ML100050357
| ML100050357 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 01/05/2010 |
| From: | Enright D J Exelon Generation Co, Exelon Nuclear |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML100050354 | List: |
| References | |
| 1.10.0101, BYRON 2010-0001 | |
| Download: ML100050357 (33) | |
Text
r.xt:lon Ct.'fleYJtiDn LtC!iyrUrl SLiUon 4450 North Cenr'dn Church Ro"d tlylCln, It GIOIOQ794 January 5, 2010 LTR: BYRON 2010-0001 FILE: 1.10.0101 p.com Nuclear United States Nuclear Regulatory Commission AlTN: Document Control Desk Washington, DC 20555-0001 Byron Station, Unit 1 Facility Operating License No.NPF-37 NRC Docket No.STN50-454
SUBJECT:
Byron Station Unit 1 90-Day Inservice Inspection Report for Interval 3, Period 1, (B1R16)The subject 90-Day Inservice Inspection Report for the Byron Station Unit 1, Refueling Outage Sixteen (B1R16)is being submitted pursuant to the requirements of Article IWA-6000,"Records and Reports" ofSectionXI,"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 1 Fall 2009 refueling outage.If there are any questions regarding this matter, please contact Dave Gudger, Regulatory Assurance Manager, at (815)-406-2800.
Respectfully, Daniel J.Enright Site Vice President Byron Generating Station DJE/RGM/TLH/cy
Attachment:
B1R16 Inservice Inspection Summary Report-Fall 2009 outage ecc: Illinois Emergency Management Agency-Division of Nuclear Safety Site Vice President-Byron Station Vice President-Licensing and Regulatory Affairs Director-Licensing and Regulatory Affairs Manager-Licensing-Braidwood, Byron and LaSalle Stations Regulatory Assurance Manager-Byron Station Exelon Document Control Desk Licensing R.McBride-Engineering, Byron Nuclear Exel n," B1R16 BYRON UNIT 1 Fall 2009 Outage INSERVICE INSPECTION
SUMMARY
REPORT For Inspection Activities from April 14, 2008 to October 8, 2009 Commercial Service Date September 16, 1985 Document Completion Date December 18, 2009 Exelon Generation Company (EGC, LLC)4300 Winfield Rd Warrenville, IL 60555 Byron Nuclear Power Station 4450 North German Church Rd.Byron, IL 61010 BYRON UNIT I B1R16 xel Nuclear INSERVICE INSPECTION
SUMMARY
REPORT JSECTION Page ii ITable of Contents 1.0 I Report Introduction SECTION DESCRIPTION PAGES I 1 I 1 I 6 I lSI-Weld/Component Listing 21 lSI-Bolts, Pumps, and Valves Listing 2 Examination PSI-Weld/Component Listing 2 2.0 Summary PSI-Bolts, Pumps, and Valves Listing 1 Tables lSI-Pressure Tests 1 lSI-Component Supports 3 lSI-Snubbers 7 3.0 IStatus of Examination Completion for the Program Plan 4.0 I Form NIS-1: Preservice and Inservice Examinations 5.0 I Form NIS-2: Repairs/Modifications 8 34 33 TOTAL PAGES IN REPORTI 120 This page left blank intentionally BYRON STATION UNIT 1 REFUELING OUTAGE 16 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 1 from April 4, 2008, through October 8,2009.The majority of these inspections were performed during the sixteenth refueling outage (B 1 R16)from September 14 through October 8,2009.B1 R16 is the third outage of the First Period in the Third Inspection Interval.The examinations were performed in compliance with the rules and regulations of ASME Section XI (applicable edition and addenda), pursuant to the requirements of 10 CFR 50.55a.See 1.7.0 of the introduction for a listing of referenced documents.
This summary report meets the requirements of ASME Code, IWA-6000 for 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 (lSI)Program Plan for Class 1, 2, 3, CC, and MC components was developed in accordance with the requirements and intent of Section XI SubsectionsIWA,IWB,IWC,IWD, IWE, IWF and IWL, 2001 Edition, through the 2003 Addenda.In addition to the ASME Section XI requirements of examination, certain Nuclear Regulatory Commission (NRC)augmented lSI inspections and industry initiatives (NEI-03-08) were required.The Byron Station Unit 1 augmented lSI examination requirements include: a)Class 1 pressure boundary for leakage at nominal operating pressure, in accordance with NRC Generic Letter 88-05;b)Class 1 Alloy 600 weld examinations in accordance with MRP-139, N-722, and N-729-1;c)Class 1 examinations of non-isolable Reactor Coolant System branch lines for Thermal Fatigue in accordance with MRP-146;d)Class 2 and 3 pressure boundary for leakage at nominal operating pressure, in accordance with NUREG 0737.Note: Specific requests for relief were developed and submitted for the NRC's review when the code and/or augmented requirement(s) were deemed to be impractical, results in excessive hardship, or an alternative examination method is determined as more suitable for the particular component.
Section 1.0 Page 1 of 6 BYRON STATION UNIT 1 REFUELING OUTAGE 16 INSERVICE INSPECTION REPORT 1.1.1 Identification of Examination Requirements TheSection7.0 of the lSI Program Plan contains the examination program tables.These tables are consistent with the tables found in Subsections IWB, IWC, IWO, IWE, IWF, and IWL-2500 of the ASME Code.The examination tables include the corresponding code category, item number, and component/weld selection in conformance with examination requirements and intent of SubsectionIWA,IWB, IWC, IWO, IWE, IWF, and IWL of Section XI of the ASME Code.-For Class 1, 2, and certainnon-classpiping components, the requirements of Risk Informed Inservice Inspection (RI-ISI)are followed using EPRI TR112657 and Table 1 of ASME Code Case N-578-1.1.1.2 Identification of Exempted Components ASME Class 1, 2, and 3 components, or parts of components, that are not included in the examination tables and that are exempt from examination, as specified in Section XI Paragraphs IWB, IWC, and IWO-1200, and Tables IWB-2500-1,2500-1, and IWO-2500-1, are identified in the NOE Program Plan in conjunction with technical justification(s) for exempting the component/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 Examination Categories B-F, B-J, C-F-1, and C-F-2, are not allowed under the requirements of the RI-ISI program.With the adoption oflSI, welds evaluated as Risk Category 6 or 7 are not required to be subject to examination.
1.1.3 Implementation
of the lSI 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 lSI Program Schedule, Byron Station Technical Specifications, and/or comply with the ASME Section XI 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/ASNT189,1995 Edition and ASNTSNT-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 Revision.The NOE procedures were developed and certified in conformance with ASME Section V and XI as applicable.
..,;...All lSI NOE, including evaluation of flaw indications, were performed in accordance with the requirements stipulated under Section XI IWA-2200.For components incorporated into the RI-ISI program, the guidance for the examination volume for a Section 1.0 Page 2 of 6 BYRON STATION UNIT 1 REFUELING OUTAGE 16 INSERVICE INSPECTION REPORT given degradation mechanism is provided by the EPRI Topical Report while the guidance for the examination method is provided by Code Case N-578-1.1.1.4 Significant Activities During B1 R16 During the refueling outage, the Alloy 600 reactor vessel hot leg safe-end welds were volumetrically examined for PWSCC per the requirements specified in139 for Category D weldments.
One Alloy 600 reactor vessel cold leg safe-end weld was visually examined for leakage per the requirements specified in N-722 for Item B15.95 weldments.
All reactor vessel bottom-mounted instrument penetrations were visually examined for leakage per the requirements specified in N-722 for Item B15.80 weldments.
The reactor vessel head surface was visually examined for evidence of leakage per the requirements specified in N-729-1 Note (4)for Item B4.1 0 components.
All weld overlays on the pressurizer safe-end welds were volumetrically examined.This examination complies with the requirements specified in MRP-139 for Category F welds and ASME Appendix 0, paragraph 0-4300(a).
Use of Appendix 0 was addressed in relief request 13-08.1.1.5 ASME Section XI Code Cases N-566-2 is incorporated into the current Byron Station lSI Program and was utilized during the 16 th fuel cycle.The implementation of the risk-informed program as described in relief request02 utilized N-578-1.For Repair/Replacement activities, code cases are identified on the applicable Form NIS-2.1.1.6 Witness and Verification of Examination The inservice inspections were witnessed and/or verified by the Authorized Nuclear Inservice Inspectors (ANII): Jeff Hendricks and Lee Malabanan.
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 Inservice Inspection
-Bolts, Pumps, and Valves Listing Section 1.0 Page 3 of 6 BYRON STATION UNIT 1 REFUELING OUTAGE 16 INSERVICE INSPECTION REPORT 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 1 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 1.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 1.See Section 5.0 for the reports.1.6.0 CONTAINMENT lSI 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 XI, Rules for Inservice Inspection of Nuclear Power Plant Components, 2001 Edition, through 2003 Addenda a)IWA-2200 Examination Methods b)IWA-6000: Records and Reports c)IWB, IWC, and IWD-1200, Components Exempt from Examination d)IWB, IWC, and IWD-2500, Examination and Pressure Test Requirements Section 1.0 Page 4 of 6 BYRON STATION UNIT 1 REFUELING OUTAGE 16 INSERVICE INSPECTION REPORT Code Case N-504-3: Alternative Rules for Repair of Classes1, 2, and 3 Austenitic Stainless Steel Piping Code Case N-566-2: Corrective Action for Leakage Identified at Bolted Connections.
Code Case N-578-1: Risk-Informed Requirements for Class 1, 2, or 3 Piping, Method B.Code Case N-722: Additional Examinations for PWR Pressure Retaining Welds 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.Nonmandatory Appendix Q: Weld Overlay Repair of Class 1, 2, and 3 Austenitic Stainless Steel Piping Weldments (2004 Edition, through 2005 Addenda).Appendix Q was required for the installation of the weld overlays using Code Case N-504-3.a)Q-4300 Inservice Inspection.
Form NIS-1, Owners Report for Inservice Inspections.
Form NIS-2, Owners Report for Repairs or Replacements.
1.7.3 American
National Standards Institute I American Societv for Nondestructive Testing ANSI/ASNT CP-189, 1995 Edition, Standard for Qualification and Certification of Nondestructive Testing Personnel.
1.7.4 American
Societv for Nondestructive Testing 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 Material Reliability Program: Primary System Piping Butt Weld Inspection and Evaluation Guideline (MRP-139)Revision 1, December 2008.Material Reliability Program: Management of Thermal Fatigue in Normally Stagnant Non-Isolable Reactor Coolant System Branch Lines (MRP-146), June 2005.Topical Report TR112657 Revision B-A, Revised Risk-Informed Inservice Inspection Procedure, December 1999.1.7.7 Nuclear Energy Institute NEI 03-08, Guideline for the Management of Materials Issues.Section 1.0 Page 5 of 6 BYRON STATION UNIT 1 REFUELING OUTAGE 16 INSERVICE INSPECTION REPORT 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-08: Alternative Requirements of Structural Weld Overlays (SWOLs)of the Pressurizer Surge, Spray, Safety and Relief Nozzles, Dissimilar Welds including the SWOLs of the Safe-End to Pipe, Reducer and Elbow Welds on Pressurizer Surge, Spray, Safety and Relief Nozzles.Section 1.0 Page 6 of 6 This page left blank intentionally 12117/2009 Weld I Component Outage Summary SYSTEM: Chemical&Volume Control System (CV)Exelon-Byron Station Unit 1 B1R16 lSI Outage Report R-A Rl.l1 1 CVA3AA-2JW-06 lCVA3AA-2 13R-02 B9.40 VT-2 NRI Pipe-Elbow 13T-Ol 13T-02 aBS16-001 R-A Rl.ll lCVA3AA-2JW-07 lCVA3AA-2 13R-02 B9.40 VT-2 NRI Elbow-Pipe 13T-Ol 13T-02 aBS16-002 R-A Rl.l1 1 CVA3B-2JW-74 lCVA3B-2 13R-02 B9.40 VT-2 NRI Pipe-Elbow 13T-Ol 13T-02 aBS16-003 R-A Rl.ll lCVA3B-2JW-75 lCVA3B-2 13R-02 B9.40 VT-2 NRI Elbow-Pipe 13T-Ol 13T-02 aBS16-004 R-A Rl.ll lCVA3B-2JW-76 lCVA3B-2 13R-02 B9.40 VT-2 NRI Pipe-Elbow 13T-Ol 13T-02 aBS16-005 R-A Rl.11 lCVA3B-2JW-77 lCVA3B-2 13R-02 B9.40 VT-2 NRI Elbow-Pipe 13T-Ol 13T-02 aBS16-006 R-A Rl.ll 1 CVA3B-2JW-84 lCVA3B-2 13R-02 B9.40 VT-2 NRI Pipe-Elbow 13T-Ol 13T-02 aBS16-007 R-A Rl.l1 lCVA3B-2JW-85 lCVA3B-2 13R-02 B9.4O VT-2 NRI Elbow-Pipe 13T-Ol 13T-02 aBS16-008 R-A Rl.l1 1 CVASAA-2JW-04 lCVA5AA-2 13R-02 B9.40 VT-2 NRI Pipe-Elbow 13T-Ol 13T-02 aBS16-009 R-A Rl.l1 lCVASAA-2JW-05 lCVA5AA-2 13R-02 B9.4O VT-2 NRI Elbow-Pipe 13T-Ol 13T-02 aBS16-010 R-A Rl.11 lCVA6AA-2JW-04 1CVA6AA-2 13R-02 B9.4O VT-2 NRI Pipe-Elbow 13T-01 13T-02 OBS16-011.*.
..
__._---.----"-,-------->>--.->>-.-._.-,,-,,-
.._--1 12117/2009 Weld I Component Outage Summary SYSTEM: Chemical&Volume Control System (CV)Exelon_Byron Station Unit 1 B1R16 lSI Outage Report R-A R1.11 1 CVA6AA-2JW-05 1CVA6AA-2 t3R-02 B9.40 VT-2 NRt Elbow-Pipe 13T-01 13T-02 aBS16-012 R-A R1.11 1CVA7AA-2JW-08 1CVA7AA-2 t3R-02 B9.40 VT-2 NRI Pipe-Elbow 13T-01 13T-02 aBS16-013 R-A R1.11 1CVA7AA-2JW-09 1CVA7AA-2 13R-02 B9.40 VT-2 NRI Etbow-Pipe 13T-01 13T-02 aBS16-014 2 12/17/2009 Weld I Component Outage Summary SYSTEM: Feedwater System (FW)ExelonM Byron Station Unit 1 B1R16 lSI Outage Report R-A R1.11 1 FW03DC-16/C03 1FW03DC-16 13R-02 C5.51 100 UT NRI R1.18 Pipe-Pipe 13T-01 13T-02 aBS16-131 R-A R1.11 1 FW03DC-16/C030 1FW03DC-16 13R-02 C5.51 100 UT NRI R1.18 Pipe-Pipe 13T-01 13T-02 aBS16-132 R-A R1.11 1 FW03DC-16/C17 1FW03DC*16 13R*02 C5.51 100 UT NRI R1.18 Pipe-Elbow 13T-01 13T-02 aBS16-133 R-A R1.11 1 FW03DC-16/C18 1FW03DC-16 13R-02 C5.51 100 UT NRI R1.18 Elbow-Pipe 13T-01 13T-02 aBS16-134 R-A R1.11 1 FW03DD-16/C26.01 1FW03DD-16 13R-02 C5.51 100 UT GEaM R1.18 Pipe-Elbow 13T-01 13T-02 aBS16-128 10 Geometry 360 0 Intermittent.
3 12117/2009 Weld I Component Outage Summary SYSTEM: Main Steam System (MS)
Byron Station Unit 1 B1R16 lSI Outage Report R-A R1.20 1 MS01 BB-32.75/C04 1 MS01 BB-32.75 13R-02 C5.51 100 UT NRI Pipe-Tee 13T-01 13T-02 CBS16-138 R-A R1.20 1 MS01 BB-32.75/C05 1 MS01 BB-32.75 13R-02 C5.51 91 UT NRI Tee-Pipe 13T-01 13T-02 CBS16-139 reduced due to branch R-A R1.20 1 MS07 AB-28/C01 1 MS07AB-28 13R-02 C5.51 100 UT NRI Tee-Pipe 13T-01 13T-02 CBS16-140 4 12117/2009 Weld I Component Outage Summary SYSTEM: Reactor Coolant System (RC)Byron Station Unit 1 B1R16 lSI Outage Report R-A R1.15 1 RC-01-R/RPVS-A F-1 1RC-01-R 13R-02 85.10 100 UT NRI 815.90RPVNozzle Safe-End HL Loop C 13T-01 100 ET NRI 13T-02 08S16-183 Volumetric examination MRP-139 0 See WO#01141706.
R-A R1.15 1 RC-01-RlRPVS-C F-1 1 RC-01-R 13R-02 85.10 VT-2 NRI 815.95RPVNozzle Safe-End CL Loop 0 13T-01 13T-02 08S16-185 8are Metal exam per N-722 requirements.
See WO#01141708.
R-A R1.15 1 RC-01-RlRPVS-D F-1 1RC-01-R 13R-02 85.10 100 UT NRI 815.90RPVNozzle Safe-End HL Loop 0 13T-01 100 ET NRI 13T-02 08S16-186 Volumetric examination MRP-139 0 See WO#01141706.
R-A R1.15 1 RC-01-R/RPVS-E F-1 1RC-01-R 13R-02 85.10 100 UT NRI 815.90 RPV Nozzle Safe-End HL Loop A 13T-01 100 ET NRI 13T-02 08S16-187 Volumetric examination MRP-139 0 See WO#01141706.
R-A R1.15 1 RC-01-RlRPVS-H F-1 1RC-01-R 13R-02 85.10 100 UT NRI 815.90 RPV Nozzle Safe-End HL Loop 8 13T-01 100 ET NRI 13T-02 08S16-190 Volumetric examination MRP-139 0 See WO#01141706.
R-A R1.20 1 RC13AA-2IW-01 1 RC13AA-2 13R-02 89.40 VT-2 NRI SOL-Pipe 13T-01 13T-02 08S16-015 R-A R1.20 1 RC13AA-2IW-02.01 1RC13AA-2 13R-02 89.40 VT-2 NRI Pipe-Tee 13T-01 13T-02 08S16-016 R-A R1.20 1 RC13AA-2IW-03 1 RC13AA-2 13R-02 89.40 VT-2 NRI Tee Reducer 13T-01 13T-02 08S16-017 R-A R1.20 1 RC13AA-2/W-04 1 RC13AA-2 13R-02 89.40 VT-2 NRI Tee-Pipe 13T-01 13T-02 08S16-018 R-A R1.20 1 RC13AA-2IW-05 1 RC13AA-2 13R-02 89.40 VT-2 NRI Pipe-Valve 13T-01 13T-02 OBS16-019 5 12117/2009 Weld I Component Outage Summary SYSTEM: Reactor Coolant System (RC)Exelon-Byron Station Unit 1 B1R16 lSI Outage Report R-A R1.20 1RC13AB-2IW-01 1 RC13AB-2 13R-02 B9.40 VT-2 NRI SOL-Pipe 13T-01 13T-02 OBS16-020 R-A R1.20 1 RC13AB-2IW-09 1 RC13AB-2 13R-02 B9.40 VT-2 NRI Pipe-Valve 13T-01 13T-02 OBS16-021 R-A R1.20 1 RC13AC-2IW-01 1RC13AC-2 13R-02 B9.40 VT-2 NRI SOL-Pipe 13T-01 13T-02 OBS16-022 R-A R1.20 1 RC13AD-2IW-01 1RC13AD-2 13R-02 B9.40 VT-2 NRI SOL-Pipe 13T-01 13T-02 OBS R-A R1.11 1 RC14AA-2IW-02 1 RC14AA-2 13R-02 B9.40 VT-2 NRI Pipe-Elbow 13T-01 13T-02 OBS16-024 R-A R1.11 1 RC14AA-2IW-03 1 RC14AA-2 13R-02 B9.40 VT-2 NRI Elbow-Pipe 13T-01 13T-02 OBS16-025 R-A R1.11 1 RC14AA-2IW-03A 1 RC14AA-2 13R-02 B9.40 VT-2 NRI Pipe-Tee 13T-01 13T-02 OBS16-026 R-A R1.11 1 RC14AA-2IW-03B 1 RC14AA-2 13R-02 B9.40 VT-2 NRI Tee-Reducer 13T-01 13T-02 OBS16-027 R-A R1.11 1 RC14AA-2IW-03C 1 RC14AA-2 13R-02 B9.40 VT-2 NRI Tee-Pipe 13T-01 13T-02 OBS 16-028-----
R-A R1.11 1 RC14AA-2IW-04 1 RC14AA-2 13R-02 B9.40 VT-2 NRI Pipe-Elbow 13T-01 13T-02 OBS16-029 R-A RU1 1 RC14AA-2IW-05 1 RC14AA-2 13R-02 B9.40 VT-2 NRI Elbow-Pipe 13T-01 13T-02 OBS16-030 6 12117/2009 Weld I Component Outage Summary SYSTEM: Reactor Coolant System (RC)Byron Station Unit 1 B1R16 lSI Outage Report R-A R1.11 1 RC14AA-2JW-06 1 RC14AA-2 13R-02 B9.40 VT-2 NRI Pipe-Valve 13T-01 13T-02 aBS16-031 R-A R1.11 1 RC14AA-2JW-07 1 RC14AA-2 13R-02 B9.40 VT-2 NRI Valve-Pipe 13T-01 13T-02 aBS16-032 R-A R1.11 1 RC14AA-2JW-08 1 RC14AA-2 13R-02 B9.40 VT-2 NRI Pipe-Tee 13T-01 13T-02 aBS16-033 R-A R1.11 1 RC14AA-2JW-09 1 RC14AA-2/3R-02 B9.40 VT-2 NRI Tee-Reducer 13T-01 13T-02 aBS16-034 R-A R1.11 1 RC14AA-2JW-101 RC14AA-2 13R-02 B9.40 VT-2 NRI Reducer-Pipe 13T-01 13T-02 aBS16-035 R-A R1.11 1 RC14AA-2JW-11 1 RC14AA-2 13R-02 B9.40 VT-2 NRI Pipe-Valve 13T-01/3T-02 aBS16-036 R-A R1.11 1 RC14AA-2JW-12 1 RC14AA-2 13R-02 B9.40 VT-2 NRI Pipe-Coupling 13T-01 13T-02 aBS16-037 R-A R1.11 1 RC14AA-2JW-13 1 RC14AA-2 13R-02 B9.40 VT-2 NRI Coupling-Pipe 13T-01 13T-02 aBS16-038 R-A R1.11 1 RC14AB-2JW-07 1 RC14AB-2 13R-02 B9.40 VT-2 NRI Coupling-Pipe 13T-01 13T-02 aBS 16-039------.------
R-A R1.11 1 RC14AB-2JW-08 1 RC14AB-2 13R-02 B9.40 VT-2 NRI Pipe-Valve 13T-01 13T-02 aBS16-040 R-A R1.11 1 RC14AB-2JW-09 1 RC14AB-2 13R-02 89.40 VT-2 NRI Valve-Pipe 13T-01 13T-02 aBS16-041 7 12117/2009 Weld I Component Outage Summary SYSTEM: Reactor Coolant System (RC)Exelon..Byron Station Unit 1 B1 R16 lSI Outage Report R-A R1.11 1 RC14AB-2IW-101 RC14AB-2 13R-02 B9.40 VT-2 NRI Pipe-Tee 13T-01 13T-02 aBS16-042 R-A R1.11 1 RC14AB-2IW-11 1RC14AB-2 13R-02 B9.40 VT-2 NRI Tee-Reducer 13T-01 13T-02 aBS16-043 R-A R1.11 1 RC14AC-2IW-08 1 RC14AC-2 13R-02 B9.40 VT-2 NRI Pipe-Valve 13T-01 13T-02 aBS16-044 R-A R1.11 1 RC14AD-2IW-08 1 RC14AD-2 13R-02 B9.40 VT-2 NRI Pipe-Valve 13T-01 13T-02 aBS16-045 R-A R1.11 1 RC14AD-2IW-09 1 RC14AD-2 13R-02 B9.40 VT-2 NRI Valve-Pipe 13T-01 13T-02 aBS16-046 R-A R1.11 1 RC14AD-2IW-101 RC14AD-2 13R-02 B9.40 VT-2 NRI Pipe-Tee 13T-01 13T-02 aBS16-047 R-A R1.11 1 RC14AD-2IW-11 1 RC14AD-2 13R-02 B9.40 VT-2 NRI Tee-Reducer 13T-01 13T-02 aBS16-048 R-A R1.11 1 RC14AD-2IW-12 1RC14AD-2 13R-02 B9.40 VT-2 NRI Tee-Pipe 13T-01 13T-02 aBS16-049 R-A R1.11 1 RC14AD-2IW-13 1 RC14AD-2 13R-02 B9.40 VT-2 NRI Pipe-Valve 13T-01 13T-02 aBS16-050
.._---------
R-A R1.11 1 RC16AA-2IW-02 1 RC16AA-2 13R-02 B9.40 VT-2 NRI Pipe-Valve 13T-01 13T-02 aBS16-051 R-A R1.11 1 RC16AA-2IW-03 1 RC16AA-2 13R-02 B9.40 VT-2 NRI Valve-Pipe 13T-01 13T-02 aBS16-052 8 12117/2009 Weld I Component Outage Summary SYSTEM: Reactor Coolant System (RC)ExeIe;n_Byron Station Unit 1 B1R16 lSI Outage Report R-A Rl.ll 1 RC16AA-2IW-04 1 RC16AA-2 13R-02 B9.40 VT-2 NRI Pipe-Elbow 13T-Ol 13T-02 aBS16-053 R-A Rl.ll 1 RC16AA-2IW-05 1 RC16AA-2 13R-02 B9.40 VT-2 NRI Elbow-Pipe 13T-Ol 13T-02 aBS16-054 R-A R1.11 1RC16AA-2IW-06 1 RC16AA-2 13R-02 B9.40 VT-2 NRI Pipe-Elbow 13T-Ol 13T-02 aBS16-055 R-A Rl.20 1 RC16AA-2IW-07 1 RC16AA-2 13R-02 B9.40 VT-2 NRI Elbow-Pipe 13T-Ol 13T-02 aBS16-056 R-A R1.20 1 RC16AA-2IW-08 1 RC16AA-2 13R-02 B9.40 VT-2 NRI Pipe-SaL 13T-Ol 13T-02 aBS16-057 R-A Rl.ll 1 RC16AB-2IW-02 1 RC16AB-2 13R-02 B9.40 VT-2 NRI Pipe-Elbow 13T-Ol 13T-02 aBS16-058 R-A Rl.20 lRC22AA-l.5/W-Ol 1 RC22AA-l.5 13R-02 B9.40 VT-2 NRI Reducer-Coupling 13T-Ol 13T-02 aBS16-059 R-A Rl.20 1 RC22AA-l.5/W-02 1 RC22AA-l.5 13R-02 B9.40 VT-2 NRI Coupling-Pipe 13T-Ol 13T-02 aBS16-060 R-A Rl.20 1 RC22AA-l.5/W-03 1 RC22AA-l.5 13R-02 B9.40 VT-2 NRI Pipe-Elbow 13T-Ol 13T-02 aBS16-061 R-A Rl.20 1 RC22AA-l.5/W-04 1 RC22AA-l.5 13R-02 B9.40 VT-2 NRI Elbow-Pipe 13T-Ol 13T-02 aBS16-062 R-A Rl.20 1 RC22AA-l.5/W
-05 1 RC22AA-l.5 13R-02 B9.40 VT-2 NRI Pipe-Elbow 13T-Ol 13T-02 aBS16-063._--_..
,,_..
.._'"----_.,-,--,--
9 12117/2009 Weld I Component Outage Summary SYSTEM: Reactor Coolant System (RC)
Byron Station Unit 1 B1 R16 lSI Outage Report A-A A1.20 1 AC22AA-1.5/W-06 1 AC22AA-1.5 13A-02 B9.40 VT-2 NAI Elbow-Pipe 13T-01 13T-02 aBS16-064 A-A A1.20 1 AC22AA-1.5/W-07 1 AC22AA-1.5 13A-02 B9.40 VT-2 NAI Pipe-Elbow 13T-01 13T-02 aBS16-065 A-A A1.20 1 AC22AA-1.5/W
-08 1 AC22AA-1.5 13A-02 B9.40 VT-2 NAI Elbow-Pipe 13T-01 13T-02 aBS16-066 A-A A1.20 1 AC22AA-1.5/W-09 1 AC22AA-1.5 13A-02 B9.40 VT-2 NAI Pipe-Elbow 13T-01 13T-02 aBS16-067 A-A A1.20 1 AC22AA-1.5/W-10 1 AC22AA-1.5 13A-02 B9.40 VT-2 NAI Elbow-Pipe 13T-01 13T-02 aBS16-068 A-A A1.20 1 AC22AA-1.5/W-11 1 AC22AA-1.5 13A-02 B9.40 VT-2 NAI Pipe-Elbow 13T-01 13T-02 aBS 16*069 A-A A1.20 1AC22AA-1.5/W-12 1 AC22AA-1.5 13A-02 B9.40 VT-2 NAI Elbow-Pipe 13T-01 13T-02 aBS16-070 A-A A1.20 1 AC22AA-1.5/W-13.01 1 AC22AA-1.5 13A-02 B9.40 VT-2 NAI Pipe-Valve 13T-01 13T-02 aBS16-071 A-A A1.20 1 AC22AA-1.5/W-14.01 1 AC22AA-1.5 13R-02 B9.40 VT-2 NRI Valve'Pipe 13T-01 13T-02 aBS16-072 R-A R1.20 1 RC22AA-1.5/W-15.
01 1 RC22AA-1.5 13R-02 B9.40 VT-2 NRI Pipe-Elbow 13T-01 13T-02 aBS 16-073-R-A R1,20 1 RC22AA-15/W-16.01 1 RC22AA-1.5 13R-02 B9.40 VT-2 NRI Elbow-Pipe 13T-01 13T-02 aBS16-074 10 12117/2009 Weld I Component Outage Summary SYSTEM: Reactor Coolant System (RC)Exelon..Byron Station Unit 1 B1 R16 lSI Outage Report R-A Rl.20 1 RC22AA-l.5/W-17 1 RC22AA-l.5 13R-02 89.40 VT-2 NRI Pipe-Coupling 13T-Ol 13T-02 08S16-075 R-A Rl.20 1 RC22AA-l.5/W-18 1 RC22AA-l.5 13R-02 89.40 VT-2 NRI Coupling-Pipe 13T-Ol 13T-02 16-076 R-A Rl.20 1 RC22AA-l.5/W-19 1 RC22AA-l.5 13R-02 89.40 VT-2 NRI Pipe-Flange 13T-Ol 13T-02 08S16-077 R-A Rl.20 1 RC22AA-l.5/W-20 1 RC22AA-l.5 13R-02 89.40 VT-2 NRI Flange-Pipe 13T-Ol 13T-02 08S16-078 R-A Rl.20 1 RC22AA-l.5/W-21 1 RC22AA-l.5 13R-02 89.40 VT-2 NRI Pipe-Tee 13T-Ol 13T-02 08S16-079 R-A Rl.20 1 RC22AA-l.5/W-22 lRC22AA-l.5 13R-02 89.40 VT-2 NRI Tee-Reducer 13T-Ol 13T-02 08S16-080 R-A Rl.20 1 RC22AA-l.5/W-23 1 RC22AA-l.5 13R-02 89.40 VT-2 NRI Tee-Pipe 13T-Ol 13T-02 08S16-081 R-A Rl.20 1 RC22AA-l.5/W-24 1 RC22AA-l.5 13R-02 89.40 VT-2 NRI Pipe-Tee 13T-Ol 13T-02 08S16-082 R-A Rl.20 1 RC22AA-l.5/W-25 1 RC22AA-l.5 13R-02 89.40 VT-2 NRI Tee-Reducer 13T-Ol 13T-02 08S16-083 R-A Rl.20 1 RC22AA-l.5/W-26 1 RC22AA-l.5 13R-02 89.40 VT-2 NRI Tee-Pipe 13T-Ol 13T-02 08S16-084 R-A R1.20 1 RC22AA-l.5/W-27 1 RC22AA-l.5 13R-02 B9.40 VT-2 NRI Pipe-Valve 13T-Ol 13T-02 OBS16-085....
...,._-".......
,-._-_._..
.11 12117/2009 Weld I Component Outage Summary SYSTEM: Reactor Coolant System (RC)Exelon-Byron Station Unit 1 B1 R16 lSI Outage Report A-A A1.20 1 AC22AA-l.5/W-28 1 AC22AA-l.5 13A-02 B9.40 VT-2 NAI Valve-Pipe 13T-Ol 13T-02 aBS16-086 A-A Al.20 1 AC22AA-l.5/W-29 1 AC22AA-l.5 13R-02 B9.40 VT-2 NAI Pipe-Elbow 13T-Ol 13T-02 aBS16-087 A-A Al.20 1 AC22AA-l.5/W-30 1 AC22AA-1.5 13A-02 B9.40 VT-2 NAI Elbow-Pipe 13T-Ol 13T-02 aBS16-088 A-A Al.20 1 AC22AA-l.5/W-31 1 AC22AA-1.5 13A-02 B9.40 VT-2 NAI Pipe-Elbow 13T-Ol 13T-02 aBS16-089 A-A Al.20 1 AC22AA-l.5/W-32 lAC22AA-l.5 13A-02 B9.40 VT-2 NAI Elbow-Pipe 13T-Ol 13T-02 aBS16-090 A-A Al.20 1 AC22AA-l.5/W-33 lAC22AA-l.5 13A-02 B9.40 VT-2 NAI Pipe-WaL 13T-Ol 13T-02 aBS16-091 R-A Al.ll 1 AC28A-3/J02 1 AC28A-3 13A-02 B9.21 100 UT NAI Pipe-Elbow 13T-Ol 13T-02 aBS16-156 A-A Rl.l1 1 AC28A-3/J03 1 RC28A-3 13A-02 B9.21 100 UT NAI Elbow-Pipe 13T-Ol 13T-02 aBS16-157 A-A Rl.l1 1 AC28A-3/J04 1 AC28A-3 13R-02 B9.21 100 UT NRI Pipe-Elbow 13T-Ol 13T-02 aBS16-158 A-A R1.11 1 AC28A-3/J05 1 RC28A-3 13A-02 B9.21 100 UT NRI Elbow-Pipe 13T-Ol 13T-02 aBS16-159 N/A N/A 1 AC28A-3/Zone11 RC28A-3 B9.21 UT NRI Elbow*SaL VT-2 NRI aBS16-216
..
__________________.______.._....________......_.___.___12 12117/2009 Weld I Component Outage Summary SYSTEM: Reactor Coolant System (RC)elcn",............................
Byron Station Unit 1 B1 R16 lSI Outage Report N/A N/A 1 RC37A-31Zone 2 Elbow-SOL 1 RC37A*3 B9.21 UT VT-2 NRI NRI OBS 16*217 Volumetric and bare metal visual per MRP-146.13 12117/2009 Weld I Component Outage Summary SYSTEM: Residual Heat Removal System (RH)Byron Station Unit 1 B1 R16 lSI Outage Report R-A R1.20 1 RH01 CA-16/C03 1RH01CA-16 13R-02 C5.11 100 UT NRI Pipe-Elbow 13T-01 13T-02 aBS16-178 R-A R1.20 1 RH02AA-8/C34 1RH02AA-8 13R-02 C5.11 100 UT NRI Reducer-Nozzle 13T-01 13T-02 aBS16-179 C-C C3.10 1 RH-02-AB/RHES-01 1RH-02-AB 100 PT IND Support Skirt aBS16-182 16 rounded indications.
Acceptable per acceptance standards.
Ref.RIR#B1R16-PT-001.
R-A R1.20 1 RH02AB-8/C02 1RH02AB-8 13R-02 C5.11 100 UT NRI Elbow-Pipe 13T-01 13T-02 aBS16-180 R-A R1.20 1 RH03AB-8/C11 1RH03AB-8 13R-02 C5.11 100 UT NRt Pipe-Elbow 13T-01 13T-02 aBS16-181 14 12117/2009 Weld I Component Outage Summary SYSTEM: Reactor Pressure Vessel (RPV)ExeIe;n..Byron Station Unit 1 B1 R16 lSI Outage Report N/A B15.80 1RC*01*RlRPVBMI 1RC*01*R RPV Bottom Mounted Instruments aBS16-223 Bare Metal exam per N-722 requirements.
See Wa#01209679.
VT-2 NRI N/A B4.10 1 RC-01-RlRPV HEAD 1 RC*01-R PEN SURFACE RPV Head Penetrations VE NRt aBS16-224 Visual Examination per N-729-1 requirements, see wa 01215583-01.
15 12117/2009 Weld I Component Outage Summary SYSTEM: Reactor Coolant System (RY)Exelon_Byron Station Unit 1 B1R16 151 Outage Report R-A R1.11 1 RY01 B-6/J30 Elbow-Pipe 1 RY01B-6 13R-02 B9.11 13T-01 13T-02 100 UT NRI OBS16-160 R-A R1.11 1 RY01 B-6/J31 Pipe-Elbow 1 RY01B-6 13R-02 B9.11 13T-01 13T-02 100 UT NRI OBS16-161 N/A N/A 1 RY01C-41J01S 1 RY01C-4 Reducer-Safe End Overlay 13R-08 100 UT NRI OBS16-162 Reexamination per Appendix Q requirements.
N/A N/A1 RY-01-S/PN-01-F1S1 RY-01-S Surge Nozzle-Safe End Overlay 13R-08 UT NRI OBS16-143 Reexamination per Appendix Q and MRP-139 Category F requirements.
No Recordable Indications with angle beam scanning.98.6%Circumferential and 97.4%Axial coverage.N/AN/A 1 RY-01-S/PN-02-F2S 1RY-01-S 13R-08 100 UT NRI Spray Nozzle Safe-End Overlay OBS16-144 Reexamination per Appendix Q and MRP-139 Category F requirements.
N/A N/A 1 RY-01-S/PN-04-F4S 1RY-01-S 13R-08 100 UT NRI Relief Nozzle Safe-End Overlay OBS16-147 Reexamination per Appendix Q and MRP-139 Category F requirements.
Baseline overlay indications outside examination volume evaluated with no change noted.N/A N/A 1 RY-01-S/PN-05-F5S 1 RY-01-S Relief Nozzle Safe-End Overlay 13R-08 100 UT NRI OBS16-149 Reexamination per Appendix Q and MRP-139 Category F requirements.
N/A NIA1 RY-01-S/PN-06-F6S 1 RY-01-S Relief Nozzle Safe-End Overlay 13R-08 100 UT NRI OBS16-150 Reexamination per Appendix Q and MRP-139 Category F requirements.N/AN/A 1 RY02A-6/J01S 1 RY02A-6 Safe End-Elbow Overlay 13R-08 100 UT NRI OBS16-173 Reexamination per Appendix Q requirements.
R-A R1.20 1 RY02A-6/J02 Elbow-Pipe 1 RY02A-6 13R-02 B9.11 13T-01 13T-02 100 UT NRI OBS16-174 R-A R 1.20 1 RY02A-6/J04 Pipe-Tee 1 RY02A-6 13R-02 B9.11 13T-01 13T-02 100 UT NRI OBS16-175 16 12117/2009 Weld I Component Outage Summary SYSTEM: Reactor Coolant System (RY)Byron Station Unit 1 B1R16 lSI Outage ReportN/AN/A 1 RY03AA-6/J01S1 RY03AA-6 13R-08 100 UT NRI Safe End-Elbow Overlay OBS16-163 Reexam ination QN/AN/A 1 RY03AB-6/J01S1 RY03AB-6 13R-08 100 UT NRI Safe End-Elbow Overlay OBS16-165 Reexamination Q N/A N/A 1 RY03AC-6/J01S1 RY03AC-6 13R-08 UT NRI Safe End-Elbow Overlay OBS16-168 Reexamination per Appendix Q requirements.
100.0%Circumferential and 99.6%Axial coverage.N/A N/A 1 RY11A-14/J01AS 1 RY11A-14 13R-08 UT NRI Safe End-Pipe Overlay OBS16-151 Reexamination per Appendix Q requirements.
No Recordable Indications with angle beam scanning.99.3%Circumferential and 98.6%Axial coverage.R-A R1.11 1 RY18A-2!W-05A 1 RY18A-2 13R-02 B9.40 VT-2 NRI Valve-Pipe 13T-01 13T-02 OBS16-092 R-A R1.11 1 RY18A-2/W-06 1 RY18A-2 13R-02 B9.40 VT-2 NRI Pipe-Elbow 13T-01 13T-02 16-093 R-A R1.11 1 RY18A-2!W-07 1 RY18A-2 13R-02 B9.40 VT-2 NRI Elbow-Pipe 13T-01 13T-02 OBS16-094 R-A R1.11 1 RY18A-2!W-08 1 RY18A-2 13R-02 B9.40 VT-2 NRI Pipe-Elbow 13T-01 13T-02 OBS16-095 R*A R1.11 1 RY18A*2!W*09 1 RY18A*2 13R-02 B9.40 VT-2 NRI Elbow-Pipe 13T-01 13T-02 OBS 16*096 R-A R1.11 1 RY18A-2!W-10 1 RY18A-2 13R-02 B9.40 VT*2 NRI Pipe-WOL 13T-01 13T-02 OSS16-097 17 12117/2009 Weld I Component Outage Summary SYSTEM: Steam Generator (SG)Byron Station Unit 1 B1R16 lSI Outage Report C-AC1.301 RC-01-BAlSGW-02 1 RC-01-BA Secondary Shell-Tube Sheet 100 UT GEOM OBS16-194 0°45°and 60°Exams.Tube sheet 10 recorded.18 12117/2009 Weld I Component Outage Summary SYSTEM: Safety Injection System (SI)Byron Station Unit 1 B1R16 lSI Outage Report R-A R1.20 1 SI02A-8/C11 1S102A-8 13R-02 C5.11 100 UT NRI Pipe-Pipe 13T-01 13T-02 OBS16-208 R-A R1.20 1 SI05AB-8/C14 1S105AB-8 13R-02 C5.11 100 UT GEOM Tee-Elbow 13T-01 13T-02 OBS16-203 Root Geometry 360 0 Intermittent.
R-A R1.20 1 SI05AB-8/C15 1S105AB-8 13R-02 C5.11 100 UT NRI Elbow-Pipe 13T-01 13T-02 OBS16-204 R-A R1.201S 108B-4/C03 1S108B-4 13R-02 C5.21 100 UT GEOM Pipe-Elbow 13T-01 13T-02 OBS16-212 Root Geometry 360 0 Intermittent.
R-A R1.20 1 S108B-4/C04 1S108B-4 13R-02 C5.21 100 UT GEOM Elbow-Penetration 13T-01 13T-02 OBS16-213 Root Geometry 360 0 Intermittent.
R-A R1.20 1 S108B-4/C05 1S108B-4 13R-02 C5.21 100 UT GEOM Pipe-Elbow 13T-01 13T-02 OBS16-214 Root Geometry 360 0 Intermittent.
R-A R1.20 1 S108B-4/C06 1S108B-4 13R-02 C5.21 100 UT GEOM Elbow-Elbow 13T-01 13T-02 OBS16-215 Root Geometry 360 0 Intermittent.
R-A R1.11 1SI08GC-1.5/W-01 1 SI08GC-1.5 13R-02 B9.40 VT-2 NRI Reducer-Coupling 13T-01 13T-02 OBS16-098
..
R-A R1.11 1SI08GC-1.5/W-02 1 SI08GC-1.5 13R-02 B9.40 VT-2 NRI Coupling-Pipe 13T-01 13T-02 OBS16-099 R-A R1.11 1 SI08GC-1.5/W-03 1S108GC-15 13R-02 B9.40 VT-2 NRI Pipe-Elbow 13T-01 13T-02 OBS16-100
..__._---,-,,-,
.._"'-----,_._---_._----.-._-,--------,>>----_.-._._.,---,_._._---,--,.---------_._._._._".-----------
19 12117/2009 Weld I Component Outage Summary SYSTEM: Safety Injection System (SI)Exelon..Byron Station Unit 1 B1R16 lSI Outage Report R-A R1.11 1 SI08GC-1.5/W-04 1 SI08GC-1.5 13R-02 B9.40 VT-2 NRI Elbow-Pipe 13T-01 13T-02 aBS16-101 R-A R1.11 1 SI08GC-1.5/W-05 1SI08GC-1.5 13R-02 B9.40 VT-2 NRI Pipe-Reducer 13T-01 13T-02 aBS16-102 R-A R1.11 1 SI08HA-2IW-01 1S108HA-2 13R-02 B9.40 VT-2 NRI Reducer-Pipe 13T-01 13T-02 aBS16-103 R-A R1.11 1 SI08HA-2IW-02 1S108HA-2 13R-02 B9.40 VT-2 NRI Pipe-Flange 13T-01 13T-02 aBS16-104 R-A R1.11 1 SI08HA-2IW-03 1S108HA-2 13R-02 B9.40 VT-2 NRI Flange-Pipe 13T-01 13T-02 aBS16-105 R-A R1.11 1 SI08HA-2IW-04 1S108HA-2 13R-02 B9.40 VT-2 NRI Pipe-Reducer 13T-01 13T-02 aBS16-106 R-A R1.11 1SIOBJA-1.5/W-06 1 SIOBJA-1.5 13R-02 B9.40 VT-2 NRI Pipe-Valve 13T-01 13T-02 aBS16-107 R-A R1.11 1 SIOBJA-1.5/W-07 1 SI08JA-1.5 13R-02 B9.40 VT-2 NRI Valve-Pipe 13T-01 13T-02 aBS16-108 R-A R1.11 1SIOBJA-1.5/W-08 1 SIOBJA-1.5 13R-02 B9.40 VT-2 NRI Pipe-Coupling 13T-01 13T-02 aBS16-109 R-A R1.11 1 SI08JA-1.5/W-09 1 SIOBJA-1.5 13R-02 B9.40 VT-2 NRI Coupling-Pipe 13T-01 13T-02 aBS16-110 R-A R1.11 1SIOBJA-1.5/W-10 1 SIOBJA-1.5 13R-02 B9.40 VT-2 NRI Pipe-Flange 13T-01 13T-02 aBS 16-111___
_____,_,____""______
__*_____,,___*______________v,_,.,___*____¥____,__"___*________._,**_"",_,_"___Y___.v 20 12117/2009 Weld I Component Outage Summary SYSTEM: Safety Injection System (SI)Exelon'A Byron Station Unit 1 B1R16 lSI Outage Report R-A R1.11 1 SIOBJA-1.5/W-11 1 SIOBJA-1.5 13R-02 B9.40 VT-2 NRt Flange-Pipe 13T-01 13T-02 CBS16-112 R-A R1.11 1SIOBJA-1.5/W-12 1 SIOBJA-1.5 13R-02 B9.40 VT-2 NRt Pipe-Elbow 13T-01 13T-02 CBS16-113 R-A R1.11 1 SIOBJA-1.5/W-13 1 SIOBJA-1.5 13R-02 B9.40 VT-2 NRI Elbow-Pipe 13T-01 13T-02 CBS16-114 R-A R1.11 1 SIOBJA-1.5/W-14 1 SIOBJA-1.5 13R-02 B9.40 VT-2 NRI Pipe-Elbow 13T-01 13T-02 CBS16-115 R-A R1.11 1 SIOBJA-1.5/W-15 1 StOBJA-1.5 t3R-02 B9.40 VT-2 NRt Elbow-Pipe 13T-01 13T-02 CBS16-116 R-A R1.20 1 SI34A-81C01 1S134A-8 t3R-02 C5.11 100 UT NRI Tee-Pipe 13T-01 13T-02 CBS16-205 R-A R1.20 1 SI34A-8/C04 1S134A-8 13R-02 C5.11 100 UT NRI Elbow-Elbow 13T-01 13T-02 CBS16-206 R-A R1.20 1 SI34A-8/C05 1S134A-8 13R-02 C5.11 100 UT NRI Elbow-Pipe 13T-01 13T-02 CBS16-207 R-A R1.20 1SI82AA-121C09 1S182AA-12 13R-02 C5.11 100 UT NRI Pipe-Elbow 13T-01 13T-02 CBS16-211 R-A R1.20 1 SI82AB-121C09 1S182AB-12 13R-02 C5.11 100 UT NRt Elbow-Pipe 13T-01 13T-02 CBS16-209 21