 2RC22AA-1.5/W-05 2RC22AA-1.5 13R-02 B9.40 VT-2 NRI Elbow -Pipe 13T-01 13T-02 OBS 17-021 9 7/25/2013 ExeIon..Byron Station Unit 2 B2R17 ISI Outage Report Weld / Component Outage Summary SYSTEM: Reactor Coolant System (RC)'Section Xl Component ID " une Rellief Technical.
Code Results Cat. Description Requet..Notes Coverage Eam Comments R-A R1.20 2RC22AC-1.5/W-01 2RC22AC-1.5 13R-02 B9.40 VT-2 NRI SOL -Pipe 13T-01 13T-02 OBS 17-022 R-A Ri.20 2RC22AC-1.5/W-06 2RC22AC-1.5 13R-02 B9.40 VT-2 NRI Pipe -Tee 13T-01 13T-02 OBS 17-023 R-A R1.20 2RC22AD-1.5/W-01 2RC22AD-1.5 13R-02 B9.40 VT-2 NRI SOL -Pipe 13T-01 13T-02 OBS 17-018 R-A R1.20 2RC22AD-1.5/W-08 2RC22AD-1.5 13R-02 89.40 VT-2 NRI Pipe -Tee 13T-01 13T-02 OBS 17-019 R-A R1.20 2RC24AA-4/J06 2RC24AA-4 13R-02 B9.11 100 UT NRI Pipe -Elbow 13T-01 13T-02 OBS 17-094 R-A R1.20 2RC24AA-4/J07 2RC24AA-4 13R-02 B9.11 100 UT NRI Elbow -Pipe 13T-01 13T-02 OBS 17-095 R-A R1.20 2RC24AA-4/J09 2RC24AA-4 13R-02 B9.11 100 UT NRI Pipe -Elbow 13T-01 13T-02 OBS 17-096 R-A R1.20 2RC24AA-4/J10 2RC24AA-4 13R-02 89.11 100 UT NRI Elbow -Pipe 13T-01 13T-02 OBS 17-097 R-A R1.20 2RC26A-2/W-01 2RC26A-2 13R-02 89.40 VT-2 NRI SOL -Pipe 13T-01 13T-02 OBS 17-034 R-A R1.20 2RC26A-2/W-02 2RC26A-2 13R-02 89.40 VT-2 NRI Pipe -Valve 13T-01 13T-02 OBS 17-035 N/A N/A 2RC28A-3/Zone 1 2RC28A-3 100 UT NRI Elbow- SOL VE NRI OBS 17-130 UT and VE examinations of the weld (2RC28A-3/J07) and elbow base materials per MRP-146 requirements see WO 01577166 for reports.10 7/25/2013 Exekln.m Byron Station Unit 2 B2R17 ISI Outage Report Weld / Component Outage Summary SYSTEM: Reactor Coolant System (RC)Section Xi lComponentlD Line Number.. Relief Technical f Code Act. Iuali Results Cat. , .... Requests Notes, Coverage xam Comments " ': .; .. ..:/.. ... ... ... ....... ...R-A R1.11 2RC30AA-1.5/W-01.01 2RC30AA-1.5 13R-02 89.40 VT-2 NRI Valve -Reducer 13T-01 13T-02 OBS 17-079 11 7/25/2013 Exel kn Byron Station Unit 2 B2R17 ISI Outage Report Weld / Component Outage Summary SYSTEM: Reactor Pressure Vessel (RPV)Section XL:' comonent ID. Line Number " Relief Technical Code Actual Reslts Cat. ,-Description
:,, Requests, Notes Coverage Exam Comments .B-N-3 B13.70 2RC-01-R/CORE SUPP 2RC-01-R VT-3 NRI STRUCT Core Support Structure 0BS 17-112A Exam not credited for ASME XI, see B2R1 3 for credited examination.
Exam area accessible due to core barrel removal.B-N-2 B13.60 2RC-01-RPINT ATTACH 2RC-01-R VT-3 NRI NONBELT Interior Attachment Non-Beltline OBS 17-112B Exam not credited for ASME XI, see B2R13 for credited examination.
Exam area accessible due to core barrel removal. See WO 01481167 for reports.N/A B15.80 2RC-01-R/RPV BMI 2RC-01-R 100 VE NRI RPV Bottom Mounted Instruments OBS 17-109 Examination per N-722-1 requirements, see WO 01480227 for reports.N/A B4.20 2RC-01-R/RPV HEAD 2RC-01-R 13R-16 84 UT IND PEN RPV Head Penetrations J-Weld 13R-18 100 PT NRI OBS 17-110 Examination per N-729-1 requirements.
Penetration 68 only. See WO#01489754.
UT Indication classified as fabrication flaw from repair welding in B2R13. No change in flaw seen in this examination.
N/A B4.10 2RC-01-R/RPV HEAD 2RC-01-R VE NRI SURF RPV Head Penetrations OBS 17-111 BMV per N-729-1 requirements, see WO 01480228 for reports.B-N-1 B13.10 2RC-01-R/RPV 2RC-01-R VT-3 NRI INTERIOR RPV Interior Surfaces OBS 17-112 Minor debris noted and cleaned during final FOSAR. See WO 01481167 for reports.12 7/25/2013 Exelk n -Byron Station Unit 2 B2R17 ISl Outage Report Weld / Component Outage Summary SYSTEM: Reactor Coolant System (RY)Section Xl Component ID Line Number " .Rellefi ..Technical Code Actual Results Cat. Description R"quests"." Notes, Coverage Exam Comments R-A R1.11 2RY18A-2/W-01 2RY18A-2 13R-02 B9.40 V1T-2 NRI Valve -Pipe 13T-01 13T-02 OBS 17-001 R-A R1.11 2RY18A-2/W-02 2RY18A-2 13R-02 B9.40 VT-2 NRI Pipe -Elbow 13T-01 13T-02 OBS 17-002 R-A R1.11 2RY18A-2/W-03 2RY18A-2 13R-02 B9.40 VT-2 NRI Elbow -Pipe 13T-01 13T-02 OBS 17-003 R-A R1.11 2RY18A-2/W-04 2RY18A-2 13R-02 B9.40 VT-2 NRI Pipe -WOL 13T-01 13T-02 OBS 17-004 13 7/25/2013 Exel )n.Byron Station Unit 2 B2R17 ISI Outage Report Weld / Component Outage Summary SYSTEM: Steam Generator (SG)Section X1 :nCopGnent ID OTLine " Relief "Technicall dCoe Actual Results'J Cat." D-escriptin
.Requests .. Notes I-Coverage Exam Comments.,,,,,,, , ..N/A B15.120 2RC-01-BA/DRAIN 2RC-01-BA VE NRI SG Channel Head Drain OBS 17-105 Examination per N-722-1 requirements, see WO 01480204 for reports.C-A C1.20 2RC-01-BA/SGC-08 2RC-01-BA 100 UT RI Upper Barrel "B" -Upper Head OBS 17-098 30% DAC spot indication with no measurable through-wall depth. Evaluated as an ID surface imperfection.
No other indications seen.N/A B15.120 2RC-01-BB/DRAIN 2RC-01-BB VE NRI SG Channel Head Drain OBS 17-106 Examination per N-722-1 requirements, see WO 01480206 for reports.C-A C1.10 2RC-01-BB/SGC-05 2RC-01-BB 100 UT NRI Lower Barrel "B" -Transition Cone OBS 17-099 100% examination and review of previously identified indications.
Previous indications seen below recording criteria.
No change noted in PSI indications.
No recordable indications were seen with current recording criteria.C-B C2.21 2RC-01-BB/SGN-03 2RC-01-BB 100 MT IND Main Steam Nozzle 100 MT RI 100 UT NRI OBS 17-100 0.3" and 0.5" linear indications (0.375" maximum allowable).
Ref: IR 01503278 and EC 393397.Examination after blending.
Both indications 0.30" in length.N/A B15.120 2RC-01-BC/DRAIN 2RC-01-BC VE NRI SG Channel Head Drain OBS 17-107 Examination per N-722-1 requirements, see WO 01480220 for reports.N/A B15.120 2RC-01-BD/DRAIN 2RC-01-BD VE NRI SG Channel Head Drain OBS 17-108 Examination per N-722-1 requirements, see WO 01480222 for reports.14 7/25/2013 ExelIn -Byron Station Unit 2 B2R17 ISI Outage Report Weld / Component Outage Summary SYSTEM: Safety Injection System (SI)Sectl6n Xi Component ID "b ne Number .Relief Technical Coe" Actual Resulte Cat. Description Requests Notes .4 Covage Exam Comments R-A R1.11 2SI08HA-21W-01 2SI08HA-2 13R-02 B9.40 VT-2 NRI Reducer -Coupling 13T-01 13T-02 OBS 17-060 R-A R1.11 2SI08HA-2/W-02 2SI08HA-2 13R-02 B9.40 VT-2 NRI Coupling -Pipe 13T-01 13T-02 01S 17-061 R-A R1.11 2SI08HA-2/W-03 2SI08HA-2 13R-02 B9.40 VT-2 NRI Pipe -Flange 13T-01 13T-02 OBS 17-062 R-A R1.11 2SI08HA-2/W-04 2SI08HA-2 13R-02 B9.40 VT-2 NRI Flange -Pipe 13T-01 13T-02 OBS 17-063 R-A R1.11 2SI08HA-2/W-05 2SI08HA-2 13R-02 89.40 VT-2 NRI Pipe -Coupling 13T-01 13T-02 OBS 17-064 R-A R1.11 2SI08HA-2/W-06 2SI08HA-2 13R-02 B9.40 VT-2 NRI Coupling -Reducer 13T-01 13T-02 OBS 17-065 R-A R1.11 2SI08JA-1.5/W-01 2SI08JA-1.5 13R-02 B9.40 VT-2 NRI Reducer -Pipe 13T-01 13T-02 OBS 17-066 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 17-067 R-A R1.11 2SI08JA-1.5/W-03 2SI08JA-1.5 13R-02 B9.40 VT-2 NRI Elbow -Pipe 13T-01 13T-02 OBS 17-068 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 17-069 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 17-070 15 7/25/2013 ExeI~n..Byron Station Unit 2 B2R17 ISI Outage Report Weld / Component Outage Summary SYSTEM: Safety Injection System (SI)Section Xi Component ID Une Number Relief Technical tbCbe : ReIsults Cat. Description, " Number- Requests Notes Coverage].
Exam I Comments -R-A R1.11 2SI08JA-1.5/W-05A 2SI08JA-1.5 13R-02 89.40 VT-2 NRI Pipe -Valve 13T-01 13T-02 OBS 17-071 R-A R1.11 2SI08JA-1.5/W-05B 2SI08JA-1.5 13R-02 B9.40 VT-2 NRI Valve -Pipe 13T-01 13T-02 CBS 17-072 R-A R1.11 2SI08JA-1.5/W-06 2SI08JA-1.5 13R-02 B9.40 VT-2 NRI Pipe -Elbow 13T-01 13T-02 0BS 17-073 R-A R1.11 2SI08JA-1.5/W-07 2SI08JA-1.5 13R-02 B9.40 VT-2 NRI Elbow -Pipe 13T-01 13T-02 OBS 17-074 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 17-075 R-A R1.11 2SI08JA-1.5/W-11 2SI08JA-1.5 13R-02 89.40 VT-2 NRI Flange -Pipe 13T-01 13T-02 0BS 17-076 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 CBS 17-077 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 17-078 16 7/25/2013 Exelon, Byron Station Unit 2 B2R17 ISI Outage Report Weld / Component Outage Summary (Preservice Inspections)
SYSTEM: Reactor Coolant System (RC)Section Xl* Com'ponent iD Line Ntmber Relief ITechnical lCode jRequited Actual lResultis cat., itemi~Desdription Requests , Notes Coverage Exam Exdam.Comments -R-A R1.11 2RC30AA-1.5/W-01.01 2RC30AA-1.5 13R-02 B9.40 SURF PT NRI Valve -Reducer 13T-01 VT-2 V-T-2 NRI 13T-02 Baseline exams of socket weld W1 with valve 2SI8900A replacement.
See WO 01480597 for reports.R-A R1.11 2RC30AB-1.5/W-01.01 2RC30AB-1.5 13R-02 B9.40 100 SURF PT NRI Valve -Reducer 13T-01 VT-2 VT-2 NRI 13T-02 Baseline exams of socket weld W1 with valve 2SI8900B replacement.
See WO 01480589 for reports.R-A R1.11 2RC30AC-1.5/W-01.01 2RC30AC-1.5 13R-02 B9.40 100 SURF PT NRI Valve -Reducer 13T-01 VT-2 VT-2 NRI 13T-02 Baseline exams of socket weld W1 with valve 2SI8900C replacement.
See WO 01480596 for reports.R-A R1.11 2RC30AD-1.5/W-01.01 2RC30AD-1.5 13R-02 B9.40 SURF PT NRI Valve -Reducer 13T-01 VT-2 VT-2 NRI 13T-02 Baseline exams of socket weld W1 with valve 2SI8900D replacement.
See WO 01480599 for reports.1 7/25/2013 7/25/2013 Exe..nI.Byron Station Unit 2 B2R17 ISI Outage Report Weld / Component Outage Summary (Preservice Inspections)
SYSTEM: Safety Injection System (SI)Sectn iXl ID " ..Line Number Relief TechnicaliCoda "Required JActual .Results Cat. '"item Description., Requests.
Notes .Coverage Exam Exam Commets R-A NA 2SI03DA-2/W-01.01 2SI03DA-2 13R-02 B9.40 100 SURF PT NRI Valve -Pipe 13T-01 VT-2 VT-2 NRI 13T-02 Baseline exams of socket weld W3 with valve 2SI8905A replacement.
See WO 01025526 for reports.R-A NA 2SI03DA-2/W-02.01 2SI03DA-2 13R-02 B9.40 100 SURF PT NRI Pipe -Elbow 13T-01 VT-2 VT-2 NRI 13T-02 Baseline exams of socket weld W4 with valve 2SI8905A replacement.
See WO 01025526 for reports.R-A NA 2SI03DA-2/W-03.01 2SI03DA-2 13R-02 B9.40 SURF PT NRI Elbow -Pipe 13T-01 VT-2 VT-2 NRI 13T-02 Baseline exams of socket weld W5 with valve 2SI8905A replacement.
See WO 01025526 for reports.R-A R1.11 2SI08JA-1.5/W-35.01 2SI08JA-1.5 13R-02 B9.40 100 SURF PT NRI Pipe -Elbow 13T-01 VT-2 VT-2 NRI 13T-02 Baseline exams of socket weld W4 with valve 2SI8900A replacement.
See WO 01480597 for reports.R-A R1.11 2SI08JA-1.5/W-36.01 2SI08JA-1.5 13R-02 B9.40 100 SURF PT NRI Elbow -Pipe 13T-01 VT-2 VT-2 NRI 13T-02 Baseline exams of socket weld W3A with valve 2SI8900A replacement.
See WO 01480597 for reports.R-A R1.11 2SI08JA-1.5/W-37.01 2SI08JA-1.5 13R-02 B9.40 100 SURF PT NRI Pipe -Valve 13T-01 VT-2 VT-2 NRI 13T-02 Baseline exams of socket weld W2A with valve 2SI8900A replacement.
See WO 01480597 for reports.R-A R1.11 2SI08JB-1.5/W-38.01 2SI08JB-1.5 13R-02 B9.40 100 SURF PT NRI Elbow- Pipe 13T-01 VT-2 VT-2 NRI 13T-02 Baseline exams of socket weld W3 with valve 1S18900B replacement.
See WO 01470598 for reports.R-A R1.11 2SI08JB-1.5/W-39.01 2SI08JB-1.5 13R-02 B9.40 100 SURF PT NRI Pipe -Valve 13T-01 VT-2 VT-2 NRI 13T-02 Baseline exams of socket weld W2 with valve 1S18900B replacement.
See WO 01470598 for reports.R-A R1.11 2SI08JC-1.5/W-39.01 2SI08JC-1.5 13R-02 B9.40 100 SURF PT NRI Pipe -Elbow 13T-01 VT-2 VT-2 NRI 13T-02 Baseline exams of socket weld W4 with valve 2SI8900C replacement.
See WO 01480596 for reports.R-A R1.11 2SI08JC-1.5/W-40.01 2SI08JC-1.5 13R-02 B9.40 100 SURF PT NRI Elbow -Pipe 13T-01 VT-2 VT-2 NRI 13T-02 Baseline exams of socket weld W3 with valve 2SI8900C replacement.
See WO 01480596 for reports.R-A R1.11 2SI08JC-1.5/W-41.01 2SI08JC-1.5 13R-02 B9.40 SURF PT NRI Pipe -Valve 13T-01 VT-2 VT-2 NRI 13T-02 Baseline exams of socket weld W2 with valve 2SI8900C replacement.
See WO 01480596 for reports.2 7/25/2013 7/25/2013 Exe' pit n-Byron Station Unit 2 B2R17 ISI Outage Report Weld / Component Outage Summary (Preservice Inspections)
SYSTEM: Safety Injection System (SI)Section Xl. Component ID .lUne Number " Relie -Technical RCbde "... Ilequired Actual fResuitsi:ý Notes Coverage Exam: Examr , comments .R-A R1.11 2SI08JD-1.5/W-38.01 2SIO8JD-1.5 13R-02 B9.40 100 SURF PT NRI Pipe -Valve 13T-01 VT-2 VT-2 NRI 13T-02 Baseline exams of socket weld W2 with valve 2SI8900D replacement.
See WO 01480599 for reports.3 7/25/2013 7/25/2013 Exekein-.............
.. Byr- s a i n ~ i Byron Station Unit 2 B2R17 ISI Outage Report Detailed Inservice Inspection Bolts, Pumps, and Valves Listing (PSI)SYSTEM: Reactor Coolant System (RY)Section Xd, Component ID, Relief, Tchnical Actual Results, catItiem Description
<(' Rec"ueste Notes 5 E rh K : Comments -.B-G-2 B7.50 2RY03BA-6/FLG 1-12 VT-i NRI Piping Flange Bolting Baseline exam for 2RY8010A replacement.
See WO 01450986 for report.I 7/25/2013 7/25/2013 Exel n-Byron Station Unit 2 B2R17 ISI Outage Report Pressure Test Outage Summary SYSTEM: Auxiliary Feedwater System (AF)Section Xi C'mponent lD' , ' Reliefs T~ Actui!' Results.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 7/25/2013 7/2512013 Exelkn.Byron Station Unit 2 B2R17 ISI Outage Report Pressure Test Outage Summary SYSTEM: Containment Spray System (CS)I Section Xil&#xfd;; Component ID Relief, I Technlcal
.Actual Rsults Cat. Item"..] Requests lNotes Exam Commentes
<K: C-H C7.10 2-CS-2-1 13T-04 VT-2 RI Minor packing leak on 2CS001A (WO 1313175, IR 0121069 & 01039250).
Minor packing leak on 2CS002A (IR 01436621).
Body to Bonnet inactive leak on 2SIO01A (IR 01436560, BACC Evaluation BYR201211222).
C-H C7.10 2-CS-2-2 13T-04 VT-2 RI Packing leakage on 2CS009A (IR 01308001).
2 7/25/2013 7/2512013 Exelkn.Byron Station Unit 2 B2R17 ISI Outage Report Pressure Test Outage Summary SYSTEM: Chemical & Volume Control System (CV).'" Section Xl.jd'inpoRent.ID Rel f. cal Actual. Results Secton Coponet I so Notes Exam Requests Comments.
...C-H C7.10 2-CV-2-1 13T-04 VT-2 RI 2CV01PA pump seals (WO 01473434).
2CV01 PA pump casing Flange (IR 01439397)
BACC Eval BYR20116107.
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 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 RI RI -2CV131 (IR# 150) Boric Acid Leakage acceptable as-is per Eval# BYR201312102.
Dry boric acid, no active leak.C-H C7.10 2-CV-2-6 13T-04 VT-2 RI 2CV8117 Relief Valve Inlet Flange IR# 1507959. Boric Acid Evaluation#
BYR201312083 accepted this condition as-is. Dry Boric acid, no active leakage.C-H C7.10 2-CV-2-7 13T-04 VT-2 NRI C-H C7.10 2-CV-2-8 13T-04 VT-2 NRI 3 7/25/2013 7/25/2013 Exel n-.Byron Station Unit 2 B2R17 ISI Outage Report Pressure Test Outage Summary SYSTEM: Fuel Pool Cooling System (FC)Sectio X1ehial Ata Results Sect ConXl"Component ID I Actal cat. , oItemt es* '," ,,a, Comments-.-
C-H C7.10 2-FC-2-1 13T-04 VT-2 NRI 10- on dried boron on pipe cap downstream of 2FC007 4 7/25/2013 725/2013 Exelenm Byron Station Unit 2 B2R17 ISI Outage Report Pressure Test Outage Summary SYSTEM: Feedwater System (FW)SectionXt lComponent ID Relief rjTechnicalj Actual Results Cat. item Requests., Notes Exam.Comments-C-H 07.1 0 2-FW-2-2 13T-04 VT-2 NRI 5 7/25/2013 7/2512013 Exel In.Byron Station Unit 2 B2R17 ISI Outage Report Pressure Test Outage Summary SYSTEM: Main Steam System (MS)Section X1 'Component ID. Reief lrechnicalJ Actual Results Cst. ItemRequests , Notes Exam&#xfd;, 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 7/25/2013 7/2512013 ExeI n.Byron Station Unit 2 B2R17 ISI Outage Report Pressure Test Outage Summary SYSTEM: Off Gas System (OG)Section XI Component 1D Cat. Item Comments Relief 11 Technical Actual.: Results Requests I"Notes Exam C-H C7.10 2-OG-2-1 13T-04 VT-2 NRI 7 7/25/2013 7/25/2013 Exelk n.Byron Station Unit 2 B2R17 ISI Outage Report Pressure Test Outage Summary SYSTEM: Primary Containment (PC)Section Componet ID Rellef Technical Actual Results Cat. Item Requests Notes Exam I Comments .?..:*..C-H C7.10 2-PC-2-1 13T-04 VT-2 NRI 8 7/25/2013 7/25/2013 ExeN no Byron Station Unit 2 B2R17 ISI Outage Report Pressure Test Outage Summary SYSTEM: Process Sampling System (PS)Section Xi lComponent ID Relief: Technical' Actual,, Results.-Cat. Item Requests Notesj Exam Comments C-H C7.10 2-PS-2-3 13T-04 VT-2 NRI C-H C7.10 2-PS-2-4 13T-04 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 9 7/25/2013 712512013 Exekn..Byron Station Unit 2 B2R17 ISI Outage Report Pressure Test Outage Summary SYSTEM: Reactor Coolant System (RC)SectionXI'Co"nponent ID Relief T al Actual. Resis Cat....Item Re"u ets Nlotes Exam Comments B-P B15.10 2-RC-1-1 13T-04 VT-2 NRI VT-2 NRI WO 01491018-01 for RX under vessel examination.
10 7/25/2013 7/2512013 Exelkn.Byron Station Unit 2 B2R17 ISI Outage Report Pressure Test Outage Summary SYSTEM: Residual Heat Removal System (RH)Section xi ID .Relief Technical:
Actual Cat. Item., Rquests Notes Exam Commients C-H C7.10 2-RH-2-1 13T-04 VT-2 RI 2RH606 Packing leakage IR 01454402 BACC Eval BYR201211391.
2RH618 Packing leakage IR 01454391 BACC Eval BYR201211390.
2CS001A Previous minor packing leak (WO 1313175, IR 0121069 & 01039250).
C-H C7.10 2-RH-2-2 13T-04 VT-2 RI 2SI138B Pipe Cap IR 01434346 BACC Eval BYR201211224.
2SI8958B Body to Bonnet IR 01434359 BACC Eval BYR20117662.
2SIJ8BA-.75 Sight Glass Flange IR 01434364 Previous leakage IR 01355737 BACC Eval BYR20129548.
2RH01 PB Previous leakage IR 01185736 BACC Eval BYR20115402.
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 11 7/25/2013 7/25/2013 Exel n-Byron Station Unit 2 B2R17 ISI Outage Report Pressure Test Outage Summary SYSTEM: Safety Injection System (SI)Section XI Component ID cat. Item , Comments , C-H C7.10 2-SI-2-1 C-H C7.10 2-SI-2-2 C-H C7.10 2-SI-2-3 C-H C7.10 2-SI-2-4 2SI8958B Body to Bonnet Previous leakage IR 00712138 BACC Eval 2007-351 C-H C7.10 2-SI-2-5 Relief Technical Actual Results.Requests Notes Exam 13T-04 VT-2 NRI 13T-04 VT-2 NRI 13T-04 VT-2 NRI 13T-04 VT-2 RI 13T-04 VT-2 NRI 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 12 7/25/2013 7/2512013 Exe n.-Byron Station Unit 2 B2R17 ISI Outage Report Pressure Test Outage Summary SYSTEM: Essential Service Water System (SX)Section Xl Compinent ID Relief Technical Actual Results: cat ite Requests, ,,, Notes ....Exam , Comments, , 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 13 7/25/2013 7125/2013 Exek.n.Byron Station Unit 2 B2R17 ISI Outage Report SYSTEM: Section xi Cat. Itein Comments F-A F1.40 F-A F1.40 F-A F1.40 F-A F1.40 F-A F1.10 F-A F1.10 F-A F1.10 F-A F1.10 F-A F1.10 F-A F1.10 F-A F1.10 F-A F1.10 F-A F1.10 F-A F1.10 F-A F1.10 Component Support Outage Summary Chemical & Volume Control System (CV)Component ID inNumber:
[ReiiefI To'Descriptlon.:..
.JRequests 2CV-01-PA/Li 2CV-01 -PA CV PUMP 2A LUG 1 2CV-01 -PA/L2 2CV-01 -PA CV PUMP 2A LUG 2 2CV-01 -PA/L3 2CV-01 -PA CV PUMP 2A LUG 3 2CV-01 -PA/L4 2CV-01 -PA CV PUMP 2A LUG 4 2CV45B-2/2RY06120X 2CV45B-2 SEISMIC 2CV45B-2/2RY06121 X 2CV45B-2 SEISMIC 2CVA3B-2/2CV1 101 OX 2CVA3B-2 SEISMIC 2CVA3B-2/2CV1 5033X 2CVA3B-2 SEISMIC 2CVA3B-2/2CV16024X 2CVA3B-2 SEISMIC 2CVA3B-2/2CV16030X 2CVA3B-2 SEISMIC 2CVA3B-2/2CV1 6084X 2CVA3B-2 SEISMIC 2CVA5AA-2/2CV1 5018V 2CVA5AA-2 VARIABLE 2CVA5AA-2/2CV1 5021 X 2CVA5AA-2 SEISMIC 2CVA6AA-2/2CV09025X 2CVA6AA-2 SEISMIC 2CVA6AA-2/2CV25025X 2CVA6AA-2 SEISMIC Actual chnIcIa .40otesExam VT-3 VT-3 VT-3 VT-3 V-r-3 VT-3 V`T-3 V`T-3 V-r-3 VT-3 VrT-3 VT-3 VT-3 VT-3 tResults-NRI NRI NRI NRI NRI NRI NRI NRI NRI NRI NRI NRI NRI NRI NRI 1 712512013 Exe-.n. .Byron Station Unit 2 B2R17 ISI Outage Report Component Support Outage Summary SYSTEM: Feedwater System (FW)Section X1 Compone LieNumber Id ..Rellef [Technical
..tua* Res.Ufs+cat. Item T6;icnriptI~io Requ.ests.
Notes Exam Comments F-A F1.20 2FW03DA-1612FW02009X 2FW03DA-16 VT-3 NRI SEISMIC F-A F1.20 2FW87CA-6/2FW0601 1X 2FW87CA-6 VT-3 NRI SEISMIC F-A F1.20 2FW87CA-6/2FW06015X 2FW87CA-6 VT-3 NRI SEISMIC F-A F1.20 2FW87CD-6/2FW09002C 2FW87CD-6 VT-3 NRI CONSTANT 2 7/2512013 Exekrnm.Byron Station Unit 2 B2R17 ISI Outage Report Component Support Outage Summary SYSTEM: Main Steam System (MS)Section Xl Component ID ft~ Line Number Reliief Technical Actual Results, Cat. Item .Description Notes Exam Com m ents.- .. ... .. *.. .......F-A F1.20 2MS07AD-28/2MS01211R 2MS07AD-28 VT-3 NRI RIGID 3 712512013 Exelnt Byron Station Unit 2 B2R17 ISl Outage Report Component Support Outage Summary SYSTEM: Reactor Coolant System (RC)Section Xl ompqoet ID Line Number 7 I -Rellef,--J.
Technical Act: a eults'cat. becrnipotiD"n .i .. .Notes Exam Comments F-A F1.40 2RC-01-BB/ULR 2RC-01 -BB SG B UPPER LATERAL RESTRAINT F-A F1.40 2RC-01-R/S 2RC-01-R VT-3 NOLK REACTOR VESSEL SUPPORT F-A F1.10 2RC16AA-2/2CV12005X 2RC16AA-2 VT-3 NRI SEISMIC F-A F1.10 2RC24AA-4/2RY06016X 2RC24AA-4 VT-3 NRI SEISMIC F-A F1.10 2RC24AA-4/2RY06035X 2RC24AA-4 VT-3 NRI SEISMIC 4 7/25/2013 Exelon -Byron Station Unit 2 B2R17 ISI Outage Report Component Support Outage Summary SYSTEM: Residual Heat Removal System (RH)Section XI Component ID -Line Number Relief. &#xfd;"Technical Actual Results Cat. Item escrption Rqusts Notes Exam Comments~F-A F1.10 2RH01AA-12/2RH02053X 2RHO1AA-12 VT-3 NRI SEISMIC F-A F1.40 2RH-01 -PA/L1 2RH-01 -PA VT-3 NRI RH PUMP 2A LUG 1 F-A F1.40 2RH-01-PA/L2 2RH-01-PA VT-3 NRI RH PUMP 2A LUG 2 F-A F1.40 2RH-01-PA/L3 2RH-01-PA VT-3 NRI RH PUMP 2A LUG 3 F-A F1.40 2RH-02-AB/L1 2RH-02-AB VT-3 NRI RH HX B LUG 1 F-A F1.40 2RH-02-AB/SKT 2RH-02-AB VT-3 NRI RH HX B SKIRT 5 7/2512013 Exeikn -Byron Station Unit 2 B2R17 ISI Outage Report Component Support Outage Summary SYSTEM: Reactor Coolant System (RY)Section Xl Component ID Line Number Reliet Technical Actual Results cat. Item iDescription eu.., Exam Comments F-A F1.10 2RY01 B-6/2RY06022X 2RY01 B-6 VT-3 NRI SEISMIC F-A F1.10 2RY01 B-6/2RY06029X 2RY01 B-6 VT-3 NOLK SEISMIC F-A F1.10 2RY1 8A-2/2RY06115V 2RY18A-2 VT-3 NOLK VARIABLE 6 7/252013e n.Byron Station Unit 2 B2R17 ISI Outage Report Component Support Outage Summary SYSTEM: Safety Injection System (SI)Section XI Component ID. Line Number Relief 2:Technical Actual Results Cat. Item ReqDescipton "Rquests .Notes Exam-.Comments~F-A F1.20 2SI06CA-8/2SI01022X 2SI05CA-8 VT-3 NRI SEISMIC F-A F1.20 2SI05CA-8/2SI01026X 2SI05CA-8 VT-3 NRI SEISMIC F-A F1.20 2SI05CA-8/2SI01038X 2SI05CA-8 VT-3 NRI SEISMIC F-A F1.20 2SI05CA-8/2SI03021X 2SI05CA-8 VT-3 NRI SEISMIC F-A F1.20 2SI06CA-8/2SI03025V 2SI05CA-8 VT-3 NRI VARIABLE F-A F1.20 2SI05CA-8/2SI03029X 2SI05CA-8 VT-3 NRI SEISMIC F-A F1.10 2SI05DA-6/2SI01017X 2SI05DA-6 VT-3 NRI SEISMIC F-A F1.10 2SI05DA-6/2SI01029X 2SI05DA-6 VT-3 NRI SEISMIC F-A F1.10 2SI05DA-6/2SI01031X 2SI05DA-6 VT-3 NRI SEISMIC F-A F1.10 2SI05DA-6/2SI01032X 2SI05DA-6 VT-3 NRI SEISMIC F-A F1.10 2SI08E-3/2SI21022X 2S108E-3 VT-3 NRI SEISMIC F-A F1.10 2SI08FA-3/2SI23011X 2SI08FA-3 VT-3 NRI SEISMIC F-A F1.10 2SI08FA-3/2SI23012A 2SI08FA-3 VT-3 NRI ANCHOR F-A F1.10 2SIO8GB-1
-1/2/2SI25004X 2SI08GB-1-1/2 VT-3 NRI SEISMIC F-A F1.10 2SIOSGB-1
-1/2/2SI25007X 2SI08GB-1-1/2 VT-3 NRI SEISMIC F-A F1.10 2SI08JA-1
-1/2/2SI24012X 2SI08JA-1-1/2 VT-3 NRI SEISMIC F-A F1.10 2SI08JA-1
-1/2/2S12501 OX 2SI08JA-1-1/2 VT-3 NRI SEISMIC F-A F1.10 2SI08JA-1
-1/2/2S125012X 2SI08JA-1-1/2 VT-3 NRI SEISMIC 7 7/25/2013 ExelIo-n.Byron Station Unit 2 B2R17 ISI Outage Report Component Support Outage Summary SYSTEM: Safety Injection System (SI)Section Xl Component ID Ltne Nuimber Relief To .ina Actual. Results*~t Ite 119cito Requsts N.otes:. "":: Exam F-A F1.10 2SIA4B-8/2RH02083X 2SIA4B-8 VT-3 NRI SEISMIC 8 7/25/2013 Exel n Byron Station Unit 2 B2R17 ISI Outage Report Component Support Outage Summary SYSTEM: Essential Service Water System (SX)Secton Xl omponent :ID Line.Number I Relief Technical Actual, Reults Item Ds "o % :Requests Notes Exam Commenits F-A F1.20 2SX06BB-16/2PC-7A 2SX06BB-16 VT-3 NRI ANCHOR VT-3 NRI F-A F1.20 2SX06BB-16/2SX07001G 2SX06BB-16 VT-3 NRI GUIDE F-A F1.20 2SX06CB-14/2SX07007X 2SX06CB-14 VT-3 NRI SEISMIC F-A F1.20 2SX07BD-10/2SX09078X 2SX07BD-10 VT-3 NRI SEISMIC F-A F1.20 2SX07CB-10/2SX09038X 2SX07CB-10 VT-3 NRI SEISMIC F-A F1.20 2SX07CD-1 0/2SX09077X 2SX07CD-1 0 VT-3 NRI SEISMIC F-A F1.20 2SX07EB-14/2SX09011X 2SX07EB-14 VT-3 NRI SEISMIC F-A F1.20 2SX08BD-10/2SX07025X 2SX08BD-10 VT-3 NRI SEISMIC 9 7/2512013 Snubber Outage Summary (Page 1 of 9)SYSTEM: Containment Spray System (CS)Exe.n...Byron Station Unit 2 Byron Station Outage B2R17 Section Xl Component ID ILIne Number. Technical Actual Results.Cat. Item ..Description .N. .s " [Requests teExam Comments F-A F1.20 2CS02AB-1 0/2CS03B022S 2CS02AB-1 0 VT-3 NRI SNUBBER SR FT PASS Note: Section Xl Category numbers N/A-ed are exempt from IWF-1 220 and IWF-2500 tables 1 7/25/2013 E-xeI n-Byron Station Unit 2 Byron Station Outage B2R17 SYSTEM: section X11 Cat. Item, Comments.NA NA NA NA NA NA F-A F1.10 NA NA NA NA NA NA NA NA NA NA NA NA F-A F1.10 F-A F1.10 F-A F1.10 F-A Fi.10 Snubber Outage Summary (Page 2 of 9)Chemical & Volume Control System (CV)T .Component ID ". .} Llne Numb. Re ,lDescription 2CV10B-3/2CV04015S 2CV10B-3 SNUBBER 2CV1 OCA-3/2CV03002S 2CV10CA-3 SNUBBER 2CV10CA-3/2CV22002S 2CV1OCA-3 SNUBBER 2CV10DB-3/2CV02009S 2CV10DB-3 SNUBBER 2CV1 4EA-2/2CV34008S 2CV14EA-2 SNUBBER 2CV14EB-2/2CV36006S 2CV14EB-2 SNUBBER 2CV1 4EC-2/2CV40007S 2CV1 4EC-2 SNUBBER 2CV14ED-2/2CV41012S 2CV14ED-2 SNUBBER 2CV15E-3/4/2CV31020S 2CV15E-3/4 SNUBBER 2CV44AB-3/4/2CV65009S 2CV44AB-3/4 SNUBBER 2CV45-2/2CV22009S 2CV45B-2 SNUBBER 2CVA5AA-2/2CV1 5054S 2CVA5AA-2 SNUBBER 2CVA7AA-2/2CV25016S 2CVA7AA-2 SNUBBER 2CVB7A-3/2CV06004S 2CVB7A-3 SNUBBER lief .Technical uests Notes SR SR SR SR SR SR SR SR SR SR SR SR SR SR ActuaI~Exam VT-3 VT-3 FrF VT-3 VIF-3 FT VT-3 FT VT-3 FrF VT-3 FT VT-3 VTF-3 Fr VTF-3 FT VT-3 VT-3 VT-3 FT VT-3*Results NRI NRI PASS NRI NRI PASS NRI PASS NRI PASS NRI NRI NRI PASS NRI PASS NRI NRI NRI PASS NRI Note: Section Xl Category numbers N/A-ed are exempt from IWF-1220 and IWF-2500 tables 2 7/25/2013 Exe In.Byron Station Unit 2 Byron Station Outage B2R17 SYSTEM: Section X1 ICat. Itemnii Comments F-A F1.20 F-A F1.20 N/A SNUB N/A SNUB F-A F1.20 F-A F1.20 F-A F1.20 F-A F1.20 Snubber Outage Summary (Page 3 of 9)Feedwater System (FW)Component i dLineNumber:
Re Descrition
~Reqi 2FW03DA-16/2FW02012S 2FW03DA-1 6 SNUBBER 2FW87CA-6/2FW06013S 2FW87CA-6 SNUBBER 2FW87CB-6/2FW07004-S1 2FW87CB-6 SNUBBER 2FW87CB-6/2FW07004-S2 2FW87CB-6 SNUBBER 2FW87CB-6/2FW07005S 2FW87CB-6 SNUBBER 2FW87CB-6/2FW07006S 2FW87CB-6 SNUBBER 2FW87CB-6/2FW07014S 2FW87CB-6 SNUBBER 2FW87CB-6/2FW07019S 2FW87CB-6 SNUBBER ilieftS Technical uests, Notes Actual SR SR DBL SR DBL SR SR SR SR SR Eam VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 FT VT-3 FT Results NRI NRI NRI NRI NRI NRI NRI PASS NRI PASS Note: Section XI Category numbers N/A-ed are exempt from IWF-1220 and IWF-2500 tables 3 712512013 ExeIv; n.Byron Station Unit 2 Byron Station Outage B2R17 Snubber Outage Summary (Page 4 of 9)SYSTEM: Main Steam System (MS)Secilon X Component ID , Line Number ' Reiief Technical Adctual Results CAt* Item .pescription" Requests Notes Exam Comments N/A SNUB 2MS01AA-30.25/2MS05007-S1 2MS01AA-30.25 DBL VT-3 NRI SNUBBER SR FT PASS N/A SNUB 2MS01AA-30.25/2MS05007-S2 2MS01AA-30.25 DBL VT-3 NRI SNUBBER SR FT PASS F-A F1.20 2MS07AD-28/2MS01 088S 2MS07AD-28 VT-3 NRI SNUBBER SR FT PASS Note: Section Xl Category numbers N/A-ed are exempt from IWF-1220 and IWF-2500 tables 4 7/25/2013 Exet n-Byron Station Unit 2 Byron Station Outage B2R17 Snubber Outage Summary (Page 5 of 9)SYSTEM: Sect[6on X, *, Cat.:, Item.Comments F-A F1.40 F-A F1.40 F-A F1.40 F-A F1.40 F-A F1.40 F-A F1.40 F-A F1.40 F-A F1.40 F-A F1.10 F-A F1.10 F-A F1.10 F-A F1.10 NA NA F-A F1.10 Reactor Coolant System (RC)lComponent " .ne Number >Descrip,=o.
.2RC01 BA-2A/2RC01 BA-A 2RC01 BA-2A SNUBBER 2RC01 BA-2A/2RC01 BA-B 2RC01 BA-2A SNUBBER 2RC01 BB-2B/2RC01 BB-A 2RC01 BB-2B SNUBBER 2RC01 BB-2B/2RC01 BB-B 2RC01 BB-2B SNUBBER 2RC01 BC-2C/2RC01 BC-A 2RC01 BC-2C SNUBBER 2RC01 BC-2C/2RC01 BC-B 2RC01 BC-2C SNUBBER 2RC01 BD-2D/2RC01 BD-A 2RC01 BD-2D SNUBBER 2RC01 BD-2D/2RC01 BD-B 2RC01 BD-2D SNUBBER 2RC13AC-2/2CV15045S 2RC13AC-2 SNUBBER 2RC14AC-2/2CV09034S 2RC1 4AC-2 SNUBBER 2RC16AA-2/2CV12006S 2RC1 6AA-2 SNUBBER 2RC1 6AB-2/2CV24003S 2RC16AB-2 SNUBBER 2RC20AC-3/4/2RC1 8009S 2RC20AC-3/4 SNUBBER 2RC22AC-1.5/2RC1 8007S 2RC22AC-1-1/2 SNUBBER i Relief Tech nical Requests Notes SR SR SR SR SR SR SR SR SR SR SR SR SR SR~Actual Exam VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 FT VT-3 VT-3 VT-3 VT-3 FT VT-3 FT VT-3 FT Results.: NRI NRI NRI NRI NRI NRI NRI NRI PASS NRI NRI NRI NRI PASS NRI PASS NRI PASS F-A F1.10 2RC22AC-1.5/2RC18014S 2RC22AC-1-1/2 VT-3 NRI SNUBBER SR NA NA 2RC48BA-1/2/2RC90A001S SNUBBER 2RC48BA-1/2 VT-3 SR Fr NRI PASS Note: Section Xl Category numbers N/A-ed are exempt from IWF-1220 and IWF-2500 tables 5 7125/2013 Exe. .n..Byron Station Unit 2 Byron Station Outage B2R17 SYSTEM: Section XlI Cat. Item., Corments .F-A F1.10 F-A F1.10 F-A F1.10 NA NA NA NA Snubber Outage Summary (Page 6 of 9)Residual Heat Removal System (RH)Component.iD'Line Number Re Desc .......ription .:, ." "" .Reqi 2RHO1AA-12/2RH02068S 2RHO1AA-12 SNUBBER 2RHO1AB-12/2RH02003S 2RHOlAB-12 SNUBBER 2RHO1AB-12/2RH02013S 2RHO1AB-12 SNUBBER 2RH26AB-3/4/2RH02115S 2RH26AB-3/4 SNUBBER 2RH26AB-3/4/2RH02116S 2RH26AB-3/4 SNUBBER SR SR SR SR SR lief T Technical.
Actual" Results uests I Notes Exam : VT-3 FT VT-3 V'-3 VT-3 FT VT-3 NRI PASS NRI NRI NRI PASS NRI Note: Section X1 Category numbers N/A-ed are exempt from IWF-1220 and IWF-2500 tables 6 7/25/2013 FxIon-Byron Station Unit 2 Byron Station Outage B2R17 Snubber Outage Summary (Page 7 of 9)SYSTEM: Section X11 Cat Item Comments,.
N/A SNUB N/A SNUB F-A F1.10 F-A F1.10 N/A SNUB N/A SNUB F-A F1.10 F-A F1.10 NA NAReactor Coolant System (RY)CopOnnt ID : '"Line Number 2RY02B-3/2RY09067-S1 2RY02B-3 SNUBBER 2RY02B-3/2RY09067-S2 2RY02B-3 SNUBBER 2RY02B-3/2RY09100S 2RY02B-3 SNUBBER 2RY06A-3/2RY09012S 2RY06A-3 SNUBBER 2RY06A-3/2RY09060-S1 2RY06A-3 SNUBBER 2RY06A-3/2RY09060-S2 2RY06A-3 SNUBBER 2RY06A-3/2RY09078S 2RY06A-3 SNUBBER 2RY06A-3/2RY09101 S 2RY06A-3 SNUBBER 2RY07AC-3/4/2RY27016S 2RY07AC-3/4 SNUBBER Relief.. echnic~a.Requests,  DBL SR DBL SR SR SR DBL SR DBL SR SR SR SR Actual Exam,, V-1-3 VT-3 VT-3 FT VT-3 Vr-3 FT VT-3 FT VT-3 VT-3 VT-3 Rjuis NRI NRI NRI PASS NRI NRI PASS NRI PASS NRI NRI NRI F-A F1.10 2RY1 1A-14/2RY05010S 2RY11A-14 VT-3 NRI SNUBBER SR Fr PASS NA NA 2RY34CD-1/2/2RC91001S 2RY34CD-1/2 V--3 NRI SNUBBER SR FT PASS Note: Section Xl Category numbers N/A-ed are exempt from IWF-1 220 and IWF-2500 tables 7 712512013 Exel en-Byron Station Unit 2 Byron Station Outage B2R17 Snubber Outage Summary (Page 8 of 9)SYSTEM: Steam Generator Blowdown System (SD)Section XI Comp6nent ID , ", Line Number. Relie ,Tefi~nlcal Actual[ Results Cat. Item .EDescriptkan
* Reque.ts " Notes E"ar Comments~NA NA 2SDO1CA-2/2SD21034S 2SDO1CA-2 VT-3 NRI SNUBBER SR FT PASS NA NA 2SD01CD-2/2SD24026S 2SD01CD-2 VT-3 NRI SNUBBER SR FT PASS NA NA 2SDO1CF-2/2SD05002-S 1 2SDO1CF-2 DBL VT-3 NRI SNUBBER SR FT PASS NA NA 2SDO1 CF-2/2SD05002-S2 2SD01CF-2 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 8 7/25/2013 Exel6n.Byron Station Unit 2 Byron Station Outage B2R17 SYSTEM: Section, X1 Cat. Itemn Comments F-A F1.10 F-A F1.20 F-A F1.10 F-A F1.10 F-A F1.10 F-A F1.10 N/A SNUB N/A SNUB F-A F1.10 Snubber Outage Summary (Page 9 of 9)Safety Injection System (SI)Component ID, linNumber Re~Description.
..2SI04D-8/2RH02061 S 2SI04D-8 SNUBBER 2SI05CA-8/2SI01023S 2SI05CA-8 SNUBBER 2SI05DD-6/2SI03009S 2SI05DD-6 SNUBBER 2SI05DD-6/2SI03018S 2SI05DD-6 SNUBBER 2SI08JD-1.5/2SI22018S 2SI08JD-1.5 SNUBBER 2SI08JD-1.5/2SI22020S 2SI08JD-1.5 SNUBBER 2SI09BC-1 0/2SI09002-$1 2SI09BC-1 0 SNUBBER 2SI09BC-1 0/2SI09002-S2 2SI09BC-1 0 SNUBBER 2SI09BD-10/2SI03001S 2SI09BD-10 SNUBBER Tie ~chnical uests~ Note~s%SR SR SR SR SR SR DBL SR DBL SR SR Actual Exam FT VIF-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 FT Vr-3 NRI PASS NRI NRI NRI NRI PASS NRI NRI PASS NRI PASS NRI R~~UI*SF Note: Section Xl Category numbers N/A-ed are exempt from IWF-1220 and IWF-2500 tables 9 (This report is used to verify that the periodic requirements of Tables IWx-2412-1 will be met by BYRON STATION UNIT 2 -3RD INTERVAL ASME SECTIO EXAMINATION STATUS REPORT N Xl I (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 Total # Exams Completed
% Exams Completed Item No. Corp Selected Min Per I Max Min Per 2 Max Per 3 % Selected Period 1 Period 2 Period 3 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%B1.30 1 1 N/A 1 N/A N/A 0 N/A 0 100.00% 100.00% 100.00% 100.00%B1.40 1 1 N/A 0 N/A N/A 0 N/A 0 100.00% 0.00% 0.00% 0.00%Totals: 7 7 N/A 5 N/A N/A 0 N/A 0 100.00% 71.43% 71.43% 71.43%1. Examination completion exceeds 50.00% for 1 st Period. The examinations were performed at the beginning of the Inspection Interval as allowed by Relief Request 13R-01.2. (B13.21 and B13.40): Examinations deferred to the end of the interval as allowed by Table IWB-2500-1.
: 3. Completion percentages of the category are not required per IWB-2412(a)(3).
Category B-B Non-Deferred Exams B2.11 2 2 B2.12 2 2 0 0 1 1 0 0 100.00%100.00%0.00%0.00%50.00%50.00%50.00%50.00%B2.40 4 1 -0 -0 25.00% 100.00% 100.00% 100.00%Totals: 8 5 1 1 2 2 2 2 0 62.50% 20.00% 60.00% 60.00%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 Exams B3.110 6 6 1 -3 0 100.00% 16.67% 66.67% 66.67%B3.120 6 6 1 -4 0 100.00% 16.67% 83.33% 83.33%B3.140 8 8 -0 -0 100.00% 50.00% 50.00% 50.00%Totals: 20 20 4 6 10 4 7 8 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 Exams B3.90 8 8 B3.100 8 8 N/A N/A 8 8 N/A N/A N/A 0 N/A 0 N/A N/A 0 0 100.00% 100.00% 100.00%100.00% 100.00% 100.00%100.00%100.00%8 N/A 0 0 Totals: 16 16 N/A 16 N/A N/A 0 N/A 0 100.00% 100.00% 100.00% 100.00%1. Per Examination Category B-D, Note 5, for PWR's in the second and successive inspection intervals, these examinations may be deferred to the end of the interval provided no repair/replacement activities have been performed on the examination item, and no flaws or relevant conditions requiring successive inspections in accordance with IWB-2420(b) are contained in the examination item.Section 3.0 Page 1 of 7
: 2. (B3.90 & B3.100): Examination completion exceeds 50.00% for 1 st Period and 75.00% for this 2 nd Period. The examinations were performed at the beginning of the Inspection Interval as allowed by Relief Request 13R-01.Category B-G-1 Non-Deferred Exams B6.40 1 1 N/A 0 N/A N/A 1 N/A 0 100.00% 0.00% 100.00% 100.00%Totals: 1 1 N/A 0 N/A N/A 1 N/A 0 100.00% 0.00% 100.00% 100.00%1. A single component representing all of the 54 Reactor Vessel Threads in Flange to be examined.Category B-G-1 Deferred Exams B6.10 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 1 N/A 0 100.00% 0.00% 100.00% 100.00%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: 42 13 N/A 6 N/A N/A 0 N/A 0 30.95% 46.15% 46.15% 46.15%1. (B6.110 & 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 performed at the beginning of the Inspection Interval as allowed by Relief Request 13R-01.2. (B6.170):
A single component represents the five sets of CETC column nuts.3. (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 and Examination Category B-L-2, Note 1. Examination is required only once per inspection interval.4. (B6.190):
Four components are tracked in the database, each representing the associated Flange Surfaces for one of the four Reactor Coolant Pumps (4 total)as reported in the ISI Program Plan. The visual examination of these components is limited to only one of the pumps per 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 Category B-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.5. (16.210):
Eight components are tracked in the database, each representing all of the Bolts and associated Nuts, Bushings, and Washers and Flange Surfaces on 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 the valves 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 (This report is used to verify that the periodic requirements of Tables IWx-2412-1 will be met by BYRON STATION UNIT 2 -3RD INTERVAL ASME SECTIO EXAMINATION STATUS REPORT N XI (The percentage requirements of Tables IWx-2412-1 apply to the Category and were the interval schedule.)
-. ... ......... applied to each Item only when practical.)
I # of Total # Exams Completed I % Exams Completed Item No. Comp Selected Min Per 1 Max Min Per 2 Max Per 3 % Selected Period 1 Period 2 Period 3 6. (B6.220 & B6.230): Eight components are tracked in the database, each representing all of the Bolts and associated Nuts, Bushings, and Washers and Flange Surfaces 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 of the 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 Examination Category 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 Exams B7.10 2 0 N/A 0 N/A N/A 0 N/A 0 0.00% 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 1 N/A 0 N/A N/A 1 N/A 0 25.00% 0.00% 100.00% 100.00%B7.50 20 5 N/A 3 N/A N/A 1 N/A 0 25.00% 60.00% 80.00% 100.00%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 7 N/A 4 N/A N/A 2 N/A 0 12.28% 57.14% 85.71% 100.00%1. Total selected for the category is limited to the components made accessible by disassembly for maintenance.
: 2. (B7.10): Two components representing the CETC and RVLIS Clamp Bolts and associated Nuts as reported in the ISI Program Plan.3. (B7.20): A single component representing all 16 Pressurizer Manway Bolts and associated Nuts as reported in the ISI Program Plan.4. (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. Per B-G-2 Note 2, the examination is limited to those vessels examined under Category B-B.5. (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 in design, size, function, and service. Examination is required only once per inspection interval within each bolted connection group.6. (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 (144 total 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 only when a pump is disassembled for maintenance, repair, or volumetric examination or bolting is removed. Also, per Examination Category B-G-2, Note 2 and Examination 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, manufacturing method, and function.
Examination is required only once per inspection interval within each valve group.7. (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 for maintenance, 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.Examination is required only once per inspection interval within each valve group.Section 3.0 Page 3 of 7 (This report is used to verify that the periodic requirements of Tables IWx-2412-1 will be met by BYRON STATION UNIT 2 -3RD INTERVAL ASME SECTIO EXAMINATION STATUS REPORT N XI (The percentage requirements of Tables IWx-2412-1 apply to the Category and were the interval schedule.)
.. .......applied to each Item only when practical.)
# of Total # Exams Completed
% Exams Completed Item 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 Exams B10.10 2 1 0 0 -0 100.00% 0.00% 00.00% 0.00%B10.20 8 3 -2 -0 37.50% 33.33% 100.00% 100.00%Totals: 10 4 1 1 2 2 2 2 0 40.00% 25.00% 75.00% 75.00%1. (B10.10):
Per Code Case N-700, for single vessels, only one welded attachment shall be selected for examination.
The attachment selected for examination shall be an attachment under continuous load during normal system operation, or an attachment subject to a potential intermittent load (seismic, water hammer, etc.) during normal system operation if an attachment under continuous load does not exist. The selected weld is the pressurizer skirt support weld.2. (B130.20):
Per Examination Category B-K, Note 5, for piping, pumps, and valves, a sample of 10% of the welded attachments associated with the component supports 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 Exams B12.20 4 0 N/A 0 N/A N/A 0 N/A 0 0.00% 0.00% 0.00% 0.00%Totals: 4 0 N/A 0 N/A N/A 0 N/A 0 0.00% 0.00% 0.00% 0.00%1. The examination of oumI casinos is limited to onlv one of the oumos Derforming similar functions in the system per Examination Categorv B-L-2, Note 1. Als O, per Examination Category B-L-2, Note 2, examination is required only when a pump is disassembled for maintenance, repair, or volumetric examination.
Examination is required only once per inspection interval.
The total selected for the category is limited to the components made accessible by disassembly for maintenance.
Category B-M-2 Deferred Exams B12.50 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. 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 same size, design, manufacturing method, and function.
Examination is required only once per inspection interval within each valve group. The total selected for the category is limited to the components made accessible by disassembly for maintenance.
Section 3.0 Page 4 of 7 (This report is used to verify that the periodic requirements of Tables IWx-2412-1 will be met by BYRON STATION UNIT 2 -3RD INTERVAL ASME SECTIO EXAMINATION STATUS REPORT N XI (The percentage requirements of Tables IWx-2412-1 apply to the Category and were the interval schedule.)
..applied to each Item only when practical.)
I # of Total # Exams Completed
% Exams Completed Item No. Comp Selected Min Per 1 Max Min Per 2 Max Per 3 % Selected Period 1 Period 2 Period 3 Category B-N-1 Non-Deferred Exams B13.10 1 1 -1 -1 50.00% 100.00% 200.00% 300.00%Totals: 1 1 1 1 1 1 1 1 1 50.00% 100.00% 200.00% 300.00%1. "% Completed" exceeds 100% since the vessel interior is selected for examination once each period (three times during the interval).
Category B-N-2 Deferred Exams B13.60 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. Examination completion exceeds 50.00% for 1st Period and 75.00% for this 2nd Period. The examination was performed at the beginning of the Inspection Interval as allowed by Relief Request 13R-01.Category B-N-3 Deferred Exams B13.70 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. Examination completion exceeds 50.00% for 1st Period and 75.00% for this 2 nd Period. The examination was performed at the beginning of the Inspection Interval as allowed by Relief Request 13R-01.Category B-O Non-Deferred Exams B14.10 5 5 N/A 2 N/A N/A 1 N/A 0 100.00% 40.00% 60.00% 60.00%Totals: 5 5 N/A 2 N/A N/A 1 N/A 0 100.00% 40.00% 60.00% 60.00%1. 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 five components represent that 10% population.
Category B-P Non-Deferred Exams B15.10 1 1 N/A 2 N/A N/A 2 N/A 1 100.00% 200.00% 400.00% 500.00%Totals: 1 1 N/A 2 N/A N/A 2 N/A 1 100.00% 200.00% 400.00% 500.00%1. "% Completed" exceeds 100% since Class 1 pressure tests are performed each refueling outage.2. One component representing the five systems in Class 1 as reported in the ISI Program Plan.Section 3.0 Page 5 of 7 (This report is used to verify that the periodic requirements of Tables IWx-2412-1 will be met by BYRON STATION UNIT 2 -3RD INTERVAL ASME SECTION XI EXAMINATION 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 wnen practical.)
# of Total # Exams Completed
% Exams Completed Item No. Comp Selected Min Per 1 Max Min Per 2 Max Per 3 % Selected Period 1 Period 2 Period 3 Category C-A Non-Deferred Exams C1.10 14 3 1 -1 1 21.43% 33.33% 66.67% 100.00%C1.20 6 1 0 1 16.67% 0.00% 0.00% 100.00%C1.30 4 1 -0 -0 25.00% 100.00% 100.00% 100.00%Totals: 24 5 1 2 2 1 1 1 2 20.83% 40.00% 60.00% 100.00%1. (C1.10 & 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 be limited to one vessel or distributed among the vessels.Category C-B Non-Deferred Exams C2.21 16 3 C2.22 4 1 1 1 1-0 1 0 18.75%25.00%20.00%33.33%100.00%50.00%66.67%100.00%75.00%100.00%100.00%100.00%Totals: 20 4 1 2 2 1 1 1 1 1. Per Examination Category C-B, Note 4, in the case of multiple vessels of similar design, size, and service, the required examinations may be limited 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 Exams C3.10 2 1 C3.20 76 8 C3.30 20 2 0-1-1 1 3 1 0 0 0 50.00% 0.00% 100.00%10.53% 12.50% 50.00%10.00% 50.00% 100.00%11.22% 18.18% 63.64%100.00%50.00%100.00%63.64%Totals: 98 11 2 2 5 4 5 6 0 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 the multiple vessels shall be selected for examination.
Conservatively, a welded attachment of each type of welded attachment of one of multiple vessels will be examined.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 the component supports selected for examination under IWF-2510 shall be examined.
This requirement is conservatively interpreted to mean that 10% of the total Class 2 welded attachments shall be examined.Section 3.0 Page 6 of 7 (This report is used to verify that the periodic requirements of Tables IWx-2412-1 will be met by BYRON STATION UNIT 2 -3RD INTERVAL ASME SECTION FYAMINATION STATUS REPORT (I (The percentage requirements of Tables IWx-1 2412-1 apply to the Category and were the interval schedule.)
applied to each Item only wnen practical.)
# of Total # Exams Completed
% Exams Completed Item No. Comp Selected Min Per I Max Min Per 2 Max Per 3 % Selected Period 1 Period 2 Period 3 Category C-H Non-Deferred Exams C7.10 70 50 N/A 50 N/A N/A 50 N/A 38 71.43% 100.00% 200.00% 276.00%Totals: 70 50 N/A 50 N/A N/A 50 N/A 38 71.43% 100.00% 200.00% 276.00%1. Seventy test components representing the twenty-four systems in Class 2 as reported in the ISI Program Plan.2. Fifty test components not exempted from test requirements by IWA-5110(c).
: 3. "% Exams Completed" exceeds 100% since the non-exempt Class 2 pressure tests are performed each inspection period.Category F-A Non-Deferred Exams F1.10 467 120 -28 -15 25.70% 29.17% 52.50% 65.00%F1.20 662 111 -44 -15 16.77% 23.42% 63.06% 76.58%F1.30 370 41 -17 -6 11.08% 21.95% 63.41% 78.05%F1.40 75 33 -11 -3 44.00% 21.21% 54.55% 63.64%Totals: 1573 305 49 77 152 76 100 151 39 19.38% 25.25% 58.03% 70.82%1. (Fl.40): Per Examination Category F-A, Note 3, for multiple components other than piping within a system of similar design, function, and service, the supports of only one of the multiple components are required to be examined.Category R-A Non-Deferred Exams (showing Risk-Informed Categories)
Cat. 1 242 61 23 Cat. 2 218 65 72 Cat. 3 0 --Cat. 4 1550 170 78 -Cat. 5 405 41 -Totals: 2415 337 130 224 405 161 20 57 9 32 29 32 25.21%29.82%10.97%10.12%13.95%37.70% 70.49% 85.25%32.58% 58.37% 72.85%56 26.35%30.47%30.09%45.27%58.80%54.62%55.07%72.53%67.20%66 32 199 364 0 1. For the requirements of Risk-Informed (RI-ISI) methodology, the individual categories have minimum selection percentages.
High Risk categories (1, 2 and 3)require 25% of the population be selected.
Medium Risk categories (4 and 5) require 10% of the population be selected.2. The populations include all Break Exclusion Region (BER) welds which have been integrated into the RISI Program and are selected in accordance with the Risk Informed BER methodology.
: 3. Per -2410 of N-578-1, the examinations of Category R-A shall be completed during each inspection interval in accordance with Table IWB-2412-1.
: 4. The number of socket weld examinations exceeds the number selected since 100% of the selected socket welds are examined each outage per ASME Code Case N-578-1, Table 1, Note 12. The total number of examinations for the interval is 811 on 337 selected components.
The percentage of completed examinations for each period is determined from the total number of examinations for the interval in Category R-A.Section 3.0 Page 7 of 7 7/25/2013 Exelon.Byron Station Unit 2 B2R17 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 1 of 52)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 National Appurtenance 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) 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 at the top of this form.Computer Generated Form 712512013 Exelkn.Byron Station Unit 2 B2R17 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 2 of 52)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 National Appurtenance 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 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 at the top of this form.Computer Generated Form 7125/2013 Exeln-Byron Station Unit 2 B2R17 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 3 of 52)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 National Appurtenance or Installer Serial No. Province No. Board No.2CS02AB- Pacific Scientific 3517 NA NA 10/2CS03B022S 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 at the top of this form.Computer Generated Form 712512013 Exe In.Byron Station Unit 2 B2R17 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 4 of 52)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)Component or Manufacturer Manufacturer State or National Appurtenance or Installer Serial No. Province No. Board No.2-CSV-2-1 Hunter Corporation N/A N/A N/A 2-CV-2-10 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 2-CV-2-6 Hunter Corporation N/A N/A N/A J 2-CV-2-8 Hunter Corporation j N/A N N/AN/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) 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 at the top of this form.Computer Generated Form 7/25/2013 Exela n-Byron Station Unit 2 B2R17 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 5 of 52)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 National Appurtenance or Installer Serial No. Province No. Board No.2CV-01-PA/Li Pacific Pumps 49772 NA 204 2CV-01-PA/L2 Pacific Pumps 49772 NA 204 2CV-01-PA/L3 Pacific Pumps 49772 NA 204 2CV-01-PA/L34 Pacific Pumps 49772 NA 204 2CV45B-2/2RY0612PX Hunter Corp. NA NA NA 2CV45B-2/2RY061210X Hunter Corp. NA NA NA 2CVA3B-2/2CV11010X Hunter Corp. NA NA NA 2CVA3B-2/2CV1 5033X Hunter Corp. NA NA NA 2CVA3B-2/2CV1 6024X Hunter Corp. NA NA NA 2CVA3B-2/2CV1 6032X Hunter Corp. NA NA NA 2CVA3B-2/2CV16084X Hunter Corp. NA NA NA 2CVA5AA- Hunter Corp. NA NA NA 2/2CV15018V 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 at the top of this form.Computer Generated Form 7/2512013 Exe1 n .Byron Station Unit 2 B2R17 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 6 of 52)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)Component or Manufacturer Manufacturer State or National Appurtenance or Installer Serial No. Province No. Board No.2CVA5AA- Hunter Corp. NA NA NA 2/2CV1 5021 X 2CVA6AA- Hunter Corp. NA NA NA 2/2CV09025XII 2CVA6AA- Hunter Corp. NA NA NA 2/2CV25025X I I I 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 at the top of this form.Computer Generated Form 7125/2013 Exeb n.-Byron Station Unit 2 B2R17 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 7 of 52)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 National Appurtenance 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 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 at the top of this form.Computer Generated Form 7125/2013 Exel en.Byron Station Unit 2 B2R17 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 8 of 52)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)Component or Manufacturer Manufacturer State or National Appurtenance or Installer or Installer Province No. Board No.Serial No.2CVA7AA-2/W-08 Hunter Corp. 2-CV-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) 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 at the top of this form.Computer Generated Form 7/25/2013 Exel in Byron Station Unit 2 B2R17 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 9 of 52)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)Component or Manufacturer Manufacturer State or National Appurtenance or Installer Serial No. Province No. Board No.2CV1 OB-3/2CV04015S Pacific Scientific NA NA NA 2CV1OCA- Pacific Scientific 17350 NA NA 3/2CV03002S 2CV1OCA- Pacific Scientific 7738 NA NA 3/2CV22002S 2CV1 0DB- Pacific Scientific 2184 NA NA 3/2CV02009S 2CV134EA-Lisega 31200814-006 NA NA 2/2CV34008S 2CV14EB- Pacific Scientific 9869 NA NA 2/2CV36006S 2CV14EC- Lisega 31200814-004 NA NA 2/2CV40007S 2CV1 4ED- Pacific Scientific 20454 NA NA 2/2CV41012S 2CV145E- Lisega 31200814-003 NA NA 3/4/2CV31020S 2CV44AB- Lisega 31200814-009 NA NA 3/4/2CV65009S 2CV45-2/2CV22009S Pacific Scientific 2195 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) 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 at the top of this form.Computer Generated Form 7/2512013 Exe. n..Byron Station Unit 2 B2R17 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 10 of 52)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)Component or Manufacturer Manufacturer State or National Appurtenance or Installer Serial No. Province No. Board No.2CVA5AA- Pacific Scientific 4462 NA NA 2/2CV1 5054S 2CVA7AA- Pacific Scientific 20711 NA NA 2/2CV25016S P S 1 N 2CVB7A-3/2CV06004S I Pacific Scientific 1 16680 1 NA I 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) 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 at the top of this form.Computer Generated Form 712512013 Exe.ltn.-Byron Station Unit 2 B2R17 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 11 of 52)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)Component or Manufacturer Manufacturer State or National Appurtenance 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) 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 at the top of this form.Computer Generated Form 7/2512013 Exekrnw Byron Station Unit 2 B2R17 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 12 of 52)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:
Feedwater System (FW)Component or Manufacturer Manufacturer State or National Appurtenance or Installer or Installer Province No. Board No.Serial 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) 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 at the top of this form.Computer Generated Form 7/2512013 Exel n.Byron Station Unit 2 B2R17 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 13 of 52)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:
Feedwater System (FW)Component or Manufacturer Manufacturer State or National Appurtenance or Installer Serial No. Province No. Board No.2FW03DA- Hunter Corp. NA NA NA 16/2FW02009X 2FW87CA- Hunter Corp. NA NA NA 6/2FW06011X X I I 2FW87CA- Hunter Corp. NA NA NA 6/2FW06015X I 2FW87CD- Hunter Corp. NA NA NA 6/2FW09002CI 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 at the top of this form.Computer Generated Form 7/2512013 E xeIon.Byron Station Unit 2 B2R17 ISl Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 14 of 52)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 National Appurtenance or Installer Serial No. Province No. Board No.2FW03DB-16/C18 Hunter Corp. 2-FW-1-N5 NA NA 2FW03DB-16/C19 Hunter Corp. 2-FW-1-N5 NA NA 2FW03DC-16/C21 Hunter Corp. 2-FW-1-N5 NA NA 2FW03DC-16/C22 Hunter Corp. 2-FW-1-N5 NA NA 2FW87CA-6/C05 Hunter Corp. 2-FW-1-N5 NA NA 2FW87CA-6/C06 Hunter Corp. 2-FW-1-N5 NA NA 2FW87CA-6/C07 Hunter Corp. 2-FW-1-N5 NA NA 2FW87CA-6/C08 Hunter Corp. 2-FW-1-N5 NA NA 2FW87CA-6/C09 Hunter Corp. 2-FW-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) 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 at the top of this form.Computer Generated Form 712512013 Exel n.Byron Station Unit 2 B2R17 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 15 of 52)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 National Appurtenance or Installer Serial No. Province No. Board No.2FW03DA- Pacific Scientific 2565 NA NA 16/2FW02012S 2FW87CA- Pacific Scientific 2865 NA NA 6/2FW06013S IIII 2FW87CB- Pacific Scientific 25717 NA NA 6/2FW07004-S1 2FW87CB- Pacific Scientific 20690 NA NA 6/2FW07004-$2 2FW87CB- Pacific Scientific 18342 NA NA 6/2FW07005S 2FW87CB- Pacific Scientific 8202 NA NA 6/2FW07006S 2FW87CB- Pacific Scientific 5939 NA NA 6/2FW07014S 2FW87CB- Pacific Scientific 2821 NA NA 6/2FW07019S 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 at the top of this form.Computer Generated Form 7/2512013 Exel n.Byron Station Unit 2 B2R17 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 16 of 52)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 National Appurtenance or Installer or Installer Province No. Board No.Serial 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) 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 at the top of this form.Computer Generated Form 7/25/2013 Exek n-Byron Station Unit 2 B2R17 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 17 of 52)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)Manufacturer Component or Manufacturer Mansturer State or National Appurtenance or Installer or Installer Province No. Board No.Serial No.2MS07AD- Hunter Corp. NA NA NA 28/2MS01 211 R 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 at the top of this form.Computer Generated Form 712512013 Exelkn.Byron Station Unit 2 B2R17 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 18 of 52)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 National Appurtenance or Installer or Installer Province No. Board No.Serial No.2MS01AA- Pacific Scientific 4976 NA NA 30.25/2MS05007-S1 2MS01AA- Pacific Scientific 1543 NA NA 30.25/2MS05007-$2I 2MS07AD- Pacific Scientific 12977 NA NA 28/2MS01088S 1 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) 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 at the top of this form.Computer Generated Form 712512013 E...-xe1rn.
Byron Station Unit 2 B2R17 ISl Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 19 of 52)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 National Appurtenance or Installer Serial No. Province No. Board 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) 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 at the top of this form.Computer Generated Form 712512013 Exel n.Byron Station Unit 2 B2R17 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 20 of 52)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:
Primary Containment (PC)Component or Manufacturer Manufacturer State or National Appurtenance or Installer or Installer Province No. Board No.Serial No.2-PC-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) 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 at the top of this form.Computer Generated Form 7/25/2013 Byron Station Unit 2 B2R17 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 21 of 52)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 Manufacturer State or National Appurtenance 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) 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 at the top of this form.Computer Generated Form 7/25/2013 Exelon.Byron Station Unit 2 B2R17 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 22 of 52)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 National Appurtenance or Installer Serial No. Province No. Board No.2-RC-1-1 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) 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 at the top of this form.Computer Generated Form 7/25/2013 Sxek nt Byron Station Unit 2 B2R17 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 23 of 52)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 National Appurtenance or Installer or Installer Province No. Board No.Serial No.2RC-01 -R/S Hunter Corp. NA NA NA 2RC16AA- Hunter Corp. NA NA NA 2/2CV1 2005X 2RC24AA- Hunter Corp. NA NA NA 4/2RY06016X 2RC24AA- Hunter Corp. NA NA NA 4/2RY06035X I _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 at the top of this form.Computer Generated Form 7/25/2013 Exeikn.Byron Station Unit 2 B2R17 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 24 of 52)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 National Appurtenance or Installer or Installer Province No. Board No.Serial No.2RC01AA-29/JO1 Hunter Corp. 2-RC-1 -N5 NA NA 2RC01AA-29/J06 Hunter Corp. 2-RC-1-N5 NA NA 2RC01AB-29/JO1 Hunter Corp. 2-RC-1-N5 NA NA 2RC01AC-29/JO1 Hunter Corp. 2-RC-1-N5 NA NA 2RC01AD-29/JO1 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-B F1 Westinghouse Corp. 640-0012-51 B-09062 N-200 2RC-01-R/RPVS-C 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-G F1 Westinghouse Corp. 640-0012-51 B-09062 N-200 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 at the top of this form.Computer Generated Form 7/25/2013 Exeion.Byron Station Unit 2 B2R17 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 25 of 52)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 National Appurtenance or Installer Serial No. Province No. Board No.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 2RC03AA-27.5/J12 Hunter Corp. 2-RC-1 -N5 NA NA 2RC03AB-27.5/J12 Hunter Corp. 2-RC-1 -N5 NA NA 2RC03AC-27.5/J13 Hunter Corp. 2-RC-1-N5 NA NA 2RC03AD-27.5/J12 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 2RC13AA-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) 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 at the top of this form.Computer Generated Form 7/2512013 Exel n.Byron Station Unit 2 B2R17 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 26 of 52)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 National Appurtenance or Installer Serial No. Province No. Board No.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 2RC14AA-2/W-06 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) 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 at the top of this form.Computer Generated Form 7/2512013 Exelon-Byron Station Unit 2 B2R17 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 27 of 52)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 National Appurtenance or Installer Serial No. Province No. Board No.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 2RC1 4AA-2/W-1 1 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 2RC16AB-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) 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 at the top of this form.Computer Generated Form 712512013 Exek n-Byron Station Unit 2 B2R17 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 28 of 52)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 National Appurtenance or Installer Serial No. Province No. Board No.2RC16AC-2/W-08 Hunter Corp. 2-RC-1-N5 NA NA I Hr 2RC16AD-2/J-01 Hunter Corp. 2-RC-1-N5 NA NA 2RC21 AA-8/J05 Hunter Corp. 2-RC-1-N5 NA NA 2RC21AA-8/J06 Hunter Corp. 2-RC-1-N5 NA NA 2RC21AB-8/J07 Hunter Corp. 2-RC-1-N5 NA NA 2RC21AB-8/J08 Hunter Corp. 2-RC-1-N5 NA NA 2RC21AB-8/J09 Hunter Corp. 2-RC-1-N5 NA NA 2RC21AB-8/J10 Hunter Corp. 2-RC-1-N5 NA NA 2RC22AA-1.5/W-05 Hunter Corp. 2-RC-1-N5 NA NA 2RC22AA-1.5/W-0 Hunter Corp. 2-RC-1-N5 NA NA 2RC22AC-1.5/W-01 Hunter Corp. 2-RC-1-N5 NA NA I2RC22AC-1
.5/W-06 Hunter Corp. J 2-RC-1 -N5 J NA NA J 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 at the top of this form.Computer Generated Form 7/25/2013 Exeh n.Byron Station Unit 2 B2R17 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 29 of 52)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 National Appurtenance or Installer or Installer Province No. Board No.Serial No.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 2RC24AA-4/J06 Hunter Corp. 2-RC-1-N5 NA NA 2RC24AA-4/J07 Hunter Corp. 2-RC-1-N5 NA NA 2RC24AA-4/J09 Hunter Corp. 2-RC-1-N5 NA NA 2RC24AA-4/J10 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 2RC30AA-1.5/W-01.01 CBI 2-RC-1-N5 NA NA 2RC30AA-1.5/W-01.01 CBI 2-RC-1-N5 NA NA 2RC30AB-1.5/W-01.01 CBI 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) 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 at the top of this form.Computer Generated Form 1 1 7/25/2013 Exelkn-Byron Station Unit 2 B2R17 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 30 of 52)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 National Appurtenance or Installer or Installer Province No. Board No.Serial No.2RC30AC-1.5/W-01
.01 CBI 2-RC-1 -N5 NA NA 2RC30AD-1.5/W-01.01 CBI 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) 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 at the top of this form.Computer Generated Form 7/25/2013 Exek n-Byron Station Unit 2 B2R17 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 31 of 52)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 National Appurtenance or Installer Serial No. Province No. Board No.2RC01 BA- Boeing 27 NA NA 2A/2RC01 BA-A 2RC01 BA- Boeing 35 NA NA 2A/2RC01 BA-B3II 2RC01 BB- Boeing 9 NA NA 2B/2RC01 BB-A 2RC01 BB- Boeing 15 NA NA 2B/2RC01 BB-B 2RC01BC- Boeing 19 NA NA 2C/2RC01 BC-A I I 2RC01 BC- Boeing 7 NA NA 2C/2RC01 BC-B 2RC01BD- Boeing 5 NA NA 2D/2RC01 BD-A 2RC01 BD- Boeing 31 NA NA 2D/2RC01 BD-B 2RC13AC- Pacific Scientific 5656 NA NA 2/2CV1 5045S 2RC14AC- Pacific Scientific 7173 NA NA 2/2CV09034S 2RC16AA- Pacific Scientific 4427 NA NA 2/2CV1 2006S 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 at the top of this form.Computer Generated Form 7/25/2013 Exe..n.Byron Station Unit 2 B2R17 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 32 of 52)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 National Appurtenance or Installer Serial No. Province No. Board No.2RC16AB- Pacific Scientific 2495 NA NA 2/2CV24003S 2RC20AC- Lisega 04616353-015 NA NA 3/4/2 RC 18009SIII 2RC22AC- Pacific Scientific 9646 NA NA 1.5/2RC 18007SI 2RC22AC- Pacific Scientific 17003 NA NA 1.5/2RC18014SI 2RC48BA- Pacific Scientific 4100 NA NA 1/2/2RC90A001 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) 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 at the top of this form.Computer Generated Form 712512013 Exei n.Byron Station Unit 2 B2R17 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 33 of 52)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 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 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 at the top of this form.Computer Generated Form 7/25/2013 Exelon-Byron Station Unit 2 B2R17 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 34 of 52)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 National Appurtenance or Installer Serial No. Province No. Board No.2RH01AA- Hunter Corp. NA NA NA 12/2RH02053X 2RH-01-PA/L1 Ingersoll Rand 127430 NA 161 2RH-01 -PA/L2 Ingersoll Rand 127430 NA 161 2RH-01 -PA/L3 Ingersoll Rand 127430 NA 161 2RH-02-AB/L1 Joseph Oat Corp. 2267-1 D U-201440 839 2RH-02-AB/SKT Joseph Oat Corp. 2267-1 D U-201440 839 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 at the top of this form.Computer Generated Form 7125/2013 Exe n..Byron Station Unit 2 B2R17 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 35 of 52)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 National Appurtenance or Installer or Installer Province No. Board No.Serial No.___ ____2RH01AA- Pacific Scientific 4620 NA NA 12/2RH02068S 2RH01AB- Pacific Scientific 2793 NA NA 12/2RH02003S IIII 2RH01 AB- Pacific Scientific 3081 NA NA 12/2RH02013S 2RH26AB- Lisega 31200814-008 NA NA 3/4/2RH02115S 2RH26AB- Pacific Scientific 9623 NA NA 3/4/2RH02116S I I I 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 at the top of this form.Computer Generated Form 7/25/2013 Byron Station Unit 2 B2R17 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 36 of 52)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 National Appurtenance or Installer Serialler Province No. Board No.2RC-01-R/CORE Westinghouse Corp. 640-0012-52 B-09062 N-200 SUPP STRUCT 2RC-01-R/INT Westinghouse Corp. 640-0012-51 B-09062 N-200 ATTACH NONBELT I I I I 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-200 PEN 2RC-01 -R/RPV HEAD Westinghouse Corp. 640-0012-52 B-09062 N-200 SURF W C 2RC-01-R/RPV Westinghouse Corp. 640-0012-51 B-09062 N-200 INTERIORI 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 at the top of this form.Computer Generated Form 712512013 Exe. n.Byron Station Unit 2 B2R17 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 37 of 52)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 National Appurtenance or Installer or Installer Province No. Board No.Serial No.2RYO3BA-6/FLG 1-12 Hunter Corp. 2-RC-1 -N5 NA NA 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) 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 at the top of this form.Computer Generated Form 7/2512013 Exei n~.Byron Station Unit 2 B2R17 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 38 of 52)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 National Appurtenance or Installer or Installer Province No. Board No.Serial No.2RY01 B-6/2RY06022X Hunter Corp. NA NA NA 2RY01 B-6/2RY06029X Hunter Corp. NA NA NA 2RY18A-2/2RY06115V Hunter Corp. NA 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) 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 at the top of this form.Computer Generated Form 7/2512013 Exelknt Byron Station Unit 2 B2R17 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 39 of 52)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 National Appurtenance or Installer or Installer Province No. Board No.Serial No.2RY18A-2/W-01 Hunter Corp. 2-RC-1-N5 NA NA_2RY18A-2/W-02 Hunter Corp. 2-RC-1-N5 NA NA 2RY18A-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) 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 at the top of this form.Computer Generated Form 7/2512013 Exel n-Byron Station Unit 2 B2R17 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 40 of 52)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 National Appurtenance or Installer Serial No. Province No. Board No.2RY02B-3/2RY09067-Pacific Scientific 16687 NA NA$1 2RY02B-3/2RY09067-Pacific Scientific 5512 NA NA S2I 2RY02B-3/2RY091 0OS Pacific Scientific 9295 NA NA 2RY06A-3/2RY09012S Pacific Scientific 10201 NA NA 2RY06A-3/2RY09060-Pacific Scientific 7345 NA NA 2RY06A-3/2RY09060-Pacific Scientific 4637 NA NA S2I 2RY06A-3/2RY09078S Pacific Scientific 7731 NA NA 2RY06A-3/2RY091 01S Pacific Scientific 18784 NA NA 2RY07AC- Pacific Scientific 2440 NA NA 3/4/2RY27016S 2RY11A- Pacific Scientific 12031 NA NA 14/2RY0501 OS I 2RY34CD- Pacific Scientific 2627 NA NA 1/2/2RC91 001QS I 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 at the top of this form.Computer Generated Form 7/25/2013 Exekenm Byron Station Unit 2 B2R17 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 41 of 52)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 Blowdown System (SD)Component or Manufacturer Manufacturer State or National Appurtenance or Installer Serial No. Province No. Board No.2SDO1 CA- Pacific Scientific 12404 NA NA 2/2SD21034S 2SD01CD- Pacific Scientific 2SD24026S NA NA 2/2SD24026S I I I I 2SD01 CF- Lisega 2SD05002-S1 NA NA 2/2SD05002-$1 1 2SD01 CF- Lisega 2SD05002-S2 NA NA 2/2SD05002-S2 I 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 at the top of this form.Computer Generated Form 7/2512013 Exel n.Byron Station Unit 2 B2R17 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 42 of 52)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)Component or Manufacturer Manufacturer State or National Appurtenance or Installer Serial No. Province No. Board No.2RC-01 -BA/DRAIN Westinghouse Corp. 2095 U-201435 15 2RC-01-BA/SGC-08 Westinghouse Corp. 2095 U-201435 15 2RC-01-BB/DRAIN Westinghouse Corp. 2096 U-201436 16 2RC-01 -BB/SGC-05 Westinghouse Corp. 2096 U-201436 16 2RC-01 -BB/SGN-03 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) 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 at the top of this form.Computer Generated Form 7/25/2013 Exektn.Byron Station Unit 2 B2R17 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 43 of 52)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 National Appurtenance or Installer or Installer Province No. Board No.Serial 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 S 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) 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 at the top of this form.Computer Generated Form 7/25/2013 Exeilon.Byron Station Unit 2 B2R17 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 44 of 52)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 National Appurtenance or Installer or Installer Province No. Board No.Serial No.2SI05CA-8/2SI01022X Hunter Corp. NA NA NA 2SI05CA-8/2SI01026X Hunter Corp. NA NA NA 2SI05CA-8/2SI01038X Hunter Corp. NA NA NA 2SI05CA-8/2SI103021 X Hunter Corp. NA NA NA 2SI05CA-8/2SI03025V Hunter Corp. NA NA NA 2SI05CA-8/2SI03029X Hunter Corp. NA NA NA 2SI05DA-6/2SI01017X Hunter Corp. NA NA NA 2SI05DA-6/2SI101029X Hunter Corp. NA NA NA 2SI05DA-6/2SI01031 X Hunter Corp. NA NA NA 2SI05DA-6/2SI01032X Hunter Corp. NA NA NA 2SI05DA-6/2SI10 032X Hunter Corp. NA NA NA 2SI08FA-3/2SI2301 1X Hunter Corp. NA 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) 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 at the top of this form.Computer Generated Form 7/25/2013 Exelon-Byron Station Unit 2 B2R17 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 45 of 52)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 National Appurtenance or Installer Serial No. Province No. Board No.2SI08FA-3/2SI23012A Hunter Corp. NA NA NA 2SI08GB Hunter Corp. NA NA NA 1/2/2SI25004X 2SI08GB Hunter Corp. NA NA NA 1/2/2SI25007X 2SI08JA Hunter Corp. NA NA NA 1/2/2SI24012X 2SI08JA Hunter Corp. NA NA NA 1/2/2S125010OX 2SI08JA Hunter Corp. NA NA NA 1B2//2SI25012X 2SIA4B-8/2RH02083X Hunter Corp. NA 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) 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 at the top of this form.Computer Generated Form 7/25/2013 Exekrn.Byron Station Unit 2 B2R17 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 46 of 52)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 National Appurtenance or Installer Serialler Province No. Board No.2SI03DA-2/W-01.01 Exelon Corp. 2-SI-1 -N5 NA NA 2SI03DA-2/W-02.01 CBI 2-SI-1 -N5 NA NA 2SI03DA-2/W-03.01 CBI 2-S1-1-N5 NA NA 2SI08HA-2/W-01 Hunter Corp. 2-SI-1-N5 NA NA 2SI08HA-2/W-02 Hunter Corp. 2-SI-1-N5 NA NA 2SI08HA-2/W-03 Hunter Corp. 2-SI-1 -N5 NA NA 2SI08HA-2/W-04 Hunter Corp. 2-SI-1 -N5 NA NA 2SI08HA-2/W-05 Hunter Corp. 2-SI-1-N5 j 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-SI-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) 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 at the top of this form.Computer Generated Form 1 1 i 7/25/2013 Exekrn.Byron Station Unit 2 B2R17 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 47 of 52)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 National Appurtenance or Installer or Installer Province No. Board No.Serial No.2SI08JA-1.5/W-04 Hunter Corp. 2-SI-1 -N5 NA NA 2SI08JA-1.5/W-05 Hunter Corp. 2-S1-1-N5 NA NA 2SI08JA-1.5/W-05A Hunter Corp. 2-SI-1 -N5 NA NA 2SI08JA-1.5/W-05B Hunter Corp. 2-SI-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-S1-1-N5 NA NA 2SI08JA-1.5/W-10 Hunter Corp. 2-S1-1-N5 NA NA 2SI08JA-1.5/W-11 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-15 Hunter Corp. 2-SI-1-N5 NA NA 2SI08JA-1.5/W-35.01 CBI 2-SI-1 -N5 NA NA 2SI08JA-1.5/W-36.01 CBI 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) 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 at the top of this form.Computer Generated Form 7/25/2013 Exel n-Byron Station Unit 2 B2R17 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 48 of 52)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 National Appurtenance or Installer or Installer Province No. Board No.Serial No.2SI08JA-1.5/W-37.01 CBI 2-SI-1-N5 NA NA 2SI08J B-1.5/W-38.01 CBI 2-SI-1-N5
~NA NA 2SI08JB-1.5/W-39.01 CBI 2-SI-1-N5 NA NA 2I0J-./-90CB 2-SI-i -N5NAA 2SI08JC- 1.5/W-39.01 CBI 2-S1-1 -N5 NA NA 2SI08JC-1.5/W-40.01 CBI 2-SI-1 -N5 NA NA 2SI08JC-1.5/W-41.01 CBI 2-SI-1-N5 NA NA 2SI08JD-1.5/W-38.01 CBI 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) 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 at the top of this form.Computer Generated Form 7/25/2013 Exel n.~Byron Station Unit 2 B2R17 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 49 of 52)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 National Appurtenance or Installer Serialler Province NoN Board No.2SI04D-8/2RH02061 S Pacific Scientific 16726 NA NA 2SI05CA-8/2SI01 023S Pacific Scientific 2545 NA NA 2SI05DD-6/2SI03009S Pacific Scientific 2553 NA NA 2SI05DD-6/2SI03018S Pacific Scientific 27115 NA NA 2SI08JD- Lisega 31200814-005 NA NA 1.5/2SI22018S 2SI08JD- Pacific Scientific 8050 NA NA 1.5/2SI22020S 2SI09BC-10/2SI09002-Pacific Scientific 25441 NA NA 2SI09BC-10/2S109002-Pacific Scientific 9347 NA NA S2 2SI09BD- Pacific Scientific 4808 NA NA 10/2SI03001 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) 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 at the top of this form.Computer Generated Form 7/25/2013 Exekin-Byron Station Unit 2 B2R17 ISl Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 50 of 52)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 National Appurtenance or Installer Serial No. Province No. Board 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) 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 at the top of this form.Computer Generated Form 7/25/2013 Exel n.Byron Station Unit 2 B2R17 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 51 of 52)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 National Appurtenance or Installer or Installer Province No. Board No.Serial No.2SX06BB-16/2PC-7A Hunter Corp. NA NA NA 2SX06BB- Hunter Corp. NA NA NA 16/2SX07001 G I I 2SX06CB- Hunter Corp. NA NA NA 14/2SX07007X 2SX07BD- Hunter Corp. NA NA NA 10/2SX09078X I I 2SX07CB- Hunter Corp. NA NA NA 10/2SX09038X 2SX07CD- Hunter Corp. NA NA NA 10/2SX09077X 2SX07EB- Hunter Corp. NA NA NA 14/2SX0901 1X 2SX08BD- Hunter Corp. NA NA NA 10/2SX07025X 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 at the top of this form.Computer Generated Form 7/25/2013 Exele-n Byron Station Unit 2 B2R17 ISl Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 52 of 52)(BACK)8. Examination Dates: 10/10/11 to 5/1/13 9. Inspection Period Identification:
Third Inspection Period 10. Inspection Interval Identification:
Third Inspection Interval 11. Applicable Edition of Section Xl: 2001 Addenda 2003 12. Date / Revision of Inspection Plan: 6/10/12 / 7 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 the Inspection Plan as required by the ASME Code, Section XI, and c) corrective measures taken conform to the rules of the ASME Code, Section XI.Certificate of Authorization No. (if applicable):
N/A Expiration Date: N/A Date: 'Z/2-/13 Signed for:Exelon Generation Company 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 inspected the components described in this Owner's Report during the period lo/1i/11 to 5, and state that to the best of my knowledge and belief, the Owner has performed examinations and tests and taken corrective measures described in this Owner's Report in accordance with the 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 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.
Inspectors Signature Cor mmissions:
A 9 4/t/2, rd Date: 20 13 National Board, State, Province, and Endorsements Computer Generated Form DOCUMENT NO.: 5A REV. NO.: 0 FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI 1 Owner Exelon Nuclear Date 4-27-13 Name 4300 Winfield Road, Warrenville, IL Sheet 1 of 1 Address 2. Plant Byron Nuclear Power Station Unit 2 Name 4450 N. German Church Road, Byron, IL Work Order No. 99147049-01 Address Repair Organization, P.O. No., Job No., etc.3. Work Performed by Byron Mechanical Type Code Symbol Stamp Not Applicable Maintenance Name Authorization No. Not Applicable 4450 N. German Church Road, Byron, IL Expiration Date Not Applicable Address 4. Identification of System FW -Feedwater 5. (a) Applicable Construction Code ASME Section III 19 74 Edition, W/75 Addenda, N/A Code Case (b) Applicable Edition of Section XI Used for Repair/Replacement Activity:
2001 Edition/2003 Addenda (c) Section Xl Code Case(s) N/A 6. Identification of Components ASME Corrected, Code National Removed, or Stamped Name of Name of Manufacturer Board Other Year Installed (Yes or No)Component Manufacturer Serial No. No. Identification Built Valve Bonnet Borg. Warner Valve S/N: N/A ETN: 2FW009C 1979 Corrected Yes 35601 7. Description of Work Machined valve bonnet seat ring surface 8. Test Conducted:
Hydrostatic E]Pneumatic E]Nominal Operating Pressure El Exempt [OF Other E] 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 number of sheets is recorded at the top of this form.
FORM NIS-2 (Back)9. Remarks WO 99147049-01 Applicable 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 '7-Z6, ,20 13 ( or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Illinois and employed by HSB CT of .Hartford, CT have)nsp cted the components described in this Owner's Report during the period to ,and state that to the best of my knowledge and belief, tKe dwner has perforrli'ed e-aminations and taken corrective measures described in this Owners 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 dfma e or a loss of any kind arising from or connected with this inspection.
Commissions fi" /2 ,V/ f A5 Inspector's Signature Date: " ,20 13 National Board, State Province, and Endorsements DOCUMENT) RH 04/20/13 1. Owner E: NO.: 3.1 REV. NO.: 0 FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section Xl xelon Nuclear Date 4/20/13 2.Name 4300 Winfield Road, Warrenville, IL Address Plant Byron Nuclear Power Station Name 4450 N. German Church Road, Byron, IL Address Sheet 1 of 1 Unit 02 Work Order No. 00543260-01 Repair Organization, P.O. No., Job No., etc.3. Work Performed by CB&VStone
& Webster Name 36400 S. Essex Road, Wilmington, IL 60481 Address Type Code Symbol Stamp Not Applicable Authorization No. Not Applicable Expiration Date Not Applicable
: 4. Identification of System MS (MAIN STEAM)5. (a) Applicable Construction Code ASME Section III 19 74 Edition, N/A Addenda, (b) Applicable Edition of Section Xl Used for Repair/Replacement Activity 2001 Editi (c) Section Xl Code Case(s) NONE 6. Identification of Components N/A Code Case on / 2003 Addenda ASME Corrected, Code National Removed, or Stamped Name of Name of Manufacturer Board Other Year Installed (Yes or No)Component Manufacturer Serial No. No. Identification Built SAFETY VALVE, 6", DRESSER BU01489 N/A 2MS016A 1500# INDUSTRIES 1989 Removed YES SAFETY VALVE, 6", DRESSER BU490 N/A 2MS016A1978 Installed YES 1500# INDUSTRIES Cat ID 1439914-1 ROD,THREADED Texas Bolt MK# LR49 N/A 2M016A1981 Removed No 1-3/8-8 Gr. B7 Bolt# 2 & 6 ROD,THREADED Nova Machine Ht. No.: 2MS016A 1-3/8-8 Gr. B7 Products NF12200854 Cat ID 37106-1 NUT, HEAVY HEX Texas Bolt MK# LR50 N/A 2MS016A 1-3/8-8 Texas Bolt MK# LR50 N/A Bolt# 2 & 6 1981 Removed No NUT, HEAVY HEX Nova Machine Ht. No.: N/A 2MS016A 1-3/8-8 Products 3W50 Cat ID 1394991-1 7. Description of Work REPLACE RELIEF VALVE 2MS016A -REPLACED 2 STUDS & 4 NUTS 8. Test Conducted:
Hydrostatic
[] Pn Other El Pressure eumatic El Nominal Operating Pressure Z Exempt E1 1060 psi Test Temp. 556 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 number of sheets is recorded at the top of this form.
FORM NIS-2 (Back)9. Remarks 00543260-01 Applicable Manufacturers Data Heports 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 o ,uthorization No. Not Applicable Signed fAj A A-" A Date :5 20 13 Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Illinois and employed by HSB CT of Har ford, CT have inpectd the components described in this Owner's Report during the periodto " ,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 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 damage0 loss of any kind arising from or connected with t'is inspection.
Q~#~6fCommissions 101el1 lzaellfllz6e Date: Inspector's Signature* 1/3 ,20 13 National Board, State Province, and Endorsements (Final))
I DOCUMENT NO.: 3.1 REV. NO.: 0 1 FORM NIS-2 OWNER'S REPORT FOR REPAIRIREPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI 1. Owner Exelon Nuclear Date 4/20/13 2.Name 4300 Winfield Road, Warrenville, IL Address Plant Byron Nuclear Power Station Name 4450 N. German Church Road, Byron, IL Address Sheet 1 of Unit 02 Work Order No. 00543261-01 Repair Organization, P.O. No., Job No., etc.1 3. Work Performed by CB&MStone
& Webster Name 36400 S. Essex Road, Wilmington, IL 60481 Address Type Code Symbol Stamp Not Ap Authorization No. Not Applicable Expiration Date Not Applicable plicable 4. Identification of System MS (MAIN STEAM)5. (a) Applicable Construction Code ASME Section III 19 74 Edition, N/A Addenda, N/A 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 Name of Component Name of Manufacturer Manufacturer Serial No.National Board No.Corrected, Removed, or Installed ASME Code Stamped (Yes or No)Other Identification Year Built I I SAFETY VALVE, 6", 1500#DRESSER INDUSTRIES 2MS013A BU01477 N/A 1978 Removed YES SAFETY VALVE, 6", DRESSER BRO9593 N/A 2MS01 3A 1977 Installed YES 1500# INDUSTRIES Cat ID 1443930-1 7. Description of Work-REPLACE RELIEF VALVE 2MS01 3A 8. Test Conducted:
Hydrostatic
[I Pn Other C] Pressure eumatic 11 1060 Nominal Operating Pressure Z Ex psi Test Temp. 556 empt El 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 number of sheets is recorded at the top of this form.
FORM NIS-2 (Back)9. Remarks 00543261-01 Applicable Manufacturer's 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 o,,.Authorization No. Not Applicable Signed (UA ( A.. 1 , ,Il/7,A)A-'-/z-Date 5" T ,20 13 Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Illinois and employed by HSB CT of H ard, CT have epsp/ected the components described in this Owner's Report during the period to " ,and state that to the best of my knowledge and belief, )the Oner has performed'-
examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section XI.By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective 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 danage or a loss of any kind arising from or connected with this inspec ion.94.A,- -Commissions
,,,, 6e Inspector's Signature National Board, State Province, and Endorsements Date: _&#xfd;./ 4.1,4..' .20 13 (Final)-)
DOCUMENT NO.: 3.1 REV. NO.: 0-7 FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI 1. Owner Exelon Nuclear Date 4/20/13 Name 4300 Winfield Road, Warrenville, IL Sheet 1 of 1 Address 2. Plant Byron Nuclear Power Station Unit 02 Name 4450 N. German Church Road, Byron, IL Work Order No. 00634678-01 Address Repair Organization, P.O. No., Job No., etc.3. Work Performed by CB&l/Stone
& Webster Type Code Symbol Stamp Not Applicable Name Authorization No. Not Applicable 36400 S. Essex Road, Wilmington, IL 60481 Expiration Date Not Applicable Address 4. Identification of System MS (MAIN STEAM)5. (a) Applicable Construction Code ASME Section 1l1 19 74_4 Edition, na Addenda, N/A 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 ASME Corrected, Code National Removed, or Stamped Name of Name of Manufacturer Board Other Year Installed (Yes or No)Component Manufacturer Serial No. No. Identification Built SAFETY VALVE, 6", DRESSER 2MS014D 150 NUTIS BU01484 N/A 2S4D1978 Removed YES 1500# INDUSTRIES SAFETY VALVE, 6", DRESSER 2MS014D 1500#BR09597 N/A 1977 Installed YES 1500#INDUSRIESCat ID 1439909-1 7. Description of Work-REPLACED RELIEF VALVE 2MS01 4D 8. Test Conducted:
Hydrostatic El Pn Other El Pressure eumatic E] Nora 1075 psi inal Operating Pressure 0 Exempt 11 Test Temp. 556 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 number of sheets is recorded at the top of this form.
FORM NIS-2 (Back)9. Remarks 00634678-01 ApplicaDle Manutacturer's Uata Heports 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 Xl.Type Code Symbol Stamp Not Applicable Certificate of uthorization No. Not Applicable Signed CAo,,w/ LA, A 49d d1/AJArc),,.___
Date T- /15 , 20 13 Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Illinois and employed by HSB CT of a ord, CT have nsected the components described in this Owner's Report during the period N, VA -to '1, and state that to the best of my knowledge and belief, t&~e wner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section XI.By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective 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 ()V -Inspector's Signature Date: A *National Board, State Province, and Endorsements
,20 13 (Final)N1 DOCUMENT NO.: 5.2 REV. NO.: 0 FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section Xl 1. Owner Exelon Nuclear Date 4-15-13 Name 4300 Winfield Road, Warrenville, IL Sheet 1 of 2 Address 2. Plant Byron Nuclear Power Station Unit 02 Name 4450 N. German Church Road, Byron, IL Work Order No. 01025526-03/12 Address Repair Organization, P.O. No., Job No., etc.3. Work Performed by Shaw/Stone
& Webster Type Code Symbol Stamp Not Applicable Byron Mechanical Maintenance Name Authorization No. Not Applicable 36400 S. Essex Road, Wilmington, IL 60481 Expiration Date Not Applicable 4450 N. German Church Rd. Byron IL 61010 Address 4. Identification of System SI -Safety Injection 5. (a) Applicable Construction Code ASME Sect III Piping 19 74 Edition, S75 Addenda, N/A Code Case (a) Applicable Construction Code ASME Sect III Valve 19 71 Edition, W72 Addenda, N/A 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 ASME Corrected, Code National Removed, or Stamped Name of Name of Manufacturer Board Other Year Installed (Yes or No)Component Manufacturer Serial No. No. Identification Built 2" CE Kerotest S/N: PS3-1 14,425 2SI8905B 1977 Removed Yes CHECK VALVE 2" 2SI8905B CHECK VALVE Kerotest S/N: 43BTB N/A CID:32726 2011 Installed Yes UTC# 0002903431 2"SCH. 160 Sandvik HT#: 462460 N/A 2SI03DA-2" 1977 Removed No PIPE () 2" SCH. 160 Consolidated 2SI03DA-2" PIPE PowerSupply HT# 505112 N/A CID:1449121 2011 Installed No PIPE__PowerSupplyUTC#
0002883505 2" 90 DEG. 6000# Alloy Stainless MK#: PI N/A 2SI03DA-2" 1977 Removed No ELBOW Co.2" 90 DEG. 6000# Consolidated HT# 44100 N/A 2SI03DA-2" 2010 Installed No ELBOW Power Supply CID:39072 2"SCH. 160 Sandvik HT#: 462460 N/A 2SI03CA-2" 1977 Removed No PIPE 2" SCH. 160 Consolidated 2SI03CA-2" PIPEHT#505112 N/A 2011 Installed No 7. Description of Work Replaced Check Valve, Pipe, Elbow and Flange 8. Test Conducted:
Hydrostatic
[]Pneumatic E]Nominal Operating Pressure Z Exempt El Other [I Pressure 2418 / 852 psi Test Temp. 476 / 84 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 number of sheets is recorded at the top of this form.
FORM NIS-2 (Back)9. Remarks 1025526-03/12 Applicable Manufacturer's Data Reports to be attached (D Welds 2,3 and 6 performed by the Byron Mechanical Maintenance department on task 12 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 Authorizatipn No., Not Applicable Signed _. Date 7-11 20 13-t -nr 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 -aord, CT have ,spted the components described in this Owner's Report during the period to 40/."- o , and state that to the best of my knowledge and belief, t~e, 6 wner has perfornleed 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 dama 2i or a loss of any kind arising from or connected with this inspection.
Commissions
,/ .f' , ///-/ A 6.Inspector's Signature Date: X ; ,20 13 National Board, State Province, and Endorsements FORM NIS-2 SUPPLEMENTAL SHEET 1. Owner Exelon Nuclear Date 4-15-13 2.Name 4300 Winfield Road, Warrenville, IL Address Plant Byron Nuclear Power Station Name 4450 N. German Church Road, Byron, IL Address Sheet 2 of 2 Unit 02 3 Work Order No. 01025526-03/12 Repair Organization, P.O. No., Job No., etc.3. Work Performed by Byron Mechanical Maintenance Type Code Symbol Stamp Not Applicable Name 4450 N. German Church Rd. Byron IL 61010 Address Authorization No.Expiration Date Not Applicable Not Applicable
: 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 Xl Used for Repair/Replacement Activity 2001 Edition / 2003 Addenda (c) Section Xl Code Case(s) NONE 6. Identification of Components ASME Corrected, Code National Removed, or Stamped Name of Name of Manufacturer Board Other Year Installed (Yes or No)Component Manufacturer Serial No. No. Identification Built ______________
SEAL WELD ON N/A N/A N/A 2S28905B N/A Installed N/A VALVE CAP PowerSuIpl 5615AN1 I I I D 4 I 2". 15000#Hunter Corp.MK#: HK655 N/A 2SI03CA-2" 1977 Removed No , 2". 15000# Consolidated HT# N/A 2S103CA-2" 2012 Installed No SWIRF FLANGE- Power Supply 5615ANE1 _ _____ CID:30443
___w K)(Final)
I DOCUMENT NO.: 4-1 REV. NO.: 0 FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section Xl 1. Owner Exelon Nuclear Date 1-4-13 2.3.Name 4300 Winfield Road, Warrenville, IL Address Plant Byron Nuclear Power Station Name 4450 N. German Church Road, Byron, IL Address Work Performed by Byron Mechanical Maintenance Name 4450 N. German Church Road, Byron, IL Address Sheet 1 of 1 Unit 02 Work Order No. 01324819-01 Repair Organization, P.O. No., Job No., etc.Type Code Symbol Stamp Not Applicable Authorization No.Expiration Date Not Applicable Not Applicable
: 4. Identification of System RH -RESIDUAL HEAT 5. (a) Applicable Construction Code ASME Section III 19 71 Edition, W/72 Addenda, N-1567 Code Case (b) Applicable Edition of Section XI Used for Repair/Replacement Activity:
2001 Editlonr2003 Addenda (c) Section XI Code Case(s) NONE 6. Identification of Components ASME Corrected, Code National Removed, or Stamped Name of Name of Manufacturer Board Other Year Installed (Yes or No)Component Manufacturer Serial No. No. Identification Built RELIEF VALVE CROSBY N56904 N/A 2RH8708A 1978 REMOVED YES 0049 RELIEF VALVE CROSBY N56904 N/A 2RH8708A RELIEF VALVE CROSB0068 N/A CAT ID 27642-1 1992 INSTALLED YES 7. Description of Work REPLACED RELIEF VALVE (PMV)8. Test Conducted:
Hydrostatic E] Pn Other [I Pressure eumatic [] Nonm 45 psi iinal Operating Pressure Z Exempt 0-Test Temp. Ambient 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 number of sheets is recorded at the top of this form.
FORM NIS-2 (Back)9. Remarks WO#01324819-01 I I I I I I Applicable manufacturers Data ieports to 156 attane J 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 gA2 Date I-I .20 13 Onor 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 H.arrtord,, , CT have inspe/pted 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 performnd el(aminations 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.
Commissions
_,.,z/,/ ,5,/ , 4..AInspector's Signature Date: / 13 National Board. State Province, and Endorsements (Final I DOCUMENTNO.:
3A REV. NO.: 0 FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI 1 .Owner Exelon Nuclear Date 04/15/2013 Name 4300 Winfield Road, Warrenville, IL Sheet 1 of 1 2.3.Address Plant Byron Nuclear Power Station Name 4450 N. German Church Road, Byron, IL Address Work Performed by Byron Mechanical Maintenance Name 4450 N. German Church Road, Byron, IL Address Unit 02 Work Order No. 01404948-14 Repair Organization, P.O. No., Job No., etc.Type Code Symbol Stamp Authorization No. Not Expiration Date Not A;Not Applicable Applicable plicable 4. Identification of System Reactor Coolant (RC)5. (a) Applicable Construction Code ASME Section III 19 74 Edition, S/74 Addenda, 1423-2 Code Case (b) Applicable Edition of Section XI Used for Repair/Replacement Activity:
2001 EditionI2003 Addenda (c) Section XI Code Case(s)6. Identification of Components Name of Cornponent Name of Manufacturer Manufacturer Serial No.National Board No.Corrected, Removed, or Installed ASME Code Stamped (Yes or No)Other Identification Year Built 6712 Loop 1 RC cold leg Westinghouse N/A 1977 Corrected yes nozzle 6713 Loop 2 RC cold leg Westinghouse N/A 1977 Corrected yes nozzle 6714 Loop 3 RC cold leg Westinghouse N/A 1977 Corrected yes nozzle 6715 Loop 4 RC cold leg Westinghouse N/A 1977 Corrected yes nozzle 7. Description of Work Removed manufacture's nameplate by grinding, pipe wall not penetrated.
: 8. Test Conducted:
Hydrostatic 5] Pn Other D Pressure eumatic 5 Norr psi tinal Operating Pressure El Test Temp.Exempt [D Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 81/2 in. x 11 in., (2)((' formation in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number I. 4f sheets is recorded at the top of this form.
FORM NIS-2 (Back)9. Remarks WO 1404948-14 Applicanie Manutacturer's uata -eports to De attacnea K)J 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 ,gAuthoriz~tion 14o. Not Applicable Signed M,,;A, Ad," &00V//Z" Date 7-fZ , 20 13 I os Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Illinois and employed by HSB CT of ,lartford, CT have'nspgcted the components described in this Owner's Report during the period zI t o j/'J_/to , and state that to the best of my knowledge and belief, the dwner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section XI.By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective 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 iZ/$
A Al 2 e_7'" -Inspector's Signature Date: OfA ,20 13 National Board, State Province, and Endorsements (Final Doc 4A FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section Xl I. Owner Exelon Nuclear Date 2-2-12 Name 4300 Wlnfield Road, Warrenville, IL Sheet 1 of 1 Address 2. Plant Byron Nuclear Power Station Unit 02 Name 4450 N. German Church Road, Byron, IL Work Order No. 01442461-.04 Address Repair Organization, P.O. No., Job No., etc.3. Work Performed by Byron Mechanical Type Code Symbol Stamp Not Applicable Maintenance Name Authorization No. Not Applicable 4450 N. German Church Road, Byron, IL Expiration Date Not Applicable Address 4. Identification of System Main Feedwater
[FW]5. (a) Applicable Construction Code ASME Section III 19 74_4 Edition, W/75* 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 ASME Corrected, Code National Removed, or Stamped Name of Name of Manufacturer Board Other Year Installed (Yes or No)Component Manufacturer Serial No. No. Identification Built GATE VALVE BORG S/N 35601 2FW009C THERMOCOUPLES WARNER N/A 1979 REMOVEDNO GATE VALVE BORG S/N 35601 2FW009C THERMOCOUPLES WARNER N/A 1979 INSTALLED NO 7. Description of Work REPLACED THERMOCOUPLES ON 2FW009C VALVE BODY 8. Test Conducted:
Hydrostatic El Pneumatic El Norm Other El Pressure psi inal Operating Pressure El Test Temp.Exempt 0 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 number of sheets is recorded at the top of this form.
FORM NIS-2 (Back)9. Remarks Work Order No. 01442461-04 Applicable Manufacturers Data Reports to be attached* Thermocouple spot welding to be in accordance with ASME Section III NC-4311.2, 1992 Ed/1 992 Addenda per EC 0000347800 and Valve Drwg 80210 Revision L. and T-Mod DCP 9901014.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 Xl.Type Code Symbol Stamp Not Applicable Certificate of Authorization No. Not Applicable Signed Date 3 20 12 Owneror 0v;-OeesDs 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 -/ ord, CT have i sp cted the components described in this Owner's Report during the period to , r.101 , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section XI.By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective 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 a loss of any kind arising from or connected with this inspection.
__________________
~Commissions d ' //,f/I6 ZY Inspector's Signature National Board, State Province, and 9ndorsements Date: ,20 12 (Final)
DOCUMENT NO.: 4.2 REV. NO.: 0 FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI 1. Owner Exelon Nuclear Date 4/17/13 Name 4300 Winfield Road, Warrenville, IL Sheet 1 of 1 Address 2. Plant Byron Nuclear Power Station Unit 02 Name 4450 N. German Church Road, Byron, IL Work Order No. 01450986-01/02 Address Repair Organization, P.O. No., Job No., etc.3. Work Performed by CB&l/Stone
& Webster Type Code Symbol Stamp Not Applicable Name Authorization No. Not Applicable 36400 S. Essex Road, Wilmington, IL 60481 Expiration Date Not Applicable Address 4. identification of System RY I PRESSURIZER
: 5. (a) Applicable Construction Code ASME Section III 19 71 Edition, W72 Addenda, na 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 ASME Corrected, Code National Removed, or Stamped Name of Name of Manufacturer Board Other Year Installed (Yes or No)Component Manufacturer Serial No. No. Identification Built RELIEF VALVE CROSBY VALVE N56964-00-0030 N/A 2RY8010A 1976 Removed YES 2RY8010A & GAGE RELIEF VALVE CROSBY VALVE N56964-00-0048 N/A CAT ID 1402762-1 1976 Installed YES 2RY8010A & GAGE I I + + 1 J t t t 7. Description of Work REMOVE / REPLACE PRESSURIZER RELIEF VALVE 2RY8010A 8. Test Conducted:
Hydrostatic El Pneumatic
[] Nominal Operating Pressure 0 Exempt El Other E] Pressure 2234 psi Test Temp. 556 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 number of sheets is recorded at the top of this form.
FORM NIS-2 (Back)9. Remarks 01450986-01/02 Applicable Manufacturer's 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 ofAuthorization No. Not Applicable Signed t, , tZ IA/,F,__ Date j-, 20 13 Owner or dwner'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 Harord, CT have ins ected the components described in this Owner's Report during the period h _6wner -to I./&#xfd; ? , and state that to the best of my knowledge and belief, he wner has performedexaminations 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 d mage r a loss of any kind arising from or connected with this inspection.
Commissions A[()Inspector's Signature Date: ,20 13 National Board, State Province, and Endorsements (Final)()
DOCUMENT NO.: 5A REV. NO.: 0 FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI 1. Owner Exelon Nuclear Date 4/18/13 Name 4300 Winfield Road, Warrenville, IL Sheet 1 of 1 Address 2. Plant Byron Nuclear Power Station Unit 02 Name 4450 N. German Church Road, Byron, IL Work Order No. 01478575-01 Address Repair Organization, P.O. No., Job No., etc.3. Work Performed by Byron Mechanical Type Code Symbol Stamp Not Applicable Maintenance Name Authorization No. Not Applicable 4450 N. German Church Road, Byron, IL Expiration Date Not Applicable Address 4. Identification of System SI -SAFETY INJECTION 5. (a) Applicable Construction Code ASME Section III 19 71 Edition, W/72 Addenda, NONE Code Case (b) Applicable Edition of Section XI Used for Repair/Replacement Activity:
2001 Editloni2003 Addenda (c) Section XI Code Case(s) NONE 6. Identification of Components ASME Corrected, Code National Removed, or Stamped Name of Name of Manufacturer Board Other Year Installed (Yes or No)Component Manufacturer Serial No. No. Identification Built SEAL WELD ON 2SI8819A VALVE CAP Flowserve 67BSC N/A 2011 CORRECTED YES 7. Description of Work REPAIR SEAL WELD 8. Test Conducted:
Hydrostatic
[] Pn Other EJ Pressure eumatic []Nominal Operating Pressure El psi Test Temp.Exempt 0 OF Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 81/22 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 number of sheets is recorded at the top of this form.
FORM NIS-2 (Back)9. Remarks WO# 01478575-01
)Applicable Manufacturer s Data R-eporrs to be anacnea 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 ofAuthorization No. Not Applicable Signed C.. i .Z A,/AAiZ) Date jt4- Z It , 20 13 Owner or Owners 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 Hartord, CT have*nspycted the components described in this Owners Report during the period to ,43 and state that to the best of my knowledge and belief, the O1wner 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 A,/& ,S," V# , (.-)A00 Inspector's Signature Date: 0?14/ ,20 13 National Board, State Province, and Endorsements (Final 0 DOCUMENT NO.: 5.2 FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI 1. Owner Exelon Nuclear Date 4/25/13 Name 4300 Winfield Road, Warrenville, IL Sheet 1 of 1 Address 2. Plant Byron Nuclear Power Station Unit 02 Name 4450 N. German Church Road, Byron, IL Work Order No. 01479994-34 Address Repair Organization, P.O. No., Job No., etc.3. Work Performed by CB&llStone
& Webster Type Code Symbol Stamp Not Applicable Name Authorization No. Not Applicable 36400 S. Essex Road, Wilmington, IL 60481 Expiration Date Not Applicable Address 4. Identification of System REACTOR COOLANT SYSTEM (RC)5. (a) Applicable Construction Code 19 71 Edition, S72/ Addenda, Code W74 Case 1355, 1493-1, 1484, 1528, NB4643 (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 ASME Corrected, Code National Removed, or Stamped Name of Name of Manufacturer Board Other Year Installed (Yes or No)Component Manufacturer Serial No. No. Identification Built S/G #16 NOZZLE Westinghouse 2096 N/A 2RC01BB 1980 Corrected YES WELD TO GEN_____7. Description of Work Base metal defect removal 8. Test Conducted:
Hydrostatic
[I Pneumatic 13 Nominal Operating Pressure E3 Exempt E]Other Z
* Pressure psi Test Temp. OF*NDE Report B2R17- MT-003 N 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 number of sheets is recorded at the top of this form.
FORM NIS-2 (Back)9. Remarks 01479994-34 Applicable Manufacturer's 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 uthorzati~n No. Not Applicable Signed r)36OAA (A\, A)I, ,, P eZ O0AA1/A,',4 7/-/-L Date -23 ,2013 Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Illinois and employed by HSB CT of Haytord, CT have ipspe~cted the components described in this Owner's Report during the period Ak &#xfd;13 -to -,and state that to the best of my knowledge and belief, ( )the 6wner has performed 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 A#,WT(R!'7i' 4,/Aa,&--Inspector's Signature National Board, State Province, and Endorsements Date: 0 ,.... 20 13 (Final)I)
DOCUMENT NO.: 5.2 REV. NO.: 0 FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI 1. Owner Exelon Nuclear Date 4/17/13 Name 4300 Winfield Road, Warrenville, IL Sheet 1 of 1 Address 2. Plant Byron Nuclear Power Station Unit 02 Name 4450 N. German Church Road, Byron, IL Work Order No. 01480596-01 Address Repair Organization, P.O. No., Job No., etc.3. Work Performed by CB&l/Stone
& Webster Type Code Symbol Stamp Not Applicable Name Authorization No. Not Applicable 36400 S. Essex Road, Wilmington, IL 60481 Expiration Date Not Applicable Address 4. Identification of System SI -Safety Injection 5. (a) Applicable Construction Code ASME Section III 19 71 Edition, W72 Addenda, None Code Case vlv/piping 74 S75 None (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 ASME Corrected, Code National Removed, or Stamped Name of Name of Manufacturer Board Other Year Installed (Yes or No)Component Manufacturer Serial No. No. Identification Built 1-1/2" CHECK KEROTEST S/N: KYA4-18 9394 2SI8900C 1976 REMOVED YES CHECK VALVE 1-1/2" CHECK VALVE Flowserve, Inc S/N: 39BUX N/A CAT ID: 23370 2013 INSTALLED YES 1-12ECK. 160AUNTE 1-1/2"SCH.
160 HUNTER HT# 479161 N/A 2SI08JC-1-1/2" 1982 REMOVED NO PIPE CORP.1-1/2" SCH. 160 Consolidated PI1Poe S upply HT# 510310 N/A CAT ID: 41105 2009 INSTALLED NO PIPE Power Supply1 1-1/2"90 DEG HUNTER HT#: NM N/A 2SI08JC-1-1/2" 1982 REMOVED NO 6000# ELBOW CORP. _1-1/2"90 DEG Consolidated HT# 44053 N/A CAT ID: 39262 2007 INSTALLED NO 6000# ELBOW Power Supply SEAL WELD ON EXELON N/A N/A N/A 2013 INSTALLED NO VALVE CAP 7. Description of Work REPLACE CHECK VALVE AND ASSOCIATED PIPING.8. Test Conducted:
Hydrostatic E] Pneumatic E] Nominal Operating Pressure Z Exempt i: Other [] Pressure 2234 / 2418 psi Test Temp. 557 / 476 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 number of sheets is recorded at the top of this form.
FORM NIS-2 (Back)9. Remarks 01480596-01 Applicable Manufacturer's 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^Authorization No. Not Applicable Signed (L- 4 O. 0, A&#xfd; .X, JA 266, Date 5"-2-d ,20 13 0=,er or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Illinois and employed by HSB CT of Harord, CT have jspocted the components described in this Owner's Report during the period to .,and state that to the best of my knowledge and belief, the (Oner has performed dxaminations 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.
Q x' .Commissions
//, X c. ._3 Inspector's Signature Date: 20 13 National Board, State Province, and Endorsements (Final)()
DOCUMENT NO.: 5.2 REV. NO.: 0 FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI 1. Owner Exelon Nuclear Date 4/17/13 Name 4300 Winfield Road, Warrenvile, IL Sheet 1 of 1 Address 2. Plant Byron Nuclear Power Station Unit 02 Name 4450 N. German Church Road, Byron, IL Work Order No. 01480597-01 Address Repair Organization, P.O. No., Job No., etc.3. Work Performed by CB&I/Stone
& Webster Type Code Symbol Stamp Not Applicable Name Authorization No. Not Applicable 36400 S. Essex Road, Wilmington, IL 60481 Expiration Date Not Applicable Address 4. Identification of System SI -Safety Injection 5. (a) Applicable Construction Code ASME Section III 19 71 Edition, W72 Addenda, None Code Case (vlv) / pipe-elbow 74 S75 None (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 ASME Corrected, Code National Removed, or Stamped Name of Name of Manufacturer Board Other Year Installed (Yes or No)Component Manufacturer Serial No. No. Identification Built 1-1/2" CHECK KEROTEST S/N: XLZ1-5 21,666 2SI8900A 1978 REMOVED YES CHECK VALVE 1-1/2" 2SI8900A CHECK Flowserve S/N: 92BVB N/A CTID230 2013 INSTALLED YES CHECK VALVE CAT ID: 23370 1-1/2"SCH.
160 HUNTER HT# 750725 N/A 2SI08JA-1-1/2" 1985 REMOVED NO PIPE CORP HT# 479161 1-1/2" SCH. 160 Consolidated 2SI8900A PIPE Power Supply CAT ID: 41105 2 1-1/2" 90 DEG HUNTER HT#: NM N/A 2SI08JA-1-1/2" 1985 REMOVED NO 6000# ELBOW CORP 1-1/2" 90 DEG Consolidated N/A 2011 INSTALLED NO 6000# ELBOW Power Supply HT#_44027 N/A CAT ID: 39262 2011 INSTALLED NO SEAL WELD ON EXELON N/A N/A N/A 2013 INSTALLED NO VALVE CAP I I I I I 7. Description of Work REPLACE CHECK VALVE AND ASSOCIATED PIPING.8. Test Conducted:
Hydrostatic 0 Other E] Pr Pneumatic
[]Nominal Operating Pressure E]Exempt [I essure 2234 / 2418 psi Test Temp. 557 / 476 '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 number of sheets is recorded at the top of this form.
FORM NIS-2 (Back)9. Remarks 01480597-01 Applicable Manufacturer's 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 (kLd , e k? &O M I 7A)TO/Z- Date .5-- Z ,20 13 Owner or Owner's Designee.
Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Illinois and employed by HSB CT of 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, tle cwner 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 AC~/ ~ ff C'Inspector's Signature National Board, State Province, and Endorsements Date: 4ft e7 ,20 13 (Final)
DOCUMENT NO.: 5.2 REV. NO.: 0 FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI 1. Owner Exelon Nuclear Date 4/17/13 Name 4300 Winfield Road, Warrenville, IL Sheet 1 of 1 Address 2. Plant Byron Nuclear Power Station Unit 02 Name 4450 N. German Church Road, Byron, IL Work Order No. 01480598-01, 12 Address Repair Organization, P.O. No., Job No., etc.3. Work Performed by CB&I/Stone
& Webster Type Code Symbol Stamp Not Applicable Name Authorization No. Not Applicable 36400 S. Essex Road, Wilmington, IL 60481 Expiration Date Not Applicable Address 4. Identification of System SI -Safety Injection 5. (a) Applicable Construction Code ASME Section III 19 71 Edition, W72 Addenda, None Code Case VIv / Pipe 74 S75 None (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 ASME Corrected, Code National Removed, or Stamped Name of Name of Manufacturer Board Other Year Installed (Yes or No)Component Manufacturer Serial No. No. Identification Built 1-1/2" CHECK KEROTEST S/N: KYA4-14 9391 2SI8900B 1976 REMOVED YES CHECK VALVE 1-1/2" 2I90 CHECK VALVE Flowserve S/N: 38BUX N/A 2SI8900B 2012 INSTALLED YES 1-1/2" VAV CAT ID: 233701 1-1/2"SCH.
160 HUNTER HT# 750725 N/A 2SI08JB-1-1/2" 1982 REMOVED NO PIPE CORP.1-1/2" SCH. 160 Consolidated 2SI8900B HT#: A3614H N/A 1998INSALLD N PIPE Power Supply CAT ID: 41105 SEAL WELD ON EXELON N/A N/A N/A -2013 INSTALLED NO VALVE CAP 7. Description of Work REPLACE CHECK VALVE AND ASSOCIATED PIPING.8. Test Conducted:
Hydrostatic
[] Pneumatic El Nominal Operating Pressure Z Exempt El Other El Pressure 2418 / 2234 psi Test Temp. 476 / 557 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 number of sheets is recorded at the top of this form.
FORM NIS-2 (Back)9. Remarks 01480598-01 Applicable Manufacturer's 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 p"uthorization tNq. Not Applicable Signed UL d, A -Date .7-. ,20 13 Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Illinois and employed by HSB CT of Hartford, CT haveinsp ted the components described in this Owner's Report during the period/", 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 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.
Commissions
",f37/ /Z,/YSW ,/i,4 '1.)Inspector's Signature Date: -lf .449f 20 13 AF_National Board, State Province, and Endorsements (Final)0 DOCUMENT NO.: 5.2 REV. NO.: 0 FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section Xl 1. Owner Exelon Nuclear Date 4-17-13 Name 4300 Winfield Road, Warrenville, IL Sheet 1 of 1 Address 2. Plant Byron Nuclear Power Station Unit 02 Name 4450 N. German Church Road, Byron, IL Work Order No. 01480599-01 Address Repair Organization, P.O. No., Job No., etc.3. Work Performed by CB&l/Stone
& Webster Type Code Symbol Stamp Not Applicable Name Authorization No. Not Applicable 36400 S. Essex Road, Wilmington, IL 60481 Expiration Date Not Applicable Address 4. Identification of System SI -Safety Injection 5. (a) Applicable Construction Code ASME Section III 1971 Edition W72Addenda, 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 ASME Corrected, Code National Removed, or Stamped Name of Name of Manufacturer Board Other Year Installed (Yes or No)Component Manufacturer Serial No. No. Identification Built 1-1/2" CHECK KEROTEST S/N: KYA4-16 9393 2SI8900D 1976 REMOVED YES CHECK VALVE 1-1/2" CHECK VALVE Flowserve, Inc. S/N: 03BQB N/A CAT ID: 23370 2010 INSTALLED YES 7. Description of Work REPLACED CHECK VALVE 8. Test Conducted:
Hydrostatic E]Pneumatic El Nominal Operating Pressure 0 Exempt El Other El Pressure 2418 / 2234 psi Test Temp. 476/ 557 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 number of sheets is recorded at the top of this form.
FORM NIS-2 (Back)9. Remarks 01480599-01 Applicable Manufacturer's 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 _l__,_ _ ." CO01/ Al&LA MQ/Z-- Date 1" /3 ,20 13* vT Owner or (&wner'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 Iart~rd, CT have* sppcted the components described in this Owner's Report during the period.1_0''re..to
-::"W.,F , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section XI.By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective 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 propert amage o.F., loss of any kind arising from or connectewith t.*s inspection./eer ,,, &#xfd;Commissions
()...... w Date: Inspector's Signature',20 13 National Board, State Province, and Endorsements (Final)
DOCUMENT NO.: 3.2 REV. NO.: 0 FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI 1. Owner Exelon Nuclear Date 4/14/13 Name 4300 Winfield Road, Warrenville, IL Sheet 1 of 1 Address 2. Plant Byron Nuclear Power Station Unit 02 Name 4450 N. German Church Road, Byron, IL Work Order No. 01481192-01
/02 Address Repair Organization, P.O. No., Job No., etc.3. Work Performed by Shaw/Stone
& Webster Type Code Symbol Stamp Not Applicable Name Authorization No. Not Applicable 36400 S. Essex Road, Wilmington, IL 60481 Expiration Date Not Applicable Address 4. Identification of System Safety Injection (SI)5. (a) Applicable Construction Code ASME Section III 19 71 Edition, W72 Addenda, 1501; Code Case 1649 (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 ASME Corrected, Code National Removed, or Stamped Name of Name of Manufacturer Board Other Year Installed (Yes or No)Component Manufacturer Serial No. No. Identification Built VALVE, RELIEF Crosby Valve N56902-00-0031 N/A 2SI8856B 2005 Removed Yes 2X3 & Gae VALVE, RELIEF Crosby Valve 2S18856B VL3 N56902-00-0007 N/A CtId874- 1975 Installed Yes 2X3 & Gage Cat Id 27740-1 7. Description of Work INSTALLED REPLACEMENT RELIEF VALVE PER PM PROGRAM 8. Test Conducted:
Hydrostatic El Pn Other E] Pressure eumatic E] Norr 201 psi ninal Operating Pressure 0 Exempt []Test Temp. na 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 number of sheets is recorded at the top of this form.
FORM NIS-2 (Back)9. Remarks 01481192-01 Applicable Manufacturer's 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 X1.Type Code Symbol Stamp Not Applicable Certificate ofAuthorization No. Not Applicable Signed O( .A;.L , A9 /'908 /INA'M- Date J--- ,2013 Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Illinois and employed by HSB CT of HalOwd, CT have ispegted the components described in this Owner's Report during the period to ,and state that to the best of my knowledge and belief, he wner has performed e/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 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 am ea loss of any kind arising from or connected with this inspection.
Commissions
',!',/K ..,,)Inspector's Signature Date: 4P 20 13 National Bfoard, State Province, and' Endorsements
)
DOCUMENT NO.: 3.2 REV. NO.: 0 FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section Xl 1. Owner Exelon Nuclear Date 4/17/13 Name 4300 Winfield Road, Warrenville, IL Sheet 1 of 1 Address 2. Plant Byron Nuclear Power Station Unit 02 Name 4450 N. German Church Road, Byron, IL Work Order No. 01481338-01/02 Address Repair Organization, P.O. No., Job No., etc.3. Work Performed by CB&I/Stone
& Webster Type Code Symbol Stamp Not Applicable Name Authorization No. Not Applicable 36400 S. Essex Road, Wilmington, IL 60481 Expiration Date Not Applicable Address 4. Identification of System Chemical Volume and Control (CV)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 Xl Code Case(s) NONE 6. Identification of Components ASME Corrected, Code National Removed, or Stamped Name of Name of Manufacturer Board Other Year Installed (Yes or No)Component Manufacturer Serial No. No. Identification Built VALVE, RELIEF CROSBY VALVE N56900-00-0018 N/A 2CV8121 1975 Removed YES____ ___ ___& GAGE _ _ _ _ _ _CROSBY VALVE2C82 VALVE, RELIEF & GAGE N56900-00-0015 N/A 2CV8121 1975 Installed YES_________&
GAGE _______Cat ID 27260-1 ______ ____7. Description of Work INSTALLED REPLACEMENT RELIEF VALVE 8. Test Conducted:
Hydrostatic El Pn Other C] Pressure eumatic E] Norr 50 psi ninal Operating Pressure 0 Exempt El Test Temp. 137 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 number of sheets is recorded at the top of this form.
FORM NIS-2 (Back)9. Remarks 01481338-01/02 Applicable Manufacturer's 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 9 f-iuthorization No. Not Applicable Signed (V&4~ (X Oe orJ Oroll- Date 10g) T20 13 Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Illinois and employed by HSB CT of ord, CT have sp ted the components described in this Owner's Report during the period* r/11 to 3 , and state that to the best of my knowledge and belief, (he 6wner has performed e~aminations 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 inpr a loss of any kind arising from or connected wijh 1his insp 9V..Commissions Inspector's Signature Date: National Board, State Province, and Endorsemnents
,20 13 7)
I DOCUMENTNO.:
3A REV. NO.: 0 FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI 1. Owner Exelon Nuclear Date 3/21/13 2.3.Name 4300 Winfield Road, Warrenville, IL Address Plant Byron Nuclear Power Station Name 4450 N. German Church Road, Byron, IL Address Work Performed by Byron Mechanical Maintenance Name 4450 N. German Church Road, Byron, IL Address Sheet 1 of 1 Unit 02 Work Order No. 01481338-02 Repair Organization, P.O. No., Job No., etc.Type Code Symbol Stamp Not Applicable Authorization No.Expiration Date Not Applicable Not Applicable
: 4. Identification of System CV 5. (a) Applicable Construction Code ASME Section III 19 71 Edition, S/72 Addenda, NONE Code Case (b) Applicable Edition of Section XI Used for Repair/Replacement Activity:
2001 Editlon/2003 Addenda (c) Section Xl Code Case(s)6. Identification of Components ASME Corrected, Code National Removed, or Stamped Name of Name of Manufacturer Board Other Year Installed (Yes or No)Component Manufacturer Serial No. No. Identification Built NOZZLE CROSBY N90137 N/A Heat # 8656978 2000 REMOVED No 0356 DISC INSERT CROSBY N90448 N/A Heat #713562 1998 REMOVED No 0329 NOZZLE CROSBY N90137 N/A CAT ID 2055-1 2009 INSTALLED No 0393 DISC INSERT CROSBY N90448 N/A CAT ID 2056-1 2009 INSTALLED No 0380 7. Description of Work REBUILD/REPAIR RELIEF VALVE 8. Test Conducted:
Hydrostatic
[] Pneumatic El Nominal Operating Pressure 0 Ex Other E] Pressure 50 psi Test Temp. 137 empt El 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 number of sheets is recorded at the top of this form.
FORM NIS-2 (Back)9. Remarks WO#01481338-02 Applicable Manutacturer's Uata Heports to De attacnea f )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 Xl.Type Code Symbol Stamp Not Applicable Certificate of Authorization No. Not Applicable Signed (Rd4, A ,f,//
Date S-/O ,20 13 Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Illinois and employed by HSB CT of CT haven spected the components described in this Owner's Report during the period 11 / to 1...-...!./.3 , 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 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 orpo a loss of any kind arising from or connected with this ins ection.__ _ _ _ _ _ _ Commissions w ';~/ ~ /&sect;Inspectors Signature National Board, State Province, and Endorsements Date: .EL "-,,. 20 13 (Final DOCUMENT NO.: 2.2 REV. NO.: 0)FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section Xl 1. Owner Exelon Nuclear Date 4-16-13 2.Name 4300 Winfield Road, Warrenville, IL Address Plant Byron Nuclear Power Station Name 4450 N. German Church Road, Byron, IL Address Sheet 1 of 1 Unit 02 3. Work Performed by CB&I/Stone
& Webster Work Order No. 01491143-01 Repair Organization, P.O. No., Job No., etc.Type Code Symbol Stamp Not Applicable Authorization No. Not Applicable Expiration Date Not Applicable Name 36400 S. Essex Road, Wilmington, IL 60481 Address 4. Identification of System (CV) CHEMICAL FEED & VOLUME CONTROL 5. (a) Applicable Construction Code 1651. 1682. 1683. 1685. 1686.ASME Section III 19 74 Edition, S74 Addenda, 1644 Rev. 7, 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 Xl Code Case(s)6. Identification of Components NONE ASME Corrected, Code National Removed, or Stamped Name of Name of Manufacturer Board Other Year Installed (Yes or No)Component Manufacturer Serial No. No. Identification Built Snubber, PSA -Pacific S/N: 6381 N/A 2S122018S 1983 Removed YES 1/2 Scientific Snubber, Lisega iS/N: 2SI22018S 301856RF2 isega31200814/005 N/A Cat. ID# 2013 Installed NO 1033720-1 7. Description of Work REPLACED WITH NEW LISEGA SNUBBER 8. Test Conducted:
Hydrostatic 11 Pneumatic E]Nominal Operating Pressure El psi Test Temp.Exempt El OF VT-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 II in., (2)( information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.
FORM NIS-2 (Back)9. Remarks 01491143-01 Applicable Manufacturer's 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 ,,. 'a Date -17 ,2013r Owner's Designee, Title I 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 i sp 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 Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section XI.By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective 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 propert dartiaj or a loss of any kind arising from or connected with this inspection.
Commissions 4,,4.71 //ZlfV A&#xb6;A.fl I- Inspector's Signature Date: , ,20 13 National Board, State Province, and Endorsements (Final), .)
DOCUMENT NO.: 6.1 REV. NO.: 0 FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section X1 1. Owner Exelon Nuclear Date 4-16-13 Name 4300 Winfield Road, Warrenville, IL Sheet 1 of 1 Address 2. Plant Byron Nuclear Power Station Unit 02 Name 4450 N. German Church Road, Byron, IL Work Order No. 01491175-01 Address Repair Organization, P.O. No., Job No., etc.3. Work Performed by CB&I/Stone
& Webster Type Code Symbol Stamp Not Applicable Name Authorization No. Not Applicable 36400 S. Essex Road, Wilmington, IL 60481 Expiration Date Not Applicable Address 4. Identification of System RY 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 N-225, N-38, 1690, N-247, & N-242-1 Code Case (b) Applicable Edition of Section X1 Used for Repair/Replacement Activity 2001 Edition / 2003 Addenda (c) Section XI Code Case(s) NONE 6. Identification of Components ASME Corrected, Code National Removed, or Stamped Name of Name of Manufacturer Board Other Year Installed (Yes or No)Component Manufacturer Serial No. No. Identification Built PIN, PIVOT GRINNELL N/A N/A 2RY09060S1 1983 Removed NO PIN, PIVOT GRINNELL N/A N/A 2RY09060S1 1998 Installed NO Cat ID 32458-1 7. Description of Work-REPLACED PIVOT PIN 8. Test Conducted:
Hydrostatic E]Pneumatic
[]Nominal Operating Pressure El psi Test Temp.Exempt El VT-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 number of sheets is recorded at the top of this form.
FORM NIS-2 (Back)9. Remarks 01491175-01
" Applicable Manufacturer's 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 __ -I , 20 13-Q&#xfd; 0&#xfd;wneres 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 Ha;tford, CT have irp 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 6wner has performedd eaminations 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 damagepr a loss of any kind arising from or connected with this inspection.p Commissions ,Z,*,",71//A Z, -/or Inspector's Signature National Board, State Province, and Endorsements Date: .,20 13 (Final)
DOCUMENT NO.: 6.1 REV. NO.: 0 FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section Xl 1. Owner Exelon Nuclear Date 4-16-13 Name 4300 Winfield Road, Warrenville, IL Sheet 1 of 1 Address 2. Plant Byron Nuclear Power Station Unit 02 Name 4450 N. German Church Road, Byron, IL Work Order No. 01491176-01 Address Repair Organization, P.O. No., Job No., etc.3. Work Performed by CB&I/Stone
& Webster Type Code Symbol Stamp Not Applicable Name Authorization No. Not Applicable 36400 S. Essex Road, Wilmington, IL 60481 Expiration Date Not Applicable Address 4. Identification of System RY 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 N-225, N-38, 1690, N-247, N-242-1 (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 ASME Corrected, Code National Removed, or Stamped Name of Name of Manufacturer Board Other Year Installed (Yes or No)Component Manufacturer Serial No. No. Identification Built PIN, PIVOT GRINNELL N/A N/A 2RY09060S2 1983 Removed NO PIN, PIVOT GRINNELL N/A N/A 2RY09060S2 1998 Installed NO Cat ID 32458-1 7. Description of Work-REPLACED PIVOT PIN 8. Test Conducted:
Hydrostatic E]Pneumatic E]Nominal Operating Pressure El Exempt LI OF VT-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 number of sheets is recorded at the top of this form.
FORM NIS-2 (Back)9. Remarks 01491176-01 Applicable Manufacturer's 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 .--- Cop,.- Date 0 -/7 ,20 13--- 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 a ord, CT have ispcted the components described in this Owner's Report during the period V;to Z/// ,and state that to the best of my knowledge and belief, the Owner has performed e aminations 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 inju orpropery damag_ or a loss of any kind arising from or connected with this inspection.
Commissions
,/ IAf, A'A,..d...-)Inspector's Signature Date: / 20 13 National Board, State Province, and Endorsements (Final))
DOCUMENT NO.: 2.2 REV. NO.: 0 FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section Xl 1 Owner Exelon Nuclear Date 4-22-13 2.Name 4300 Winfield Road, Warrenville, IL Address Plant Byron Nuclear Power Station Name 4450 N. German Church Road, Byron, IL Address Sheet 1 -of 1 Unit 02 Work Order No. 01491202-01 Repair Organization, P.O. No., Job No., etc.3. Work Performed by CB&I/Stone
& Webster Name 36400 S. Essex Road, Wilmington, IL 60481 Address Type Code Symbol Stamp Not Ap Authorization No. Not Applicable Expiration Date Not Applicable plicable 4. Identification of System (CV) CHEMICAL FEED & VOLUME CONTROL 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 ASME Corrected, Code National Removed, or Stamped Name of Name of Manufacturer Board Other Year Installed (Yes or No)Component Manufacturer Serial No. No. Identification Built Snubber, PSA -Pacific S/N: 13212 N/A 2CV40007S 1983 Removed YES 1/4 SSierdtific Snubber, Lisega Lisega S/N: N/A 2CV40007S 2013 Installed NO 301856RF1 31200814/004
: 7. Description of Work REPLACED NEW LISEGA SNUBBER 8. Test Conducted:
Hydrostatic El VT-3 Other 0 Pr Pneumatic Ij essure Nominal Operating Pressure [psi Test Temp. _Exempt El 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 number of sheets is recorded at the top of this form.
FORM NIS-2 (Back)9. Remarks 01491202-01 Applicable Manufacturer's 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 Xl.Type Code Symbol Stamp Not Applicable Certificate of Authorization No. Not Applicable Signed -" ' ,,Y .Date -/: , 20 13 Owners 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 -Hartord, CT have ij.pjcted the components described in this Owner's Report during the period to z J ,and state that to the best of my knowledge and belief, he wner has performed examinations and taken corrective measures described in this Owners 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 ropertqamage o loss of any kind arising from or connected with this inspection.
P Commissions " *',fr i//i ,/'1,4/ t, ,VX. el _Inspector's Signature Date: _itZ , 20 13 National Board, State Province, and Endorsements (Final)
DOCUMENT NO.: 2.2 REV. NO.: 0 FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI Owner Exelon Nuclear Date 4-16-13 2.Name 4300 Winfield Road, Warrenville, IL Address Plant Byron Nuclear Power Station Name 4450 N. German Church Road, Byron, IL Address Sheet 1 of 1 Unit 02 Work Order No. 01491239-01 Repair Organization, P.O. No., Job No., etc.3, Work Performed by CB&I/Stone
& Webster Name 36400 S. Essex Road, Wilmington, IL 60481 Type Code Symbol Authorization No.Expiration Date Stamp Not Ap Not Applicable
'plicable Not Applicable Address 4. Identification of System (CV) CHEMICAL FEED & VOLUME CONTROL 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 Xl Code Case(s) NONE 6. Identification of Components ASME Corrected, Code National Removed, or Stamped Name of Name of Manufacturer Board Other Year Installed (Yes or No)Component Manufacturer Serial No. No. Identification Built Snubber, PSA -Pacific S/N: 12677 N/A 2CV34008S 1983 Removed YES 1/2 Scientific eS/N: 2CV34008S 301Subrs Lisega S/N: N/A Cat ID# 2013 Installed NO 1033720-1 7. Description of Work REPLACED WITH A NEW LISEGA SNUBBER 8. Test Conducted:
Hydrostatic El Pneumatic
[I Non-VT-3 Other 0 Pressure psi inal Operating Pressure EI Test Temp.Exempt El OF Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 81/2/2 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 number of sheets is recorded at the top of this form.
FORM NIS-2 (Back)9. Remarks 01491239-01 Applicable Manufacturer's 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 Xl.Type Code Symbol Stamp Not Applicable Certificate of Authorization No. Not Applicable Signed ,- -"-etS.- Date 6 -/7 20 13Owners 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 H Hford, CT have 1spected the components described in this Owner's Report during the period 97,7 4 to .,and state that to the best of my knowledge and belief, the wner has performed edxaminations 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 dama e or a loss of any kind arising from or connected with this inspection.
Commissions
,-f/h /AI s. / xW Al _t)Inspector's Signature Date: ,20 13 National Board, State Province, and Endorsements (Final))
DOCUMENT NO.: 2A REV. NO.: 0 FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI 1. Owner Exelon Nuclear Date 4-24-13 Name 4300 Winfield Road, Warrenville, IL Sheet 1 of 1 Address 2. Plant Byron Nuclear Power Station Unit 02 Name 4450 N. German Church Road, Byron, IL Work Order No. 01505356-01 Address Repair Organization, P.O. No., Job No., etc.3. Work Performed by CB&I Type Code Symbol Stamp Not Applicable Name Authorization No. Not Applicable 36400 S. Essex Road, Wilmington, IL 60481 Expiration Date Not Applicable Address 4. Identification of System CV- CHEMICAL FEED AND VOLUME CONTROL 5. (a) Applicable Construction Code ASME Section III 19 74 Edition, S/75 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 ASME Corrected, Code National Removed, or Stamped Name of Name of Manufacturer Board Other Year Installed (Yes or No)Component Manufacturer Serial No. No. Identification Built PIPE, 3" Serial No. N/A 2CV19A-3" (PARTIAL)
Hunter Corp. 11440 Spool CV-26-8 1977 Removed Yes FLANGES, 3", Chicago Tube Heat No.: N/A 2CV32MA 1987 Installed NO 600 LB (2 ea.) & Iron ALZB-1 CID# 20147-1 BLANK PLATE Energy Steel & Heat No.: N/A 2CV32MA 2013 Installed NO Supply Co. E7T4 CID# 1457699-1 STUDS, 3/4' Nova Machine Heat No.: N/A 2CV32MA STUDS,_3/4" Products Inc. 3017675 CID# 37094-1 2011 Installed NO NUTS, 3/4 Nova Machine Heat No.: N/A 2CV32MA NUTS,_3/4_
Products Inc. 5092414 CID# 1394886-1 2011 Installed NO PIPE, 3" Hunter Corp. Serial No. N/A 2CV80A-3" (PARTIAL) 11434 Spool CV-26-1 1977 Removed Yes FLANGES, 3", Chicago Tube Heat No.: N/A 2CV33MA 1987 Installed NO 600 LB (2 ea.) & Iron ALZB-1 CID# 20147-1 BLANK PLATE Energy Steel & Heat No.: N/A 2CV33MA 2013 Installed NO Supply Co. E7T4 CID# 1457699-1 STUDS, 3/4" Nova Machine Heat No.: N/A 2CV33MA Products Inc. 3017675 CID# 37094-1 2 NUTS, 3/4" Nova Machine Heat No.: N/A 2CV33MA 1 Products Inc. 5092414 1 CID# 1394886-1 2 I 7. Description of Work INSTALLED NEW BLANK PLATE ASSEMBLIES PER EC#379229 8. Test Conducted:
Hydrostatic El Pn Other E] Pressure eumatic E[ Norr 353 psi ninal Operating Pressure [0 Exempt E]Test Temp. 112 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 number of sheets is recorded at the top of this form.
FORM NIS-2 (Back)9. Remarks 01505356-01 Applicable Manufacturers uata Heports to ne attacnea 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 , 20 13 wn"-e r r wner'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 ipspected the components described in this Owner's Report during the period to ,and state that to the best of my knowledge and belief, e 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.
_w._ __4 _ _- __ Commissions ,l/l,, l% " X&4,, Inspector's Signature National Board, State Province, and Endorsements Date: 4 W /e 20 13 (Final Doc 4A FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI 1. Owner Exelon Nuclear Date 5% 2-- 13 Name 4300 Winfield Road, Warrenville, IL Sheet 1 of 1 Address 2. Plant Byron Nuclear Power Station Unit 02 Name 4450 N. German Church Road, Byron, IL Work Order No. 01512586-04 Address Repair Organization, P.O. No., Job No., etc.3. Work Performed by Byron Mechanical Type Code Symbol Stamp Not Applicable Maintenance Name Authorization No. Not Applicable 4450 N. German Church Road, Byron, IL Expiration Date Not Applicable Address 4. Identification of System Main Feedwater
[FW]5. (a) Applicable Construction Code ASME Section III 19 74 Edition, W/75* 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 ASME Corrected, Code National Removed, or Stamped Name of Name of Manufacturer Board Other Year Installed (Yes or No)Component Manufacturer Serial No. No. Identification Built GATE VALVE BORG S/N 35601 2FW009C THERMOCOUPLES WARNER N/A 1979 REMVE NO GATE VALVE BORG S/N 35601 2FW009C THERMOCOUPLES WARNER N/A 1979 INSTALLED NO 7. Description of Work REPLACED THERMOCOUPLES TO 2FW009C VALVE BODY 8. Test Conducted:
Hydrostatic
[I Pr Other [3 Pressure ieumatic El Nominal Operating Pressure El Exempt ED OF 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 number of sheets is recorded at the top of this form.
FORM NIS-2 (Back)9. Remarks Work Order No. 01512586-04 Applicable Manufacturer's Data Reports to be attached , Thermocouple spot welding to be in accordance with ASME Section III NC-4311.2, 1992 Ed/1992 Addenda per EC 0000374800 and Valve Drwg 80210 Revision L. and T-Mod DCP 9901014.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!,uthorization No. Not Applicable Signed V AA0J( Date 5- 2o-_,20 Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Illinois and employed by HSB CT of Hart rd, 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, Owner has performed Gxaminations 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 dama or a loss of any kind arising from or connected with this inspection.
Commissions ,/. c.Inspector's Signature National Board, State Province, and Endorsements Date: , 20 /13 (Final)
DOCUMENT NO.: 3A REV. NO.: 0 FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI 1 Owner Exelon Nuclear Date 4/25/13 Name 4300 Winfield Road, Warrenville, IL Sheet 1 of 1 Address 2. Plant Byron Nuclear Power Station Unit 02 Name 4450 N. German Church Road, Byron, IL Work Order No. 01561181-01 Address Repair Organization, P.O. No., Job No., etc.3. Work Performed by Byron Mechanical Type Code Symbol Stamp Not Applicable Maintenance Name Authorization No. Not Applicable 4450 N. German Church Road, Byron, IL Expiration Date Not Applicable Address 4. Identification of System MS -MAIN STEAM 5. (a) Applicable Construction Code ASME Section III 19 74 Edition, S74 Addenda, 1682-1 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 ASME Corrected, Code National Removed, or Stamped Name of Name of Manufacturer Board Other Year Installed (Yes or No)Component Manufacturer Serial No. No. Identification Built Valve W-K-M Valve S/N NA Plug HT#32635 1994 Removed NO Trim Set Valve 70-117595 2MS018A Valve Flowserve S/N# C I# 1449830-1 Trim Set L9366-1-5 UTC#2904650
: 7. Description of Work REPLACE VALVE TRIM SET PER EC:390008 8. Test Conducted:
Hydrostatic El Pr Other I] Pressure eumatic E] Nominal Operating Pressure El Exempt 0 OF psi Test Temp.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 number of sheets is recorded at the top of this form.
FORM NIS-2 (Back)9. Remarks W/O#01561181-01 I Appiicable ManuTacturers Data Reports to be attacnedJ 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 oJuthorization No. Not Applicable Signed A([)a;& t .(V AJ , G 4oe06lijAiTC A-/'.. Date L/ 2 ,20 13 Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Illinois and employed by HSB CT of I-lartford, CT have inso~cted the components described in this Owners Report during the period to , and state that to the best of my knowledge and belief, -J the 6 wner has performed 5 xaminations and taken corrective measures described in this Owners 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 injur or joperty dage or ,Joss of any kind arising from or connect d wit t is inspection
________________
~Commissions4"//5 A Ki In spectol s Signature National Board, State Province, and Endorsements Date: 1 20 13 DOCUMENTNO.:
3A REV. NO.: 0 FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI 1. Owner Exelon Nuclear Date 4/23/13 Name 4300 Winfield Road, Warrenville, IL Sheet 1 of 1 Address 2. Plant Byron Nuclear Power Station Unit 02 Name 4450 N. German Church Road, Byron, IL Work Order No. 01561185-01 Address Repair Organization, P.O. No., Job No., etc.3. Work Performed by Byron Mechanical Type Code Symbol Stamp Not Applicable Maintenance Name Authorization No. Not Applicable 4450 N. German Church Road, Byron, IL Expiration Date Not Applicable Address 4. Identification of System MS -MAIN STEAM 5. (a) Applicable Construction Code ASME Section III 19 74 Edition, S74 Addenda, 1682-1 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 ASME Corrected, Code National Removed, or Stamped Name of Name of Manufacturer Board Other Year Installed (Yes or No)Component Manufacturer Serial No. No. Identification Built Valve Anchor Darling Valve S/N# NA Plug HT#32635 Trim Set 70-117596 2MS018B Valve Flowserve S/N# CI#1461659-1 Trim Set P0924-1 S/N:1 UTC# 2932916 2 7. Description of Work REPLACE VALVE TRIM SET PER EC:390008 8. Test Conducted:
Hydrostatic E] Pn Other D Pressure eumatic E] Norr psi ninal Operating Pressure E]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 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 number of sheets is recorded at the top of this form.
FORM NIS-2 (Back)L 9. Remarks W/O#01561185-01 3, Appllcable Manufacturer s uata Heports to be attacned 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 Xl.Type Code Symbol Stamp Not Applicable CertificateA Authorization No. Not Applicable Signed (:kA. -AJ!LA d00R8o11vA-q.
Date 41- 30 ,20 0A Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Illinois and employed by HSB CT of J-laptford, CT have .ected the components described in this Owner's Report during the period ,AA3 to -,and state that to the best of my knowledge and belief, the 6wner has performre6examinations 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 inje or a loss of any kind arising from or connected with this inspection.
Commissions AM41%1f /%//9*A1iC-
---Inspector's Signature Date: /National Board, State Orovince, and -Endorsements
,20 ,/5)
DOCUMENTNO.:
3A REV. NO.: 0 FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI 1 Owner Exelon Nuclear Date 04/25/13 Name 4300 Winfield Road, Warrenville, IL Sheet 1 of 1 Address 2. Plant Byron Nuclear Power Station Unit 01 Name 4450 N. German Church Road, Byron, IL Work Order No. 01561187-01 Address Repair Organization, P.O. No., Job No., etc.3. Work Performed by Byron Mechanical Type Code Symbol Stamp Not Applicable Maintenance Name Authorization No. Not Applicable 4450 N. German Church Road, Byron, IL Expiration Date Not Applicable Address 4. Identification of System MS -MAIN STEAM 5. (a) Applicable Construction Code ASME Section III 19 74 Edition, S/74 Addenda, 1682-1 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 ASME Corrected, Code National Removed, or Stamped Name of Name of Manufacturer Board Other Year installed (Yes or No)Component Manufacturer Serial No. No. Identification Built Valve W.K.M. VALVE S/N: 1910 PLUG S/N#1 Trim Set VALVE 70-117597 2MS01 8C Valve Flowserve VALVE S/N: Ct#-1461659-1 Trim Set Corp. P0924-1S/N:2 NA UTC#-2932918 2012 Installed Yes 7. Description of Work REPLACE VALVE TRIM SET PER EC:390008 8. Test Conducted:
Hydrostatic 11 Pneumatic
[]Nominal Operating Pressure El Exempt [OF Other El Pressure psi Test Temp.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 number of sheets is recorded at the top of this form.
FORM NIS-2 (Back)9. Remarks WO: 1561187-01
)Applicaule Manuraciurers uaia I-Reports to De attacned 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 It),AA OC, ,uUQ ,1w A (dODvIA1i/
07?- Date -7 20 13 Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Illinois and employed by HSB CT of Ha/gord, CT have)/rsp cted the components described in this Owner's Report during the period 31,2111S to ,and state that to the best of my knowledge and belief, the O'wner has performed examinations and taken corrective measures described in this Owners 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 propertyama-geer a loss of any kind arising from or connected with this inspection.
_______________,,___Commissions x/- s f4Z? (.)Inspector's Signature Date: Z ,20 13 National Board, State Province, and Endorsements (Final I DOCUMENT NO.: 3A REV. NO.: 0 FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI 1 Owner Exelon Nuclear Date 4/25/13 Name 4300 Winfield Road, Warrenville, IL Sheet 1 of 1 Address 2. Plant Byron Nuclear Power Station Unit 01 Name 4450 N. German Church Road, Byron, IL Work Order No. 1561189-01 Address Repair Organization, P.O. No., Job No., etc.3. Work Performed by Byron Mechanical Type Code Symbol Stamp Not Applicable Maintenance Name Authorization No. Not Applicable 4450 N. German Church Road, Byron, IL Expiration Date Not Applicable Address 4. Identification of System MS -MAIN STEAM 5. (a) Applicable Construction Code ASME Section III 19 74 Edition, S/74 Addenda, 1682-1 Code Case (b) Applicable Edition of Section X1 Used for Repair/Replacement Activity:
2001 Edition/2003 Addenda (c) Section XI Code Case(s) N/A 6. Identification of Components ASME Corrected, Code National Removed, or Stamped Name of Name of Manufacturer Board Other Year Installed (Yes or No)Component Manufacturer Serial No. No. Identification Built Valve W-K-M VALVE S/N: NA PLUG HT#76506 Trim Set Valve 70-117598 2MS018D Valve Flowserve S/N# CI#1461659-1 Trim Set Corp. P0924-1 S/N:3 NA UTC#2932919 2012 Installed Yes 7. Description of Work REPLACE VALVE TRIM SET PER EC:390008 8. Test Conducted:
Hydrostatic E] Pr Other E] Pressure leumatic E] Nominal Operating Pressure C]psi Test T emp.Exempt 0 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 number of sheets is recorded at the top of this form.
FORM NIS-2 (Back)9. Remarks WO: 1561189-01 Applicable Manufacturer's Data Reports to be attacned --d 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 Xl.Type Code Symbol Stamp Not Applicable Certificate of Authorization No. Not Applicable Signed ., (A,, IUJ-L, g.
Date --Z7 ,20 13 Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Illinois and employed by HSB CT of Hatord, CT have* sp cted the components described in this Owner's Report during the period S to 0 '73 , 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 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 orpropert damaor a loss of any kind arising from or connected with this inspection.
Commissions
,~~ L /V ,~ il".4 Inspector's Signature Date: wd' ti' ,20 13 National Board, State Province, and Endorsements (Final FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI 1.Owner Exelon Nuclear Date 3-26-13 2.3.Name 4300 Winfield Road, Warrenville, IL Address Plant Byron Nuclear Power Station Name 4450 N. German Church Road, Byron, IL Address Work Performed by NWS Technologies, LLC 131 Venture Boulevard Spartanburg, SC 29306 Address Sheet 1 of 1 Unit 02 P.O. 00485139 Rev. 01 Repair Organization, P.O. No., Job No., etc.Type Code Symbol Stamp Authorization No. 632/ 81 Expiration Date 4-3-15/4 VR / NR-9-15 4. Identification of System MAIN STEAM (MS)5. (a) Applicable Construction Code ASME Section III 19 74.4 Edition, N/A 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)6. Identification of Components NONE ASME Corrected, Code National Removed, or Stamped Name of Name of Manufacturer Board Other Year Installed (Yes or No)Component Manufacturer Serial No. No. Identification Built MAIN STEAMN/VALVE S/N: CAT ID#SAFETY RELIEF DRESSER BU01490 N/A 1439914-1 1978 REMOVED YES VALVE MAIN STEAM VALVE S/N: CAT ID#SAFETY RELIEF DRESSER N/A 1439914-1 1978 CORRECTED YES VALVEBU01490 VALVE DISK DRESSER S/N: AAJ04 N/A VALVE S/N" 1978 REMOVED NO BU01490 CAT ID#(INCONNEL X-750) DRESSER S/N: AGM19 N/A 1438465-1 2011 INSTALLED NO DISK UTC# 2894630 VALVE S/N: Spindle DRESSER S/N: G1299 N/A BU01490 1978 REMOVED NO DRESSER CAT ID#Spindle CONSOLIDA S/N: AGD80 N/A 1449980-1 2011 INSTALLED NO TED UTC# 2891523 Compression Screw DRESSER N/A N/A VALVE 1978 REMOVED NO BU01490 1978 RMVD N DRESSER CAT ID#Compression Screw CONSOLIDA S/N: AGF31 N/A 1452424-1 UTC# 2011 INSTALLED NO TED 2893937 7.Description of Work Refurbished MS relief valve, replaced disc, spindle, compression screw. Installed extended wear mod EC 339376 and anti-rotation mod EC 340678.8. Test Conducted:
Hydrostatic r_1 Pneumatic F] Nominal Operating Pressure []Exempt []
Other E] 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 numbe\of sheets is recorded at the top of this form.)
FORM NIS-2 (Back)9. Remarks P.O. 00485139 Rev. 01 Applicable Manufacturer's 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 pAithorization No. Not Applicable Signed ,v, A.. CA ,, 41 kmAJa- Date -- Y 20 13 Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Illinois and employed by HSB CT of Hartford, CT have spted the components described in this Owner's Report during the period to ,and state that to the best of my knowledge and belief, Owner has performed examinations and taken corrective measures described in this Owners 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 Owners Report.Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage, a loss of any kind arising from or connected with this inspection.
___.. ____________
Commissions f/,,/Z/Af,' ,V, c Inspector's Signature Date: National Board, State Provinge, and Endorsements
,20 13 FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI 1. Owner Exelon Nuclear Name 4300 Winfleld Road, Warrenvllle, IL Date 4-2-13 Sheet 1 of 2 2.Address Plant Byron Nuclear Power Station Name 4450 N. German Church Road, Byron, IL Address Unit 01 P.O. 00495705 Rev-1 3. Work Performed by NWS Technologies, LLC 131 Venture Boulevard Spartanburg, SC 29306 Address Repair Organization, P.O. No., Job No., etc.Type Code Symbol Stamp VR / NR Authorization No. 632 / 81 Expiration Date 4-3-15 / 4-9-15 4. Identification of System MAIN STEAM (MS)5. (a) Applicable Construction Code ASME Section III 19 74 Edition, N/A 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 ASME Corrected, Code National Removed, or Stamped Name of Name of Manufacturer Board Other Year Installed (Yes or No)Component Manufacturer Serial No. No. Identification Built MAIN STEAM VALVE S/N: VALVE UTC#SAFETY RELIEF DRESSER BR09593 N/A 2926784 1977 CORRECTED YES VALVE VALVE S/N: SPINDLE DRESSER S/N: G9776 N/A BR09593 1977 REMOVED NO CAT ID#SPINDLE DRESSER S/N: AGD81 N/A 1449980-1 2011 INSTALLED NO UTC# 2884360 COMPRESSION DRESSER S/N: N/A N/A VALVE S/N: 1977 REMOVED NO SCREW BR09593 ,OPE O CAT ID#COMPRESSION DRESSER S/N: AHL18 N/A 1452424-1 2013 INSTALLED NO SCREW UTC# 2935518 7. Description of Work Refurbished valve / installed new spindle & compression screw.8. Test Conducted:
Hydrostatic E Pn Other EJ Pressure eumatic []Nominal Operating Pressure C]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 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 number of sheets is recorded at the top of this form.
FORM NIS-2 SUPPLEMENTAL SHEET 6/ 31LcL 1. Owner Exelon Nuclear Name 4300 Winfleld Road. Warrenville.
IL Date 4-2-13 (..)Sheet 2 of 2 Address 2. Plant Byron Nuclear Power Station Name 4450 N. German Church Road, Byron, IL Address Unit 01 P.O. 00495705 Rev-1 Repair Organization, P.O. No., Job No., etc.Type Code Symbol Stamp VR / NR Authorization No. 632 /81 Expiration Date 4-3-15 / 4-9-15 3. Work Performed by NWS Technologies, LLC 131 Venture Boulevard Spartanburg, SC 29306 Address 4. Identification of System MAIN STEAM (MS)5. (a) Applicable Construction Code ASME Section III 19 74 Edition, N/A 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 ASME Corrected, Code National Removed, or Stamped Name of Name of Manufacturer Board Other Year Installed (Yes or No)Component Manufacturer Serial No. No. Identification Built MAIN STEAM VALVE S/N: VALVE UTC#SAFETY RELIEF DRESSER BR09597 N/A 2926786 1977 CORRECTED YES VALVE VALVE S/N:K SPINDLE DRESSER S/N: G9776 N/A BR09597 1977 REMOVED NO SPINDLE DRESSER S/N: AGD76 N/A CAT ID# 1449980-1 UTC# 2884360 2011 INSTALLED NO COMPRSSIONVALVE S/N: COMPRESSION DRESSER S/N: N/A N/A VALVE 1977 REMOVED NO SCREW BR09597 COMPRESSION DRESSER S/N: AHL16 N/A CAT ID# 1452424-1 SCREW UTC# 2935518 2013 INSTALLED NO DISC DRESSER S/N: ADC97 N/A VALVEBR 2000 REMOVED NO BR09597 2001 INSALED NO DISC DRESSER S/N: ADG34 N/A ValrmvedBR0960 2001 INSTALLED NO (Final)
FORM NIS-2 (Back) " 'I 6/'9. Remarks P.O. 00495705 Rev-1 Applicable Manufacturers Data Reports to be attached NWS Traveler 12-353 Valve S/N: BR09593 NWS Traveler 12-354 Valve S/N: BR09597 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 AppIlcable Signed Dt 01--we r' 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 /Harord, CT have ipsp/cted the components described in this Owner's Report during the period Ieto WE, 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 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.
_____________________
Commissions
,4#f.47/ AZt/1 P/ ._s/'Inspector's Signature National Board, State Province, and Endorsements Date: ,20 13 or}}

Revision as of 20:38, 17 March 2019

90-Day Inservice Inspection Report for Interval 3, Period 3, (B2R17)
ML13217A093
Person / Time
Site: Byron Constellation icon.png
Issue date: 07/29/2013
From: Kearney F A
Exelon Generation Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
1.10.0101, BYRON 2013-0100
Download: ML13217A093 (184)
v • d • e


Text

ArExelon Generation July 29, 2013 LTR: BYRON 2013-0100 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 Byron Generating Station 4450 North German Church Road Byron, IL 61010-9794 www.exeloncorp.com

SUBJECT:

Byron Station Unit 2 90-Day Inservice Inspection Report for Interval 3, Period 3, (B2R17)The subject 90- Day Inservice Inspection Report for the Byron Station Unit 2, Refueling Outage Seventeen (B2R17) 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 2001 Edition through the 2003 Addenda. The report covers the inservice inspections conducted prior to and during the Unit 2 Spring 2013 refueling outage.ithere are any questions regarding this matter, please contact Steve Gackstetter, Regulatory Assurance Manager, at (815)-406-2800.

Respectfully, Site Vice President Byron Generating Station FAK/RGM!LMZ/cy

Attachment:

B2R1 7 Inservice Inspection Sumrnary Report -Spring 2013 outage kc1 f.

Ad,,:i BYRON ANU.- Exelon Generation.

UNIT 2 B2R17 Spring 2013 Outage INSERVICE INSPECTION

SUMMARY

REPORT For Inspection Activities from October 10, 2011 to May 1, 2013 Commercial Service Date August 21, 1987 Document Completion Date July 29, 2013 Exelon Generation Company (EGC, LLC)4300 Winfield Rd Warrenville, IL 60555 Byron Nuclear Power Station 4450 North German Church Rd.Byron, IL 61010 AVEMW ExeLon Generation.

BYRON UNIT 2 B2R17 INSERVICE INSPECTION

SUMMARY

REPORT SECTION SECTION DESCRIPTION PAGES i lCover Page 1 ii ITable of Contents 1 1.0 IReport Introduction 6 2.1 ISI -Weld / Component Listing 16 Examination 2.2 PSI -Weld / Component Listing 3 2.0 Summary 2.3 PSI -Bolts, Pumps, and Valves Listing 1 2ary 2.4 ISI -Pressure Tests 13 2.5 ISI -Component Supports 9 2.6 ISI -Snubbers 9 3.0 Status of Examination Completion for the Program Plan 7 1 4.0 IForm NIS-i: Preservice and Inservice Examinations 52 5.0 Form N IS-2: Repairs / Modifications 65 TOTAL PAGES IN REPORTI 183 1 BYRON STATION UNIT 2 REFUELING OUTAGE 17 INSERVICE 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 October 10, 2011, through May 1, 2013. The majority of these inspections were performed during the seventeenth refueling outage (B2R137) from April 8 through May 1, 2013.B2R17 is the first outage of the Third Period in the Third Inspection Interval.The examinations were performed in compliance with the rules and regulations of ASME Section Xl (applicable edition and addenda), pursuant to the requirements of 10 CFR 50.55a.See Section 1.7.0 for a listing of referenced documents.

This summary report meets the requirements of ASME Code, IWA-6000 for the inspection of Class 1 and 2 components and piping. Class CC and MC components in the Containment Inservice Inspection (CISI) program are included when examination results require reporting as specified in 10 CFR 50.55a.The Nondestructive Examination (NDE) Inservice Inspection (ISI) Program Plan for Class 1, 2, 3, CC, and MC components was developed in accordance with the requirements and intent of Section Xl Subsections IWA, IWB, IWC, IWD, IWE, IWF and IWL, 2001 Edition, through the 2003 Addenda.In addition to the ASME Section Xl requirements of examination, certain Nuclear Regulatory Commission (NRC) augmented ISI inspections and industry initiatives (NEI-03-08) were required.

The Byron Station Unit 2 augmented ISI examination requirements include: a) Class 1 pressure boundary for leakage at nominal operating pressure, in accordance with N RC Generic Letter 88-05;b) Class 1 Alloy 600 weld examinations in accordance with N-722, N-729-1 and N-770-1;c) Class 2 and 3 pressure boundary for leakage at nominal operating pressure, in accordance with NUREG 0737.d) Class 1 examinations of non-isolable Reactor Coolant System branch lines for Thermal Fatigue in accordance with MRP-146;e) Examination of RCP Flywheels in accordance with Regulatory Guide 1.14.Note: Specific requests for relief were developed and submitted for NRC review when the code and/or augmented requirement(s) were deemed impractical, results in excessive hardship, or an alternative examination method is determined as more suitable for the particular component.

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 Section Xl of the ASME Code. The examination tables include the corresponding code category, item number, and component/weld selection in conformance with examination requirements of Subsections IWA, IWB, IWC, IWD, IWE, IWF, and IWL.Section 1.0 Page 1 of 6 BYRON STATION UNIT 2 REFUELING OUTAGE 17 INSERVICE INSPECTION REPORT For Class 1, 2, and certain non-class piping components, the requirements of Risk Informed Inservice Inspection (RI-ISI) are followed using EPRI TR1 12657 and Table 1 of ASME Code Case N-578-1.Augmented examinations as specified by NRC and industry initiatives are included in these tables.1.1.2 Identification of Exempted Components ASME Class 1 and Class 2 components, or parts of components, that are not included in the examination tables and are exempt from examination, as specified in Section Xl Paragraphs IWB and IWC-1200, and Tables IWB-2500-1 and IWC-2500-1 are identified in the ISI Program Plan in conjunction with technical justification(s) for exempting the component or system.Class 1 or 2 piping welds exempted by IWB and IWC-1200 are not included in the RI-ISI program. Previous selection and examination exemptions identified in Tables IWB and IWC-2500-1 for the piping Examination Categories B-F, B-J, C-F-i, and C-F-2, are not incorporated into the RI-ISI program. With the adoption of RI-ISI, piping welds classified as Risk Category 6 or 7 are not subject to examination.

1.1.3 Implementation

of the ISI Program Exelon Nuclear, or its designee, visually examined ASME components utilizing the following test methods: VT-1, VT-2, and VT-3. The components examined comply with the ISI Program Schedule, Byron Station Technical Specifications, and/or comply with the ASME Section Xl Repair/Replacement Program.Certified personnel performed and evaluated visual examinations (i.e., VT-1, VT-2, and VT-3) of Class 1, 2, and 3 components, and supports.

Exelon Nuclear personnel certification procedures comply with the requirements of ANSI/ASNT CP-189, 1995 Edition and ASNT SNT-TC-1A, 1984 Edition.Certified personnel performed and evaluated all NDE. Personnel were certified to the requirements of the ASNT SNT-TC-1A, 1984 Edition. Additionally, ultrasonic examiners were certified in accordance with ANSI/ASNT CP-189, 1995 Edition. The NDE procedures were developed and certified in conformance with ASME Section V and Xl as applicable.

All ISI NDE, including evaluation of flaw indications, were performed in accordance with the requirements stipulated under Section Xl IWA-2200.

For components incorporated into the RI-ISI program, the guidance for the examination volume for a given degradation mechanism is provided by the EPRI Topical Report while the guidance for the examination method is provided by Code Case N-578-1. Augmented examinations are performed using the examination method specified in the governing regulatory or industry documents.

1.1.4 Significant

Activities During B2R17 The reactor vessel head exterior surface was visually examined for evidence of leakage per the requirements specified in N-729-1 Note (4) for Item B4.10 components.

One repaired reactor head penetration was examined with surface and volumetric methods per Item B4.20 and the approved relief request 13R-16.During the refueling outage, the Alloy 600 welds were examined for PWSCC per the requirements specified in N-722-1: Section 1.0 Page 2 of 6 BYRON STATION UNIT 2 REFUELING OUTAGE 17 INSERVICE INSPECTION REPORT" All reactor vessel bottom-mounted instrument penetrations were visually examined for leakage Item B15.80 weldments." The steam generator primary channel head drains were visually examined for leakage for Item B15.120 weldments.

A mechanical stress improvement process was performed on the reactor hot and cold leg nozzle safe-end welds. After the stress improvement process, the welds were volumetrically examined per the requirements specified in ASME Code Case N-770-1. With this application, the safe-end welds are now classified as Inspection Item D under N-770-1.1.1.5 ASME Section Xl Code Cases The implementation of the risk-informed program as described in relief request 13R-02 utilized N-578-1. For Repair/Replacement activities, code cases are identified on the applicable Form NIS-2.N-460 Alternative Examination Coverage for Class 1 and Class 2 Welds.N-508-3 Rotation of Serviced Snubbers and Pressure Relief Valves for the Purpose of Testing.N-513-2 Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping.N-566-2 Corrective Action for Leakage Identified at Bolted Connections.

N-597-2 Requirements for Analytical Evaluation of Pipe Wall Thinning.N-639 Alternative Calibration Block Material.N-648-1 Alternative Requirements for Inner Radius Examinations of Class 1 Reactor Vessel Nozzles.N-665 Alternative Requirements for Beam Angle Measurements Using Refracted Longitudinal Wave Search Units.N-685 Lighting Requirements for Surface Examination N-686-1 Alternative Requirements for Visual Examinations, VT-1, VT-2, and VT-3 N-695 Qualification Requirements for Dissimilar Metal Piping Welds.N-696 Qualification Requirements for Appendix VIII Piping Examinations Conducted From the Inside Surface.N-700 Alternative Rules for Selection of Classes 1, 2, and 3 Vessel Welded Attachments for Examination.

N-705 Evaluation Criteria for Temporary Acceptance of Degradation in Moderate Energy Class 2 or 3 Vessels and Tanks N-706 Alternative Examination Requirements of Table IWB-2500-1 and Table IWC-2500-1 for PWR Stainless Steel Residual and Regenerative Heat Exchangers N-753 Vision Tests Section 1.0 Page 3 of 6 BYRON STATION UNIT 2 REFUELING OUTAGE 17 INSERVICE INSPECTION REPORT 1.1.6 Witness and Verification of Examination The inservice inspections were witnessed and/or verified by the Authorized Nuclear Inservice Inspectors (ANII): Jeff Hendricks and Greg Feigel. These inspectors are associated with Hartford Steam Boiler CT of Harford, Connecticut, Chicago Branch, at 2443 Warrenville Rd., Suite 500, Lisle, Illinois 60532.1.2.0 EXAMINATION SUMMARIES The following section lists the summaries of examinations performed during the refueling cycle. Refer to Section 2.0 for each summary table for information or for specific tests and examinations conducted during this term.Welds & Components Summaries Inservice Inspection

-Weld / Component Listing Preservice Inspection

-Weld / Component Listing Preservice 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 is contained 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 the reports.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 the reports.1.6.0 CONTAINMENT ISI PROGRAM No reportable conditions were identified for Class CC and Class MC components during this fuel cycle.1.7.0 REFERENCED DOCUMENTS 1.7.1 Code of Federal Regulations, Title 10 Energy 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 Xl, Rules for Inservice Inspection of Nuclear Power Plant Components, 2001 Edition, through 2003 Addenda Section 1.0 Page 4 of 6 BYRON STATION UNIT 2 REFUELING OUTAGE 17 INSERVICE INSPECTION REPORT Subsection IWA: General Requirements Subsection IWB: Requirements for Class 1 Components Subsection IWC: Requirements for Class 2 Components Subsection IWD: Requirements for Class 3 Components Subsection IWE: Requirements for Class MC/Class CC Metallic Liners Components Subsection IWF: Requirements for Class 1, 2, 3, and MC Component Supports Subsection IWL: Requirements for Class CC Concrete Components a) IWA-2200 Examination Methods b) IWA-6000:

Records and Reports c) IWB, and IWC-1200, Components Exempt from Examination d) IWB, IWC, IWE, IWF, and IWL-2500, Examination and Pressure Test Requirements 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-722-1: Additional Examinations for PWR Pressure Retaining Welds in Class 1 Components Fabricated With Alloy 600/82/182 Materials.

Code Case N-729-1: Alternative Examination Requirements for PWR Reactor Vessel Upper Heads With Nozzles Having Pressure-Retaining Partial-Penetration Welds.Code Case N-770-1: Alternative Examination Requirements and Acceptance Standards for Class 1 PWR Piping and Vessel Nozzle Butt Welds Fabricated with UNS N06082 or UNS W86182 Weld Filler Material With or Without Application of Listed Mitigation Activities.

Form NIS-1, Owners Report for Inservice Inspections.

Form NIS-2, Owners Report for Repairs or Replacements.

1.7.3 American

National Standards Institute

/ American Society for Nondestructive Testing ANSI/ASNT CP-189, 1995 Edition, Standard for Qualification and Certification of Nondestructive Testing Personnel.

1.7.4 American

Society for Nondestructive Testinq ASNT Recommended Practice No. SNT-TC-1A, 1984 Edition, Personnel Qualification and Certification in Nondestructive Testing.1.7.5 Miscellaneous NRC Documents Generic Letter 88-05, Boric Acid Corrosion of Carbon Steel Reactor Pressure Boundary Components in PWR Plants.NUREG 0737, Clarification of TMI Action Plan Requirements.

1.7.6 Electric

Power Research Institute Topical Report TR1 12657 Revision B-A, Revised Risk-Informed Inservice Inspection Procedure, December 1999.Section 1.0 Page 5 of 6 BYRON STATION UNIT 2 REFUELING OUTAGE 17 INSERVICE INSPECTION REPORT Materials Reliability Program: Management of Thermal Fatigue in Normally Stagnant Non-Isolable Reactor Coolant System Branch Lines (MRP-146, Revision 1), June 2011 1.7.7 Nuclear Energy Institute NEI 03-08, Guideline for the Management of Materials Issues.1.7.8 Byron Station Documents Relief Request 13R-02: Alternate Risk-Informed Selection and Examination Criteria for Category B-F, B-J, C-F- 1, and C-F-2 Pressure Retaining Piping Welds.Relief Request 13R-14: Alternative Requirements for the Repair of a Reactor Vessel Head Penetration In Accordance with 10 CFR 50.55a(a)(3)(i)

Relief Request 13R-1 6: Alternate Examination Frequency under ASME Code Case N-729-1 for Reactor Vessel Head Penetration Welds.Section 1.0 Page 6 of 6 7/25/2013 Exeleln -Byron Station Unit 2 B2R17 ISI Outage Report Weld / Component Outage Summary SYSTEM: Chemical & Volume Control System (CV)Section X: Com ponent ID L1"ine Number. Relief Technical Code Actual Results.I Cat. Description Requests Notes Coverage Exam Comments /~R-A R1.11 2CVA3B-2/W-70 2CVA3B-2 13R-02 B9.40 VT-2 NRI Pipe -Elbow 13T-01 13T-02 OBS17-005 R-A R1.11 2CVA3B-2/W-71 2CVA3B-2 13R-02 B9.40 VT-2 NRI Elbow -Pipe 13T-01 13T-02 OBS17-006 R-A R1.11 2CVA3B-2/W-72 2CVA3B-2 13R-02 B9.40 VT-2 NRI Pipe -Elbow 13T-01 13T-02 OBS17-007 R-A R1.11 2CVA3B-2/W-73 2CVA3B-2 13R-02 B9.40 VT-2 NRI Elbow -Pipe 13T-01 13T-02 OBS17-008 R-A R1.11 2CVA3B-2/W-80 2CVA3B-2 13R-02 B9.40 VT-2 NRI Pipe -Elbow 13T-01 13T-02 OBS17-009 R-A R1.11 2CVA3B-2iW-81 2CVA3B-2 13R-02 B9.40 VT-2 NRI Elbow -Pipe 13T-01 13T-02 OBS17-010 R-A R1.11 2CVA5AA-2/W-06 2CVA5AA-2 13R-02 89.40 VT-2 NRI Pipe -Elbow 13T-01 13T-02 OBS17-011 R-A R1.11 2CVA5AA-2/W-07 2CVA5AA-2 13R-02 B9.40 VT-2 NRI Elbow -Pipe 13T-01 13T-02 OBS17-012 R-A R1.11 2CVA6AA-2/W-04 2CVA6AA-2 13R-02 89.40 VT-2 NRI Pipe -Elbow 13T-01 13T-02 OBS17-013 R-A R1.11 2CVA6AA-2/W-05 2CVA6AA-2 13R-02 89.40 VT-2 NRI Elbow -Pipe 13T-01 13T-02 OBS17-014 R-A R1.11 2CVA7AA-2/W-06 2CVA7AA-2 13R-02 89.40 VT-2 NRI Pipe -Elbow 13T-01 13T-02 OBS17-050 1 7/25/2013 Exe in., Byron Station Unit 2 B2R17 ISI Outage Report Weld / Component Outage Summary SYSTEM: Chemical & Volume Control System (CV)ectlon Xl,ýComponent 1D Line Number Relief Code. Actual Results.CatD"scription Requests: ,Notes ; ~ Coverage..

Exam.Comments-R-A R1.11 2CVA7AA-2/W-07 2CVA7AA-2 13R-02 19.40 VT-2 NRI Elbow -Pipe 13T-01 13T-02 OBS17-051 R-A R1.11 2CVA7AA-2/W-08 2CVA7AA-2 13R-02 89.40 VT-2 NRI Pipe -Elbow 13T-01 13T-02 OBS17-052 2 7/25/2013 Exeln ..............................

...~ .t t o ~ i Byron Station Unit 2 B2R17 ISI Outage Report Weld / Component Outage Summary SYSTEM: Feedwater System (FW)Section Xl, ComponetID

." Line Number Relief Technical C6 ..e Actual Results Cat. IDescription Requests.

Notes Coverage Exam Comments_

_ ._. ...R-A R1.11 2FW03DB-16/118 2FW03DB-16 13R-02 05.51 100 UT Nil R1.18 Pipe- Elbow 13T-01 13T-02 OBS17-080 R-A R1.11 2FW03DB-16/C19 2FW03DB-16 13R-02 C5.51 100 UT NRI R1.18 Elbow-Pipe 13T-01 13T-02 OBS17-081 R-A R1.11 2FW03DC-16/C21 2FW03DC-16 13R-02 C5.51 100 UT NRI R1.18 Pipe-Elbow 13T-01 13T-02 OBS17-082 R-A R1.11 2FW03DC-16/C22 2FW03DC-16 13R-02 C5.51 100 UT NRI R1.18 Elbow-Pipe 13T-01 13T-02 OBS17-083 Weld obstructed 11 "-17" CCW on downstream side due to non-removable support. Code coverage was not limited by the obstruction.

R-A R1.11 2FW87CA-6/C05 2FW87CA-6 13R-02 C5.51 100 UT NRI R1.18 Pipe-Pipe 13T-01 13T-02 OBS17-125 R-A R1.11 2FW87CA-6/C06 2FW87CA-6 13R-02 C5.51 100 UT GEOM R1.18 Pipe-Elbow 13T-01 13T-02 OBS17-126 ID Geometry at 0". Weld crown from 2" CCW to 2" CW ground flush to aid scanning across weld.R-A R1.11 2FW87CA-6/C07 2FW87CA-6 13R-02 C5.51 100 UT NRI R1.18 Elbow-Pipe 13T-01 13T-02 OBS17-127 R-A R1.11 2FW87CA-6/C08 2FW87CA-6 13R-02 C5.51 100 UT NRI R1.18 Pipe-Elbow 13T-01 13T-02 OBS17-128 R-A R1.11 2FW87CA-6/C09 2FW87CA-6 13R-02 C5.51 100 UT NRI R1.18 Elbow-Pipe 13T-01 13T-02 OBS17-129 3 7/25/2013 Exeklnm Byron Station Unit 2 B2R17 ISI Outage Report Weld / Component Outage Summary SYSTEM: Reactor Coolant System (RC)Section XlL iComponentlD LineNurber Relief .Technical Cod ActuaL Results Cat. Description Requests.

Notes Coverage.

Exam Comments .., R-A R1.20 2RC01AA-29/JO1 2RC01AA-29 13R-02 B9.11 97 UT NRI Safe End -Pipe 13T-01 100 ET NRI 13T-02 OBS17-132 Outlet Nozzle @ 338' Safe-End Weld. Post-MSIP automated UT and ET examination from ID surface. See WO 01480225 for reports.Scan obstructed by counterbore geometry.

Exam not credited for RI-ISI, see B2R16 for credited examination.

R-A R1.20 2RC01AA-29/J06 2RC01AA-29 13R-02 B9.40 VT-2 NRI SOL -Thermowell 13T-01 13T-02 OBS17-015 R-A R1.20 2RC01AB-29/J01 2RC01AB-29 13R-02 B9.11 94 UT NRI Safe End -Pipe 13T-01 100 ET NRI 13T-02 OBS17-133 Outlet Nozzle @ 2020 Safe-End Weld. Post-MSIP automated UT and ET examination from ID surface. See WO 01480225 for reports.Scan obstructed by counterbore geometry.

Exam not credited for RI-ISI, see B2R16 for credited examination.

R-A R1.20 2RC01AC-29/JO1 2RC01AC-29 13R-02 B9.11 98 UT NRI Safe End -Pipe 13T-01 100 ET NRI 13T-02 OBS17-134 Outlet Nozzle @ 1580 Safe-End Weld. Post-MSIP automated UT and ET examination from ID surface. See WO 01480225 for reports.Scan obstructed by counterbore geometry.

Exam not credited for RI-ISI, see B2R16 for credited examination.

R-A R1.20 2RC01AD-29/JO1 2RC01AD-29 13R-02 B9.11 90 UT NRI Safe End -Pipe 13T-01 100 ET NRI 13T-02 OBS17-135 Outlet Nozzle @ 220 Safe-End Weld. Post-MSIP automated UT and ET examination from ID surface. See WO 01480225 for reports.Scan obstructed by counterbore geometry (actual coverage:

90.28%). Exam not credited for RI-ISI, see B2R16 for credited examination.

R-A R1.15 2RC-01-R/RPVS-A F1 2RC-01-R 13R-02 85.10 100 UT NRI 815.90 RPV Nozzle Safe-End HL Loop D 13T-01 100 ET NRI A-2 13T-02 OBS17-113 Outlet Nozzle @ 22' Safe-End Weld. Post-MSIP automated UT and ET examination from ID surface. Per N-722-1 Note(5) and N-770-1 Note(3), the UT examination is acceptable in lieu of the BMV. See WO 01480225 for reports.R-A R1.15 2RC-01-R/RPVS-B F1 2RC-01-R 13R-02 85.10 100 UT NRI B15.95 RPV Nozzle Safe-End CL Loop D 13T-01 100 ET NRI 13T-02 OBS17-114 Inlet Nozzle @ 67' Safe-End Weld. Post-MSIP automated UT and ET examination from ID surface. Per N-722-1 Note(5) and N-770-1 Note(3), the UT examination is acceptable in lieu of the BMV. See WO 01480225 for reports.R-A R1.15 2RC-01-R/RPVS-C F1 2RC-01-R 13R-02 B5.10 100 UT NRI 815.95 RPV Nozzle Safe-End CL Loop C 13T-01 100 ET NRI 13T-02 OBS17-115 Inlet Nozzle @ 1130 Safe-End Weld. Post-MSIP automated UT and ET examination from ID surface. Per N-722-1 Note(5) and N-770-1 Note(3), the UT examination is acceptable in lieu of the BMV. See WO 01480225 for reports.4 7/25/2013 Exekln,.Byron Station Unit 2 B2R17 ISI Outage Report Weld / Component Outage Summary SYSTEM: Reactor Coolant System (RC)Section Xl Component ID Number Relief Code I Actual e Results Cat.. Description Request Notes ..Coverage 1 Exam%, Comments ,.......,, R-A R1.15 2RC-01-R/RPVS-D F1 2RC-01-R B15.90 RPV Nozzle Safe-End HL Loop C A-2 13R-02 135.10 13T-01 13T-02 98 UT NRI 100 ET NRI OBS17-116 Outlet Nozzle @ 1580 Safe-End Weld. Post-MSIP automated UT and ET examination from ID surface. Per N-722-1 Note(5) and N-770-1 Note(3), the UT examination is acceptable in lieu of the BMV. See WO 01480225 for reports.R-A R1.15 2RC-01-R/RPVS-E F1 2RC-01-R B15.90 RPV Nozzle Safe-End HL Loop B A-2 13R-02 135.10 13T-01 13T-02 100 100 UT NRI ET NRI OBS17-117 Outlet Nozzle @ 2020 Safe-End Weld. Post-MSIP automated UT and ET examination from ID surface. Per N-722-1 Note(5) and N-770-1 Note(3), the UT examination is acceptable in lieu of the BMV. See WO 01480225 for reports.R-A R1.15 2RC-01-R/RPVS-F F1 2RC-01-R 815.95 RPV Nozzle Safe-End CL Loop B 13R-02 85.10 13T-01 13T-02 100 100 UT ET NRI NRI OBS17-118 Inlet Nozzle @ 247- Safe-End Weld. Post-MSIP automated UT and ET examination from ID surface. Per N-722-1 Note(5) and N-770-1 Note(3), the UT examination is acceptable in lieu of the BMV. See WO 01480225 for reports.R-A R1.15 2RC-01-R/RPVS-G F1 2RC-01-R B15.95 RPV Nozzle Safe-End CL Loop A 13R-02 85.10 13T-01 13T-02 100 UT 100 ET NRI NRI OBS17-119 Inlet Nozzle @ 2931 Safe-End Weld. Post-MSIP automated UT and ET examination from ID surface. Per N-722-1 Note(5) and N-770-1 Note(3), the UT examination is acceptable in lieu of the BMV. See WO 01480225 for reports.R-A R1.15 2RC-01-R/RPVS-H F1 2RC-01-R 615.90 RPV Nozzle Safe-End HL Loop A A-2 13R-02 85.10 13T-01 13T-02 100 UT NRI 100 ET NRI OBS17-120 Outlet Nozzle @ 3380 Safe-End Weld. Post-MSIP automated UT and ET examination from ID surface. Per N-722-1 Note(5) and N-770-1 Note(3), the UT examination is acceptable in lieu of the BMV. See WO 01480225 for reports.R-A R1.20 2RC03AA-27.5/JO2A 2RC03AA-27.5 13R-02 B9.40 VT-2 NRI SOL -Thermowell 13T-01 13T-02 OBS17-016 R-A R1.20 2RC03AA-27.5/J04 2RC03AA-27.5 13R-02 B9.40 VT-2 NRI SOL -Thermowell 13T-01 13T-02 OBS17-017 R-A R1.20 2RC03AA-27.5/J12 2RC03AA-27.5 13R-02 69.11 91 UT NRI Elbow -Safe End 13T-01 100 ET NRI 13T-02 OBS17-121 Inlet Nozzle @ 293' Safe-End Weld. Post-MSIP automated UT and ET examination from ID surface. See WO 01480225 for reports.Scan obstructed by counterbore geometry (actual coverage:

90.75%).5 7/25/2013 Exe k n.0 Byron Station Unit 2 B2R17 ISI Outage Report Weld / Component Outage Summary SYSTEM: Reactor Coolant System (RC)Sectl Xl "Component ID Line Number Relief Technical

.Actual Results.Cat-. -(scription Requests Note..Coverage4!":

Exam Comments .R-A R1.20 2RC03AB-27.5/J12 2RC03AB-27.5 13R-02 B9.11 95 UT NRI Elbow -Safe End 13T-01 100 ET NRI 13T-02 OBS17-122 Inlet Nozzle @ 2470 Safe-End Weld. Post-MSIP automated UT and ET examination from ID surface. See WO 01480225 for reports.Scan obstructed by counterbore geometry.R-A R1.20 2RC03AC-27.5/J13 2RC03AC-27.5 13R-02 B9.11 96 UT NRI Elbow -Safe End 13T-01 100 ET NRI 13T-02 OBS17-123 Inlet Nozzle @ 113' Safe-End Weld. Post-MSIP automated UT and ET examination from ID surface. See WO 01480225 for reports.Scan obstructed by counterbore geometry.R-A R1.20 2RC03AD-27.5/J12 2RC03AD-27.5 13R-02 B9.11 92 UT NRI Elbow -Safe End 13T-01 100 ET NRI 13T-02 OBS17-124 Inlet Nozzle @ 670 Safe-End Weld. Post-MSIP automated UT and ET examination from ID surface. See WO 01480225 for reports.Scan obstructed by counterbore geometry.R-A R1.20 2RC13AA-2/W-01 2RC13AA-2 13R-02 B9.40 VT-2 NRI SOL- Pipe 13T-01 13T-02 OBS17-026 R-A R1.20 2RC13AA-2/W-02 2RC13AA-2 13R-02 B9.40 VT-2 NRI Pipe -Tee 13T-01 13T-02 OBS17-027 R-A R1.20 2RC13AA-2/W-03 2RC13AA-2 13R-02 B9.40 VT-2 NRI Tee -Reducer 13T-01 13T-02 OBS17-028 R-A R1.20 2RC13AA-2/W-04 2RC13AA-2 13R-02 B9.40 VT-2 NRI Tee -Pipe 13T-01 13T-02 OBS17-029 R-A R1.20 2RC13AA-2/W-05 2RC13AA-2 13R-02 89.40 VT-2 NRI Pipe -Valve 13T-01 13T-02 OBS17-030 R-A R1.20 2RC13AB-2/W-01 2RC13AB-2 13R-02 B9.40 VT-2 NRI SOL -Pipe 13T-01 13T-02 OBS17-031 R-A R1.20 2RC13AC-2/W-01 2RC13AC-2 13R-02 B9.40 VT-2 NRI SOL- Pipe 13T-01 13T-02 OBS17-032 6 7/25/2013 Exehon-Byron Station Unit 2 B2R17 ISI Outage Report Weld / Component Outage Summary SYSTEM: Reactor Coolant System (RC)on- IXl:"'Component ID " 1Line Number Relief Technical Code., A:: 1ai, Results.Cat; Description Requests.

Notes Coverage Exam Comments..

R-A R1.20 2RC13AD-2/W-01 2RC13AD-2 13R-02 B9.40 VT-2 NRI SOL- Pipe 13T-01 13T-02 OBS17-033 R-A R1.11 2RC14AA-2/W-01 2RC14AA-2 13R-02 B9.40 VT-2 NRI SOL -Pipe 13T-01 13T-02 OBS17-036 R-A R1.11 2RC14AA-2/W-01A 2RC14AA-2 13R-02 69.40 VT-2 NRI Pipe -Tee 13T-01 13T-02 OBS17-037 R-A R1.11 2RC14AA-2/W-01B 2RC14AA-2 13R-02 69.40 VT-2 NRI Tee -Reducer 13T-01 13T-02 OBS17-038 R-A R1.11 2RC14AA-2/W-01C 2RC14AA-2 13R-02 B9.40 VT-2 NRI Tee -Pipe 13T-01 13T-02 OBS17-039 R-A R1.11 2RC14AA-2/W-02 2RC14AA-2 13R-02 B9.40 VT-2 NRI Pipe -Elbow 13T-01 13T-02 OBS17-040 R-A R1.11 2RC14AA-2/W-03 2RC14AA-2 13R-02 B9.40 VT-2 NRI Elbow -Pipe 13T-01 13T-02 OBS17-041 R-A R1.11 2RC14AA-2/W-04 2RC14AA-2 13R-02 69.40 VT-2 NRI Pipe -Elbow 13T-01 13T-02 OBS17-042 R-A R1.11 2RC14AA-2/W-05 2RC14AA-2 13R-02 B9.40 VT-2 NRI Elbow -Pipe 13T-01 13T-02 OBS17-043 R-A R1.11 2RC14AA-2/W-06 2RC14AA-2 13R-02 69.40 VT-2 NRI Pipe -Valve 13T-01 13T-02 OBS17-044 R-A R1.11 2RC14AA-2/W-07 2RC14AA-2 13R-02 B9.40 VT-2 NRI Valve -Pipe 13T-01 13T-02 OBS17-045 7 7/25/2013 Exelk n.-Byron Station Unit 2 B2R17 ISI Outage Report Weld / Component Outage Summary SYSTEM: Reactor Coolant System (RC)Section Xl Component ID Li" Number Relief Technical Code. Actual.: Results. i Ct". Description'

Requests Notes .Coverage Examn Comments R-A R1.11 2RC14AA-2/W-08 2RC14AA-2 13R-02 89.40 VT-2 NRI Pipe -Tee 13T-01 13T-02 OBS17-046 R-A R1.11 2RC14AA-2/W-09 2RC14AA-2 13R-02 B9.40 VT-2 NRI Tee -Reducer 13T-01 13T-02 OBS17-047 R-A R1.11 2RC14AA-2/W-10 2RC14AA-2 13R-02 B9.40 VT-2 NRI Tee -Pipe 13T-01 13T-02 OBS17-048 R-A R1.11 2RC14AA-2/W-11 2RC14AA-2 13R-02 B9.40 VT-2 NRI Pipe -Valve 13T-01 13T-02 OBS17-049 R-A R1.11 2RC16AA-2/W-03 2RC16AA-2 13R-02 B9.40 VT-2 NRI Valve -Pipe 13T-01 13T-02 OBS17-053 R-A R1.11 2RC16AA-2/W-04 2RC16AA-2 13R-02 B9.40 VT-2 NRI Pipe -Elbow 13T-01 13T-02 OBS17-054 R-A R1.11 2RC16AA-2/W-05 2RC16AA-2 13R-02 B9.40 VT-2 NRI Elbow -Pipe 13T-01 13T-02 OBS17-055 R-A R1.11 2RC16AA-2/W-06 2RC16AA-2 13R-02 B9.40 VT-2 NRI Pipe -Elbow 13T-01 13T-02 OBS17-056 R-A R1.11 2RC16AA-2/W-07 2RC16AA-2 13R-02 B9.40 VT-2 NRI Elbow -Pipe 13T-01 13T-02 OBS17-057 R-A R1.11 2RC16AB-2/W-04 2RC16AB-2 13R-02 B9.40 VT-2 NRI Pipe -Elbow 13T-01 13T-02 OBS17-058 R-A R1.11 2RC16AB-2/W-05 2RC16AB-2 13R-02 B9.40 VT-2 NRI Elbow -Pipe 13T-01 13T-02 OBS17-059 8 7125/2013 Exe. ...Byron Station Unit 2 B2R17 ISI Outage Report Weld / Component Outage Summary SYSTEM: Reactor Coolant System (RC)bComponent ID RefLine Number Rle Technical Code :tuai Results.Cat. Description Requests Notes.. Coverage, Exam R-A R1.20 2RC16AC-2/W-08 2RC16AC-2 13R-02 B9.40 VT-2 NRI Pipe -SOL 13T-01 13T-02 OBS17-024 R-A R1.20 2RC16AD-2/W-01 2RC16AD-2 13R-02 B9.40 VT-2 NRI Valve -Pipe 13T-01 13T-02 OBS17-025 R-A R1.11 2RC21AA-8/J05 2RC21AA-8 13R-02 B9.11 100 UT NRI Pipe -Elbow 13T-01 13T-02 OBS17-086 ID Geometry seen below recording levels.R-A R1.11 2RC21AA-8/J06 2RC21AA-8 13R-02 B9.11 100 UT NRI Elbow -Pipe 13T-01 13T-02 OBS17-087 ID Geometry seen below recording levels.R-A R1.11 2RC21AB-8/J07 2RC21AB-8 13R-02 B9.11 100 UT NRI Pipe -Elbow 13T-01 13T-02 OBS17-090 R-A R1.11 2RC21AB-8/J08 2RC21AB-8 13R-02 B9.11 100 UT NRI Elbow -Pipe 13T-01 13T-02 OBS17-091 R-A R1.11 2RC21AB-8/J09 2RC21AB-8 13R-02 B9.11 100 UT NRI Pipe -Elbow 13T-01 13T-02 OBS17-092 R-A R1.11 2RC21AB-8/J10 2RC21AB-8 13R-02 B9.11 100 UT NRI Elbow -Pipe 13T-01 13T-02 OBS17-093 R-A R1.20 2RC22AA-1.5/W-01 2RC22AA-1.5 13R-02 69.40 VT-2 NRI SOL- Pipe 13T-01 13T-02 OBS17-020 R-A R1.20 2RC22AA-1.5/W-05 2RC22AA-1.5 13R-02 B9.40 VT-2 NRI Elbow -Pipe 13T-01 13T-02 OBS17-021 9 7/25/2013 ExeIon..Byron Station Unit 2 B2R17 ISI Outage Report Weld / Component Outage Summary SYSTEM: Reactor Coolant System (RC)'Section Xl Component ID " une Rellief Technical.

Code Results Cat. Description Requet..Notes Coverage Eam Comments R-A R1.20 2RC22AC-1.5/W-01 2RC22AC-1.5 13R-02 B9.40 VT-2 NRI SOL -Pipe 13T-01 13T-02 OBS17-022 R-A Ri.20 2RC22AC-1.5/W-06 2RC22AC-1.5 13R-02 B9.40 VT-2 NRI Pipe -Tee 13T-01 13T-02 OBS17-023 R-A R1.20 2RC22AD-1.5/W-01 2RC22AD-1.5 13R-02 B9.40 VT-2 NRI SOL -Pipe 13T-01 13T-02 OBS17-018 R-A R1.20 2RC22AD-1.5/W-08 2RC22AD-1.5 13R-02 89.40 VT-2 NRI Pipe -Tee 13T-01 13T-02 OBS17-019 R-A R1.20 2RC24AA-4/J06 2RC24AA-4 13R-02 B9.11 100 UT NRI Pipe -Elbow 13T-01 13T-02 OBS17-094 R-A R1.20 2RC24AA-4/J07 2RC24AA-4 13R-02 B9.11 100 UT NRI Elbow -Pipe 13T-01 13T-02 OBS17-095 R-A R1.20 2RC24AA-4/J09 2RC24AA-4 13R-02 B9.11 100 UT NRI Pipe -Elbow 13T-01 13T-02 OBS17-096 R-A R1.20 2RC24AA-4/J10 2RC24AA-4 13R-02 89.11 100 UT NRI Elbow -Pipe 13T-01 13T-02 OBS17-097 R-A R1.20 2RC26A-2/W-01 2RC26A-2 13R-02 89.40 VT-2 NRI SOL -Pipe 13T-01 13T-02 OBS17-034 R-A R1.20 2RC26A-2/W-02 2RC26A-2 13R-02 89.40 VT-2 NRI Pipe -Valve 13T-01 13T-02 OBS17-035 N/A N/A 2RC28A-3/Zone 1 2RC28A-3 100 UT NRI Elbow- SOL VE NRI OBS17-130 UT and VE examinations of the weld (2RC28A-3/J07) and elbow base materials per MRP-146 requirements see WO 01577166 for reports.10 7/25/2013 Exekln.m Byron Station Unit 2 B2R17 ISI Outage Report Weld / Component Outage Summary SYSTEM: Reactor Coolant System (RC)Section Xi lComponentlD Line Number.. Relief Technical f Code Act. Iuali Results Cat. , .... Requests Notes, Coverage xam Comments " ': .; .. ..:/.. ... ... ... ....... ...R-A R1.11 2RC30AA-1.5/W-01.01 2RC30AA-1.5 13R-02 89.40 VT-2 NRI Valve -Reducer 13T-01 13T-02 OBS17-079 11 7/25/2013 Exel kn Byron Station Unit 2 B2R17 ISI Outage Report Weld / Component Outage Summary SYSTEM: Reactor Pressure Vessel (RPV)Section XL:' comonent ID. Line Number " Relief Technical Code Actual Reslts Cat. ,-Description

,, Requests, Notes Coverage Exam Comments .B-N-3 B13.70 2RC-01-R/CORE SUPP 2RC-01-R VT-3 NRI STRUCT Core Support Structure 0BS 17-112A Exam not credited for ASME XI, see B2R1 3 for credited examination.

Exam area accessible due to core barrel removal.B-N-2 B13.60 2RC-01-RPINT ATTACH 2RC-01-R VT-3 NRI NONBELT Interior Attachment Non-Beltline OBS 17-112B Exam not credited for ASME XI, see B2R13 for credited examination.

Exam area accessible due to core barrel removal. See WO 01481167 for reports.N/A B15.80 2RC-01-R/RPV BMI 2RC-01-R 100 VE NRI RPV Bottom Mounted Instruments OBS17-109 Examination per N-722-1 requirements, see WO 01480227 for reports.N/A B4.20 2RC-01-R/RPV HEAD 2RC-01-R 13R-16 84 UT IND PEN RPV Head Penetrations J-Weld 13R-18 100 PT NRI OBS17-110 Examination per N-729-1 requirements.

Penetration 68 only. See WO#01489754.

UT Indication classified as fabrication flaw from repair welding in B2R13. No change in flaw seen in this examination.

N/A B4.10 2RC-01-R/RPV HEAD 2RC-01-R VE NRI SURF RPV Head Penetrations OBS17-111 BMV per N-729-1 requirements, see WO 01480228 for reports.B-N-1 B13.10 2RC-01-R/RPV 2RC-01-R VT-3 NRI INTERIOR RPV Interior Surfaces OBS17-112 Minor debris noted and cleaned during final FOSAR. See WO 01481167 for reports.12 7/25/2013 Exelk n -Byron Station Unit 2 B2R17 ISl Outage Report Weld / Component Outage Summary SYSTEM: Reactor Coolant System (RY)Section Xl Component ID Line Number " .Rellefi ..Technical Code Actual Results Cat. Description R"quests"." Notes, Coverage Exam Comments R-A R1.11 2RY18A-2/W-01 2RY18A-2 13R-02 B9.40 V1T-2 NRI Valve -Pipe 13T-01 13T-02 OBS17-001 R-A R1.11 2RY18A-2/W-02 2RY18A-2 13R-02 B9.40 VT-2 NRI Pipe -Elbow 13T-01 13T-02 OBS17-002 R-A R1.11 2RY18A-2/W-03 2RY18A-2 13R-02 B9.40 VT-2 NRI Elbow -Pipe 13T-01 13T-02 OBS17-003 R-A R1.11 2RY18A-2/W-04 2RY18A-2 13R-02 B9.40 VT-2 NRI Pipe -WOL 13T-01 13T-02 OBS17-004 13 7/25/2013 Exel )n.Byron Station Unit 2 B2R17 ISI Outage Report Weld / Component Outage Summary SYSTEM: Steam Generator (SG)Section X1 :nCopGnent ID OTLine " Relief "Technicall dCoe Actual Results'J Cat." D-escriptin

.Requests .. Notes I-Coverage Exam Comments.,,,,,,, , ..N/A B15.120 2RC-01-BA/DRAIN 2RC-01-BA VE NRI SG Channel Head Drain OBS17-105 Examination per N-722-1 requirements, see WO 01480204 for reports.C-A C1.20 2RC-01-BA/SGC-08 2RC-01-BA 100 UT RI Upper Barrel "B" -Upper Head OBS17-098 30% DAC spot indication with no measurable through-wall depth. Evaluated as an ID surface imperfection.

No other indications seen.N/A B15.120 2RC-01-BB/DRAIN 2RC-01-BB VE NRI SG Channel Head Drain OBS17-106 Examination per N-722-1 requirements, see WO 01480206 for reports.C-A C1.10 2RC-01-BB/SGC-05 2RC-01-BB 100 UT NRI Lower Barrel "B" -Transition Cone OBS17-099 100% examination and review of previously identified indications.

Previous indications seen below recording criteria.

No change noted in PSI indications.

No recordable indications were seen with current recording criteria.C-B C2.21 2RC-01-BB/SGN-03 2RC-01-BB 100 MT IND Main Steam Nozzle 100 MT RI 100 UT NRI OBS17-100 0.3" and 0.5" linear indications (0.375" maximum allowable).

Ref: IR 01503278 and EC 393397.Examination after blending.

Both indications 0.30" in length.N/A B15.120 2RC-01-BC/DRAIN 2RC-01-BC VE NRI SG Channel Head Drain OBS17-107 Examination per N-722-1 requirements, see WO 01480220 for reports.N/A B15.120 2RC-01-BD/DRAIN 2RC-01-BD VE NRI SG Channel Head Drain OBS17-108 Examination per N-722-1 requirements, see WO 01480222 for reports.14 7/25/2013 ExelIn -Byron Station Unit 2 B2R17 ISI Outage Report Weld / Component Outage Summary SYSTEM: Safety Injection System (SI)Sectl6n Xi Component ID "b ne Number .Relief Technical Coe" Actual Resulte Cat. Description Requests Notes .4 Covage Exam Comments R-A R1.11 2SI08HA-21W-01 2SI08HA-2 13R-02 B9.40 VT-2 NRI Reducer -Coupling 13T-01 13T-02 OBS17-060 R-A R1.11 2SI08HA-2/W-02 2SI08HA-2 13R-02 B9.40 VT-2 NRI Coupling -Pipe 13T-01 13T-02 01S17-061 R-A R1.11 2SI08HA-2/W-03 2SI08HA-2 13R-02 B9.40 VT-2 NRI Pipe -Flange 13T-01 13T-02 OBS17-062 R-A R1.11 2SI08HA-2/W-04 2SI08HA-2 13R-02 B9.40 VT-2 NRI Flange -Pipe 13T-01 13T-02 OBS17-063 R-A R1.11 2SI08HA-2/W-05 2SI08HA-2 13R-02 89.40 VT-2 NRI Pipe -Coupling 13T-01 13T-02 OBS17-064 R-A R1.11 2SI08HA-2/W-06 2SI08HA-2 13R-02 B9.40 VT-2 NRI Coupling -Reducer 13T-01 13T-02 OBS17-065 R-A R1.11 2SI08JA-1.5/W-01 2SI08JA-1.5 13R-02 B9.40 VT-2 NRI Reducer -Pipe 13T-01 13T-02 OBS17-066 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 OBS17-067 R-A R1.11 2SI08JA-1.5/W-03 2SI08JA-1.5 13R-02 B9.40 VT-2 NRI Elbow -Pipe 13T-01 13T-02 OBS17-068 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 OBS17-069 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 OBS17-070 15 7/25/2013 ExeI~n..Byron Station Unit 2 B2R17 ISI Outage Report Weld / Component Outage Summary SYSTEM: Safety Injection System (SI)Section Xi Component ID Une Number Relief Technical tbCbe : ReIsults Cat. Description, " Number- Requests Notes Coverage].

Exam I Comments -R-A R1.11 2SI08JA-1.5/W-05A 2SI08JA-1.5 13R-02 89.40 VT-2 NRI Pipe -Valve 13T-01 13T-02 OBS17-071 R-A R1.11 2SI08JA-1.5/W-05B 2SI08JA-1.5 13R-02 B9.40 VT-2 NRI Valve -Pipe 13T-01 13T-02 CBS17-072 R-A R1.11 2SI08JA-1.5/W-06 2SI08JA-1.5 13R-02 B9.40 VT-2 NRI Pipe -Elbow 13T-01 13T-02 0BS17-073 R-A R1.11 2SI08JA-1.5/W-07 2SI08JA-1.5 13R-02 B9.40 VT-2 NRI Elbow -Pipe 13T-01 13T-02 OBS17-074 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 OBS17-075 R-A R1.11 2SI08JA-1.5/W-11 2SI08JA-1.5 13R-02 89.40 VT-2 NRI Flange -Pipe 13T-01 13T-02 0BS17-076 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 CBS17-077 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 OBS17-078 16 7/25/2013 Exelon, Byron Station Unit 2 B2R17 ISI Outage Report Weld / Component Outage Summary (Preservice Inspections)

SYSTEM: Reactor Coolant System (RC)Section Xl* Com'ponent iD Line Ntmber Relief ITechnical lCode jRequited Actual lResultis cat., itemi~Desdription Requests , Notes Coverage Exam Exdam.Comments -R-A R1.11 2RC30AA-1.5/W-01.01 2RC30AA-1.5 13R-02 B9.40 SURF PT NRI Valve -Reducer 13T-01 VT-2 V-T-2 NRI 13T-02 Baseline exams of socket weld W1 with valve 2SI8900A replacement.

See WO 01480597 for reports.R-A R1.11 2RC30AB-1.5/W-01.01 2RC30AB-1.5 13R-02 B9.40 100 SURF PT NRI Valve -Reducer 13T-01 VT-2 VT-2 NRI 13T-02 Baseline exams of socket weld W1 with valve 2SI8900B replacement.

See WO 01480589 for reports.R-A R1.11 2RC30AC-1.5/W-01.01 2RC30AC-1.5 13R-02 B9.40 100 SURF PT NRI Valve -Reducer 13T-01 VT-2 VT-2 NRI 13T-02 Baseline exams of socket weld W1 with valve 2SI8900C replacement.

See WO 01480596 for reports.R-A R1.11 2RC30AD-1.5/W-01.01 2RC30AD-1.5 13R-02 B9.40 SURF PT NRI Valve -Reducer 13T-01 VT-2 VT-2 NRI 13T-02 Baseline exams of socket weld W1 with valve 2SI8900D replacement.

See WO 01480599 for reports.1 7/25/2013 7/25/2013 Exe..nI.Byron Station Unit 2 B2R17 ISI Outage Report Weld / Component Outage Summary (Preservice Inspections)

SYSTEM: Safety Injection System (SI)Sectn iXl ID " ..Line Number Relief TechnicaliCoda "Required JActual .Results Cat. '"item Description., Requests.

Notes .Coverage Exam Exam Commets R-A NA 2SI03DA-2/W-01.01 2SI03DA-2 13R-02 B9.40 100 SURF PT NRI Valve -Pipe 13T-01 VT-2 VT-2 NRI 13T-02 Baseline exams of socket weld W3 with valve 2SI8905A replacement.

See WO 01025526 for reports.R-A NA 2SI03DA-2/W-02.01 2SI03DA-2 13R-02 B9.40 100 SURF PT NRI Pipe -Elbow 13T-01 VT-2 VT-2 NRI 13T-02 Baseline exams of socket weld W4 with valve 2SI8905A replacement.

See WO 01025526 for reports.R-A NA 2SI03DA-2/W-03.01 2SI03DA-2 13R-02 B9.40 SURF PT NRI Elbow -Pipe 13T-01 VT-2 VT-2 NRI 13T-02 Baseline exams of socket weld W5 with valve 2SI8905A replacement.

See WO 01025526 for reports.R-A R1.11 2SI08JA-1.5/W-35.01 2SI08JA-1.5 13R-02 B9.40 100 SURF PT NRI Pipe -Elbow 13T-01 VT-2 VT-2 NRI 13T-02 Baseline exams of socket weld W4 with valve 2SI8900A replacement.

See WO 01480597 for reports.R-A R1.11 2SI08JA-1.5/W-36.01 2SI08JA-1.5 13R-02 B9.40 100 SURF PT NRI Elbow -Pipe 13T-01 VT-2 VT-2 NRI 13T-02 Baseline exams of socket weld W3A with valve 2SI8900A replacement.

See WO 01480597 for reports.R-A R1.11 2SI08JA-1.5/W-37.01 2SI08JA-1.5 13R-02 B9.40 100 SURF PT NRI Pipe -Valve 13T-01 VT-2 VT-2 NRI 13T-02 Baseline exams of socket weld W2A with valve 2SI8900A replacement.

See WO 01480597 for reports.R-A R1.11 2SI08JB-1.5/W-38.01 2SI08JB-1.5 13R-02 B9.40 100 SURF PT NRI Elbow- Pipe 13T-01 VT-2 VT-2 NRI 13T-02 Baseline exams of socket weld W3 with valve 1S18900B replacement.

See WO 01470598 for reports.R-A R1.11 2SI08JB-1.5/W-39.01 2SI08JB-1.5 13R-02 B9.40 100 SURF PT NRI Pipe -Valve 13T-01 VT-2 VT-2 NRI 13T-02 Baseline exams of socket weld W2 with valve 1S18900B replacement.

See WO 01470598 for reports.R-A R1.11 2SI08JC-1.5/W-39.01 2SI08JC-1.5 13R-02 B9.40 100 SURF PT NRI Pipe -Elbow 13T-01 VT-2 VT-2 NRI 13T-02 Baseline exams of socket weld W4 with valve 2SI8900C replacement.

See WO 01480596 for reports.R-A R1.11 2SI08JC-1.5/W-40.01 2SI08JC-1.5 13R-02 B9.40 100 SURF PT NRI Elbow -Pipe 13T-01 VT-2 VT-2 NRI 13T-02 Baseline exams of socket weld W3 with valve 2SI8900C replacement.

See WO 01480596 for reports.R-A R1.11 2SI08JC-1.5/W-41.01 2SI08JC-1.5 13R-02 B9.40 SURF PT NRI Pipe -Valve 13T-01 VT-2 VT-2 NRI 13T-02 Baseline exams of socket weld W2 with valve 2SI8900C replacement.

See WO 01480596 for reports.2 7/25/2013 7/25/2013 Exe' pit n-Byron Station Unit 2 B2R17 ISI Outage Report Weld / Component Outage Summary (Preservice Inspections)

SYSTEM: Safety Injection System (SI)Section Xl. Component ID .lUne Number " Relie -Technical RCbde "... Ilequired Actual fResuitsi:ý Notes Coverage Exam: Examr , comments .R-A R1.11 2SI08JD-1.5/W-38.01 2SIO8JD-1.5 13R-02 B9.40 100 SURF PT NRI Pipe -Valve 13T-01 VT-2 VT-2 NRI 13T-02 Baseline exams of socket weld W2 with valve 2SI8900D replacement.

See WO 01480599 for reports.3 7/25/2013 7/25/2013 Exekein-.............

.. Byr- s a i n ~ i Byron Station Unit 2 B2R17 ISI Outage Report Detailed Inservice Inspection Bolts, Pumps, and Valves Listing (PSI)SYSTEM: Reactor Coolant System (RY)Section Xd, Component ID, Relief, Tchnical Actual Results, catItiem Description

<(' Rec"ueste Notes 5 E rh K : Comments -.B-G-2 B7.50 2RY03BA-6/FLG 1-12 VT-i NRI Piping Flange Bolting Baseline exam for 2RY8010A replacement.

See WO 01450986 for report.I 7/25/2013 7/25/2013 Exel n-Byron Station Unit 2 B2R17 ISI Outage Report Pressure Test Outage Summary SYSTEM: Auxiliary Feedwater System (AF)Section Xi C'mponent lD' , ' Reliefs T~ Actui!' Results.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 7/25/2013 7/2512013 Exelkn.Byron Station Unit 2 B2R17 ISI Outage Report Pressure Test Outage Summary SYSTEM: Containment Spray System (CS)I Section Xilý; Component ID Relief, I Technlcal

.Actual Rsults Cat. Item"..] Requests lNotes Exam Commentes

<K: C-H C7.10 2-CS-2-1 13T-04 VT-2 RI Minor packing leak on 2CS001A (WO 1313175, IR 0121069 & 01039250).

Minor packing leak on 2CS002A (IR 01436621).

Body to Bonnet inactive leak on 2SIO01A (IR 01436560, BACC Evaluation BYR201211222).

C-H C7.10 2-CS-2-2 13T-04 VT-2 RI Packing leakage on 2CS009A (IR 01308001).

2 7/25/2013 7/2512013 Exelkn.Byron Station Unit 2 B2R17 ISI Outage Report Pressure Test Outage Summary SYSTEM: Chemical & Volume Control System (CV).'" Section Xl.jd'inpoRent.ID Rel f. cal Actual. Results Secton Coponet I so Notes Exam Requests Comments.

...C-H C7.10 2-CV-2-1 13T-04 VT-2 RI 2CV01PA pump seals (WO 01473434).

2CV01 PA pump casing Flange (IR 01439397)

BACC Eval BYR20116107.

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 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 RI RI -2CV131 (IR# 150) Boric Acid Leakage acceptable as-is per Eval# BYR201312102.

Dry boric acid, no active leak.C-H C7.10 2-CV-2-6 13T-04 VT-2 RI 2CV8117 Relief Valve Inlet Flange IR# 1507959. Boric Acid Evaluation#

BYR201312083 accepted this condition as-is. Dry Boric acid, no active leakage.C-H C7.10 2-CV-2-7 13T-04 VT-2 NRI C-H C7.10 2-CV-2-8 13T-04 VT-2 NRI 3 7/25/2013 7/25/2013 Exel n-.Byron Station Unit 2 B2R17 ISI Outage Report Pressure Test Outage Summary SYSTEM: Fuel Pool Cooling System (FC)Sectio X1ehial Ata Results Sect ConXl"Component ID I Actal cat. , oItemt es* '," ,,a, Comments-.-

C-H C7.10 2-FC-2-1 13T-04 VT-2 NRI 10- on dried boron on pipe cap downstream of 2FC007 4 7/25/2013 725/2013 Exelenm Byron Station Unit 2 B2R17 ISI Outage Report Pressure Test Outage Summary SYSTEM: Feedwater System (FW)SectionXt lComponent ID Relief rjTechnicalj Actual Results Cat. item Requests., Notes Exam.Comments-C-H 07.1 0 2-FW-2-2 13T-04 VT-2 NRI 5 7/25/2013 7/2512013 Exel In.Byron Station Unit 2 B2R17 ISI Outage Report Pressure Test Outage Summary SYSTEM: Main Steam System (MS)Section X1 'Component ID. Reief lrechnicalJ Actual Results Cst. ItemRequests , Notes Examý, 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 7/25/2013 7/2512013 ExeI n.Byron Station Unit 2 B2R17 ISI Outage Report Pressure Test Outage Summary SYSTEM: Off Gas System (OG)Section XI Component 1D Cat. Item Comments Relief 11 Technical Actual.: Results Requests I"Notes Exam C-H C7.10 2-OG-2-1 13T-04 VT-2 NRI 7 7/25/2013 7/25/2013 Exelk n.Byron Station Unit 2 B2R17 ISI Outage Report Pressure Test Outage Summary SYSTEM: Primary Containment (PC)Section Componet ID Rellef Technical Actual Results Cat. Item Requests Notes Exam I Comments .?..:*..C-H C7.10 2-PC-2-1 13T-04 VT-2 NRI 8 7/25/2013 7/25/2013 ExeN no Byron Station Unit 2 B2R17 ISI Outage Report Pressure Test Outage Summary SYSTEM: Process Sampling System (PS)Section Xi lComponent ID Relief: Technical' Actual,, Results.-Cat. Item Requests Notesj Exam Comments C-H C7.10 2-PS-2-3 13T-04 VT-2 NRI C-H C7.10 2-PS-2-4 13T-04 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 9 7/25/2013 712512013 Exekn..Byron Station Unit 2 B2R17 ISI Outage Report Pressure Test Outage Summary SYSTEM: Reactor Coolant System (RC)SectionXI'Co"nponent ID Relief T al Actual. Resis Cat....Item Re"u ets Nlotes Exam Comments B-P B15.10 2-RC-1-1 13T-04 VT-2 NRI VT-2 NRI WO 01491018-01 for RX under vessel examination.

10 7/25/2013 7/2512013 Exelkn.Byron Station Unit 2 B2R17 ISI Outage Report Pressure Test Outage Summary SYSTEM: Residual Heat Removal System (RH)Section xi ID .Relief Technical:

Actual Cat. Item., Rquests Notes Exam Commients C-H C7.10 2-RH-2-1 13T-04 VT-2 RI 2RH606 Packing leakage IR 01454402 BACC Eval BYR201211391.

2RH618 Packing leakage IR 01454391 BACC Eval BYR201211390.

2CS001A Previous minor packing leak (WO 1313175, IR 0121069 & 01039250).

C-H C7.10 2-RH-2-2 13T-04 VT-2 RI 2SI138B Pipe Cap IR 01434346 BACC Eval BYR201211224.

2SI8958B Body to Bonnet IR 01434359 BACC Eval BYR20117662.

2SIJ8BA-.75 Sight Glass Flange IR 01434364 Previous leakage IR 01355737 BACC Eval BYR20129548.

2RH01 PB Previous leakage IR 01185736 BACC Eval BYR20115402.

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 11 7/25/2013 7/25/2013 Exel n-Byron Station Unit 2 B2R17 ISI Outage Report Pressure Test Outage Summary SYSTEM: Safety Injection System (SI)Section XI Component ID cat. Item , Comments , C-H C7.10 2-SI-2-1 C-H C7.10 2-SI-2-2 C-H C7.10 2-SI-2-3 C-H C7.10 2-SI-2-4 2SI8958B Body to Bonnet Previous leakage IR 00712138 BACC Eval 2007-351 C-H C7.10 2-SI-2-5 Relief Technical Actual Results.Requests Notes Exam 13T-04 VT-2 NRI 13T-04 VT-2 NRI 13T-04 VT-2 NRI 13T-04 VT-2 RI 13T-04 VT-2 NRI 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 12 7/25/2013 7/2512013 Exe n.-Byron Station Unit 2 B2R17 ISI Outage Report Pressure Test Outage Summary SYSTEM: Essential Service Water System (SX)Section Xl Compinent ID Relief Technical Actual Results: cat ite Requests, ,,, Notes ....Exam , Comments, , 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 13 7/25/2013 7125/2013 Exek.n.Byron Station Unit 2 B2R17 ISI Outage Report SYSTEM: Section xi Cat. Itein Comments F-A F1.40 F-A F1.40 F-A F1.40 F-A F1.40 F-A F1.10 F-A F1.10 F-A F1.10 F-A F1.10 F-A F1.10 F-A F1.10 F-A F1.10 F-A F1.10 F-A F1.10 F-A F1.10 F-A F1.10 Component Support Outage Summary Chemical & Volume Control System (CV)Component ID inNumber:

[ReiiefI To'Descriptlon.:..

.JRequests 2CV-01-PA/Li 2CV-01 -PA CV PUMP 2A LUG 1 2CV-01 -PA/L2 2CV-01 -PA CV PUMP 2A LUG 2 2CV-01 -PA/L3 2CV-01 -PA CV PUMP 2A LUG 3 2CV-01 -PA/L4 2CV-01 -PA CV PUMP 2A LUG 4 2CV45B-2/2RY06120X 2CV45B-2 SEISMIC 2CV45B-2/2RY06121 X 2CV45B-2 SEISMIC 2CVA3B-2/2CV1 101 OX 2CVA3B-2 SEISMIC 2CVA3B-2/2CV1 5033X 2CVA3B-2 SEISMIC 2CVA3B-2/2CV16024X 2CVA3B-2 SEISMIC 2CVA3B-2/2CV16030X 2CVA3B-2 SEISMIC 2CVA3B-2/2CV1 6084X 2CVA3B-2 SEISMIC 2CVA5AA-2/2CV1 5018V 2CVA5AA-2 VARIABLE 2CVA5AA-2/2CV1 5021 X 2CVA5AA-2 SEISMIC 2CVA6AA-2/2CV09025X 2CVA6AA-2 SEISMIC 2CVA6AA-2/2CV25025X 2CVA6AA-2 SEISMIC Actual chnIcIa .40otesExam VT-3 VT-3 VT-3 VT-3 V-r-3 VT-3 V`T-3 V`T-3 V-r-3 VT-3 VrT-3 VT-3 VT-3 VT-3 tResults-NRI NRI NRI NRI NRI NRI NRI NRI NRI NRI NRI NRI NRI NRI NRI 1 712512013 Exe-.n. .Byron Station Unit 2 B2R17 ISI Outage Report Component Support Outage Summary SYSTEM: Feedwater System (FW)Section X1 Compone LieNumber Id ..Rellef [Technical

..tua* Res.Ufs+cat. Item T6;icnriptI~io Requ.ests.

Notes Exam Comments F-A F1.20 2FW03DA-1612FW02009X 2FW03DA-16 VT-3 NRI SEISMIC F-A F1.20 2FW87CA-6/2FW0601 1X 2FW87CA-6 VT-3 NRI SEISMIC F-A F1.20 2FW87CA-6/2FW06015X 2FW87CA-6 VT-3 NRI SEISMIC F-A F1.20 2FW87CD-6/2FW09002C 2FW87CD-6 VT-3 NRI CONSTANT 2 7/2512013 Exekrnm.Byron Station Unit 2 B2R17 ISI Outage Report Component Support Outage Summary SYSTEM: Main Steam System (MS)Section Xl Component ID ft~ Line Number Reliief Technical Actual Results, Cat. Item .Description Notes Exam Com m ents.- .. ... .. *.. .......F-A F1.20 2MS07AD-28/2MS01211R 2MS07AD-28 VT-3 NRI RIGID 3 712512013 Exelnt Byron Station Unit 2 B2R17 ISl Outage Report Component Support Outage Summary SYSTEM: Reactor Coolant System (RC)Section Xl ompqoet ID Line Number 7 I -Rellef,--J.

Technical Act: a eults'cat. becrnipotiD"n .i .. .Notes Exam Comments F-A F1.40 2RC-01-BB/ULR 2RC-01 -BB SG B UPPER LATERAL RESTRAINT F-A F1.40 2RC-01-R/S 2RC-01-R VT-3 NOLK REACTOR VESSEL SUPPORT F-A F1.10 2RC16AA-2/2CV12005X 2RC16AA-2 VT-3 NRI SEISMIC F-A F1.10 2RC24AA-4/2RY06016X 2RC24AA-4 VT-3 NRI SEISMIC F-A F1.10 2RC24AA-4/2RY06035X 2RC24AA-4 VT-3 NRI SEISMIC 4 7/25/2013 Exelon -Byron Station Unit 2 B2R17 ISI Outage Report Component Support Outage Summary SYSTEM: Residual Heat Removal System (RH)Section XI Component ID -Line Number Relief. ý"Technical Actual Results Cat. Item escrption Rqusts Notes Exam Comments~F-A F1.10 2RH01AA-12/2RH02053X 2RHO1AA-12 VT-3 NRI SEISMIC F-A F1.40 2RH-01 -PA/L1 2RH-01 -PA VT-3 NRI RH PUMP 2A LUG 1 F-A F1.40 2RH-01-PA/L2 2RH-01-PA VT-3 NRI RH PUMP 2A LUG 2 F-A F1.40 2RH-01-PA/L3 2RH-01-PA VT-3 NRI RH PUMP 2A LUG 3 F-A F1.40 2RH-02-AB/L1 2RH-02-AB VT-3 NRI RH HX B LUG 1 F-A F1.40 2RH-02-AB/SKT 2RH-02-AB VT-3 NRI RH HX B SKIRT 5 7/2512013 Exeikn -Byron Station Unit 2 B2R17 ISI Outage Report Component Support Outage Summary SYSTEM: Reactor Coolant System (RY)Section Xl Component ID Line Number Reliet Technical Actual Results cat. Item iDescription eu.., Exam Comments F-A F1.10 2RY01 B-6/2RY06022X 2RY01 B-6 VT-3 NRI SEISMIC F-A F1.10 2RY01 B-6/2RY06029X 2RY01 B-6 VT-3 NOLK SEISMIC F-A F1.10 2RY1 8A-2/2RY06115V 2RY18A-2 VT-3 NOLK VARIABLE 6 7/252013e n.Byron Station Unit 2 B2R17 ISI Outage Report Component Support Outage Summary SYSTEM: Safety Injection System (SI)Section XI Component ID. Line Number Relief 2:Technical Actual Results Cat. Item ReqDescipton "Rquests .Notes Exam-.Comments~F-A F1.20 2SI06CA-8/2SI01022X 2SI05CA-8 VT-3 NRI SEISMIC F-A F1.20 2SI05CA-8/2SI01026X 2SI05CA-8 VT-3 NRI SEISMIC F-A F1.20 2SI05CA-8/2SI01038X 2SI05CA-8 VT-3 NRI SEISMIC F-A F1.20 2SI05CA-8/2SI03021X 2SI05CA-8 VT-3 NRI SEISMIC F-A F1.20 2SI06CA-8/2SI03025V 2SI05CA-8 VT-3 NRI VARIABLE F-A F1.20 2SI05CA-8/2SI03029X 2SI05CA-8 VT-3 NRI SEISMIC F-A F1.10 2SI05DA-6/2SI01017X 2SI05DA-6 VT-3 NRI SEISMIC F-A F1.10 2SI05DA-6/2SI01029X 2SI05DA-6 VT-3 NRI SEISMIC F-A F1.10 2SI05DA-6/2SI01031X 2SI05DA-6 VT-3 NRI SEISMIC F-A F1.10 2SI05DA-6/2SI01032X 2SI05DA-6 VT-3 NRI SEISMIC F-A F1.10 2SI08E-3/2SI21022X 2S108E-3 VT-3 NRI SEISMIC F-A F1.10 2SI08FA-3/2SI23011X 2SI08FA-3 VT-3 NRI SEISMIC F-A F1.10 2SI08FA-3/2SI23012A 2SI08FA-3 VT-3 NRI ANCHOR F-A F1.10 2SIO8GB-1

-1/2/2SI25004X 2SI08GB-1-1/2 VT-3 NRI SEISMIC F-A F1.10 2SIOSGB-1

-1/2/2SI25007X 2SI08GB-1-1/2 VT-3 NRI SEISMIC F-A F1.10 2SI08JA-1

-1/2/2SI24012X 2SI08JA-1-1/2 VT-3 NRI SEISMIC F-A F1.10 2SI08JA-1

-1/2/2S12501 OX 2SI08JA-1-1/2 VT-3 NRI SEISMIC F-A F1.10 2SI08JA-1

-1/2/2S125012X 2SI08JA-1-1/2 VT-3 NRI SEISMIC 7 7/25/2013 ExelIo-n.Byron Station Unit 2 B2R17 ISI Outage Report Component Support Outage Summary SYSTEM: Safety Injection System (SI)Section Xl Component ID Ltne Nuimber Relief To .ina Actual. Results*~t Ite 119cito Requsts N.otes:. "":: Exam F-A F1.10 2SIA4B-8/2RH02083X 2SIA4B-8 VT-3 NRI SEISMIC 8 7/25/2013 Exel n Byron Station Unit 2 B2R17 ISI Outage Report Component Support Outage Summary SYSTEM: Essential Service Water System (SX)Secton Xl omponent :ID Line.Number I Relief Technical Actual, Reults Item Ds "o % :Requests Notes Exam Commenits F-A F1.20 2SX06BB-16/2PC-7A 2SX06BB-16 VT-3 NRI ANCHOR VT-3 NRI F-A F1.20 2SX06BB-16/2SX07001G 2SX06BB-16 VT-3 NRI GUIDE F-A F1.20 2SX06CB-14/2SX07007X 2SX06CB-14 VT-3 NRI SEISMIC F-A F1.20 2SX07BD-10/2SX09078X 2SX07BD-10 VT-3 NRI SEISMIC F-A F1.20 2SX07CB-10/2SX09038X 2SX07CB-10 VT-3 NRI SEISMIC F-A F1.20 2SX07CD-1 0/2SX09077X 2SX07CD-1 0 VT-3 NRI SEISMIC F-A F1.20 2SX07EB-14/2SX09011X 2SX07EB-14 VT-3 NRI SEISMIC F-A F1.20 2SX08BD-10/2SX07025X 2SX08BD-10 VT-3 NRI SEISMIC 9 7/2512013 Snubber Outage Summary (Page 1 of 9)SYSTEM: Containment Spray System (CS)Exe.n...Byron Station Unit 2 Byron Station Outage B2R17 Section Xl Component ID ILIne Number. Technical Actual Results.Cat. Item ..Description .N. .s " [Requests teExam Comments F-A F1.20 2CS02AB-1 0/2CS03B022S 2CS02AB-1 0 VT-3 NRI SNUBBER SR FT PASS Note: Section Xl Category numbers N/A-ed are exempt from IWF-1 220 and IWF-2500 tables 1 7/25/2013 E-xeI n-Byron Station Unit 2 Byron Station Outage B2R17 SYSTEM: section X11 Cat. Item, Comments.NA NA NA NA NA NA F-A F1.10 NA NA NA NA NA NA NA NA NA NA NA NA F-A F1.10 F-A F1.10 F-A F1.10 F-A Fi.10 Snubber Outage Summary (Page 2 of 9)Chemical & Volume Control System (CV)T .Component ID ". .} Llne Numb. Re ,lDescription 2CV10B-3/2CV04015S 2CV10B-3 SNUBBER 2CV1 OCA-3/2CV03002S 2CV10CA-3 SNUBBER 2CV10CA-3/2CV22002S 2CV1OCA-3 SNUBBER 2CV10DB-3/2CV02009S 2CV10DB-3 SNUBBER 2CV1 4EA-2/2CV34008S 2CV14EA-2 SNUBBER 2CV14EB-2/2CV36006S 2CV14EB-2 SNUBBER 2CV1 4EC-2/2CV40007S 2CV1 4EC-2 SNUBBER 2CV14ED-2/2CV41012S 2CV14ED-2 SNUBBER 2CV15E-3/4/2CV31020S 2CV15E-3/4 SNUBBER 2CV44AB-3/4/2CV65009S 2CV44AB-3/4 SNUBBER 2CV45-2/2CV22009S 2CV45B-2 SNUBBER 2CVA5AA-2/2CV1 5054S 2CVA5AA-2 SNUBBER 2CVA7AA-2/2CV25016S 2CVA7AA-2 SNUBBER 2CVB7A-3/2CV06004S 2CVB7A-3 SNUBBER lief .Technical uests Notes SR SR SR SR SR SR SR SR SR SR SR SR SR SR ActuaI~Exam VT-3 VT-3 FrF VT-3 VIF-3 FT VT-3 FT VT-3 FrF VT-3 FT VT-3 VTF-3 Fr VTF-3 FT VT-3 VT-3 VT-3 FT VT-3*Results NRI NRI PASS NRI NRI PASS NRI PASS NRI PASS NRI NRI NRI PASS NRI PASS NRI NRI NRI PASS NRI Note: Section Xl Category numbers N/A-ed are exempt from IWF-1220 and IWF-2500 tables 2 7/25/2013 Exe In.Byron Station Unit 2 Byron Station Outage B2R17 SYSTEM: Section X1 ICat. Itemnii Comments F-A F1.20 F-A F1.20 N/A SNUB N/A SNUB F-A F1.20 F-A F1.20 F-A F1.20 F-A F1.20 Snubber Outage Summary (Page 3 of 9)Feedwater System (FW)Component i dLineNumber:

Re Descrition

~Reqi 2FW03DA-16/2FW02012S 2FW03DA-1 6 SNUBBER 2FW87CA-6/2FW06013S 2FW87CA-6 SNUBBER 2FW87CB-6/2FW07004-S1 2FW87CB-6 SNUBBER 2FW87CB-6/2FW07004-S2 2FW87CB-6 SNUBBER 2FW87CB-6/2FW07005S 2FW87CB-6 SNUBBER 2FW87CB-6/2FW07006S 2FW87CB-6 SNUBBER 2FW87CB-6/2FW07014S 2FW87CB-6 SNUBBER 2FW87CB-6/2FW07019S 2FW87CB-6 SNUBBER ilieftS Technical uests, Notes Actual SR SR DBL SR DBL SR SR SR SR SR Eam VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 FT VT-3 FT Results NRI NRI NRI NRI NRI NRI NRI PASS NRI PASS Note: Section XI Category numbers N/A-ed are exempt from IWF-1220 and IWF-2500 tables 3 712512013 ExeIv; n.Byron Station Unit 2 Byron Station Outage B2R17 Snubber Outage Summary (Page 4 of 9)SYSTEM: Main Steam System (MS)Secilon X Component ID , Line Number ' Reiief Technical Adctual Results CAt* Item .pescription" Requests Notes Exam Comments N/A SNUB 2MS01AA-30.25/2MS05007-S1 2MS01AA-30.25 DBL VT-3 NRI SNUBBER SR FT PASS N/A SNUB 2MS01AA-30.25/2MS05007-S2 2MS01AA-30.25 DBL VT-3 NRI SNUBBER SR FT PASS F-A F1.20 2MS07AD-28/2MS01 088S 2MS07AD-28 VT-3 NRI SNUBBER SR FT PASS Note: Section Xl Category numbers N/A-ed are exempt from IWF-1220 and IWF-2500 tables 4 7/25/2013 Exet n-Byron Station Unit 2 Byron Station Outage B2R17 Snubber Outage Summary (Page 5 of 9)SYSTEM: Sect[6on X, *, Cat.:, Item.Comments F-A F1.40 F-A F1.40 F-A F1.40 F-A F1.40 F-A F1.40 F-A F1.40 F-A F1.40 F-A F1.40 F-A F1.10 F-A F1.10 F-A F1.10 F-A F1.10 NA NA F-A F1.10 Reactor Coolant System (RC)lComponent " .ne Number >Descrip,=o.

.2RC01 BA-2A/2RC01 BA-A 2RC01 BA-2A SNUBBER 2RC01 BA-2A/2RC01 BA-B 2RC01 BA-2A SNUBBER 2RC01 BB-2B/2RC01 BB-A 2RC01 BB-2B SNUBBER 2RC01 BB-2B/2RC01 BB-B 2RC01 BB-2B SNUBBER 2RC01 BC-2C/2RC01 BC-A 2RC01 BC-2C SNUBBER 2RC01 BC-2C/2RC01 BC-B 2RC01 BC-2C SNUBBER 2RC01 BD-2D/2RC01 BD-A 2RC01 BD-2D SNUBBER 2RC01 BD-2D/2RC01 BD-B 2RC01 BD-2D SNUBBER 2RC13AC-2/2CV15045S 2RC13AC-2 SNUBBER 2RC14AC-2/2CV09034S 2RC1 4AC-2 SNUBBER 2RC16AA-2/2CV12006S 2RC1 6AA-2 SNUBBER 2RC1 6AB-2/2CV24003S 2RC16AB-2 SNUBBER 2RC20AC-3/4/2RC1 8009S 2RC20AC-3/4 SNUBBER 2RC22AC-1.5/2RC1 8007S 2RC22AC-1-1/2 SNUBBER i Relief Tech nical Requests Notes SR SR SR SR SR SR SR SR SR SR SR SR SR SR~Actual Exam VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 FT VT-3 VT-3 VT-3 VT-3 FT VT-3 FT VT-3 FT Results.: NRI NRI NRI NRI NRI NRI NRI NRI PASS NRI NRI NRI NRI PASS NRI PASS NRI PASS F-A F1.10 2RC22AC-1.5/2RC18014S 2RC22AC-1-1/2 VT-3 NRI SNUBBER SR NA NA 2RC48BA-1/2/2RC90A001S SNUBBER 2RC48BA-1/2 VT-3 SR Fr NRI PASS Note: Section Xl Category numbers N/A-ed are exempt from IWF-1220 and IWF-2500 tables 5 7125/2013 Exe. .n..Byron Station Unit 2 Byron Station Outage B2R17 SYSTEM: Section XlI Cat. Item., Corments .F-A F1.10 F-A F1.10 F-A F1.10 NA NA NA NA Snubber Outage Summary (Page 6 of 9)Residual Heat Removal System (RH)Component.iD'Line Number Re Desc .......ription .:, ." "" .Reqi 2RHO1AA-12/2RH02068S 2RHO1AA-12 SNUBBER 2RHO1AB-12/2RH02003S 2RHOlAB-12 SNUBBER 2RHO1AB-12/2RH02013S 2RHO1AB-12 SNUBBER 2RH26AB-3/4/2RH02115S 2RH26AB-3/4 SNUBBER 2RH26AB-3/4/2RH02116S 2RH26AB-3/4 SNUBBER SR SR SR SR SR lief T Technical.

Actual" Results uests I Notes Exam : VT-3 FT VT-3 V'-3 VT-3 FT VT-3 NRI PASS NRI NRI NRI PASS NRI Note: Section X1 Category numbers N/A-ed are exempt from IWF-1220 and IWF-2500 tables 6 7/25/2013 FxIon-Byron Station Unit 2 Byron Station Outage B2R17 Snubber Outage Summary (Page 7 of 9)SYSTEM: Section X11 Cat Item Comments,.

N/A SNUB N/A SNUB F-A F1.10 F-A F1.10 N/A SNUB N/A SNUB F-A F1.10 F-A F1.10 NA NAReactor Coolant System (RY)CopOnnt ID : '"Line Number 2RY02B-3/2RY09067-S1 2RY02B-3 SNUBBER 2RY02B-3/2RY09067-S2 2RY02B-3 SNUBBER 2RY02B-3/2RY09100S 2RY02B-3 SNUBBER 2RY06A-3/2RY09012S 2RY06A-3 SNUBBER 2RY06A-3/2RY09060-S1 2RY06A-3 SNUBBER 2RY06A-3/2RY09060-S2 2RY06A-3 SNUBBER 2RY06A-3/2RY09078S 2RY06A-3 SNUBBER 2RY06A-3/2RY09101 S 2RY06A-3 SNUBBER 2RY07AC-3/4/2RY27016S 2RY07AC-3/4 SNUBBER Relief.. echnic~a.Requests, DBL SR DBL SR SR SR DBL SR DBL SR SR SR SR Actual Exam,, V-1-3 VT-3 VT-3 FT VT-3 Vr-3 FT VT-3 FT VT-3 VT-3 VT-3 Rjuis NRI NRI NRI PASS NRI NRI PASS NRI PASS NRI NRI NRI F-A F1.10 2RY1 1A-14/2RY05010S 2RY11A-14 VT-3 NRI SNUBBER SR Fr PASS NA NA 2RY34CD-1/2/2RC91001S 2RY34CD-1/2 V--3 NRI SNUBBER SR FT PASS Note: Section Xl Category numbers N/A-ed are exempt from IWF-1 220 and IWF-2500 tables 7 712512013 Exel en-Byron Station Unit 2 Byron Station Outage B2R17 Snubber Outage Summary (Page 8 of 9)SYSTEM: Steam Generator Blowdown System (SD)Section XI Comp6nent ID , ", Line Number. Relie ,Tefi~nlcal Actual[ Results Cat. Item .EDescriptkan

  • Reque.ts " Notes E"ar Comments~NA NA 2SDO1CA-2/2SD21034S 2SDO1CA-2 VT-3 NRI SNUBBER SR FT PASS NA NA 2SD01CD-2/2SD24026S 2SD01CD-2 VT-3 NRI SNUBBER SR FT PASS NA NA 2SDO1CF-2/2SD05002-S 1 2SDO1CF-2 DBL VT-3 NRI SNUBBER SR FT PASS NA NA 2SDO1 CF-2/2SD05002-S2 2SD01CF-2 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 8 7/25/2013 Exel6n.Byron Station Unit 2 Byron Station Outage B2R17 SYSTEM: Section, X1 Cat. Itemn Comments F-A F1.10 F-A F1.20 F-A F1.10 F-A F1.10 F-A F1.10 F-A F1.10 N/A SNUB N/A SNUB F-A F1.10 Snubber Outage Summary (Page 9 of 9)Safety Injection System (SI)Component ID, linNumber Re~Description.

..2SI04D-8/2RH02061 S 2SI04D-8 SNUBBER 2SI05CA-8/2SI01023S 2SI05CA-8 SNUBBER 2SI05DD-6/2SI03009S 2SI05DD-6 SNUBBER 2SI05DD-6/2SI03018S 2SI05DD-6 SNUBBER 2SI08JD-1.5/2SI22018S 2SI08JD-1.5 SNUBBER 2SI08JD-1.5/2SI22020S 2SI08JD-1.5 SNUBBER 2SI09BC-1 0/2SI09002-$1 2SI09BC-1 0 SNUBBER 2SI09BC-1 0/2SI09002-S2 2SI09BC-1 0 SNUBBER 2SI09BD-10/2SI03001S 2SI09BD-10 SNUBBER Tie ~chnical uests~ Note~s%SR SR SR SR SR SR DBL SR DBL SR SR Actual Exam FT VIF-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 FT Vr-3 NRI PASS NRI NRI NRI NRI PASS NRI NRI PASS NRI PASS NRI R~~UI*SF Note: Section Xl Category numbers N/A-ed are exempt from IWF-1220 and IWF-2500 tables 9 (This report is used to verify that the periodic requirements of Tables IWx-2412-1 will be met by BYRON STATION UNIT 2 -3RD INTERVAL ASME SECTIO EXAMINATION STATUS REPORT N Xl I (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.)

  1. of Total # Exams Completed

% Exams Completed Item No. Corp Selected Min Per I Max Min Per 2 Max Per 3 % Selected Period 1 Period 2 Period 3 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%B1.30 1 1 N/A 1 N/A N/A 0 N/A 0 100.00% 100.00% 100.00% 100.00%B1.40 1 1 N/A 0 N/A N/A 0 N/A 0 100.00% 0.00% 0.00% 0.00%Totals: 7 7 N/A 5 N/A N/A 0 N/A 0 100.00% 71.43% 71.43% 71.43%1. Examination completion exceeds 50.00% for 1 st Period. The examinations were performed at the beginning of the Inspection Interval as allowed by Relief Request 13R-01.2. (B13.21 and B13.40): Examinations deferred to the end of the interval as allowed by Table IWB-2500-1.

3. Completion percentages of the category are not required per IWB-2412(a)(3).

Category B-B Non-Deferred Exams B2.11 2 2 B2.12 2 2 0 0 1 1 0 0 100.00%100.00%0.00%0.00%50.00%50.00%50.00%50.00%B2.40 4 1 -0 -0 25.00% 100.00% 100.00% 100.00%Totals: 8 5 1 1 2 2 2 2 0 62.50% 20.00% 60.00% 60.00%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 Exams B3.110 6 6 1 -3 0 100.00% 16.67% 66.67% 66.67%B3.120 6 6 1 -4 0 100.00% 16.67% 83.33% 83.33%B3.140 8 8 -0 -0 100.00% 50.00% 50.00% 50.00%Totals: 20 20 4 6 10 4 7 8 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 Exams B3.90 8 8 B3.100 8 8 N/A N/A 8 8 N/A N/A N/A 0 N/A 0 N/A N/A 0 0 100.00% 100.00% 100.00%100.00% 100.00% 100.00%100.00%100.00%8 N/A 0 0 Totals: 16 16 N/A 16 N/A N/A 0 N/A 0 100.00% 100.00% 100.00% 100.00%1. Per Examination Category B-D, Note 5, for PWR's in the second and successive inspection intervals, these examinations may be deferred to the end of the interval provided no repair/replacement activities have been performed on the examination item, and no flaws or relevant conditions requiring successive inspections in accordance with IWB-2420(b) are contained in the examination item.Section 3.0 Page 1 of 7

2. (B3.90 & B3.100): Examination completion exceeds 50.00% for 1 st Period and 75.00% for this 2 nd Period. The examinations were performed at the beginning of the Inspection Interval as allowed by Relief Request 13R-01.Category B-G-1 Non-Deferred Exams B6.40 1 1 N/A 0 N/A N/A 1 N/A 0 100.00% 0.00% 100.00% 100.00%Totals: 1 1 N/A 0 N/A N/A 1 N/A 0 100.00% 0.00% 100.00% 100.00%1. A single component representing all of the 54 Reactor Vessel Threads in Flange to be examined.Category B-G-1 Deferred Exams B6.10 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 1 N/A 0 100.00% 0.00% 100.00% 100.00%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: 42 13 N/A 6 N/A N/A 0 N/A 0 30.95% 46.15% 46.15% 46.15%1. (B6.110 & 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 performed at the beginning of the Inspection Interval as allowed by Relief Request 13R-01.2. (B6.170):

A single component represents the five sets of CETC column nuts.3. (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 and Examination Category B-L-2, Note 1. Examination is required only once per inspection interval.4. (B6.190):

Four components are tracked in the database, each representing the associated Flange Surfaces for one of the four Reactor Coolant Pumps (4 total)as reported in the ISI Program Plan. The visual examination of these components is limited to only one of the pumps per 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 Category B-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.5. (16.210):

Eight components are tracked in the database, each representing all of the Bolts and associated Nuts, Bushings, and Washers and Flange Surfaces on 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 the valves 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 (This report is used to verify that the periodic requirements of Tables IWx-2412-1 will be met by BYRON STATION UNIT 2 -3RD INTERVAL ASME SECTIO EXAMINATION STATUS REPORT N XI (The percentage requirements of Tables IWx-2412-1 apply to the Category and were the interval schedule.)

-. ... ......... applied to each Item only when practical.)

I # of Total # Exams Completed I % Exams Completed Item No. Comp Selected Min Per 1 Max Min Per 2 Max Per 3 % Selected Period 1 Period 2 Period 3 6. (B6.220 & B6.230): Eight components are tracked in the database, each representing all of the Bolts and associated Nuts, Bushings, and Washers and Flange Surfaces 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 of the 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 Examination Category 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 Exams B7.10 2 0 N/A 0 N/A N/A 0 N/A 0 0.00% 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 1 N/A 0 N/A N/A 1 N/A 0 25.00% 0.00% 100.00% 100.00%B7.50 20 5 N/A 3 N/A N/A 1 N/A 0 25.00% 60.00% 80.00% 100.00%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 7 N/A 4 N/A N/A 2 N/A 0 12.28% 57.14% 85.71% 100.00%1. Total selected for the category is limited to the components made accessible by disassembly for maintenance.

2. (B7.10): Two components representing the CETC and RVLIS Clamp Bolts and associated Nuts as reported in the ISI Program Plan.3. (B7.20): A single component representing all 16 Pressurizer Manway Bolts and associated Nuts as reported in the ISI Program Plan.4. (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. Per B-G-2 Note 2, the examination is limited to those vessels examined under Category B-B.5. (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 in design, size, function, and service. Examination is required only once per inspection interval within each bolted connection group.6. (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 (144 total 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 only when a pump is disassembled for maintenance, repair, or volumetric examination or bolting is removed. Also, per Examination Category B-G-2, Note 2 and Examination 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, manufacturing method, and function.

Examination is required only once per inspection interval within each valve group.7. (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 for maintenance, 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.Examination is required only once per inspection interval within each valve group.Section 3.0 Page 3 of 7 (This report is used to verify that the periodic requirements of Tables IWx-2412-1 will be met by BYRON STATION UNIT 2 -3RD INTERVAL ASME SECTIO EXAMINATION STATUS REPORT N XI (The percentage requirements of Tables IWx-2412-1 apply to the Category and were the interval schedule.)

.. .......applied to each Item only when practical.)

  1. of Total # Exams Completed

% Exams Completed Item 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 Exams B10.10 2 1 0 0 -0 100.00% 0.00% 00.00% 0.00%B10.20 8 3 -2 -0 37.50% 33.33% 100.00% 100.00%Totals: 10 4 1 1 2 2 2 2 0 40.00% 25.00% 75.00% 75.00%1. (B10.10):

Per Code Case N-700, for single vessels, only one welded attachment shall be selected for examination.

The attachment selected for examination shall be an attachment under continuous load during normal system operation, or an attachment subject to a potential intermittent load (seismic, water hammer, etc.) during normal system operation if an attachment under continuous load does not exist. The selected weld is the pressurizer skirt support weld.2. (B130.20):

Per Examination Category B-K, Note 5, for piping, pumps, and valves, a sample of 10% of the welded attachments associated with the component supports 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 Exams B12.20 4 0 N/A 0 N/A N/A 0 N/A 0 0.00% 0.00% 0.00% 0.00%Totals: 4 0 N/A 0 N/A N/A 0 N/A 0 0.00% 0.00% 0.00% 0.00%1. The examination of oumI casinos is limited to onlv one of the oumos Derforming similar functions in the system per Examination Categorv B-L-2, Note 1. Als O, per Examination Category B-L-2, Note 2, examination is required only when a pump is disassembled for maintenance, repair, or volumetric examination.

Examination is required only once per inspection interval.

The total selected for the category is limited to the components made accessible by disassembly for maintenance.

Category B-M-2 Deferred Exams B12.50 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. 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 same size, design, manufacturing method, and function.

Examination is required only once per inspection interval within each valve group. The total selected for the category is limited to the components made accessible by disassembly for maintenance.

Section 3.0 Page 4 of 7 (This report is used to verify that the periodic requirements of Tables IWx-2412-1 will be met by BYRON STATION UNIT 2 -3RD INTERVAL ASME SECTIO EXAMINATION STATUS REPORT N XI (The percentage requirements of Tables IWx-2412-1 apply to the Category and were the interval schedule.)

..applied to each Item only when practical.)

I # of Total # Exams Completed

% Exams Completed Item No. Comp Selected Min Per 1 Max Min Per 2 Max Per 3 % Selected Period 1 Period 2 Period 3 Category B-N-1 Non-Deferred Exams B13.10 1 1 -1 -1 50.00% 100.00% 200.00% 300.00%Totals: 1 1 1 1 1 1 1 1 1 50.00% 100.00% 200.00% 300.00%1. "% Completed" exceeds 100% since the vessel interior is selected for examination once each period (three times during the interval).

Category B-N-2 Deferred Exams B13.60 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. Examination completion exceeds 50.00% for 1st Period and 75.00% for this 2nd Period. The examination was performed at the beginning of the Inspection Interval as allowed by Relief Request 13R-01.Category B-N-3 Deferred Exams B13.70 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. Examination completion exceeds 50.00% for 1st Period and 75.00% for this 2 nd Period. The examination was performed at the beginning of the Inspection Interval as allowed by Relief Request 13R-01.Category B-O Non-Deferred Exams B14.10 5 5 N/A 2 N/A N/A 1 N/A 0 100.00% 40.00% 60.00% 60.00%Totals: 5 5 N/A 2 N/A N/A 1 N/A 0 100.00% 40.00% 60.00% 60.00%1. 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 five components represent that 10% population.

Category B-P Non-Deferred Exams B15.10 1 1 N/A 2 N/A N/A 2 N/A 1 100.00% 200.00% 400.00% 500.00%Totals: 1 1 N/A 2 N/A N/A 2 N/A 1 100.00% 200.00% 400.00% 500.00%1. "% Completed" exceeds 100% since Class 1 pressure tests are performed each refueling outage.2. One component representing the five systems in Class 1 as reported in the ISI Program Plan.Section 3.0 Page 5 of 7 (This report is used to verify that the periodic requirements of Tables IWx-2412-1 will be met by BYRON STATION UNIT 2 -3RD INTERVAL ASME SECTION XI EXAMINATION 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 wnen practical.)

  1. of Total # Exams Completed

% Exams Completed Item No. Comp Selected Min Per 1 Max Min Per 2 Max Per 3 % Selected Period 1 Period 2 Period 3 Category C-A Non-Deferred Exams C1.10 14 3 1 -1 1 21.43% 33.33% 66.67% 100.00%C1.20 6 1 0 1 16.67% 0.00% 0.00% 100.00%C1.30 4 1 -0 -0 25.00% 100.00% 100.00% 100.00%Totals: 24 5 1 2 2 1 1 1 2 20.83% 40.00% 60.00% 100.00%1. (C1.10 & 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 be limited to one vessel or distributed among the vessels.Category C-B Non-Deferred Exams C2.21 16 3 C2.22 4 1 1 1 1-0 1 0 18.75%25.00%20.00%33.33%100.00%50.00%66.67%100.00%75.00%100.00%100.00%100.00%Totals: 20 4 1 2 2 1 1 1 1 1. Per Examination Category C-B, Note 4, in the case of multiple vessels of similar design, size, and service, the required examinations may be limited 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 Exams C3.10 2 1 C3.20 76 8 C3.30 20 2 0-1-1 1 3 1 0 0 0 50.00% 0.00% 100.00%10.53% 12.50% 50.00%10.00% 50.00% 100.00%11.22% 18.18% 63.64%100.00%50.00%100.00%63.64%Totals: 98 11 2 2 5 4 5 6 0 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 the multiple vessels shall be selected for examination.

Conservatively, a welded attachment of each type of welded attachment of one of multiple vessels will be examined.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 the component supports selected for examination under IWF-2510 shall be examined.

This requirement is conservatively interpreted to mean that 10% of the total Class 2 welded attachments shall be examined.Section 3.0 Page 6 of 7 (This report is used to verify that the periodic requirements of Tables IWx-2412-1 will be met by BYRON STATION UNIT 2 -3RD INTERVAL ASME SECTION FYAMINATION STATUS REPORT (I (The percentage requirements of Tables IWx-1 2412-1 apply to the Category and were the interval schedule.)

applied to each Item only wnen practical.)

  1. of Total # Exams Completed

% Exams Completed Item No. Comp Selected Min Per I Max Min Per 2 Max Per 3 % Selected Period 1 Period 2 Period 3 Category C-H Non-Deferred Exams C7.10 70 50 N/A 50 N/A N/A 50 N/A 38 71.43% 100.00% 200.00% 276.00%Totals: 70 50 N/A 50 N/A N/A 50 N/A 38 71.43% 100.00% 200.00% 276.00%1. Seventy test components representing the twenty-four systems in Class 2 as reported in the ISI Program Plan.2. Fifty test components not exempted from test requirements by IWA-5110(c).

3. "% Exams Completed" exceeds 100% since the non-exempt Class 2 pressure tests are performed each inspection period.Category F-A Non-Deferred Exams F1.10 467 120 -28 -15 25.70% 29.17% 52.50% 65.00%F1.20 662 111 -44 -15 16.77% 23.42% 63.06% 76.58%F1.30 370 41 -17 -6 11.08% 21.95% 63.41% 78.05%F1.40 75 33 -11 -3 44.00% 21.21% 54.55% 63.64%Totals: 1573 305 49 77 152 76 100 151 39 19.38% 25.25% 58.03% 70.82%1. (Fl.40): Per Examination Category F-A, Note 3, for multiple components other than piping within a system of similar design, function, and service, the supports of only one of the multiple components are required to be examined.Category R-A Non-Deferred Exams (showing Risk-Informed Categories)

Cat. 1 242 61 23 Cat. 2 218 65 72 Cat. 3 0 --Cat. 4 1550 170 78 -Cat. 5 405 41 -Totals: 2415 337 130 224 405 161 20 57 9 32 29 32 25.21%29.82%10.97%10.12%13.95%37.70% 70.49% 85.25%32.58% 58.37% 72.85%56 26.35%30.47%30.09%45.27%58.80%54.62%55.07%72.53%67.20%66 32 199 364 0 1. For the requirements of Risk-Informed (RI-ISI) methodology, the individual categories have minimum selection percentages.

High Risk categories (1, 2 and 3)require 25% of the population be selected.

Medium Risk categories (4 and 5) require 10% of the population be selected.2. The populations include all Break Exclusion Region (BER) welds which have been integrated into the RISI Program and are selected in accordance with the Risk Informed BER methodology.

3. Per -2410 of N-578-1, the examinations of Category R-A shall be completed during each inspection interval in accordance with Table IWB-2412-1.
4. The number of socket weld examinations exceeds the number selected since 100% of the selected socket welds are examined each outage per ASME Code Case N-578-1, Table 1, Note 12. The total number of examinations for the interval is 811 on 337 selected components.

The percentage of completed examinations for each period is determined from the total number of examinations for the interval in Category R-A.Section 3.0 Page 7 of 7 7/25/2013 Exelon.Byron Station Unit 2 B2R17 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 1 of 52)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 National Appurtenance 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) 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 at the top of this form.Computer Generated Form 712512013 Exelkn.Byron Station Unit 2 B2R17 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 2 of 52)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 National Appurtenance 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 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 at the top of this form.Computer Generated Form 7125/2013 Exeln-Byron Station Unit 2 B2R17 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 3 of 52)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 National Appurtenance or Installer Serial No. Province No. Board No.2CS02AB- Pacific Scientific 3517 NA NA 10/2CS03B022S 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 at the top of this form.Computer Generated Form 712512013 Exe In.Byron Station Unit 2 B2R17 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 4 of 52)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)Component or Manufacturer Manufacturer State or National Appurtenance or Installer Serial No. Province No. Board No.2-CSV-2-1 Hunter Corporation N/A N/A N/A 2-CV-2-10 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 2-CV-2-6 Hunter Corporation N/A N/A N/A J 2-CV-2-8 Hunter Corporation j N/A N N/AN/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) 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 at the top of this form.Computer Generated Form 7/25/2013 Exela n-Byron Station Unit 2 B2R17 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 5 of 52)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 National Appurtenance or Installer Serial No. Province No. Board No.2CV-01-PA/Li Pacific Pumps 49772 NA 204 2CV-01-PA/L2 Pacific Pumps 49772 NA 204 2CV-01-PA/L3 Pacific Pumps 49772 NA 204 2CV-01-PA/L34 Pacific Pumps 49772 NA 204 2CV45B-2/2RY0612PX Hunter Corp. NA NA NA 2CV45B-2/2RY061210X Hunter Corp. NA NA NA 2CVA3B-2/2CV11010X Hunter Corp. NA NA NA 2CVA3B-2/2CV1 5033X Hunter Corp. NA NA NA 2CVA3B-2/2CV1 6024X Hunter Corp. NA NA NA 2CVA3B-2/2CV1 6032X Hunter Corp. NA NA NA 2CVA3B-2/2CV16084X Hunter Corp. NA NA NA 2CVA5AA- Hunter Corp. NA NA NA 2/2CV15018V 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 at the top of this form.Computer Generated Form 7/2512013 Exe1 n .Byron Station Unit 2 B2R17 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 6 of 52)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)Component or Manufacturer Manufacturer State or National Appurtenance or Installer Serial No. Province No. Board No.2CVA5AA- Hunter Corp. NA NA NA 2/2CV1 5021 X 2CVA6AA- Hunter Corp. NA NA NA 2/2CV09025XII 2CVA6AA- Hunter Corp. NA NA NA 2/2CV25025X I I I 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 at the top of this form.Computer Generated Form 7125/2013 Exeb n.-Byron Station Unit 2 B2R17 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 7 of 52)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 National Appurtenance 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 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 at the top of this form.Computer Generated Form 7125/2013 Exel en.Byron Station Unit 2 B2R17 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 8 of 52)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)Component or Manufacturer Manufacturer State or National Appurtenance or Installer or Installer Province No. Board No.Serial No.2CVA7AA-2/W-08 Hunter Corp. 2-CV-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) 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 at the top of this form.Computer Generated Form 7/25/2013 Exel in Byron Station Unit 2 B2R17 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 9 of 52)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)Component or Manufacturer Manufacturer State or National Appurtenance or Installer Serial No. Province No. Board No.2CV1 OB-3/2CV04015S Pacific Scientific NA NA NA 2CV1OCA- Pacific Scientific 17350 NA NA 3/2CV03002S 2CV1OCA- Pacific Scientific 7738 NA NA 3/2CV22002S 2CV1 0DB- Pacific Scientific 2184 NA NA 3/2CV02009S 2CV134EA-Lisega 31200814-006 NA NA 2/2CV34008S 2CV14EB- Pacific Scientific 9869 NA NA 2/2CV36006S 2CV14EC- Lisega 31200814-004 NA NA 2/2CV40007S 2CV1 4ED- Pacific Scientific 20454 NA NA 2/2CV41012S 2CV145E- Lisega 31200814-003 NA NA 3/4/2CV31020S 2CV44AB- Lisega 31200814-009 NA NA 3/4/2CV65009S 2CV45-2/2CV22009S Pacific Scientific 2195 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) 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 at the top of this form.Computer Generated Form 7/2512013 Exe. n..Byron Station Unit 2 B2R17 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 10 of 52)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)Component or Manufacturer Manufacturer State or National Appurtenance or Installer Serial No. Province No. Board No.2CVA5AA- Pacific Scientific 4462 NA NA 2/2CV1 5054S 2CVA7AA- Pacific Scientific 20711 NA NA 2/2CV25016S P S 1 N 2CVB7A-3/2CV06004S I Pacific Scientific 1 16680 1 NA I 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) 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 at the top of this form.Computer Generated Form 712512013 Exe.ltn.-Byron Station Unit 2 B2R17 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 11 of 52)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)Component or Manufacturer Manufacturer State or National Appurtenance 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) 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 at the top of this form.Computer Generated Form 7/2512013 Exekrnw Byron Station Unit 2 B2R17 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 12 of 52)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:

Feedwater System (FW)Component or Manufacturer Manufacturer State or National Appurtenance or Installer or Installer Province No. Board No.Serial 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) 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 at the top of this form.Computer Generated Form 7/2512013 Exel n.Byron Station Unit 2 B2R17 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 13 of 52)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:

Feedwater System (FW)Component or Manufacturer Manufacturer State or National Appurtenance or Installer Serial No. Province No. Board No.2FW03DA- Hunter Corp. NA NA NA 16/2FW02009X 2FW87CA- Hunter Corp. NA NA NA 6/2FW06011X X I I 2FW87CA- Hunter Corp. NA NA NA 6/2FW06015X I 2FW87CD- Hunter Corp. NA NA NA 6/2FW09002CI 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 at the top of this form.Computer Generated Form 7/2512013 E xeIon.Byron Station Unit 2 B2R17 ISl Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 14 of 52)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 National Appurtenance or Installer Serial No. Province No. Board No.2FW03DB-16/C18 Hunter Corp. 2-FW-1-N5 NA NA 2FW03DB-16/C19 Hunter Corp. 2-FW-1-N5 NA NA 2FW03DC-16/C21 Hunter Corp. 2-FW-1-N5 NA NA 2FW03DC-16/C22 Hunter Corp. 2-FW-1-N5 NA NA 2FW87CA-6/C05 Hunter Corp. 2-FW-1-N5 NA NA 2FW87CA-6/C06 Hunter Corp. 2-FW-1-N5 NA NA 2FW87CA-6/C07 Hunter Corp. 2-FW-1-N5 NA NA 2FW87CA-6/C08 Hunter Corp. 2-FW-1-N5 NA NA 2FW87CA-6/C09 Hunter Corp. 2-FW-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) 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 at the top of this form.Computer Generated Form 712512013 Exel n.Byron Station Unit 2 B2R17 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 15 of 52)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 National Appurtenance or Installer Serial No. Province No. Board No.2FW03DA- Pacific Scientific 2565 NA NA 16/2FW02012S 2FW87CA- Pacific Scientific 2865 NA NA 6/2FW06013S IIII 2FW87CB- Pacific Scientific 25717 NA NA 6/2FW07004-S1 2FW87CB- Pacific Scientific 20690 NA NA 6/2FW07004-$2 2FW87CB- Pacific Scientific 18342 NA NA 6/2FW07005S 2FW87CB- Pacific Scientific 8202 NA NA 6/2FW07006S 2FW87CB- Pacific Scientific 5939 NA NA 6/2FW07014S 2FW87CB- Pacific Scientific 2821 NA NA 6/2FW07019S 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 at the top of this form.Computer Generated Form 7/2512013 Exel n.Byron Station Unit 2 B2R17 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 16 of 52)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 National Appurtenance or Installer or Installer Province No. Board No.Serial 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) 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 at the top of this form.Computer Generated Form 7/25/2013 Exek n-Byron Station Unit 2 B2R17 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 17 of 52)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)Manufacturer Component or Manufacturer Mansturer State or National Appurtenance or Installer or Installer Province No. Board No.Serial No.2MS07AD- Hunter Corp. NA NA NA 28/2MS01 211 R 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 at the top of this form.Computer Generated Form 712512013 Exelkn.Byron Station Unit 2 B2R17 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 18 of 52)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 National Appurtenance or Installer or Installer Province No. Board No.Serial No.2MS01AA- Pacific Scientific 4976 NA NA 30.25/2MS05007-S1 2MS01AA- Pacific Scientific 1543 NA NA 30.25/2MS05007-$2I 2MS07AD- Pacific Scientific 12977 NA NA 28/2MS01088S 1 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) 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 at the top of this form.Computer Generated Form 712512013 E...-xe1rn.

Byron Station Unit 2 B2R17 ISl Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 19 of 52)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 National Appurtenance or Installer Serial No. Province No. Board 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) 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 at the top of this form.Computer Generated Form 712512013 Exel n.Byron Station Unit 2 B2R17 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 20 of 52)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:

Primary Containment (PC)Component or Manufacturer Manufacturer State or National Appurtenance or Installer or Installer Province No. Board No.Serial No.2-PC-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) 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 at the top of this form.Computer Generated Form 7/25/2013 Byron Station Unit 2 B2R17 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 21 of 52)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 Manufacturer State or National Appurtenance 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) 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 at the top of this form.Computer Generated Form 7/25/2013 Exelon.Byron Station Unit 2 B2R17 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 22 of 52)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 National Appurtenance or Installer Serial No. Province No. Board No.2-RC-1-1 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) 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 at the top of this form.Computer Generated Form 7/25/2013 Sxek nt Byron Station Unit 2 B2R17 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 23 of 52)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 National Appurtenance or Installer or Installer Province No. Board No.Serial No.2RC-01 -R/S Hunter Corp. NA NA NA 2RC16AA- Hunter Corp. NA NA NA 2/2CV1 2005X 2RC24AA- Hunter Corp. NA NA NA 4/2RY06016X 2RC24AA- Hunter Corp. NA NA NA 4/2RY06035X I _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 at the top of this form.Computer Generated Form 7/25/2013 Exeikn.Byron Station Unit 2 B2R17 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 24 of 52)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 National Appurtenance or Installer or Installer Province No. Board No.Serial No.2RC01AA-29/JO1 Hunter Corp. 2-RC-1 -N5 NA NA 2RC01AA-29/J06 Hunter Corp. 2-RC-1-N5 NA NA 2RC01AB-29/JO1 Hunter Corp. 2-RC-1-N5 NA NA 2RC01AC-29/JO1 Hunter Corp. 2-RC-1-N5 NA NA 2RC01AD-29/JO1 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-B F1 Westinghouse Corp. 640-0012-51 B-09062 N-200 2RC-01-R/RPVS-C 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-G F1 Westinghouse Corp. 640-0012-51 B-09062 N-200 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 at the top of this form.Computer Generated Form 7/25/2013 Exeion.Byron Station Unit 2 B2R17 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 25 of 52)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 National Appurtenance or Installer Serial No. Province No. Board No.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 2RC03AA-27.5/J12 Hunter Corp. 2-RC-1 -N5 NA NA 2RC03AB-27.5/J12 Hunter Corp. 2-RC-1 -N5 NA NA 2RC03AC-27.5/J13 Hunter Corp. 2-RC-1-N5 NA NA 2RC03AD-27.5/J12 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 2RC13AA-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) 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 at the top of this form.Computer Generated Form 7/2512013 Exel n.Byron Station Unit 2 B2R17 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 26 of 52)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 National Appurtenance or Installer Serial No. Province No. Board No.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 2RC14AA-2/W-06 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) 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 at the top of this form.Computer Generated Form 7/2512013 Exelon-Byron Station Unit 2 B2R17 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 27 of 52)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 National Appurtenance or Installer Serial No. Province No. Board No.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 2RC1 4AA-2/W-1 1 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 2RC16AB-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) 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 at the top of this form.Computer Generated Form 712512013 Exek n-Byron Station Unit 2 B2R17 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 28 of 52)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 National Appurtenance or Installer Serial No. Province No. Board No.2RC16AC-2/W-08 Hunter Corp. 2-RC-1-N5 NA NA I Hr 2RC16AD-2/J-01 Hunter Corp. 2-RC-1-N5 NA NA 2RC21 AA-8/J05 Hunter Corp. 2-RC-1-N5 NA NA 2RC21AA-8/J06 Hunter Corp. 2-RC-1-N5 NA NA 2RC21AB-8/J07 Hunter Corp. 2-RC-1-N5 NA NA 2RC21AB-8/J08 Hunter Corp. 2-RC-1-N5 NA NA 2RC21AB-8/J09 Hunter Corp. 2-RC-1-N5 NA NA 2RC21AB-8/J10 Hunter Corp. 2-RC-1-N5 NA NA 2RC22AA-1.5/W-05 Hunter Corp. 2-RC-1-N5 NA NA 2RC22AA-1.5/W-0 Hunter Corp. 2-RC-1-N5 NA NA 2RC22AC-1.5/W-01 Hunter Corp. 2-RC-1-N5 NA NA I2RC22AC-1

.5/W-06 Hunter Corp. J 2-RC-1 -N5 J NA NA J 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 at the top of this form.Computer Generated Form 7/25/2013 Exeh n.Byron Station Unit 2 B2R17 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 29 of 52)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 National Appurtenance or Installer or Installer Province No. Board No.Serial No.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 2RC24AA-4/J06 Hunter Corp. 2-RC-1-N5 NA NA 2RC24AA-4/J07 Hunter Corp. 2-RC-1-N5 NA NA 2RC24AA-4/J09 Hunter Corp. 2-RC-1-N5 NA NA 2RC24AA-4/J10 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 2RC30AA-1.5/W-01.01 CBI 2-RC-1-N5 NA NA 2RC30AA-1.5/W-01.01 CBI 2-RC-1-N5 NA NA 2RC30AB-1.5/W-01.01 CBI 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) 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 at the top of this form.Computer Generated Form 1 1 7/25/2013 Exelkn-Byron Station Unit 2 B2R17 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 30 of 52)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 National Appurtenance or Installer or Installer Province No. Board No.Serial No.2RC30AC-1.5/W-01

.01 CBI 2-RC-1 -N5 NA NA 2RC30AD-1.5/W-01.01 CBI 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) 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 at the top of this form.Computer Generated Form 7/25/2013 Exek n-Byron Station Unit 2 B2R17 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 31 of 52)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 National Appurtenance or Installer Serial No. Province No. Board No.2RC01 BA- Boeing 27 NA NA 2A/2RC01 BA-A 2RC01 BA- Boeing 35 NA NA 2A/2RC01 BA-B3II 2RC01 BB- Boeing 9 NA NA 2B/2RC01 BB-A 2RC01 BB- Boeing 15 NA NA 2B/2RC01 BB-B 2RC01BC- Boeing 19 NA NA 2C/2RC01 BC-A I I 2RC01 BC- Boeing 7 NA NA 2C/2RC01 BC-B 2RC01BD- Boeing 5 NA NA 2D/2RC01 BD-A 2RC01 BD- Boeing 31 NA NA 2D/2RC01 BD-B 2RC13AC- Pacific Scientific 5656 NA NA 2/2CV1 5045S 2RC14AC- Pacific Scientific 7173 NA NA 2/2CV09034S 2RC16AA- Pacific Scientific 4427 NA NA 2/2CV1 2006S 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 at the top of this form.Computer Generated Form 7/25/2013 Exe..n.Byron Station Unit 2 B2R17 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 32 of 52)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 National Appurtenance or Installer Serial No. Province No. Board No.2RC16AB- Pacific Scientific 2495 NA NA 2/2CV24003S 2RC20AC- Lisega 04616353-015 NA NA 3/4/2 RC 18009SIII 2RC22AC- Pacific Scientific 9646 NA NA 1.5/2RC 18007SI 2RC22AC- Pacific Scientific 17003 NA NA 1.5/2RC18014SI 2RC48BA- Pacific Scientific 4100 NA NA 1/2/2RC90A001 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) 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 at the top of this form.Computer Generated Form 712512013 Exei n.Byron Station Unit 2 B2R17 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 33 of 52)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 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 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 at the top of this form.Computer Generated Form 7/25/2013 Exelon-Byron Station Unit 2 B2R17 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 34 of 52)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 National Appurtenance or Installer Serial No. Province No. Board No.2RH01AA- Hunter Corp. NA NA NA 12/2RH02053X 2RH-01-PA/L1 Ingersoll Rand 127430 NA 161 2RH-01 -PA/L2 Ingersoll Rand 127430 NA 161 2RH-01 -PA/L3 Ingersoll Rand 127430 NA 161 2RH-02-AB/L1 Joseph Oat Corp. 2267-1 D U-201440 839 2RH-02-AB/SKT Joseph Oat Corp. 2267-1 D U-201440 839 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 at the top of this form.Computer Generated Form 7125/2013 Exe n..Byron Station Unit 2 B2R17 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 35 of 52)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 National Appurtenance or Installer or Installer Province No. Board No.Serial No.___ ____2RH01AA- Pacific Scientific 4620 NA NA 12/2RH02068S 2RH01AB- Pacific Scientific 2793 NA NA 12/2RH02003S IIII 2RH01 AB- Pacific Scientific 3081 NA NA 12/2RH02013S 2RH26AB- Lisega 31200814-008 NA NA 3/4/2RH02115S 2RH26AB- Pacific Scientific 9623 NA NA 3/4/2RH02116S I I I 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 at the top of this form.Computer Generated Form 7/25/2013 Byron Station Unit 2 B2R17 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 36 of 52)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 National Appurtenance or Installer Serialler Province No. Board No.2RC-01-R/CORE Westinghouse Corp. 640-0012-52 B-09062 N-200 SUPP STRUCT 2RC-01-R/INT Westinghouse Corp. 640-0012-51 B-09062 N-200 ATTACH NONBELT I I I I 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-200 PEN 2RC-01 -R/RPV HEAD Westinghouse Corp. 640-0012-52 B-09062 N-200 SURF W C 2RC-01-R/RPV Westinghouse Corp. 640-0012-51 B-09062 N-200 INTERIORI 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 at the top of this form.Computer Generated Form 712512013 Exe. n.Byron Station Unit 2 B2R17 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 37 of 52)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 National Appurtenance or Installer or Installer Province No. Board No.Serial No.2RYO3BA-6/FLG 1-12 Hunter Corp. 2-RC-1 -N5 NA NA 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) 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 at the top of this form.Computer Generated Form 7/2512013 Exei n~.Byron Station Unit 2 B2R17 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 38 of 52)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 National Appurtenance or Installer or Installer Province No. Board No.Serial No.2RY01 B-6/2RY06022X Hunter Corp. NA NA NA 2RY01 B-6/2RY06029X Hunter Corp. NA NA NA 2RY18A-2/2RY06115V Hunter Corp. NA 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) 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 at the top of this form.Computer Generated Form 7/2512013 Exelknt Byron Station Unit 2 B2R17 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 39 of 52)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 National Appurtenance or Installer or Installer Province No. Board No.Serial No.2RY18A-2/W-01 Hunter Corp. 2-RC-1-N5 NA NA_2RY18A-2/W-02 Hunter Corp. 2-RC-1-N5 NA NA 2RY18A-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) 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 at the top of this form.Computer Generated Form 7/2512013 Exel n-Byron Station Unit 2 B2R17 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 40 of 52)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 National Appurtenance or Installer Serial No. Province No. Board No.2RY02B-3/2RY09067-Pacific Scientific 16687 NA NA$1 2RY02B-3/2RY09067-Pacific Scientific 5512 NA NA S2I 2RY02B-3/2RY091 0OS Pacific Scientific 9295 NA NA 2RY06A-3/2RY09012S Pacific Scientific 10201 NA NA 2RY06A-3/2RY09060-Pacific Scientific 7345 NA NA 2RY06A-3/2RY09060-Pacific Scientific 4637 NA NA S2I 2RY06A-3/2RY09078S Pacific Scientific 7731 NA NA 2RY06A-3/2RY091 01S Pacific Scientific 18784 NA NA 2RY07AC- Pacific Scientific 2440 NA NA 3/4/2RY27016S 2RY11A- Pacific Scientific 12031 NA NA 14/2RY0501 OS I 2RY34CD- Pacific Scientific 2627 NA NA 1/2/2RC91 001QS I 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 at the top of this form.Computer Generated Form 7/25/2013 Exekenm Byron Station Unit 2 B2R17 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 41 of 52)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 Blowdown System (SD)Component or Manufacturer Manufacturer State or National Appurtenance or Installer Serial No. Province No. Board No.2SDO1 CA- Pacific Scientific 12404 NA NA 2/2SD21034S 2SD01CD- Pacific Scientific 2SD24026S NA NA 2/2SD24026S I I I I 2SD01 CF- Lisega 2SD05002-S1 NA NA 2/2SD05002-$1 1 2SD01 CF- Lisega 2SD05002-S2 NA NA 2/2SD05002-S2 I 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 at the top of this form.Computer Generated Form 7/2512013 Exel n.Byron Station Unit 2 B2R17 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 42 of 52)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)Component or Manufacturer Manufacturer State or National Appurtenance or Installer Serial No. Province No. Board No.2RC-01 -BA/DRAIN Westinghouse Corp. 2095 U-201435 15 2RC-01-BA/SGC-08 Westinghouse Corp. 2095 U-201435 15 2RC-01-BB/DRAIN Westinghouse Corp. 2096 U-201436 16 2RC-01 -BB/SGC-05 Westinghouse Corp. 2096 U-201436 16 2RC-01 -BB/SGN-03 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) 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 at the top of this form.Computer Generated Form 7/25/2013 Exektn.Byron Station Unit 2 B2R17 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 43 of 52)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 National Appurtenance or Installer or Installer Province No. Board No.Serial 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 S 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) 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 at the top of this form.Computer Generated Form 7/25/2013 Exeilon.Byron Station Unit 2 B2R17 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 44 of 52)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 National Appurtenance or Installer or Installer Province No. Board No.Serial No.2SI05CA-8/2SI01022X Hunter Corp. NA NA NA 2SI05CA-8/2SI01026X Hunter Corp. NA NA NA 2SI05CA-8/2SI01038X Hunter Corp. NA NA NA 2SI05CA-8/2SI103021 X Hunter Corp. NA NA NA 2SI05CA-8/2SI03025V Hunter Corp. NA NA NA 2SI05CA-8/2SI03029X Hunter Corp. NA NA NA 2SI05DA-6/2SI01017X Hunter Corp. NA NA NA 2SI05DA-6/2SI101029X Hunter Corp. NA NA NA 2SI05DA-6/2SI01031 X Hunter Corp. NA NA NA 2SI05DA-6/2SI01032X Hunter Corp. NA NA NA 2SI05DA-6/2SI10 032X Hunter Corp. NA NA NA 2SI08FA-3/2SI2301 1X Hunter Corp. NA 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) 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 at the top of this form.Computer Generated Form 7/25/2013 Exelon-Byron Station Unit 2 B2R17 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 45 of 52)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 National Appurtenance or Installer Serial No. Province No. Board No.2SI08FA-3/2SI23012A Hunter Corp. NA NA NA 2SI08GB Hunter Corp. NA NA NA 1/2/2SI25004X 2SI08GB Hunter Corp. NA NA NA 1/2/2SI25007X 2SI08JA Hunter Corp. NA NA NA 1/2/2SI24012X 2SI08JA Hunter Corp. NA NA NA 1/2/2S125010OX 2SI08JA Hunter Corp. NA NA NA 1B2//2SI25012X 2SIA4B-8/2RH02083X Hunter Corp. NA 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) 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 at the top of this form.Computer Generated Form 7/25/2013 Exekrn.Byron Station Unit 2 B2R17 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 46 of 52)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 National Appurtenance or Installer Serialler Province No. Board No.2SI03DA-2/W-01.01 Exelon Corp. 2-SI-1 -N5 NA NA 2SI03DA-2/W-02.01 CBI 2-SI-1 -N5 NA NA 2SI03DA-2/W-03.01 CBI 2-S1-1-N5 NA NA 2SI08HA-2/W-01 Hunter Corp. 2-SI-1-N5 NA NA 2SI08HA-2/W-02 Hunter Corp. 2-SI-1-N5 NA NA 2SI08HA-2/W-03 Hunter Corp. 2-SI-1 -N5 NA NA 2SI08HA-2/W-04 Hunter Corp. 2-SI-1 -N5 NA NA 2SI08HA-2/W-05 Hunter Corp. 2-SI-1-N5 j 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-SI-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) 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 at the top of this form.Computer Generated Form 1 1 i 7/25/2013 Exekrn.Byron Station Unit 2 B2R17 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 47 of 52)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 National Appurtenance or Installer or Installer Province No. Board No.Serial No.2SI08JA-1.5/W-04 Hunter Corp. 2-SI-1 -N5 NA NA 2SI08JA-1.5/W-05 Hunter Corp. 2-S1-1-N5 NA NA 2SI08JA-1.5/W-05A Hunter Corp. 2-SI-1 -N5 NA NA 2SI08JA-1.5/W-05B Hunter Corp. 2-SI-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-S1-1-N5 NA NA 2SI08JA-1.5/W-10 Hunter Corp. 2-S1-1-N5 NA NA 2SI08JA-1.5/W-11 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-15 Hunter Corp. 2-SI-1-N5 NA NA 2SI08JA-1.5/W-35.01 CBI 2-SI-1 -N5 NA NA 2SI08JA-1.5/W-36.01 CBI 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) 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 at the top of this form.Computer Generated Form 7/25/2013 Exel n-Byron Station Unit 2 B2R17 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 48 of 52)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 National Appurtenance or Installer or Installer Province No. Board No.Serial No.2SI08JA-1.5/W-37.01 CBI 2-SI-1-N5 NA NA 2SI08J B-1.5/W-38.01 CBI 2-SI-1-N5

~NA NA 2SI08JB-1.5/W-39.01 CBI 2-SI-1-N5 NA NA 2I0J-./-90CB 2-SI-i -N5NAA 2SI08JC- 1.5/W-39.01 CBI 2-S1-1 -N5 NA NA 2SI08JC-1.5/W-40.01 CBI 2-SI-1 -N5 NA NA 2SI08JC-1.5/W-41.01 CBI 2-SI-1-N5 NA NA 2SI08JD-1.5/W-38.01 CBI 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) 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 at the top of this form.Computer Generated Form 7/25/2013 Exel n.~Byron Station Unit 2 B2R17 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 49 of 52)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 National Appurtenance or Installer Serialler Province NoN Board No.2SI04D-8/2RH02061 S Pacific Scientific 16726 NA NA 2SI05CA-8/2SI01 023S Pacific Scientific 2545 NA NA 2SI05DD-6/2SI03009S Pacific Scientific 2553 NA NA 2SI05DD-6/2SI03018S Pacific Scientific 27115 NA NA 2SI08JD- Lisega 31200814-005 NA NA 1.5/2SI22018S 2SI08JD- Pacific Scientific 8050 NA NA 1.5/2SI22020S 2SI09BC-10/2SI09002-Pacific Scientific 25441 NA NA 2SI09BC-10/2S109002-Pacific Scientific 9347 NA NA S2 2SI09BD- Pacific Scientific 4808 NA NA 10/2SI03001 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) 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 at the top of this form.Computer Generated Form 7/25/2013 Exekin-Byron Station Unit 2 B2R17 ISl Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 50 of 52)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 National Appurtenance or Installer Serial No. Province No. Board 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) 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 at the top of this form.Computer Generated Form 7/25/2013 Exel n.Byron Station Unit 2 B2R17 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 51 of 52)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 National Appurtenance or Installer or Installer Province No. Board No.Serial No.2SX06BB-16/2PC-7A Hunter Corp. NA NA NA 2SX06BB- Hunter Corp. NA NA NA 16/2SX07001 G I I 2SX06CB- Hunter Corp. NA NA NA 14/2SX07007X 2SX07BD- Hunter Corp. NA NA NA 10/2SX09078X I I 2SX07CB- Hunter Corp. NA NA NA 10/2SX09038X 2SX07CD- Hunter Corp. NA NA NA 10/2SX09077X 2SX07EB- Hunter Corp. NA NA NA 14/2SX0901 1X 2SX08BD- Hunter Corp. NA NA NA 10/2SX07025X 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 at the top of this form.Computer Generated Form 7/25/2013 Exele-n Byron Station Unit 2 B2R17 ISl Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 52 of 52)(BACK)8. Examination Dates: 10/10/11 to 5/1/13 9. Inspection Period Identification:

Third Inspection Period 10. Inspection Interval Identification:

Third Inspection Interval 11. Applicable Edition of Section Xl: 2001 Addenda 2003 12. Date / Revision of Inspection Plan: 6/10/12 / 7 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 the Inspection Plan as required by the ASME Code,Section XI, and c) corrective measures taken conform to the rules of the ASME Code,Section XI.Certificate of Authorization No. (if applicable):

N/A Expiration Date: N/A Date: 'Z/2-/13 Signed for:Exelon Generation Company 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 inspected the components described in this Owner's Report during the period lo/1i/11 to 5, and state that to the best of my knowledge and belief, the Owner has performed examinations and tests and taken corrective measures described in this Owner's Report in accordance with the 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 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.

Inspectors Signature Cor mmissions:

A 9 4/t/2, rd Date: 20 13 National Board, State, Province, and Endorsements Computer Generated Form DOCUMENT NO.: 5A REV. NO.: 0 FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI 1 Owner Exelon Nuclear Date 4-27-13 Name 4300 Winfield Road, Warrenville, IL Sheet 1 of 1 Address 2. Plant Byron Nuclear Power Station Unit 2 Name 4450 N. German Church Road, Byron, IL Work Order No. 99147049-01 Address Repair Organization, P.O. No., Job No., etc.3. Work Performed by Byron Mechanical Type Code Symbol Stamp Not Applicable Maintenance Name Authorization No. Not Applicable 4450 N. German Church Road, Byron, IL Expiration Date Not Applicable Address 4. Identification of System FW -Feedwater 5. (a) Applicable Construction Code ASME Section III 19 74 Edition, W/75 Addenda, N/A Code Case (b) Applicable Edition of Section XI Used for Repair/Replacement Activity:

2001 Edition/2003 Addenda (c) Section Xl Code Case(s) N/A 6. Identification of Components ASME Corrected, Code National Removed, or Stamped Name of Name of Manufacturer Board Other Year Installed (Yes or No)Component Manufacturer Serial No. No. Identification Built Valve Bonnet Borg. Warner Valve S/N: N/A ETN: 2FW009C 1979 Corrected Yes 35601 7. Description of Work Machined valve bonnet seat ring surface 8. Test Conducted:

Hydrostatic E]Pneumatic E]Nominal Operating Pressure El Exempt [OF Other E] 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 number of sheets is recorded at the top of this form.

FORM NIS-2 (Back)9. Remarks WO 99147049-01 Applicable 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 '7-Z6, ,20 13 ( or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Illinois and employed by HSB CT of .Hartford, CT have)nsp cted the components described in this Owner's Report during the period to ,and state that to the best of my knowledge and belief, tKe dwner has perforrli'ed e-aminations and taken corrective measures described in this Owners 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 dfma e or a loss of any kind arising from or connected with this inspection.

Commissions fi" /2 ,V/ f A5 Inspector's Signature Date: " ,20 13 National Board, State Province, and Endorsements DOCUMENT) RH 04/20/13 1. Owner E: NO.: 3.1 REV. NO.: 0 FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section Xl xelon Nuclear Date 4/20/13 2.Name 4300 Winfield Road, Warrenville, IL Address Plant Byron Nuclear Power Station Name 4450 N. German Church Road, Byron, IL Address Sheet 1 of 1 Unit 02 Work Order No. 00543260-01 Repair Organization, P.O. No., Job No., etc.3. Work Performed by CB&VStone

& Webster Name 36400 S. Essex Road, Wilmington, IL 60481 Address Type Code Symbol Stamp Not Applicable Authorization No. Not Applicable Expiration Date Not Applicable

4. Identification of System MS (MAIN STEAM)5. (a) Applicable Construction Code ASME Section III 19 74 Edition, N/A Addenda, (b) Applicable Edition of Section Xl Used for Repair/Replacement Activity 2001 Editi (c) Section Xl Code Case(s) NONE 6. Identification of Components N/A Code Case on / 2003 Addenda ASME Corrected, Code National Removed, or Stamped Name of Name of Manufacturer Board Other Year Installed (Yes or No)Component Manufacturer Serial No. No. Identification Built SAFETY VALVE, 6", DRESSER BU01489 N/A 2MS016A 1500# INDUSTRIES 1989 Removed YES SAFETY VALVE, 6", DRESSER BU490 N/A 2MS016A1978 Installed YES 1500# INDUSTRIES Cat ID 1439914-1 ROD,THREADED Texas Bolt MK# LR49 N/A 2M016A1981 Removed No 1-3/8-8 Gr. B7 Bolt# 2 & 6 ROD,THREADED Nova Machine Ht. No.: 2MS016A 1-3/8-8 Gr. B7 Products NF12200854 Cat ID 37106-1 NUT, HEAVY HEX Texas Bolt MK# LR50 N/A 2MS016A 1-3/8-8 Texas Bolt MK# LR50 N/A Bolt# 2 & 6 1981 Removed No NUT, HEAVY HEX Nova Machine Ht. No.: N/A 2MS016A 1-3/8-8 Products 3W50 Cat ID 1394991-1 7. Description of Work REPLACE RELIEF VALVE 2MS016A -REPLACED 2 STUDS & 4 NUTS 8. Test Conducted:

Hydrostatic

[] Pn Other El Pressure eumatic El Nominal Operating Pressure Z Exempt E1 1060 psi Test Temp. 556 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 number of sheets is recorded at the top of this form.

FORM NIS-2 (Back)9. Remarks 00543260-01 Applicable Manufacturers Data Heports 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 o ,uthorization No. Not Applicable Signed fAj A A-" A Date :5 20 13 Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Illinois and employed by HSB CT of Har ford, CT have inpectd the components described in this Owner's Report during the periodto " ,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 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 damage0 loss of any kind arising from or connected with t'is inspection.

Q~#~6fCommissions 101el1 lzaellfllz6e Date: Inspector's Signature* 1/3 ,20 13 National Board, State Province, and Endorsements (Final))

I DOCUMENT NO.: 3.1 REV. NO.: 0 1 FORM NIS-2 OWNER'S REPORT FOR REPAIRIREPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI 1. Owner Exelon Nuclear Date 4/20/13 2.Name 4300 Winfield Road, Warrenville, IL Address Plant Byron Nuclear Power Station Name 4450 N. German Church Road, Byron, IL Address Sheet 1 of Unit 02 Work Order No. 00543261-01 Repair Organization, P.O. No., Job No., etc.1 3. Work Performed by CB&MStone

& Webster Name 36400 S. Essex Road, Wilmington, IL 60481 Address Type Code Symbol Stamp Not Ap Authorization No. Not Applicable Expiration Date Not Applicable plicable 4. Identification of System MS (MAIN STEAM)5. (a) Applicable Construction Code ASME Section III 19 74 Edition, N/A Addenda, N/A 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 Name of Component Name of Manufacturer Manufacturer Serial No.National Board No.Corrected, Removed, or Installed ASME Code Stamped (Yes or No)Other Identification Year Built I I SAFETY VALVE, 6", 1500#DRESSER INDUSTRIES 2MS013A BU01477 N/A 1978 Removed YES SAFETY VALVE, 6", DRESSER BRO9593 N/A 2MS01 3A 1977 Installed YES 1500# INDUSTRIES Cat ID 1443930-1 7. Description of Work-REPLACE RELIEF VALVE 2MS01 3A 8. Test Conducted:

Hydrostatic

[I Pn Other C] Pressure eumatic 11 1060 Nominal Operating Pressure Z Ex psi Test Temp. 556 empt El 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 number of sheets is recorded at the top of this form.

FORM NIS-2 (Back)9. Remarks 00543261-01 Applicable Manufacturer's 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 o,,.Authorization No. Not Applicable Signed (UA ( A.. 1 , ,Il/7,A)A-'-/z-Date 5" T ,20 13 Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Illinois and employed by HSB CT of H ard, CT have epsp/ected the components described in this Owner's Report during the period to " ,and state that to the best of my knowledge and belief, )the Oner has performed'-

examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective 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 danage or a loss of any kind arising from or connected with this inspec ion.94.A,- -Commissions

,,,, 6e Inspector's Signature National Board, State Province, and Endorsements Date: _ý./ 4.1,4..' .20 13 (Final)-)

DOCUMENT NO.: 3.1 REV. NO.: 0-7 FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI 1. Owner Exelon Nuclear Date 4/20/13 Name 4300 Winfield Road, Warrenville, IL Sheet 1 of 1 Address 2. Plant Byron Nuclear Power Station Unit 02 Name 4450 N. German Church Road, Byron, IL Work Order No. 00634678-01 Address Repair Organization, P.O. No., Job No., etc.3. Work Performed by CB&l/Stone

& Webster Type Code Symbol Stamp Not Applicable Name Authorization No. Not Applicable 36400 S. Essex Road, Wilmington, IL 60481 Expiration Date Not Applicable Address 4. Identification of System MS (MAIN STEAM)5. (a) Applicable Construction Code ASME Section 1l1 19 74_4 Edition, na Addenda, N/A 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 ASME Corrected, Code National Removed, or Stamped Name of Name of Manufacturer Board Other Year Installed (Yes or No)Component Manufacturer Serial No. No. Identification Built SAFETY VALVE, 6", DRESSER 2MS014D 150 NUTIS BU01484 N/A 2S4D1978 Removed YES 1500# INDUSTRIES SAFETY VALVE, 6", DRESSER 2MS014D 1500#BR09597 N/A 1977 Installed YES 1500#INDUSRIESCat ID 1439909-1 7. Description of Work-REPLACED RELIEF VALVE 2MS01 4D 8. Test Conducted:

Hydrostatic El Pn Other El Pressure eumatic E] Nora 1075 psi inal Operating Pressure 0 Exempt 11 Test Temp. 556 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 number of sheets is recorded at the top of this form.

FORM NIS-2 (Back)9. Remarks 00634678-01 ApplicaDle Manutacturer's Uata Heports 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 Xl.Type Code Symbol Stamp Not Applicable Certificate of uthorization No. Not Applicable Signed CAo,,w/ LA, A 49d d1/AJArc),,.___

Date T- /15 , 20 13 Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Illinois and employed by HSB CT of a ord, CT have nsected the components described in this Owner's Report during the period N, VA -to '1, and state that to the best of my knowledge and belief, t&~e wner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective 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 ()V -Inspector's Signature Date: A *National Board, State Province, and Endorsements

,20 13 (Final)N1 DOCUMENT NO.: 5.2 REV. NO.: 0 FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section Xl 1. Owner Exelon Nuclear Date 4-15-13 Name 4300 Winfield Road, Warrenville, IL Sheet 1 of 2 Address 2. Plant Byron Nuclear Power Station Unit 02 Name 4450 N. German Church Road, Byron, IL Work Order No. 01025526-03/12 Address Repair Organization, P.O. No., Job No., etc.3. Work Performed by Shaw/Stone

& Webster Type Code Symbol Stamp Not Applicable Byron Mechanical Maintenance Name Authorization No. Not Applicable 36400 S. Essex Road, Wilmington, IL 60481 Expiration Date Not Applicable 4450 N. German Church Rd. Byron IL 61010 Address 4. Identification of System SI -Safety Injection 5. (a) Applicable Construction Code ASME Sect III Piping 19 74 Edition, S75 Addenda, N/A Code Case (a) Applicable Construction Code ASME Sect III Valve 19 71 Edition, W72 Addenda, N/A 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 ASME Corrected, Code National Removed, or Stamped Name of Name of Manufacturer Board Other Year Installed (Yes or No)Component Manufacturer Serial No. No. Identification Built 2" CE Kerotest S/N: PS3-1 14,425 2SI8905B 1977 Removed Yes CHECK VALVE 2" 2SI8905B CHECK VALVE Kerotest S/N: 43BTB N/A CID:32726 2011 Installed Yes UTC# 0002903431 2"SCH. 160 Sandvik HT#: 462460 N/A 2SI03DA-2" 1977 Removed No PIPE () 2" SCH. 160 Consolidated 2SI03DA-2" PIPE PowerSupply HT# 505112 N/A CID:1449121 2011 Installed No PIPE__PowerSupplyUTC#

0002883505 2" 90 DEG. 6000# Alloy Stainless MK#: PI N/A 2SI03DA-2" 1977 Removed No ELBOW Co.2" 90 DEG. 6000# Consolidated HT# 44100 N/A 2SI03DA-2" 2010 Installed No ELBOW Power Supply CID:39072 2"SCH. 160 Sandvik HT#: 462460 N/A 2SI03CA-2" 1977 Removed No PIPE 2" SCH. 160 Consolidated 2SI03CA-2" PIPEHT#505112 N/A 2011 Installed No 7. Description of Work Replaced Check Valve, Pipe, Elbow and Flange 8. Test Conducted:

Hydrostatic

[]Pneumatic E]Nominal Operating Pressure Z Exempt El Other [I Pressure 2418 / 852 psi Test Temp. 476 / 84 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 number of sheets is recorded at the top of this form.

FORM NIS-2 (Back)9. Remarks 1025526-03/12 Applicable Manufacturer's Data Reports to be attached (D Welds 2,3 and 6 performed by the Byron Mechanical Maintenance department on task 12 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 Authorizatipn No., Not Applicable Signed _. Date 7-11 20 13-t -nr 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 -aord, CT have ,spted the components described in this Owner's Report during the period to 40/."- o , and state that to the best of my knowledge and belief, t~e, 6 wner has perfornleed 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 dama 2i or a loss of any kind arising from or connected with this inspection.

Commissions

,/ .f' , ///-/ A 6.Inspector's Signature Date: X ; ,20 13 National Board, State Province, and Endorsements FORM NIS-2 SUPPLEMENTAL SHEET 1. Owner Exelon Nuclear Date 4-15-13 2.Name 4300 Winfield Road, Warrenville, IL Address Plant Byron Nuclear Power Station Name 4450 N. German Church Road, Byron, IL Address Sheet 2 of 2 Unit 02 3 Work Order No. 01025526-03/12 Repair Organization, P.O. No., Job No., etc.3. Work Performed by Byron Mechanical Maintenance Type Code Symbol Stamp Not Applicable Name 4450 N. German Church Rd. Byron IL 61010 Address Authorization No.Expiration Date Not Applicable Not Applicable

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 Xl Used for Repair/Replacement Activity 2001 Edition / 2003 Addenda (c) Section Xl Code Case(s) NONE 6. Identification of Components ASME Corrected, Code National Removed, or Stamped Name of Name of Manufacturer Board Other Year Installed (Yes or No)Component Manufacturer Serial No. No. Identification Built ______________

SEAL WELD ON N/A N/A N/A 2S28905B N/A Installed N/A VALVE CAP PowerSuIpl 5615AN1 I I I D 4 I 2". 15000#Hunter Corp.MK#: HK655 N/A 2SI03CA-2" 1977 Removed No , 2". 15000# Consolidated HT# N/A 2S103CA-2" 2012 Installed No SWIRF FLANGE- Power Supply 5615ANE1 _ _____ CID:30443

___w K)(Final)

I DOCUMENT NO.: 4-1 REV. NO.: 0 FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section Xl 1. Owner Exelon Nuclear Date 1-4-13 2.3.Name 4300 Winfield Road, Warrenville, IL Address Plant Byron Nuclear Power Station Name 4450 N. German Church Road, Byron, IL Address Work Performed by Byron Mechanical Maintenance Name 4450 N. German Church Road, Byron, IL Address Sheet 1 of 1 Unit 02 Work Order No. 01324819-01 Repair Organization, P.O. No., Job No., etc.Type Code Symbol Stamp Not Applicable Authorization No.Expiration Date Not Applicable Not Applicable

4. Identification of System RH -RESIDUAL HEAT 5. (a) Applicable Construction Code ASME Section III 19 71 Edition, W/72 Addenda, N-1567 Code Case (b) Applicable Edition of Section XI Used for Repair/Replacement Activity:

2001 Editlonr2003 Addenda (c)Section XI Code Case(s) NONE 6. Identification of Components ASME Corrected, Code National Removed, or Stamped Name of Name of Manufacturer Board Other Year Installed (Yes or No)Component Manufacturer Serial No. No. Identification Built RELIEF VALVE CROSBY N56904 N/A 2RH8708A 1978 REMOVED YES 0049 RELIEF VALVE CROSBY N56904 N/A 2RH8708A RELIEF VALVE CROSB0068 N/A CAT ID 27642-1 1992 INSTALLED YES 7. Description of Work REPLACED RELIEF VALVE (PMV)8. Test Conducted:

Hydrostatic E] Pn Other [I Pressure eumatic [] Nonm 45 psi iinal Operating Pressure Z Exempt 0-Test Temp. Ambient 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 number of sheets is recorded at the top of this form.

FORM NIS-2 (Back)9. Remarks WO#01324819-01 I I I I I I Applicable manufacturers Data ieports to 156 attane J 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 gA2 Date I-I .20 13 Onor 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 H.arrtord,, , CT have inspe/pted 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 performnd el(aminations 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.

Commissions

_,.,z/,/ ,5,/ , 4..AInspector's Signature Date: / 13 National Board. State Province, and Endorsements (Final I DOCUMENTNO.:

3A REV. NO.: 0 FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI 1 .Owner Exelon Nuclear Date 04/15/2013 Name 4300 Winfield Road, Warrenville, IL Sheet 1 of 1 2.3.Address Plant Byron Nuclear Power Station Name 4450 N. German Church Road, Byron, IL Address Work Performed by Byron Mechanical Maintenance Name 4450 N. German Church Road, Byron, IL Address Unit 02 Work Order No. 01404948-14 Repair Organization, P.O. No., Job No., etc.Type Code Symbol Stamp Authorization No. Not Expiration Date Not A;Not Applicable Applicable plicable 4. Identification of System Reactor Coolant (RC)5. (a) Applicable Construction Code ASME Section III 19 74 Edition, S/74 Addenda, 1423-2 Code Case (b) Applicable Edition of Section XI Used for Repair/Replacement Activity:

2001 EditionI2003 Addenda (c)Section XI Code Case(s)6. Identification of Components Name of Cornponent Name of Manufacturer Manufacturer Serial No.National Board No.Corrected, Removed, or Installed ASME Code Stamped (Yes or No)Other Identification Year Built 6712 Loop 1 RC cold leg Westinghouse N/A 1977 Corrected yes nozzle 6713 Loop 2 RC cold leg Westinghouse N/A 1977 Corrected yes nozzle 6714 Loop 3 RC cold leg Westinghouse N/A 1977 Corrected yes nozzle 6715 Loop 4 RC cold leg Westinghouse N/A 1977 Corrected yes nozzle 7. Description of Work Removed manufacture's nameplate by grinding, pipe wall not penetrated.

8. Test Conducted:

Hydrostatic 5] Pn Other D Pressure eumatic 5 Norr psi tinal Operating Pressure El Test Temp.Exempt [D Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 81/2 in. x 11 in., (2)((' formation in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number I. 4f sheets is recorded at the top of this form.

FORM NIS-2 (Back)9. Remarks WO 1404948-14 Applicanie Manutacturer's uata -eports to De attacnea K)J 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 ,gAuthoriz~tion 14o. Not Applicable Signed M,,;A, Ad," &00V//Z" Date 7-fZ , 20 13 I os Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Illinois and employed by HSB CT of ,lartford, CT have'nspgcted the components described in this Owner's Report during the period zI t o j/'J_/to , and state that to the best of my knowledge and belief, the dwner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective 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 iZ/$

A Al 2 e_7'" -Inspector's Signature Date: OfA ,20 13 National Board, State Province, and Endorsements (Final Doc 4A FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section Xl I. Owner Exelon Nuclear Date 2-2-12 Name 4300 Wlnfield Road, Warrenville, IL Sheet 1 of 1 Address 2. Plant Byron Nuclear Power Station Unit 02 Name 4450 N. German Church Road, Byron, IL Work Order No. 01442461-.04 Address Repair Organization, P.O. No., Job No., etc.3. Work Performed by Byron Mechanical Type Code Symbol Stamp Not Applicable Maintenance Name Authorization No. Not Applicable 4450 N. German Church Road, Byron, IL Expiration Date Not Applicable Address 4. Identification of System Main Feedwater

[FW]5. (a) Applicable Construction Code ASME Section III 19 74_4 Edition, W/75* 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 ASME Corrected, Code National Removed, or Stamped Name of Name of Manufacturer Board Other Year Installed (Yes or No)Component Manufacturer Serial No. No. Identification Built GATE VALVE BORG S/N 35601 2FW009C THERMOCOUPLES WARNER N/A 1979 REMOVEDNO GATE VALVE BORG S/N 35601 2FW009C THERMOCOUPLES WARNER N/A 1979 INSTALLED NO 7. Description of Work REPLACED THERMOCOUPLES ON 2FW009C VALVE BODY 8. Test Conducted:

Hydrostatic El Pneumatic El Norm Other El Pressure psi inal Operating Pressure El Test Temp.Exempt 0 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 number of sheets is recorded at the top of this form.

FORM NIS-2 (Back)9. Remarks Work Order No. 01442461-04 Applicable Manufacturers Data Reports to be attached* Thermocouple spot welding to be in accordance with ASME Section III NC-4311.2, 1992 Ed/1 992 Addenda per EC 0000347800 and Valve Drwg 80210 Revision L. and T-Mod DCP 9901014.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 Xl.Type Code Symbol Stamp Not Applicable Certificate of Authorization No. Not Applicable Signed Date 3 20 12 Owneror 0v;-OeesDs 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 -/ ord, CT have i sp cted the components described in this Owner's Report during the period to , r.101 , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective 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 a loss of any kind arising from or connected with this inspection.

__________________

~Commissions d ' //,f/I6 ZY Inspector's Signature National Board, State Province, and 9ndorsements Date: ,20 12 (Final)

DOCUMENT NO.: 4.2 REV. NO.: 0 FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI 1. Owner Exelon Nuclear Date 4/17/13 Name 4300 Winfield Road, Warrenville, IL Sheet 1 of 1 Address 2. Plant Byron Nuclear Power Station Unit 02 Name 4450 N. German Church Road, Byron, IL Work Order No. 01450986-01/02 Address Repair Organization, P.O. No., Job No., etc.3. Work Performed by CB&l/Stone

& Webster Type Code Symbol Stamp Not Applicable Name Authorization No. Not Applicable 36400 S. Essex Road, Wilmington, IL 60481 Expiration Date Not Applicable Address 4. identification of System RY I PRESSURIZER

5. (a) Applicable Construction Code ASME Section III 19 71 Edition, W72 Addenda, na 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 ASME Corrected, Code National Removed, or Stamped Name of Name of Manufacturer Board Other Year Installed (Yes or No)Component Manufacturer Serial No. No. Identification Built RELIEF VALVE CROSBY VALVE N56964-00-0030 N/A 2RY8010A 1976 Removed YES 2RY8010A & GAGE RELIEF VALVE CROSBY VALVE N56964-00-0048 N/A CAT ID 1402762-1 1976 Installed YES 2RY8010A & GAGE I I + + 1 J t t t 7. Description of Work REMOVE / REPLACE PRESSURIZER RELIEF VALVE 2RY8010A 8. Test Conducted:

Hydrostatic El Pneumatic

[] Nominal Operating Pressure 0 Exempt El Other E] Pressure 2234 psi Test Temp. 556 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 number of sheets is recorded at the top of this form.

FORM NIS-2 (Back)9. Remarks 01450986-01/02 Applicable Manufacturer's 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 ofAuthorization No. Not Applicable Signed t, , tZ IA/,F,__ Date j-, 20 13 Owner or dwner'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 Harord, CT have ins ected the components described in this Owner's Report during the period h _6wner -to I./ý ? , and state that to the best of my knowledge and belief, he wner has performedexaminations 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 d mage r a loss of any kind arising from or connected with this inspection.

Commissions A[()Inspector's Signature Date: ,20 13 National Board, State Province, and Endorsements (Final)()

DOCUMENT NO.: 5A REV. NO.: 0 FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI 1. Owner Exelon Nuclear Date 4/18/13 Name 4300 Winfield Road, Warrenville, IL Sheet 1 of 1 Address 2. Plant Byron Nuclear Power Station Unit 02 Name 4450 N. German Church Road, Byron, IL Work Order No. 01478575-01 Address Repair Organization, P.O. No., Job No., etc.3. Work Performed by Byron Mechanical Type Code Symbol Stamp Not Applicable Maintenance Name Authorization No. Not Applicable 4450 N. German Church Road, Byron, IL Expiration Date Not Applicable Address 4. Identification of System SI -SAFETY INJECTION 5. (a) Applicable Construction Code ASME Section III 19 71 Edition, W/72 Addenda, NONE Code Case (b) Applicable Edition of Section XI Used for Repair/Replacement Activity:

2001 Editloni2003 Addenda (c)Section XI Code Case(s) NONE 6. Identification of Components ASME Corrected, Code National Removed, or Stamped Name of Name of Manufacturer Board Other Year Installed (Yes or No)Component Manufacturer Serial No. No. Identification Built SEAL WELD ON 2SI8819A VALVE CAP Flowserve 67BSC N/A 2011 CORRECTED YES 7. Description of Work REPAIR SEAL WELD 8. Test Conducted:

Hydrostatic

[] Pn Other EJ Pressure eumatic []Nominal Operating Pressure El psi Test Temp.Exempt 0 OF Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 81/22 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 number of sheets is recorded at the top of this form.

FORM NIS-2 (Back)9. Remarks WO# 01478575-01

)Applicable Manufacturer s Data R-eporrs to be anacnea 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 ofAuthorization No. Not Applicable Signed C.. i .Z A,/AAiZ) Date jt4- Z It , 20 13 Owner or Owners 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 Hartord, CT have*nspycted the components described in this Owners Report during the period to ,43 and state that to the best of my knowledge and belief, the O1wner 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 A,/& ,S," V# , (.-)A00 Inspector's Signature Date: 0?14/ ,20 13 National Board, State Province, and Endorsements (Final 0 DOCUMENT NO.: 5.2 FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI 1. Owner Exelon Nuclear Date 4/25/13 Name 4300 Winfield Road, Warrenville, IL Sheet 1 of 1 Address 2. Plant Byron Nuclear Power Station Unit 02 Name 4450 N. German Church Road, Byron, IL Work Order No. 01479994-34 Address Repair Organization, P.O. No., Job No., etc.3. Work Performed by CB&llStone

& Webster Type Code Symbol Stamp Not Applicable Name Authorization No. Not Applicable 36400 S. Essex Road, Wilmington, IL 60481 Expiration Date Not Applicable Address 4. Identification of System REACTOR COOLANT SYSTEM (RC)5. (a) Applicable Construction Code 19 71 Edition, S72/ Addenda, Code W74 Case 1355, 1493-1, 1484, 1528, NB4643 (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 ASME Corrected, Code National Removed, or Stamped Name of Name of Manufacturer Board Other Year Installed (Yes or No)Component Manufacturer Serial No. No. Identification Built S/G #16 NOZZLE Westinghouse 2096 N/A 2RC01BB 1980 Corrected YES WELD TO GEN_____7. Description of Work Base metal defect removal 8. Test Conducted:

Hydrostatic

[I Pneumatic 13 Nominal Operating Pressure E3 Exempt E]Other Z

  • Pressure psi Test Temp. OF*NDE Report B2R17- MT-003 N 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 number of sheets is recorded at the top of this form.

FORM NIS-2 (Back)9. Remarks 01479994-34 Applicable Manufacturer's 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 uthorzati~n No. Not Applicable Signed r)36OAA (A\, A)I, ,, P eZ O0AA1/A,',4 7/-/-L Date -23 ,2013 Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Illinois and employed by HSB CT of Haytord, CT have ipspe~cted the components described in this Owner's Report during the period Ak ý13 -to -,and state that to the best of my knowledge and belief, ( )the 6wner has performed 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 A#,WT(R!'7i' 4,/Aa,&--Inspector's Signature National Board, State Province, and Endorsements Date: 0 ,.... 20 13 (Final)I)

DOCUMENT NO.: 5.2 REV. NO.: 0 FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI 1. Owner Exelon Nuclear Date 4/17/13 Name 4300 Winfield Road, Warrenville, IL Sheet 1 of 1 Address 2. Plant Byron Nuclear Power Station Unit 02 Name 4450 N. German Church Road, Byron, IL Work Order No. 01480596-01 Address Repair Organization, P.O. No., Job No., etc.3. Work Performed by CB&l/Stone

& Webster Type Code Symbol Stamp Not Applicable Name Authorization No. Not Applicable 36400 S. Essex Road, Wilmington, IL 60481 Expiration Date Not Applicable Address 4. Identification of System SI -Safety Injection 5. (a) Applicable Construction Code ASME Section III 19 71 Edition, W72 Addenda, None Code Case vlv/piping 74 S75 None (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 ASME Corrected, Code National Removed, or Stamped Name of Name of Manufacturer Board Other Year Installed (Yes or No)Component Manufacturer Serial No. No. Identification Built 1-1/2" CHECK KEROTEST S/N: KYA4-18 9394 2SI8900C 1976 REMOVED YES CHECK VALVE 1-1/2" CHECK VALVE Flowserve, Inc S/N: 39BUX N/A CAT ID: 23370 2013 INSTALLED YES 1-12ECK. 160AUNTE 1-1/2"SCH.

160 HUNTER HT# 479161 N/A 2SI08JC-1-1/2" 1982 REMOVED NO PIPE CORP.1-1/2" SCH. 160 Consolidated PI1Poe S upply HT# 510310 N/A CAT ID: 41105 2009 INSTALLED NO PIPE Power Supply1 1-1/2"90 DEG HUNTER HT#: NM N/A 2SI08JC-1-1/2" 1982 REMOVED NO 6000# ELBOW CORP. _1-1/2"90 DEG Consolidated HT# 44053 N/A CAT ID: 39262 2007 INSTALLED NO 6000# ELBOW Power Supply SEAL WELD ON EXELON N/A N/A N/A 2013 INSTALLED NO VALVE CAP 7. Description of Work REPLACE CHECK VALVE AND ASSOCIATED PIPING.8. Test Conducted:

Hydrostatic E] Pneumatic E] Nominal Operating Pressure Z Exempt i: Other [] Pressure 2234 / 2418 psi Test Temp. 557 / 476 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 number of sheets is recorded at the top of this form.

FORM NIS-2 (Back)9. Remarks 01480596-01 Applicable Manufacturer's 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^Authorization No. Not Applicable Signed (L- 4 O. 0, Aý .X, JA 266, Date 5"-2-d ,20 13 0=,er or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Illinois and employed by HSB CT of Harord, CT have jspocted the components described in this Owner's Report during the period to .,and state that to the best of my knowledge and belief, the (Oner has performed dxaminations 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.

Q x' .Commissions

//, X c. ._3 Inspector's Signature Date: 20 13 National Board, State Province, and Endorsements (Final)()

DOCUMENT NO.: 5.2 REV. NO.: 0 FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI 1. Owner Exelon Nuclear Date 4/17/13 Name 4300 Winfield Road, Warrenvile, IL Sheet 1 of 1 Address 2. Plant Byron Nuclear Power Station Unit 02 Name 4450 N. German Church Road, Byron, IL Work Order No. 01480597-01 Address Repair Organization, P.O. No., Job No., etc.3. Work Performed by CB&I/Stone

& Webster Type Code Symbol Stamp Not Applicable Name Authorization No. Not Applicable 36400 S. Essex Road, Wilmington, IL 60481 Expiration Date Not Applicable Address 4. Identification of System SI -Safety Injection 5. (a) Applicable Construction Code ASME Section III 19 71 Edition, W72 Addenda, None Code Case (vlv) / pipe-elbow 74 S75 None (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 ASME Corrected, Code National Removed, or Stamped Name of Name of Manufacturer Board Other Year Installed (Yes or No)Component Manufacturer Serial No. No. Identification Built 1-1/2" CHECK KEROTEST S/N: XLZ1-5 21,666 2SI8900A 1978 REMOVED YES CHECK VALVE 1-1/2" 2SI8900A CHECK Flowserve S/N: 92BVB N/A CTID230 2013 INSTALLED YES CHECK VALVE CAT ID: 23370 1-1/2"SCH.

160 HUNTER HT# 750725 N/A 2SI08JA-1-1/2" 1985 REMOVED NO PIPE CORP HT# 479161 1-1/2" SCH. 160 Consolidated 2SI8900A PIPE Power Supply CAT ID: 41105 2 1-1/2" 90 DEG HUNTER HT#: NM N/A 2SI08JA-1-1/2" 1985 REMOVED NO 6000# ELBOW CORP 1-1/2" 90 DEG Consolidated N/A 2011 INSTALLED NO 6000# ELBOW Power Supply HT#_44027 N/A CAT ID: 39262 2011 INSTALLED NO SEAL WELD ON EXELON N/A N/A N/A 2013 INSTALLED NO VALVE CAP I I I I I 7. Description of Work REPLACE CHECK VALVE AND ASSOCIATED PIPING.8. Test Conducted:

Hydrostatic 0 Other E] Pr Pneumatic

[]Nominal Operating Pressure E]Exempt [I essure 2234 / 2418 psi Test Temp. 557 / 476 '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 number of sheets is recorded at the top of this form.

FORM NIS-2 (Back)9. Remarks 01480597-01 Applicable Manufacturer's 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 (kLd , e k? &O M I 7A)TO/Z- Date .5-- Z ,20 13 Owner or Owner's Designee.

Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Illinois and employed by HSB CT of 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, tle cwner 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 AC~/ ~ ff C'Inspector's Signature National Board, State Province, and Endorsements Date: 4ft e7 ,20 13 (Final)

DOCUMENT NO.: 5.2 REV. NO.: 0 FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI 1. Owner Exelon Nuclear Date 4/17/13 Name 4300 Winfield Road, Warrenville, IL Sheet 1 of 1 Address 2. Plant Byron Nuclear Power Station Unit 02 Name 4450 N. German Church Road, Byron, IL Work Order No. 01480598-01, 12 Address Repair Organization, P.O. No., Job No., etc.3. Work Performed by CB&I/Stone

& Webster Type Code Symbol Stamp Not Applicable Name Authorization No. Not Applicable 36400 S. Essex Road, Wilmington, IL 60481 Expiration Date Not Applicable Address 4. Identification of System SI -Safety Injection 5. (a) Applicable Construction Code ASME Section III 19 71 Edition, W72 Addenda, None Code Case VIv / Pipe 74 S75 None (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 ASME Corrected, Code National Removed, or Stamped Name of Name of Manufacturer Board Other Year Installed (Yes or No)Component Manufacturer Serial No. No. Identification Built 1-1/2" CHECK KEROTEST S/N: KYA4-14 9391 2SI8900B 1976 REMOVED YES CHECK VALVE 1-1/2" 2I90 CHECK VALVE Flowserve S/N: 38BUX N/A 2SI8900B 2012 INSTALLED YES 1-1/2" VAV CAT ID: 233701 1-1/2"SCH.

160 HUNTER HT# 750725 N/A 2SI08JB-1-1/2" 1982 REMOVED NO PIPE CORP.1-1/2" SCH. 160 Consolidated 2SI8900B HT#: A3614H N/A 1998INSALLD N PIPE Power Supply CAT ID: 41105 SEAL WELD ON EXELON N/A N/A N/A -2013 INSTALLED NO VALVE CAP 7. Description of Work REPLACE CHECK VALVE AND ASSOCIATED PIPING.8. Test Conducted:

Hydrostatic

[] Pneumatic El Nominal Operating Pressure Z Exempt El Other El Pressure 2418 / 2234 psi Test Temp. 476 / 557 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 number of sheets is recorded at the top of this form.

FORM NIS-2 (Back)9. Remarks 01480598-01 Applicable Manufacturer's 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 p"uthorization tNq. Not Applicable Signed UL d, A -Date .7-. ,20 13 Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Illinois and employed by HSB CT of Hartford, CT haveinsp ted the components described in this Owner's Report during the period/", 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 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.

Commissions

",f37/ /Z,/YSW ,/i,4 '1.)Inspector's Signature Date: -lf .449f 20 13 AF_National Board, State Province, and Endorsements (Final)0 DOCUMENT NO.: 5.2 REV. NO.: 0 FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section Xl 1. Owner Exelon Nuclear Date 4-17-13 Name 4300 Winfield Road, Warrenville, IL Sheet 1 of 1 Address 2. Plant Byron Nuclear Power Station Unit 02 Name 4450 N. German Church Road, Byron, IL Work Order No. 01480599-01 Address Repair Organization, P.O. No., Job No., etc.3. Work Performed by CB&l/Stone

& Webster Type Code Symbol Stamp Not Applicable Name Authorization No. Not Applicable 36400 S. Essex Road, Wilmington, IL 60481 Expiration Date Not Applicable Address 4. Identification of System SI -Safety Injection 5. (a) Applicable Construction Code ASME Section III 1971 Edition W72Addenda, 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 ASME Corrected, Code National Removed, or Stamped Name of Name of Manufacturer Board Other Year Installed (Yes or No)Component Manufacturer Serial No. No. Identification Built 1-1/2" CHECK KEROTEST S/N: KYA4-16 9393 2SI8900D 1976 REMOVED YES CHECK VALVE 1-1/2" CHECK VALVE Flowserve, Inc. S/N: 03BQB N/A CAT ID: 23370 2010 INSTALLED YES 7. Description of Work REPLACED CHECK VALVE 8. Test Conducted:

Hydrostatic E]Pneumatic El Nominal Operating Pressure 0 Exempt El Other El Pressure 2418 / 2234 psi Test Temp. 476/ 557 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 number of sheets is recorded at the top of this form.

FORM NIS-2 (Back)9. Remarks 01480599-01 Applicable Manufacturer's 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 _l__,_ _ ." CO01/ Al&LA MQ/Z-- Date 1" /3 ,20 13* vT Owner or (&wner'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 Iart~rd, CT have* sppcted the components described in this Owner's Report during the period.1_0re..to

-::"W.,F , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective 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 propert amage o.F., loss of any kind arising from or connectewith t.*s inspection./eer ,,, ýCommissions

()...... w Date: Inspector's Signature',20 13 National Board, State Province, and Endorsements (Final)

DOCUMENT NO.: 3.2 REV. NO.: 0 FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI 1. Owner Exelon Nuclear Date 4/14/13 Name 4300 Winfield Road, Warrenville, IL Sheet 1 of 1 Address 2. Plant Byron Nuclear Power Station Unit 02 Name 4450 N. German Church Road, Byron, IL Work Order No. 01481192-01

/02 Address Repair Organization, P.O. No., Job No., etc.3. Work Performed by Shaw/Stone

& Webster Type Code Symbol Stamp Not Applicable Name Authorization No. Not Applicable 36400 S. Essex Road, Wilmington, IL 60481 Expiration Date Not Applicable Address 4. Identification of System Safety Injection (SI)5. (a) Applicable Construction Code ASME Section III 19 71 Edition, W72 Addenda, 1501; Code Case 1649 (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 ASME Corrected, Code National Removed, or Stamped Name of Name of Manufacturer Board Other Year Installed (Yes or No)Component Manufacturer Serial No. No. Identification Built VALVE, RELIEF Crosby Valve N56902-00-0031 N/A 2SI8856B 2005 Removed Yes 2X3 & Gae VALVE, RELIEF Crosby Valve 2S18856B VL3 N56902-00-0007 N/A CtId874- 1975 Installed Yes 2X3 & Gage Cat Id 27740-1 7. Description of Work INSTALLED REPLACEMENT RELIEF VALVE PER PM PROGRAM 8. Test Conducted:

Hydrostatic El Pn Other E] Pressure eumatic E] Norr 201 psi ninal Operating Pressure 0 Exempt []Test Temp. na 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 number of sheets is recorded at the top of this form.

FORM NIS-2 (Back)9. Remarks 01481192-01 Applicable Manufacturer's 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 X1.Type Code Symbol Stamp Not Applicable Certificate ofAuthorization No. Not Applicable Signed O( .A;.L , A9 /'908 /INA'M- Date J--- ,2013 Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Illinois and employed by HSB CT of HalOwd, CT have ispegted the components described in this Owner's Report during the period to ,and state that to the best of my knowledge and belief, he wner has performed e/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 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 am ea loss of any kind arising from or connected with this inspection.

Commissions

',!',/K ..,,)Inspector's Signature Date: 4P 20 13 National Bfoard, State Province, and' Endorsements

)

DOCUMENT NO.: 3.2 REV. NO.: 0 FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section Xl 1. Owner Exelon Nuclear Date 4/17/13 Name 4300 Winfield Road, Warrenville, IL Sheet 1 of 1 Address 2. Plant Byron Nuclear Power Station Unit 02 Name 4450 N. German Church Road, Byron, IL Work Order No. 01481338-01/02 Address Repair Organization, P.O. No., Job No., etc.3. Work Performed by CB&I/Stone

& Webster Type Code Symbol Stamp Not Applicable Name Authorization No. Not Applicable 36400 S. Essex Road, Wilmington, IL 60481 Expiration Date Not Applicable Address 4. Identification of System Chemical Volume and Control (CV)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 Xl Code Case(s) NONE 6. Identification of Components ASME Corrected, Code National Removed, or Stamped Name of Name of Manufacturer Board Other Year Installed (Yes or No)Component Manufacturer Serial No. No. Identification Built VALVE, RELIEF CROSBY VALVE N56900-00-0018 N/A 2CV8121 1975 Removed YES____ ___ ___& GAGE _ _ _ _ _ _CROSBY VALVE2C82 VALVE, RELIEF & GAGE N56900-00-0015 N/A 2CV8121 1975 Installed YES_________&

GAGE _______Cat ID 27260-1 ______ ____7. Description of Work INSTALLED REPLACEMENT RELIEF VALVE 8. Test Conducted:

Hydrostatic El Pn Other C] Pressure eumatic E] Norr 50 psi ninal Operating Pressure 0 Exempt El Test Temp. 137 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 number of sheets is recorded at the top of this form.

FORM NIS-2 (Back)9. Remarks 01481338-01/02 Applicable Manufacturer's 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 9 f-iuthorization No. Not Applicable Signed (V&4~ (X Oe orJ Oroll- Date 10g) T20 13 Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Illinois and employed by HSB CT of ord, CT have sp ted the components described in this Owner's Report during the period* r/11 to 3 , and state that to the best of my knowledge and belief, (he 6wner has performed e~aminations 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 inpr a loss of any kind arising from or connected wijh 1his insp 9V..Commissions Inspector's Signature Date: National Board, State Province, and Endorsemnents

,20 13 7)

I DOCUMENTNO.:

3A REV. NO.: 0 FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI 1. Owner Exelon Nuclear Date 3/21/13 2.3.Name 4300 Winfield Road, Warrenville, IL Address Plant Byron Nuclear Power Station Name 4450 N. German Church Road, Byron, IL Address Work Performed by Byron Mechanical Maintenance Name 4450 N. German Church Road, Byron, IL Address Sheet 1 of 1 Unit 02 Work Order No. 01481338-02 Repair Organization, P.O. No., Job No., etc.Type Code Symbol Stamp Not Applicable Authorization No.Expiration Date Not Applicable Not Applicable

4. Identification of System CV 5. (a) Applicable Construction Code ASME Section III 19 71 Edition, S/72 Addenda, NONE Code Case (b) Applicable Edition of Section XI Used for Repair/Replacement Activity:

2001 Editlon/2003 Addenda (c) Section Xl Code Case(s)6. Identification of Components ASME Corrected, Code National Removed, or Stamped Name of Name of Manufacturer Board Other Year Installed (Yes or No)Component Manufacturer Serial No. No. Identification Built NOZZLE CROSBY N90137 N/A Heat # 8656978 2000 REMOVED No 0356 DISC INSERT CROSBY N90448 N/A Heat #713562 1998 REMOVED No 0329 NOZZLE CROSBY N90137 N/A CAT ID 2055-1 2009 INSTALLED No 0393 DISC INSERT CROSBY N90448 N/A CAT ID 2056-1 2009 INSTALLED No 0380 7. Description of Work REBUILD/REPAIR RELIEF VALVE 8. Test Conducted:

Hydrostatic

[] Pneumatic El Nominal Operating Pressure 0 Ex Other E] Pressure 50 psi Test Temp. 137 empt El 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 number of sheets is recorded at the top of this form.

FORM NIS-2 (Back)9. Remarks WO#01481338-02 Applicable Manutacturer's Uata Heports to De attacnea f )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 Xl.Type Code Symbol Stamp Not Applicable Certificate of Authorization No. Not Applicable Signed (Rd4, A ,f,//

Date S-/O ,20 13 Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Illinois and employed by HSB CT of CT haven spected the components described in this Owner's Report during the period 11 / to 1...-...!./.3 , 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 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 orpo a loss of any kind arising from or connected with this ins ection.__ _ _ _ _ _ _ Commissions w ';~/ ~ /§Inspectors Signature National Board, State Province, and Endorsements Date: .EL "-,,. 20 13 (Final DOCUMENT NO.: 2.2 REV. NO.: 0)FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section Xl 1. Owner Exelon Nuclear Date 4-16-13 2.Name 4300 Winfield Road, Warrenville, IL Address Plant Byron Nuclear Power Station Name 4450 N. German Church Road, Byron, IL Address Sheet 1 of 1 Unit 02 3. Work Performed by CB&I/Stone

& Webster Work Order No. 01491143-01 Repair Organization, P.O. No., Job No., etc.Type Code Symbol Stamp Not Applicable Authorization No. Not Applicable Expiration Date Not Applicable Name 36400 S. Essex Road, Wilmington, IL 60481 Address 4. Identification of System (CV) CHEMICAL FEED & VOLUME CONTROL 5. (a) Applicable Construction Code 1651. 1682. 1683. 1685. 1686.ASME Section III 19 74 Edition, S74 Addenda, 1644 Rev. 7, 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 Xl Code Case(s)6. Identification of Components NONE ASME Corrected, Code National Removed, or Stamped Name of Name of Manufacturer Board Other Year Installed (Yes or No)Component Manufacturer Serial No. No. Identification Built Snubber, PSA -Pacific S/N: 6381 N/A 2S122018S 1983 Removed YES 1/2 Scientific Snubber, Lisega iS/N: 2SI22018S 301856RF2 isega31200814/005 N/A Cat. ID# 2013 Installed NO 1033720-1 7. Description of Work REPLACED WITH NEW LISEGA SNUBBER 8. Test Conducted:

Hydrostatic 11 Pneumatic E]Nominal Operating Pressure El psi Test Temp.Exempt El OF VT-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 II in., (2)( information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

FORM NIS-2 (Back)9. Remarks 01491143-01 Applicable Manufacturer's 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 ,,. 'a Date -17 ,2013r Owner's Designee, Title I 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 i sp 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 Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective 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 propert dartiaj or a loss of any kind arising from or connected with this inspection.

Commissions 4,,4.71 //ZlfV A¶A.fl I- Inspector's Signature Date: , ,20 13 National Board, State Province, and Endorsements (Final), .)

DOCUMENT NO.: 6.1 REV. NO.: 0 FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section X1 1. Owner Exelon Nuclear Date 4-16-13 Name 4300 Winfield Road, Warrenville, IL Sheet 1 of 1 Address 2. Plant Byron Nuclear Power Station Unit 02 Name 4450 N. German Church Road, Byron, IL Work Order No. 01491175-01 Address Repair Organization, P.O. No., Job No., etc.3. Work Performed by CB&I/Stone

& Webster Type Code Symbol Stamp Not Applicable Name Authorization No. Not Applicable 36400 S. Essex Road, Wilmington, IL 60481 Expiration Date Not Applicable Address 4. Identification of System RY 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 N-225, N-38, 1690, N-247, & N-242-1 Code Case (b) Applicable Edition of Section X1 Used for Repair/Replacement Activity 2001 Edition / 2003 Addenda (c)Section XI Code Case(s) NONE 6. Identification of Components ASME Corrected, Code National Removed, or Stamped Name of Name of Manufacturer Board Other Year Installed (Yes or No)Component Manufacturer Serial No. No. Identification Built PIN, PIVOT GRINNELL N/A N/A 2RY09060S1 1983 Removed NO PIN, PIVOT GRINNELL N/A N/A 2RY09060S1 1998 Installed NO Cat ID 32458-1 7. Description of Work-REPLACED PIVOT PIN 8. Test Conducted:

Hydrostatic E]Pneumatic

[]Nominal Operating Pressure El psi Test Temp.Exempt El VT-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 number of sheets is recorded at the top of this form.

FORM NIS-2 (Back)9. Remarks 01491175-01

" Applicable Manufacturer's 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 __ -I , 20 13-Qý 0ýwneres 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 Ha;tford, CT have irp 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 6wner has performedd eaminations 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 damagepr a loss of any kind arising from or connected with this inspection.p Commissions ,Z,*,",71//A Z, -/or Inspector's Signature National Board, State Province, and Endorsements Date: .,20 13 (Final)

DOCUMENT NO.: 6.1 REV. NO.: 0 FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section Xl 1. Owner Exelon Nuclear Date 4-16-13 Name 4300 Winfield Road, Warrenville, IL Sheet 1 of 1 Address 2. Plant Byron Nuclear Power Station Unit 02 Name 4450 N. German Church Road, Byron, IL Work Order No. 01491176-01 Address Repair Organization, P.O. No., Job No., etc.3. Work Performed by CB&I/Stone

& Webster Type Code Symbol Stamp Not Applicable Name Authorization No. Not Applicable 36400 S. Essex Road, Wilmington, IL 60481 Expiration Date Not Applicable Address 4. Identification of System RY 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 N-225, N-38, 1690, N-247, N-242-1 (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 ASME Corrected, Code National Removed, or Stamped Name of Name of Manufacturer Board Other Year Installed (Yes or No)Component Manufacturer Serial No. No. Identification Built PIN, PIVOT GRINNELL N/A N/A 2RY09060S2 1983 Removed NO PIN, PIVOT GRINNELL N/A N/A 2RY09060S2 1998 Installed NO Cat ID 32458-1 7. Description of Work-REPLACED PIVOT PIN 8. Test Conducted:

Hydrostatic E]Pneumatic E]Nominal Operating Pressure El Exempt LI OF VT-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 number of sheets is recorded at the top of this form.

FORM NIS-2 (Back)9. Remarks 01491176-01 Applicable Manufacturer's 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 .--- Cop,.- Date 0 -/7 ,20 13--- 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 a ord, CT have ispcted the components described in this Owner's Report during the period V;to Z/// ,and state that to the best of my knowledge and belief, the Owner has performed e aminations 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 inju orpropery damag_ or a loss of any kind arising from or connected with this inspection.

Commissions

,/ IAf, A'A,..d...-)Inspector's Signature Date: / 20 13 National Board, State Province, and Endorsements (Final))

DOCUMENT NO.: 2.2 REV. NO.: 0 FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section Xl 1 Owner Exelon Nuclear Date 4-22-13 2.Name 4300 Winfield Road, Warrenville, IL Address Plant Byron Nuclear Power Station Name 4450 N. German Church Road, Byron, IL Address Sheet 1 -of 1 Unit 02 Work Order No. 01491202-01 Repair Organization, P.O. No., Job No., etc.3. Work Performed by CB&I/Stone

& Webster Name 36400 S. Essex Road, Wilmington, IL 60481 Address Type Code Symbol Stamp Not Ap Authorization No. Not Applicable Expiration Date Not Applicable plicable 4. Identification of System (CV) CHEMICAL FEED & VOLUME CONTROL 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 ASME Corrected, Code National Removed, or Stamped Name of Name of Manufacturer Board Other Year Installed (Yes or No)Component Manufacturer Serial No. No. Identification Built Snubber, PSA -Pacific S/N: 13212 N/A 2CV40007S 1983 Removed YES 1/4 SSierdtific Snubber, Lisega Lisega S/N: N/A 2CV40007S 2013 Installed NO 301856RF1 31200814/004

7. Description of Work REPLACED NEW LISEGA SNUBBER 8. Test Conducted:

Hydrostatic El VT-3 Other 0 Pr Pneumatic Ij essure Nominal Operating Pressure [psi Test Temp. _Exempt El 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 number of sheets is recorded at the top of this form.

FORM NIS-2 (Back)9. Remarks 01491202-01 Applicable Manufacturer's 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 Xl.Type Code Symbol Stamp Not Applicable Certificate of Authorization No. Not Applicable Signed -" ' ,,Y .Date -/: , 20 13 Owners 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 -Hartord, CT have ij.pjcted the components described in this Owner's Report during the period to z J ,and state that to the best of my knowledge and belief, he wner has performed examinations and taken corrective measures described in this Owners 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 ropertqamage o loss of any kind arising from or connected with this inspection.

P Commissions " *',fr i//i ,/'1,4/ t, ,VX. el _Inspector's Signature Date: _itZ , 20 13 National Board, State Province, and Endorsements (Final)

DOCUMENT NO.: 2.2 REV. NO.: 0 FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI Owner Exelon Nuclear Date 4-16-13 2.Name 4300 Winfield Road, Warrenville, IL Address Plant Byron Nuclear Power Station Name 4450 N. German Church Road, Byron, IL Address Sheet 1 of 1 Unit 02 Work Order No. 01491239-01 Repair Organization, P.O. No., Job No., etc.3, Work Performed by CB&I/Stone

& Webster Name 36400 S. Essex Road, Wilmington, IL 60481 Type Code Symbol Authorization No.Expiration Date Stamp Not Ap Not Applicable

'plicable Not Applicable Address 4. Identification of System (CV) CHEMICAL FEED & VOLUME CONTROL 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 Xl Code Case(s) NONE 6. Identification of Components ASME Corrected, Code National Removed, or Stamped Name of Name of Manufacturer Board Other Year Installed (Yes or No)Component Manufacturer Serial No. No. Identification Built Snubber, PSA -Pacific S/N: 12677 N/A 2CV34008S 1983 Removed YES 1/2 Scientific eS/N: 2CV34008S 301Subrs Lisega S/N: N/A Cat ID# 2013 Installed NO 1033720-1 7. Description of Work REPLACED WITH A NEW LISEGA SNUBBER 8. Test Conducted:

Hydrostatic El Pneumatic

[I Non-VT-3 Other 0 Pressure psi inal Operating Pressure EI Test Temp.Exempt El OF Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 81/2/2 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 number of sheets is recorded at the top of this form.

FORM NIS-2 (Back)9. Remarks 01491239-01 Applicable Manufacturer's 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 Xl.Type Code Symbol Stamp Not Applicable Certificate of Authorization No. Not Applicable Signed ,- -"-etS.- Date 6 -/7 20 13Owners 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 H Hford, CT have 1spected the components described in this Owner's Report during the period 97,7 4 to .,and state that to the best of my knowledge and belief, the wner has performed edxaminations 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 dama e or a loss of any kind arising from or connected with this inspection.

Commissions

,-f/h /AI s. / xW Al _t)Inspector's Signature Date: ,20 13 National Board, State Province, and Endorsements (Final))

DOCUMENT NO.: 2A REV. NO.: 0 FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI 1. Owner Exelon Nuclear Date 4-24-13 Name 4300 Winfield Road, Warrenville, IL Sheet 1 of 1 Address 2. Plant Byron Nuclear Power Station Unit 02 Name 4450 N. German Church Road, Byron, IL Work Order No. 01505356-01 Address Repair Organization, P.O. No., Job No., etc.3. Work Performed by CB&I Type Code Symbol Stamp Not Applicable Name Authorization No. Not Applicable 36400 S. Essex Road, Wilmington, IL 60481 Expiration Date Not Applicable Address 4. Identification of System CV- CHEMICAL FEED AND VOLUME CONTROL 5. (a) Applicable Construction Code ASME Section III 19 74 Edition, S/75 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 ASME Corrected, Code National Removed, or Stamped Name of Name of Manufacturer Board Other Year Installed (Yes or No)Component Manufacturer Serial No. No. Identification Built PIPE, 3" Serial No. N/A 2CV19A-3" (PARTIAL)

Hunter Corp. 11440 Spool CV-26-8 1977 Removed Yes FLANGES, 3", Chicago Tube Heat No.: N/A 2CV32MA 1987 Installed NO 600 LB (2 ea.) & Iron ALZB-1 CID# 20147-1 BLANK PLATE Energy Steel & Heat No.: N/A 2CV32MA 2013 Installed NO Supply Co. E7T4 CID# 1457699-1 STUDS, 3/4' Nova Machine Heat No.: N/A 2CV32MA STUDS,_3/4" Products Inc. 3017675 CID# 37094-1 2011 Installed NO NUTS, 3/4 Nova Machine Heat No.: N/A 2CV32MA NUTS,_3/4_

Products Inc. 5092414 CID# 1394886-1 2011 Installed NO PIPE, 3" Hunter Corp. Serial No. N/A 2CV80A-3" (PARTIAL) 11434 Spool CV-26-1 1977 Removed Yes FLANGES, 3", Chicago Tube Heat No.: N/A 2CV33MA 1987 Installed NO 600 LB (2 ea.) & Iron ALZB-1 CID# 20147-1 BLANK PLATE Energy Steel & Heat No.: N/A 2CV33MA 2013 Installed NO Supply Co. E7T4 CID# 1457699-1 STUDS, 3/4" Nova Machine Heat No.: N/A 2CV33MA Products Inc. 3017675 CID# 37094-1 2 NUTS, 3/4" Nova Machine Heat No.: N/A 2CV33MA 1 Products Inc. 5092414 1 CID# 1394886-1 2 I 7. Description of Work INSTALLED NEW BLANK PLATE ASSEMBLIES PER EC#379229 8. Test Conducted:

Hydrostatic El Pn Other E] Pressure eumatic E[ Norr 353 psi ninal Operating Pressure [0 Exempt E]Test Temp. 112 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 number of sheets is recorded at the top of this form.

FORM NIS-2 (Back)9. Remarks 01505356-01 Applicable Manufacturers uata Heports to ne attacnea 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 , 20 13 wn"-e r r wner'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 ipspected the components described in this Owner's Report during the period to ,and state that to the best of my knowledge and belief, e 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.

_w._ __4 _ _- __ Commissions ,l/l,, l% " X&4,, Inspector's Signature National Board, State Province, and Endorsements Date: 4 W /e 20 13 (Final Doc 4A FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI 1. Owner Exelon Nuclear Date 5% 2-- 13 Name 4300 Winfield Road, Warrenville, IL Sheet 1 of 1 Address 2. Plant Byron Nuclear Power Station Unit 02 Name 4450 N. German Church Road, Byron, IL Work Order No. 01512586-04 Address Repair Organization, P.O. No., Job No., etc.3. Work Performed by Byron Mechanical Type Code Symbol Stamp Not Applicable Maintenance Name Authorization No. Not Applicable 4450 N. German Church Road, Byron, IL Expiration Date Not Applicable Address 4. Identification of System Main Feedwater

[FW]5. (a) Applicable Construction Code ASME Section III 19 74 Edition, W/75* 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 ASME Corrected, Code National Removed, or Stamped Name of Name of Manufacturer Board Other Year Installed (Yes or No)Component Manufacturer Serial No. No. Identification Built GATE VALVE BORG S/N 35601 2FW009C THERMOCOUPLES WARNER N/A 1979 REMVE NO GATE VALVE BORG S/N 35601 2FW009C THERMOCOUPLES WARNER N/A 1979 INSTALLED NO 7. Description of Work REPLACED THERMOCOUPLES TO 2FW009C VALVE BODY 8. Test Conducted:

Hydrostatic

[I Pr Other [3 Pressure ieumatic El Nominal Operating Pressure El Exempt ED OF 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 number of sheets is recorded at the top of this form.

FORM NIS-2 (Back)9. Remarks Work Order No. 01512586-04 Applicable Manufacturer's Data Reports to be attached , Thermocouple spot welding to be in accordance with ASME Section III NC-4311.2, 1992 Ed/1992 Addenda per EC 0000374800 and Valve Drwg 80210 Revision L. and T-Mod DCP 9901014.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!,uthorization No. Not Applicable Signed V AA0J( Date 5- 2o-_,20 Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Illinois and employed by HSB CT of Hart rd, 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, Owner has performed Gxaminations 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 dama or a loss of any kind arising from or connected with this inspection.

Commissions ,/. c.Inspector's Signature National Board, State Province, and Endorsements Date: , 20 /13 (Final)

DOCUMENT NO.: 3A REV. NO.: 0 FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI 1 Owner Exelon Nuclear Date 4/25/13 Name 4300 Winfield Road, Warrenville, IL Sheet 1 of 1 Address 2. Plant Byron Nuclear Power Station Unit 02 Name 4450 N. German Church Road, Byron, IL Work Order No. 01561181-01 Address Repair Organization, P.O. No., Job No., etc.3. Work Performed by Byron Mechanical Type Code Symbol Stamp Not Applicable Maintenance Name Authorization No. Not Applicable 4450 N. German Church Road, Byron, IL Expiration Date Not Applicable Address 4. Identification of System MS -MAIN STEAM 5. (a) Applicable Construction Code ASME Section III 19 74 Edition, S74 Addenda, 1682-1 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 ASME Corrected, Code National Removed, or Stamped Name of Name of Manufacturer Board Other Year Installed (Yes or No)Component Manufacturer Serial No. No. Identification Built Valve W-K-M Valve S/N NA Plug HT#32635 1994 Removed NO Trim Set Valve 70-117595 2MS018A Valve Flowserve S/N# C I# 1449830-1 Trim Set L9366-1-5 UTC#2904650

7. Description of Work REPLACE VALVE TRIM SET PER EC:390008 8. Test Conducted:

Hydrostatic El Pr Other I] Pressure eumatic E] Nominal Operating Pressure El Exempt 0 OF psi Test Temp.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 number of sheets is recorded at the top of this form.

FORM NIS-2 (Back)9. Remarks W/O#01561181-01 I Appiicable ManuTacturers Data Reports to be attacnedJ 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 oJuthorization No. Not Applicable Signed A([)a;& t .(V AJ , G 4oe06lijAiTC A-/'.. Date L/ 2 ,20 13 Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Illinois and employed by HSB CT of I-lartford, CT have inso~cted the components described in this Owners Report during the period to , and state that to the best of my knowledge and belief, -J the 6 wner has performed 5 xaminations and taken corrective measures described in this Owners 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 injur or joperty dage or ,Joss of any kind arising from or connect d wit t is inspection

________________

~Commissions4"//5 A Ki In spectol s Signature National Board, State Province, and Endorsements Date: 1 20 13 DOCUMENTNO.:

3A REV. NO.: 0 FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI 1. Owner Exelon Nuclear Date 4/23/13 Name 4300 Winfield Road, Warrenville, IL Sheet 1 of 1 Address 2. Plant Byron Nuclear Power Station Unit 02 Name 4450 N. German Church Road, Byron, IL Work Order No. 01561185-01 Address Repair Organization, P.O. No., Job No., etc.3. Work Performed by Byron Mechanical Type Code Symbol Stamp Not Applicable Maintenance Name Authorization No. Not Applicable 4450 N. German Church Road, Byron, IL Expiration Date Not Applicable Address 4. Identification of System MS -MAIN STEAM 5. (a) Applicable Construction Code ASME Section III 19 74 Edition, S74 Addenda, 1682-1 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 ASME Corrected, Code National Removed, or Stamped Name of Name of Manufacturer Board Other Year Installed (Yes or No)Component Manufacturer Serial No. No. Identification Built Valve Anchor Darling Valve S/N# NA Plug HT#32635 Trim Set 70-117596 2MS018B Valve Flowserve S/N# CI#1461659-1 Trim Set P0924-1 S/N:1 UTC# 2932916 2 7. Description of Work REPLACE VALVE TRIM SET PER EC:390008 8. Test Conducted:

Hydrostatic E] Pn Other D Pressure eumatic E] Norr psi ninal Operating Pressure E]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 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 number of sheets is recorded at the top of this form.

FORM NIS-2 (Back)L 9. Remarks W/O#01561185-01 3, Appllcable Manufacturer s uata Heports to be attacned 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 Xl.Type Code Symbol Stamp Not Applicable CertificateA Authorization No. Not Applicable Signed (:kA. -AJ!LA d00R8o11vA-q.

Date 41- 30 ,20 0A Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Illinois and employed by HSB CT of J-laptford, CT have .ected the components described in this Owner's Report during the period ,AA3 to -,and state that to the best of my knowledge and belief, the 6wner has performre6examinations 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 inje or a loss of any kind arising from or connected with this inspection.

Commissions AM41%1f /%//9*A1iC-

---Inspector's Signature Date: /National Board, State Orovince, and -Endorsements

,20 ,/5)

DOCUMENTNO.:

3A REV. NO.: 0 FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI 1 Owner Exelon Nuclear Date 04/25/13 Name 4300 Winfield Road, Warrenville, IL Sheet 1 of 1 Address 2. Plant Byron Nuclear Power Station Unit 01 Name 4450 N. German Church Road, Byron, IL Work Order No. 01561187-01 Address Repair Organization, P.O. No., Job No., etc.3. Work Performed by Byron Mechanical Type Code Symbol Stamp Not Applicable Maintenance Name Authorization No. Not Applicable 4450 N. German Church Road, Byron, IL Expiration Date Not Applicable Address 4. Identification of System MS -MAIN STEAM 5. (a) Applicable Construction Code ASME Section III 19 74 Edition, S/74 Addenda, 1682-1 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 ASME Corrected, Code National Removed, or Stamped Name of Name of Manufacturer Board Other Year installed (Yes or No)Component Manufacturer Serial No. No. Identification Built Valve W.K.M. VALVE S/N: 1910 PLUG S/N#1 Trim Set VALVE 70-117597 2MS01 8C Valve Flowserve VALVE S/N: Ct#-1461659-1 Trim Set Corp. P0924-1S/N:2 NA UTC#-2932918 2012 Installed Yes 7. Description of Work REPLACE VALVE TRIM SET PER EC:390008 8. Test Conducted:

Hydrostatic 11 Pneumatic

[]Nominal Operating Pressure El Exempt [OF Other El Pressure psi Test Temp.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 number of sheets is recorded at the top of this form.

FORM NIS-2 (Back)9. Remarks WO: 1561187-01

)Applicaule Manuraciurers uaia I-Reports to De attacned 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 It),AA OC, ,uUQ ,1w A (dODvIA1i/

07?- Date -7 20 13 Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Illinois and employed by HSB CT of Ha/gord, CT have)/rsp cted the components described in this Owner's Report during the period 31,2111S to ,and state that to the best of my knowledge and belief, the O'wner has performed examinations and taken corrective measures described in this Owners 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 propertyama-geer a loss of any kind arising from or connected with this inspection.

_______________,,___Commissions x/- s f4Z? (.)Inspector's Signature Date: Z ,20 13 National Board, State Province, and Endorsements (Final I DOCUMENT NO.: 3A REV. NO.: 0 FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI 1 Owner Exelon Nuclear Date 4/25/13 Name 4300 Winfield Road, Warrenville, IL Sheet 1 of 1 Address 2. Plant Byron Nuclear Power Station Unit 01 Name 4450 N. German Church Road, Byron, IL Work Order No. 1561189-01 Address Repair Organization, P.O. No., Job No., etc.3. Work Performed by Byron Mechanical Type Code Symbol Stamp Not Applicable Maintenance Name Authorization No. Not Applicable 4450 N. German Church Road, Byron, IL Expiration Date Not Applicable Address 4. Identification of System MS -MAIN STEAM 5. (a) Applicable Construction Code ASME Section III 19 74 Edition, S/74 Addenda, 1682-1 Code Case (b) Applicable Edition of Section X1 Used for Repair/Replacement Activity:

2001 Edition/2003 Addenda (c)Section XI Code Case(s) N/A 6. Identification of Components ASME Corrected, Code National Removed, or Stamped Name of Name of Manufacturer Board Other Year Installed (Yes or No)Component Manufacturer Serial No. No. Identification Built Valve W-K-M VALVE S/N: NA PLUG HT#76506 Trim Set Valve 70-117598 2MS018D Valve Flowserve S/N# CI#1461659-1 Trim Set Corp. P0924-1 S/N:3 NA UTC#2932919 2012 Installed Yes 7. Description of Work REPLACE VALVE TRIM SET PER EC:390008 8. Test Conducted:

Hydrostatic E] Pr Other E] Pressure leumatic E] Nominal Operating Pressure C]psi Test T emp.Exempt 0 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 number of sheets is recorded at the top of this form.

FORM NIS-2 (Back)9. Remarks WO: 1561189-01 Applicable Manufacturer's Data Reports to be attacned --d 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 Xl.Type Code Symbol Stamp Not Applicable Certificate of Authorization No. Not Applicable Signed ., (A,, IUJ-L, g.

Date --Z7 ,20 13 Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Illinois and employed by HSB CT of Hatord, CT have* sp cted the components described in this Owner's Report during the period S to 0 '73 , 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 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 orpropert damaor a loss of any kind arising from or connected with this inspection.

Commissions

,~~ L /V ,~ il".4 Inspector's Signature Date: wd' ti' ,20 13 National Board, State Province, and Endorsements (Final FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI 1.Owner Exelon Nuclear Date 3-26-13 2.3.Name 4300 Winfield Road, Warrenville, IL Address Plant Byron Nuclear Power Station Name 4450 N. German Church Road, Byron, IL Address Work Performed by NWS Technologies, LLC 131 Venture Boulevard Spartanburg, SC 29306 Address Sheet 1 of 1 Unit 02 P.O. 00485139 Rev. 01 Repair Organization, P.O. No., Job No., etc.Type Code Symbol Stamp Authorization No. 632/ 81 Expiration Date 4-3-15/4 VR / NR-9-15 4. Identification of System MAIN STEAM (MS)5. (a) Applicable Construction Code ASME Section III 19 74.4 Edition, N/A 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)6. Identification of Components NONE ASME Corrected, Code National Removed, or Stamped Name of Name of Manufacturer Board Other Year Installed (Yes or No)Component Manufacturer Serial No. No. Identification Built MAIN STEAMN/VALVE S/N: CAT ID#SAFETY RELIEF DRESSER BU01490 N/A 1439914-1 1978 REMOVED YES VALVE MAIN STEAM VALVE S/N: CAT ID#SAFETY RELIEF DRESSER N/A 1439914-1 1978 CORRECTED YES VALVEBU01490 VALVE DISK DRESSER S/N: AAJ04 N/A VALVE S/N" 1978 REMOVED NO BU01490 CAT ID#(INCONNEL X-750) DRESSER S/N: AGM19 N/A 1438465-1 2011 INSTALLED NO DISK UTC# 2894630 VALVE S/N: Spindle DRESSER S/N: G1299 N/A BU01490 1978 REMOVED NO DRESSER CAT ID#Spindle CONSOLIDA S/N: AGD80 N/A 1449980-1 2011 INSTALLED NO TED UTC# 2891523 Compression Screw DRESSER N/A N/A VALVE 1978 REMOVED NO BU01490 1978 RMVD N DRESSER CAT ID#Compression Screw CONSOLIDA S/N: AGF31 N/A 1452424-1 UTC# 2011 INSTALLED NO TED 2893937 7.Description of Work Refurbished MS relief valve, replaced disc, spindle, compression screw. Installed extended wear mod EC 339376 and anti-rotation mod EC 340678.8. Test Conducted:

Hydrostatic r_1 Pneumatic F] Nominal Operating Pressure []Exempt []

Other E] 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 numbe\of sheets is recorded at the top of this form.)

FORM NIS-2 (Back)9. Remarks P.O. 00485139 Rev. 01 Applicable Manufacturer's 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 pAithorization No. Not Applicable Signed ,v, A.. CA ,, 41 kmAJa- Date -- Y 20 13 Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Illinois and employed by HSB CT of Hartford, CT have spted the components described in this Owner's Report during the period to ,and state that to the best of my knowledge and belief, Owner has performed examinations and taken corrective measures described in this Owners 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 Owners Report.Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage, a loss of any kind arising from or connected with this inspection.

___.. ____________

Commissions f/,,/Z/Af,' ,V, c Inspector's Signature Date: National Board, State Provinge, and Endorsements

,20 13 FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI 1. Owner Exelon Nuclear Name 4300 Winfleld Road, Warrenvllle, IL Date 4-2-13 Sheet 1 of 2 2.Address Plant Byron Nuclear Power Station Name 4450 N. German Church Road, Byron, IL Address Unit 01 P.O. 00495705 Rev-1 3. Work Performed by NWS Technologies, LLC 131 Venture Boulevard Spartanburg, SC 29306 Address Repair Organization, P.O. No., Job No., etc.Type Code Symbol Stamp VR / NR Authorization No. 632 / 81 Expiration Date 4-3-15 / 4-9-15 4. Identification of System MAIN STEAM (MS)5. (a) Applicable Construction Code ASME Section III 19 74 Edition, N/A 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 ASME Corrected, Code National Removed, or Stamped Name of Name of Manufacturer Board Other Year Installed (Yes or No)Component Manufacturer Serial No. No. Identification Built MAIN STEAM VALVE S/N: VALVE UTC#SAFETY RELIEF DRESSER BR09593 N/A 2926784 1977 CORRECTED YES VALVE VALVE S/N: SPINDLE DRESSER S/N: G9776 N/A BR09593 1977 REMOVED NO CAT ID#SPINDLE DRESSER S/N: AGD81 N/A 1449980-1 2011 INSTALLED NO UTC# 2884360 COMPRESSION DRESSER S/N: N/A N/A VALVE S/N: 1977 REMOVED NO SCREW BR09593 ,OPE O CAT ID#COMPRESSION DRESSER S/N: AHL18 N/A 1452424-1 2013 INSTALLED NO SCREW UTC# 2935518 7. Description of Work Refurbished valve / installed new spindle & compression screw.8. Test Conducted:

Hydrostatic E Pn Other EJ Pressure eumatic []Nominal Operating Pressure C]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 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 number of sheets is recorded at the top of this form.

FORM NIS-2 SUPPLEMENTAL SHEET 6/ 31LcL 1. Owner Exelon Nuclear Name 4300 Winfleld Road. Warrenville.

IL Date 4-2-13 (..)Sheet 2 of 2 Address 2. Plant Byron Nuclear Power Station Name 4450 N. German Church Road, Byron, IL Address Unit 01 P.O. 00495705 Rev-1 Repair Organization, P.O. No., Job No., etc.Type Code Symbol Stamp VR / NR Authorization No. 632 /81 Expiration Date 4-3-15 / 4-9-15 3. Work Performed by NWS Technologies, LLC 131 Venture Boulevard Spartanburg, SC 29306 Address 4. Identification of System MAIN STEAM (MS)5. (a) Applicable Construction Code ASME Section III 19 74 Edition, N/A 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 ASME Corrected, Code National Removed, or Stamped Name of Name of Manufacturer Board Other Year Installed (Yes or No)Component Manufacturer Serial No. No. Identification Built MAIN STEAM VALVE S/N: VALVE UTC#SAFETY RELIEF DRESSER BR09597 N/A 2926786 1977 CORRECTED YES VALVE VALVE S/N:K SPINDLE DRESSER S/N: G9776 N/A BR09597 1977 REMOVED NO SPINDLE DRESSER S/N: AGD76 N/A CAT ID# 1449980-1 UTC# 2884360 2011 INSTALLED NO COMPRSSIONVALVE S/N: COMPRESSION DRESSER S/N: N/A N/A VALVE 1977 REMOVED NO SCREW BR09597 COMPRESSION DRESSER S/N: AHL16 N/A CAT ID# 1452424-1 SCREW UTC# 2935518 2013 INSTALLED NO DISC DRESSER S/N: ADC97 N/A VALVEBR 2000 REMOVED NO BR09597 2001 INSALED NO DISC DRESSER S/N: ADG34 N/A ValrmvedBR0960 2001 INSTALLED NO (Final)

FORM NIS-2 (Back) " 'I 6/'9. Remarks P.O. 00495705 Rev-1 Applicable Manufacturers Data Reports to be attached NWS Traveler 12-353 Valve S/N: BR09593 NWS Traveler 12-354 Valve S/N: BR09597 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 AppIlcable Signed Dt 01--we r' 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 /Harord, CT have ipsp/cted the components described in this Owner's Report during the period Ieto WE, 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 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.

_____________________

Commissions

,4#f.47/ AZt/1 P/ ._s/'Inspector's Signature National Board, State Province, and Endorsements Date: ,20 13 or

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