ML081930790: Difference between revisions
StriderTol (talk | contribs) (Created page by program invented by StriderTol) |
StriderTol (talk | contribs) (Created page by program invented by StriderTol) |
||
| Line 1: | Line 1: | ||
# | {{Adams | ||
| number = ML081930790 | |||
| issue date = 07/11/2008 | |||
| title = 90-Day Inservice Inspection Report for Interval 3, Period 1, Outage 2 (B1R15) | |||
| author name = Hoots D M | |||
| author affiliation = Exelon Generation Co, LLC, Exelon Nuclear | |||
| addressee name = | |||
| addressee affiliation = NRC/Document Control Desk, NRC/NRR | |||
| docket = 05000454 | |||
| license number = NPF-037 | |||
| contact person = | |||
| case reference number = 1.10.0101, BYRON 2008-0067 | |||
| document type = Inservice/Preservice Inspection and Test Report, Letter | |||
| page count = 109 | |||
}} | |||
=Text= | |||
{{#Wiki_filter:Exelon Genernflon Company, L-C www.exeloneorp.co m Rvron Station 4450 North Ger=n,an Church Road Byron, IL 61010-9794 July 11, 2008 LTR: BYRON 2008-0067 FILE: 1.10.0101 United States Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Respectfully, Byron Station, Unit 1 Facility Operating License No. NPF-37 NRC Docket No, STNSO-.454 | |||
==SUBJECT:== | |||
Byron Station Unit 1 90-Day Inservice Inspection Report for Interval 3, Period 1, Outage 2 (BIR15) The subject 90-Day Inservice Inspection Report for the Byron Station Unit 1, Refueling Outage Fifteen (BiR15) 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 1 Spring 2008 refueling outage. If there are any questions regarding this matter, please contact W. Grundmann, Regulatory Assurance Manager, at (815)-406-2800. vid M. Hoots Site Vice President Byron Generating Station DMH/RGM/TLH/jeh Attachment | |||
: BlR15 Inservice Inspection Summary Report - Spring 2008 outage Exelon. Nuclear BYRON Exelon.-UNIT 1 Nuclear B1R15 Spring 2008 Outage INSERVICE INSPECTION | |||
==SUMMARY== | |||
REPORT For Inspection Activities from October 16, 2006 to April 14, 2008 Commercial Service Date September 16, 1985 Document Completion Date July 9, 2008 Exelon Generation Company (EGC, LLC) 4300 Winfield Rd Warrenville, IL 60555 Byron Nuclear Power Station 4450 North German Church Rd. Byron, I L 61010 BYRON UNIT 1 B1R15 Exelonrim Nuclear INSERVICE INSPECTION | |||
==SUMMARY== | |||
REPORT SECTION SECTION DESCRIPTION PAGES I [Cov er Page ii Table of Contents 1.0 Report introduction TOTAL PAGES IN REPORT] 253 ISI - Weld / Component Listing 16 _ _ ISI- Bolts, Pumps, and Valves Listing 3 Examination PSI - We ld / Component Listing 1 2.0 Summary PSI - Bolts, Pumps, and Valves Listing _ _ 2 Tables ISI - Pressure Tests _ 9 ISI - Component Supports 10 _ ISI - Snubbers 6 3.0 - Status of Examination Completion for the Program Plan 4.0 Form NIS-1: Preservice and Inservice Examinations 46 5.0 Form NIS-2: Repairs/ Modifications 145 | |||
==1.0 INTRODUCTION== | |||
BYRON STATION UNIT 1 REFUELING OUTAGE 15 INSERVICE INSPECTION REPORT 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 October 16, 2006 through April 14, 2008. The majority of these inspections were performed during the fifteenth refueling outage (B1 R15) from March 23 through April 14, 2008. The examinations were performed in compliance with the rules and regulations of ASME Section XI, Division 1, Rules for Inservice Inspection of Nuclear Power Plant Components, (applicable edition and addenda), pursuant to the requirements of 10 CFR 50.55a, Codes and Standards. 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. See 7.0 in this section for a listing of referenced documents. The Nondestructive Examination (NDE) Inservice Inspection (ISI) Program Plan for Class 1, 2, and 3 components was developed in accordance with the requirements and intent of Section XI Subsections IWA, 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 ISI inspections were required. The Byron Station Unit 1 augmented ISI examination requirements include: a) Class 1 pressure boundary for leakage at nominal operating pressure, in accordance with NRC Generic Letter 88-05, Boric Acid Corrosion of Carbon Steel Reactor Pressure Boundary Components in PWR Plants; b) Class 2 and 3 pressure boundary for leakage at nominal operating pressure, in accordance with NUREG 0737, Clarification of TMI Action Plan Requirements c) Examination of RCP Flywheels in accordance with Regulatory Guide 1.14. 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. 1.1 Identification of Examination Requirements The Section 7.0 of the ISI Program Plan contains the examination program tables. These tables are presented in a tabular format consistent with the tables found in Subsections IWB, IWC, IWD, 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 Section 1.0 Page 1 of 5 of Subsection IWA, IWB, IWC, IWD, IWE, IWF, and IWL of Section XI of the ASME Code. For Class 1, 2, and certain non-class piping 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. 1.2 Identification of Exem pted Components BYRON STATION UNIT 1 REFUELING OUTAGE 15 INSERVICE INSPECTION REPORT 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 IWD-1200, Components Exempt from Examination, and Tables IWB-2500-1, IWC-2500-1, and IWD-2500-1, are identified in the NDE 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 of RI-ISI, welds evaluated as Risk Category 6 or 7 are not required to be subject to examination. 1.3 Implementation of the ISI Proqra m 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 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/ASNT CP-189, 1995 Edition and ASNT SNT-TC-1 A, 1984 Edition. Certified personnel performed and evaluated all NDE. Personnel were certified to the requirements of the ASNT SNT-TC-1 A, 1984 Edition. Additionally, ultrasonic examiners were certified in accordance with ANSI/ASNT CP-189, 1995 Revision. The NDE procedures were developed and certified in conformance with ASME Section V and XI as applicable. All ISI NDE, including evaluation of flaw indications, were performed in accordance with the requirements stipulated under Section XI, Subarticle IWA-2200 Examination Methods. 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. Section 1.0 Page 2 of 5 | |||
===1.4 Significant=== | |||
Section XI Activities Du rinQB1 R15 BYRON STATION UNIT 1 REFUELING OUTAGE 15 INSERVICE INSPECTION REPORT During the refueling outage, the Alloy 600 reactor vessel safe-end welds were visually examined for evidence of leakage per the requirements specified in EPRI MRP-139. 1.5 ASME Section XI Code Cases The following code case is incorporated into the current Byron Station ISI Program and were utilized during the 15"' fuel cycle. N-566-2 Corrective Action for Leakage Identified at Bolted Connections. The following code case is used for the implementation of the risk-informed program as described in relief request 13R-02. N-578-1 Risk-Informed Requirements for Class 1, 2, or 3 Piping, Method B. 1.6 Witness and Verification of Examination The inservice inspections were witnessed and/or verified by the Authorized Nuclear Inservice Inspectors (ANTI): 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. 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 Preservice Inspection - Weld / Component Listing Preservice Inspection - Bolts, Pumps, and Valves Listing " System Pressure Test Summaries " Component Support Examination Summary " Component Snubber Test Summary 3.0 UNIT 1 EXAMINATION COMPLETION STATUS A summary table of the examination status of Class 1, 2, and 3 components is contained in Section 3.0. Section 1.0 Page 3 of 5 4.0 FORM NIS-1 DATA SHEETS BYRON STATION UNIT 1 REFUELING OUTAGE 15 INSERVICE INSPECTION REPORT ASME Form NIS-1, Owners Report for Inservice Inspections, were filed during the cycle for Unit 1. See Section 4.0 for the reports. 5.0 FORM NIS-2 DATA SHEETS ASME Form NIS-2, Owners Report for Repairs or Replacements, were filed during the cycle for Unit 1. See Section 5.0 for the reports. 6.0 CONTAINMENT ISI PROGRAM No reportable conditions were identified for Class CC and Class MC components during this fuel cycle. 7.0 REFERENCED DOCUMENTS 7.1 Code of Federal Regulations, Title 10 Energy Part 50, Domestic Licensing of Production and Utilization Facilities 50.55a, Codes and Standards | |||
===7.2 American=== | |||
Society of Mechanical Engineers (ASME) 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. 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 | |||
===7.4 American=== | |||
Society for Nondestructive Testing ASNT Recommended Practice No. SNT-TC-1 A, 1984 Edition, Personnel Qualification and Certification in Nondestructive Testing 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. Section 1.0 Page 4 of 5 | |||
===7.6 Electric_=== | |||
Power Research Institute BYRON STATION UNIT 1 REFUELING OUTAGE 15 INSERVICE INSPECTION REPORT Material Reliability Program Primary System Piping Butt Weld Inspection and Evaluation Guideline (MRP-139) | |||
July 14, 2005. Topical Report TR112657 Revision B-A, Revised Risk-Informed Inservice Inspection Procedure, December 1999. Section 1.0 Page 5 of 5 7/812008 Weld / Component Outage Summary SYSTEM: Chemical & Volume Control System (CV) 1;;=ct;,nI c,'I I C{xie Aclua! Exelon- Byron ~Station Unit 1 BI R15 ISI Outage Report R-A A1.11 1CVA3AA-2/W-O6 1CVA3AA-2 13R-02 139.40 VT-2 NRI Pipe - Elbow 13T-01 13T-02 OBS 15-001 R-A R1.11 1CVA3AA-2/W-07 1CVA3AA-2 13R-02 89.40 VT-2 NRI Elbow - Pipe 13T-01 13T-02 OBS 15-002 R-A R1.11 1CVA3B-2/W-74 1CVA3B-2 13R-02 89.40 VT-2 NRI Pipe - Elbow 13T-01 13T-02 OBS 15-003 R-A RIA1 1CVA3B-21W-75 1CVA3B-2 13R-02 89.40 VT-2 NRI Elbow - Pipe 13T-01 13T-02 OBS 15-004 R-A 81,11 1 CVA3B-2/W-76 1 CVA38-2 13R-02 139.40 VT-2 NRI Pipe - Elbow 13T-01 13T-02 OBS 15-005 R-A R1.11 1CVA3B-2M-77 1CVA3B-2 13R-02 139.40 VT-2 NRI Elbow - Pipe 13T-01 13T-02 OBS 15-006 R-A R1.11 1CVA3B-2/W-84 1CVA38-2 13R-02 139.40 VT-2 NRI Pipe - Elbow 13T-01 13T-02 OBS 15-007 R-A 81.11 1CVA3B-2/W-85 1CVA3B-2 13R-02 139.40 VT-2 NRI Elbow - Pipe 13T-01 13T-02 OBS 15-008 R-A R1.11 1CVA5AA-2/W-04 1CVA5AA-2 138-02 139.40 VT-2 NRI Pipe - Elbow 13T-01 13T-02 OBS 15-009 R-A R1.11 1CVASAA-2/W-05 1CVA5AA-2 13R-02 89.40 VT-2 NRI Elbow - Pipe 13T-01 13T-02 OBS 15-010 R-A R1.11 1CVA6AA-2/W-04 1CVA6AA-2 13R-02 89.40 VT-2 NRI Pipe - Elbow 13T-01 13T-02 OBS 15-011 7,8/2008 Weld / Component Outage Summary SYSTEM: Chemical & Volume Control System (CV) F ,.;., .. ? 3 f odP Actual t~c" p"."+art re°tip:. _.,~ t4o, - Over~lge Exam &elejn- Byron "Station Unit 1 B1 R15 ISI Outage Report R-A R1.11 OBS 15-012 ICVA6AA-2IW-05 Elbow - Pipe 1CVA6AA-2 13R-02 139.40 13T-01 13T-02 VT-2 NRI R-A R1.11 1CVA7AA-21W-08 1CVA7AA-2 13R-02 89.40 VT-2 NRI Pipe - Elbow 13T-01 13T-02 OBS 15-013 R-A R1.11 1CVA7AA-2/W-09 1CVA7AA-2 13R-02 139.40 VT-2 NRI Elbow - Pipe 13T-01 13T-02 OBS 15-014 7,812008 Weld / Component Outage Summary SYSTEM: Feedwater System (FW) Cr-repo: " g:~2 , De"'c"Ipt | |||
";n Rescan of B1R14 indication per 18 00756048. R-A R1.11 1FW87CA-61C08A 1FW87CA-6 13R-02 C5.51 UT IND 81.18 Pipe - SOL 13T-01 13T-02 _ByronStation Unit 1 B1 R15 ISI Outage Report P ,;,lr,? r~cf,-ic ,.Ii ;'~x , e :~ctu31 r?0" ga(T:as Ne'ces r0v"" ro-i'Ae Exam Exelein-7/8/2008 Weld / Component Outage Summary SYSTEM: Reactor Coolant System (RC) on x Ccr,~t~u;>n4 t. tiaarnut~~n NA RG1.14 1RC-01-PA/FLYWHEEL RCP Flywheel OBS 15-153 1) 5/32" LI and 2) 1/16' AI. Acceptable. Ref: R-A 81.15 1RC-01-R/RPVS-A F-1 RPV Nozzle Safe-End HL OBS 15-155 Bare-Metal examination per MRP-139 requir R-A 141.15 1 RC-01-R/RPVS-D F-1 RPV Nozzle Safe-End HL OBS 15-156 B are-Metal examination per MRP-139 requ ir R-A 141.15 1RC-01-R/RPVS-E F-1 RPV Nozzle Safe-End HL OBS 15-157 Bare-Metal examination p erMR P-139 requir OBS 15-158 Bare-Metal examination per MRP-139 requir R-A 147.15 1RC-01-R/RPVS-H F-1 RPV Nozzle Safe-End HL R-A 141.20 1 RC13AA-2/W-01 SOL - Pipe OBS 15-015 &elejn- Byron --~ Station Unit 1 B1R15 ISI Outage Report R-A 81.20 1 RC13AA-2/W-02 | |||
.01 Pipe - Tee OBS 15-016 R-A 141.20 1AC13AA-2/W-03 Tee - Reducer OBS 15-017 R-A 141.20 1 RC13AA-2/W-04 Tee - Pipe OBS 15-018 R-A 141.20 1 RC13AA-2M-05 Pipe - Valve OBS 15-019 1RC-01-PA PT IND AIR 2008-237. - _ 1RC-01-R 138-02 85.10 BMV NRI Loop C 13T-01 ments. 13T-02 1 RC-01-R 1314-02 B5.10 BMV NRI Loop D 13T-01 ments. 13T-02 1RC-01-R 1314-02 85.10 BMV NRI Loop A 13T-01 ments. 13T-02 1RC-01-R 1314-02 B5.10 BMV NRI oop B 13T-01 ments. 13T-02 1 RC13AA-2 1314-02 B9.40 VT-2 NRI 13T-01 13T-02 1 RC13AA-2 1314-02 B9.40 VT-2 NRI 13T-01 13T-02 1RC13AA-2 1314-02 B9.40 VT-2 NRI 13T-01 13T-02 1 RC13AA-2 1314-02 B9.40 VT-2 NRI 13T-01 13T-02 1 RC13AA-2 1314-02 89.40 VT-2 NRI 13T-01 13T-02 7,8/2008 Weld l Component Outage Summary SYSTEM: Reactor Coolant System (RC) OBS 15-030 1,1"'1+"_ NUf"aDer Exel6n- Byron -Station Unit 1 B1 1415 ISI Outage Report ,,Gs? Arf,Ug; R P4tti~$ Exert? R-A 141.20 1 RC13AB-2/W-01 1 RC13AB-2 1314-02 89.40 VT-2 NRI SOL - Pipe 137-01 137-02 OBS 15-020 R-A 81.20 1RC13AB-2/W-09 1RC13AB-2 1314-02 139.40 VT-2 NRI Pipe - Valve 137-01 137-02 OBS 15-021 R-A 141.20 1RC13AC-2/W-01 1RC13AC-2 1314-02 89.40 VT-2 NRI SOL - Pipe 137-01 137-02 OBS 15-022 R-A 141.20 1 RC13AD-2/W-01 1 RC13AD-2 1314-02 89.40 VT-2 NRI SOL - Pipe 137-01 137-02 OBS 15-023 R-A 141.11 1 RC14AA-2/W-02 1 RC14AA-2 1314-02 139.40 VT-2 NRI Pipe - Elbow 137-01 137-02 OBS 15-024 R-A 141.11 1RC14AA-2/W-03 1RC14AA-2 138-02 139.40 VT-2 NRI Elbow - Pipe 137-01 137-02 OBS 15-025 R-A 141.11 1RC14AA-2/W-03A 1RC14AA-2 1314-02 139.40 VT-2 NRI Pipe - Tee 137-01 137-02 OBS 15-026 R-A 141.11 1 RC14AA-2/W-0313 1 RC14AA-2 1314-02 89.40 VT-2 NRI Tee - Reducer 137-01 137-02 OBS 15-027 R-A 141.11 1RC14AA-2JW-03C 1RC14AA-2 1314-02 139.40 VT-2 NRI Tee - Pipe 137-01 137-02 OBS 15-028 R-A 81.11 1 RC14AA-2/W-04 1 RC14AA-2 1314-02 139.40 VT-2 NRI Pipe - Elbow 137-01 137-02 OBS 15-029 R-A 141.11 1 RC14AA-2IW-05 1 RC14AA-2 1314-02 139.40 VT-2 NRI Elbow - Pipe 137-01 137-02 7/8/2008 Weld / Component Outage Summary SYSTEM: Reactor Coolant System (RC) <;r~,p~ : " rnt !iQ N::1 , 11 '11)0r P,y'ie! 1-t, Code At;l*ai r":ot;::n , iotes cxvf~ratle Exam &elejn- Byron Station Unit 1 B1 R15 ISI Outage Report R-A R1.11 1 RC14AA-2/W-06 1 RC14AA-2 13R-02 139.40 VT-2 NRI Pipe - Valve 137-01 137-02 OBS 15-031 R-A RI A 1 1 RC14AA-2/W-07 1 RC14AA-2 13R-02 89.40 VT-2 NRI Valve - Pipe 137-01 137-02 OBS 15-032 R-A R1.11 1 RC14AA-2/W-08 1 RC14AA-2 13R-02 139.40 VT-2 NRI Pipe - Tee 137-01 137-02 OBS 15-033 R-A R1.11 1 RC14AA-2/W-09 1 RC14AA-2 13R-02 139.40 VT-2 NRI Tee - Reducer 137-01 137-02 OBS 15-034 R-A R1.11 1RC14AA-2/W-10 1RC14AA-2 13R-02 139.40 VT-2 NRI Reducer - Pipe 137-01 137-02 OBS 15-035 R-A R1.11 1 RC14AA-2/W-11 1 RC14AA-2 13R-02 139.40 VT-2 NRI Pipe - Valve 137-01 137-02 OBS 15-036 R-A R1.11 1 RC14AA-2/W-12 1 RC14AA-2 13R-02 139.40 VT-2 NRI Pipe - Coupling 137-01 137-02 OBS 15-037 R-A R1.11 IRC14AA-2/W-13 1RC14AA-2 13R-02 89.40 VT-2 NRI Coupling - Pipe 137-01 137-02 OBS 15-038 R-A R1.11 1RC14AB-2/W-07 1RC14AB-2 13R-02 89.40 VT-2 NRI Coupling - Pipe 137-01 137-02 OBS 15-039 R-A R1.11 1RC14AB-2/W-08 1RC14AB-2 13R-02 139.40 VT-2 NRI Pipe - Valve 137-01 137-02 OBS 15-040 R-A R1.11 1 RC14AB-2/W-09 1 RC14AB-2 13R-02 89.40 VT-2 NRI Valve - Pipe 137-01 137-02 OBS 15-041 7,8/2008 Weld / Component Outage Summary SYSTEM: Reactor Coolant System (RC) 6celein_ __ Byron Station Unit 1 B1R15 ISI Outage Report R-A 81.11 1 RC14AB-2/W-10 1 RC14AB-2 13R-02 139.40 VT-2 NRI Pipe - Tee 137-01 137-02 OBS 15-042 R-A R1.11 1RC14AB-2JW-11 1RC14AB-2 13R-02 139.40 VT-2 NRI Tee - Reducer 137-01 137-02 OBS 15-043 R-A R1.11 1 RC14AC-2/W-08 1 RC14AC-2 13R-02 89.40 VT-2 NRI Pipe - Valve 137-01 137-02 OBS 15-044 R-A 81.11 1RC14AD-2fW-08 1RC14AD-2 13R-02 139.40 VT-2 NRI Pipe - Valve 137-01 137-02 OBS 15-045 R-A R1.11 1 RC14AD-2/W-09 1 RC14AD-2 13R-02 139.40 VT-2 NRI Valve - Pipe 137-01 137-02 OBS 15-046 R-A 81.11 1 RC14AD-2IW-10 1 RC14AD-2 13R-02 139.40 VT-2 NRI Pipe - Tee 137-01 137-02 OBS 15-047 R-A R1.11 1 RC14AD-2/W-11 1 RC14AD-2 13R-02 139.40 VT-2 NRI Tee - Reducer 137-01 137-02 OBS 15-048 R-A R1.11 1RC14AD-2JW-12 1RC14AD-2 13R-02 89.40 VT-2 NRI Tee - Pipe 137-01 137-02 OBS 15-049 R-A R1.11 1RC14AD-21W-13 1RC14AD-2 13R-02 89.40 VT-2 NRI Pipe - Valve 137-01 137-02 OBS 15-050 R-A R1.11 1RC16AA-2/W-02 1RC16AA-2 13R-02 89.40 VT-2 NRI Pipe - Valve 137-01 137-02 OBS 15-051 R-A R1.11 1 RC16AA-2IW-03 1 RC16AA-2 138-02 139.40 VT-2 NRI Valve - Pipe 137-01 137-02 OBS 15-052 7,8/2008 Weld / Component Outage Summary SYSTEM: Reactor Coolant System (RC) bcelein_ Byron Station Unit 1 B1R15 ISI Outage Report !t t' . .,..^F+.S :r?..;.p A,c;2li 1t. F$e c;:.:!2:a tuf-M '''14" , ';!L'S R-A R1.11 1RC16AA-2/W-04 1RC16AA-2 13R-02 139.40 VT-2 NRI Pipe - Elbow 13T-01 13T-02 OBS 15-0 53 R-A R1.11 1 RC16AA-2/W-05 1 RC16AA-2 13R-02 139.40 VT-2 NRI Elbow - Pipe 13T-01 13T-02 OBS 15-054 R-A R1.11 1 RC16AA-2/W-06 1 RC16AA-2 13R-02 139.40 VT-2 NRI Pipe - Elbow 13T-01 13T-02 O BS 15-0 55 R-A R1.20 1RC16AA-2/W-07 1RC16AA-2 13R-02 89.40 VT-2 NRI Elbow - Pipe 13T-01 13T-02 OBS 15-056 R-A R1.20 1RC16AA-2/W-08 1RC16AA-2 13R-02 139.40 VT-2 NRI Pipe - SOL 13T-01 13T-02 OBS 15-057 R-A R1.11 1 RC16AB-2/W-02 1 RC16AB-2 13R-02 89.40 VT-2 NRI Pipe - Elbow 13T-01 13T-02 OBS 15-058 R-A 81.20 1 RC22AA-1.5/W-01 1 RC22AA-1.5 13R-02 139.40 VT-2 NRI Reducer - Coupling 13T-01 13T-02 OBS 15-059 R-A R1.20 1 RC22AA-1.5/W-02 1 RC22AA-1.5 13R-02 139.40 VT-2 NRI Coupling - Pipe 13T-01 13T-02 OBS 15-060 R-A R1.20 1RC22AA-1.5/W-03 IRC22AA-1.5 13R-02 139.40 VT-2 NRI Pipe - Elbow 13T-01 13T-02 OBS 15-061 R-A R1.20 1 RC22AA-1.5/W-04 1 RC22AA-1.5 13R-02 139.40 VT-2 NRI Elbow - Pipe 13T-01 13T-02 OBS 15-062 R-A R1.20 1 RC22AA-1.5/W-05 1 RC22AA-1.5 13R-02 89.40 VT-2 NRI Pipe - Elbow 13T-01 13T-02 OBS 15-063 7,11/2008 Weld / Component Outage Summary SYSTEM: Reactor Coolant System (RC) ~": r~:e. :~1~ors Exelein_ Byron W Station Unit t B1 R16 ISI Outage Report cxAe Ar , ,:~al He ~,,uIt; R-A R1.20 1 RC22AA-1.51W-06 1 RC22AA-1.5 13R-02 139.40 VT-2 NRI Elbow - Pipe 13T-01 13T-02 OBS 15-064 R-A R1.20 1 RC22AA-1.51W-07 1 RC22AA-1.5 13R-02 89.40 VT-2 NRI Pipe - Elbow 13T-01 13T-02 OBS 15-065 R-A R1.20 1 RC22AA-1.5/W-08 1 RC22AA-1.5 138-02 139.40 VT-2 NRI Elbow - Pipe 13T-01 13T-02 OB S 15-0 66 R-A 81.20 1 RC22AA-1.5PN-09 1 RC22AA-1.5 13R-02 139.40 VT-2 NRI Pipe - Elbow 13T-01 13T-02 OBS 15-067 R-A Rt20 1RC22AA-1.5/W-10 1RC22AA-1.5 13R-02 139.40 VT-2 NRI Elbow - Pipe 13T-01 13T-02 OBS 15-068 R-A Rt20 1 RC22AA-1.5/W-11 1 RC22AA-1.5 13R-02 89.40 VT-2 NRI Pipe - Elbow 13T-01 13T-02 OBS 15-069 R-A R1.20 1RC22AA-1.5/W-12 1RC22AA-1.5 13R-02 89.40 VT-2 NRI Elbow - Pipe 13T-01 13T-02 OBS 15-070 8-A R1.20 1 RC22AA-1.5/W-13.01 1 RC22AA-1.5 13R-02 139.40 VT-2 NRI Pipe - Valve I3T-01 13T-02 OBS 15-071 R-A R1.20 1 RC22AA-1.5/W-14.01 1 RC22AA-1.5 13R-02 139.40 VT-2 NRI Valve - Pipe 13T-01 13T-02 OBS 15-072 R-A R1.20 IRC22AA-1.5/W-15.01 1RC22AA-1.5 13R-02 139.40 VT-2 NRI Pipe - Elbow 13T-01 13T-02 OBS 15-073 R-A R1.20 1 RC22AA-1.5/W-16.01 1 RC22AA-1.5 13R-02 139.40 VT-2 NRI Elbow - Pipe 13T-01 13T-02 OBS 15-074 7/812008 Weld / Component Outage Summary SYSTEM: Reactor Coolant System (RC) C=at. (~aolr+rE , rw Exelein- Byron ~Station Unit 1 B1R15 ISI Outage Report OBS 15-085 10 R-A 131.20 1 RC22AA-1.5/W-17 1 RC22AA-1.5 1313-02 139.40 VT-2 NRI Pipe - Coupling 137-01 137-02 O BS 15-0 75 R-A 131.20 1RC22AA-1.5/W-18 1RC22AA-1.5 1313-02 89.40 VT-2 NRI Coupling - Pipe 137-01 137-02 OBS 15-076 R-A 131.20 1 RC22AA-1.5/W-19 1 RC22AA-1.5 1313-02 139.40 VT-2 NRI Pipe - Flange 137-01 137-02 OB S 15-077 R-A 131.20 1 RC22AA-1.5/W-20 1 RC22AA-1.5 1313-02 139.40 VT-2 NRI Flange - Pipe 137-01 137-02 OBS 15-078 R-A 131.20 1 RC22AA-1.5/W-21 1 RC22AA-1.5 1313-02 139.40 VT-2 NRI Pipe - Tee 137-01 137-02 OBS 15-079 R-A 131.20 1 RC22AA-1.5/W-22 1 RC22AA-1.5 1313-02 139.40 VT-2 NRI Tee - Reducer 137-01 137-02 OBS 15-080 R-A 131.20 1 RC22AA-1.5/W-23 1 RC22AA-1.5 138-02 139.40 VT-2 NRI Tee - Pipe 137-01 137-02 OBS 15-081 R-A 131.20 1 RC22AA-1.5/W-24 1 RC22AA-1.5 1313-02 89.40 VT-2 NRI Pipe - Tee 137-01 137-02 OBS 15-082 R-A 131.20 1 RC22AA-1.5/W-25 1 RC22AA-1.5 1313-02 139.40 VT-2 NRI Tee - Reducer 137-01 137-02 OBS 15-083 R-A 131.20 1 RC22AA-1.5/W-26 1 RC22AA-1.5 1313-02 89.40 VT-2 NRI Tee - Pipe 137-01 137-02 OBS 15-084 R-A 131.20 1 RC22AA-1.5/W-27 1 RC22AA-1.5 1313-02 139.40 VT-2 NRI Pipe - Valve 137-01 137-02 7,812008 Weld / Component Outage Summary SYSTEM: Reactor Coolant System (RC) eqj{',,18 N,+t"'S &elejn- Byron __Station Unit 1 131 R15 ISI Outage Report OBS 15-091 R-A 111.20 1 RC22AA-1.5/W-28 1 RC22AA-1.5 1311-02 139.40 VT-2 NRI Valve - Pipe 13T-01 13T-02 OBS 15-086 R-A 81.20 1 RC22AA-1.5/W-29 1 RC22AA-1.5 1311-02 139.40 VT-2 NRI Pipe - Elbow 13T-01 13T-02 OBS 15-087 R-A 111.20 1 RC22AA-1.5/W-30 1 RC22AA-1.5 138-02 139.40 VT-2 NRI Elbow - Pipe 13T-01 13T-02 OBS 15-088 R-A 111.20 1RC22AA-1.5/W-31 1RC22AA-1 | |||
.5 1311-02 139.40 VT-2 NRI Pipe - Elbow 13T-01 13T-02 OBS 15-089 R-A 111.20 1 RC22AA-1.5/W-32 1 RC22AA-1.5 1311-02 139.40 VT-2 NRI Elbow - Pipe 13T-01 13T-02 OBS 15-090 R-A 111.20 1 RC22AA-1.5/W-33 1 RC22AA-1.5 1311-02 B9.40 VT-2 NRI Pipe - WOL 13T-01 13T-02 7/8/2008 Weld / Component Outage Summary SYSTEM: Reactor Pressure Vessel (RPV) Fw:xf C, ;,de Arl wi ) Xquys VT-3 RI OBS 15-144 IR 00757175 for foreign m aterial on flange surface. All other conditions NRI. Exelon_ Byron Station Unit t B1R15 ISI Outage Report Pj l .'W's x I f ,.1 via L qa_ ~ c 3t bswov= cv" ,:~ws B-N-1 813.10 IRC-01-R/RPV 1 RC-01 -R INTERIOR RPV Interior Surfaces 7,8/2008 Weld / Component Outage Summary SYSTEM: Reactor Coolant System (RY) Exelon- Byron ~Station Unit 1 B1 R15 ISI Outage Report ^,ra;~~at .f19 !', ui,n OBS 15-097 R-A 81.11 1RY18A-2/W-05A 1RY18A-2 1311-02 139.40 VT-2 NRI Valve - Pipe 13T-01 13T-02 OBS 15-092 R-A 111.11 1 RY18A-21W-06 I RY18A-2 1311-02 139.40 VT-2 NRI Pipe - Elbow 13T-01 13T-02 OBS 15-093 R-A 111.11 1 RY18A-27W-07 1 RY18A-2 1311-02 139.40 VT-2 NRI Elbow- Pipe 13T-01 13T-02 OBS 15-094 R-A 111.11 1RY18A-21W-08 1RY18A-2 1311-02 89.40 VT-2 NRI Pipe - Elbow 13T-01 13T-02 OBS 15-095 R-A 111.11 1 RY18A-2/W-09 1 RY18A-2 1311-02 139.40 VT-2 NRI Elbow - Pipe 13T-01 13T-02 OBS 15-096 R-A 111.11 1 RY18A-2/VV-10 1 RY18A-2 1311-02 139.40 VT-2 NRI Pipe - WOL 13T-01 13T-02 7/8(20NO8 Weld / Component Outage Summary SYSTEM: Steam Generator (SG) Liri, 1.1 , m~~,r C-B C2.22 1RC-01-BB/N-3-NIR 1RC-01-BB UT NRI FW Nozzle Inner Radius OBS 15 -151 Roiqlf c 1, F ,!,: w cc-(~e Act , ,;a Exelon. BI R1 5 ISI Outage Report 7/8/2008 Weld / Component Outage Summary SYSTEM: Safety Injection System (SI) PT NRI PT NRI PT NRI Exelein- 11----"-.,----, Byron Station Unit 1 B1 R15 ISI Outage Report Cr>4 r- Actu:ii pa : , ,jIts OBS 15-152 Welded Attachment (VALVE ENC. 1S18811A) | |||
R-A 81.11 1 SI08GC-1.5/W-01 1 SI08GC-1 .5 13R-02 89.40 VT-2 NRI Reducer - Coupling 137-01 137-02 OBS 15-098 R-A R1.11 1SI08GC-1.5/W-02 1S108GC-1.5 13R-02 B9.40 VT-2 NRI Coupling - Pipe 137-01 137-02 OBS 15-099 R-A R1.11 1S108GC-1.5/W-03 1SI08GC-1.5 13R-02 89.40 VT-2 NRI Pipe - Elbow 137-01 137-02 OBS 15-100 R-A R1.11 1SI08GC-1.5/W-04 1S108GC-1.5 13R-02 59.40 VT-2 NRI Elbow - Pipe 137-01 137-02 OBS 15-101 R-A R1.11 1S108GC-1.5/W-05 1SI08GC-1.5 13R-02 B9.40 VT-2 NRI Pipe - Reducer 137-01 137-02 OBS 15-102 R-A 81.11 1SI08HA-2/W-01 1SI08HA-2 13R-02 B9.40 VT-2 NRI Reducer - Pipe 137-01 137-02 OBS 15-103 R-A 81.11 1SI08HA-2/W-02 1SI08HA-2 13R-02 89.40 VT-2 NRI Pipe - Flange 137-01 137-02 OBS 15-104 R-A R1.11 1SI08HA-2/W-03 1SI08HA-2 13R-02 B9.40 VT-2 NRI Flange - Pipe 137-01 137-02 OBS 15-105 B-K B10.20 1S103DA-2/W-09 1SI03DA-2 100 Closure Plate 1RB-61A OBS 15-149 C-C C3.20 1SI05BA-8/C01A 1SI05BA-8 NA 100 Closure Plate 1 PC-50 OBS 15-123 C-C C3.20 1SI06BA-24/C02A 1S106BA-24 100 7,8/2008 Weld / Component Outage Summary SYSTEM: Safety Injection System (SI) Exelon- Byron Station Unit 1 B1 R15 ISI Outage Report {7 ( ".n , N c, {° OW apt 1 o ,~, e Actual OBS 15-116 1 6 R-A 81.11 1SI08HA-2/W-04 1SI08HA-2 1311-02 89.40 VT-2 NRI Pipe - Reducer 13T-01 13T-02 OBS 15-106 R-A 111.11 1SI08JA-1.5/W-06 1SI08JA-1.5 1311-02 89.40 VT-2 NRI Pipe - Valve 13T-01 13T-02 CBS 15-107 R-A 111.11 1 $I08JA-1.5/W-07 1 SI08JA-1.5 1311-02 B9.40 VT-2 NRI Valve - Pipe 13T-01 13T-02 OBS 15-108 R-A 111.11 1S108JA-1.5/W-08 1SI08JA-1.5 1311-02 139.40 VT-2 NRI Pipe - Coupling 13T-01 13T-02 OBS 15-109 R-A 111.11 1 SI08JA-1.5/W-09 1 SI08JA-1.5 1311-02 139.40 VT-2 NRI Coupling - Pipe 13T-Ot 13T-02 OBS 15-110 R-A 111.11 1SI08JA-t5/W-10 1SI08JA-1.5 1311-02 139.40 VT-2 NRI Pipe - Flange 13T-01 13T-02 OBS 15-111 R-A 81.11 1SI08JA-1.5/W-11 1SI08JA-1.5 1311-02 89.40 VT-2 NRI Flange - Pipe 13T-01 13T-02 OBS 15-112 R-A 111.11 1SI08JA-1.5/W-12 1SI08JA-1.5 1311-02 139.40 VT-2 NRI Pipe - Elbow 13T-01 13T-02 OBS 15-113 R-A 81.11 1Sl08JA-t5/W-13 1SI08JA-1.5 1311-02 139.40 VT-2 NRI Elbow - Pipe I3T-01 13T-02 OBS 15-114 R-A 111.11 1SI08JA-1.5/W-14 1SI08JA-1.5 1311-02 89.40 VT-2 NRI Pipe - Elbow 13T-01 13T-02 OBS 15-115 R-A 111.11 1SI08JA-1.51W-15 IS108JA-1.5 1311-02 139.40 VT-2 NRI Elbow - Pipe 13T-01 13T-02 7/a/2008 Bolts, Pumps, and Valves Outage Summary SYSTEM: Reactor Pressure Vessel (RPV) Cat, ;teal Co,,Crlpl; in OBS 15-148 Washe rs 3 to 11, 13 to 18, 55, 56, and 60. !:M Fit:que ils Exelein- Byron Station Unit 1 131 R15 ISI Outage Report I r'urrtjai ~+t; ults Exam Co%~;r`~t>rtE s B-G-1 136.10 1 RC-01-R/N01-N18 NA VT-1 NRI RPV Closure Head Nuts OBS 15-145 N16 d ent on OD surface. B-G-1 136.20 1RC-01-R/S01-S18 NA UT NRI RPV Closure Head Studs OBS 15-146 Studs 01 to 07, 9, 11, 12, 14 to 18, 55, 56, and 57. B-G-1 136.50 1RC-01-R(W01-W18 NA VT-1 NRI Closure Washers 7/8/2008 Bolts, Pumps, and Valves Outage Summary SYSTEM: Steam Generator (SG) ._ "-.f t aJr3 (.7t. Cc_, ,* ^eplt$ ~zc:r ;tour, &elejn- --- Byron~Station Unit 1 B1 R15 ISI Outage Report Fsr:i at '"" ci,n-cal Actua, Rofautls FiW1t.rPStg OBS 15-137 B-G-1 136.100 1RC-01-BA/FLG SURF-CL NA VT-1 NRI Manway Flange Surface (Crossunder) | |||
OBS 15-130 El-G-1 86.100 1RC-01-BA/FLG SURF-HL NA VT-1 NRI Manway Flange Surface (Hot Leg) OBS 15-131 B-G-1 136.100 1RC-01-BB/FLG SURF-CL NA VT-1 NRI Manway Flange Surface (Crossunder) | |||
OBS 15-132 B-G-1 136.100 1RC-01-BB/FLG SURF-HL NA VT-1 NRI Manway Flange Surface (Hot Leg) OBS 15-133 B-G-1 136.100 1RC-01-BC/FLG SURF-CL NA VT-1 NRI Manway Flange Surface (Crossunder) | |||
OBS 15-134 B-G-1 136.100 1RC-01-BC/FLG SURF-HL NA VT-1 NRI Manway Flange Surface (Hot Leg) OBS 15-135 B-G-1 136.100 1RC-01-BD/FLG SURF-CL NA VT-1 NRI Manway Flange Surface (Crossunder) | |||
OBS 15-136 B-G-1 136.100 1RC-01-BD/FLG SURF-HL NA VT-1 NRI Manway Flange Surface (Hot Leg) 7/8/2008 Bolts, Pumps, and Valves Outage Summary SYSTEM: Safety Injection System (SI) B-G-2 B7.50 IS108JA-1.5/FLG 1-4 NA PFB-S1-2 VT-1 NAI Piping Flange Bolting OBS 15-154 Dissassembled under WO 1042252. Exelon- Byron Station Unit 1 B1R15 ISI Outage Report P1 TtchtItC.l; 4GIU39 Heg"tiIs E isa*tq 7/ar2008 Weld / Component Outage Summary (Preservice Inspections) | |||
SYSTEM: Feedwater System (FW) IttaY? ?;zf~rtCtlihfl rtrn1s Baseline exam of replacement pipe weld W-4, WO 00955081. rb~, t (V" htot "er~h~~caa~ | |||
t:; Rg~uirf, iucsis Note,S ^.tir"`tat. f-x jeh Exelein- Byron Station Unit 1 B1 R1 S ISI Outage Report F t,Bults R-A R1.11 1FW03DA-16/C01 | |||
.01 1FW03DA-16 13R-02 C5.51 100 SURF MT NRI R1.18 Valve-Pipe 13T-01 100 VOL-E UT GEOM 13T-02 Baseline exam of replacement pipe weld W-1, WO 00955081. R-A R1.11 1FW03DA-16/C01B 1FW03DA-16 13R-02 C5.51 100 SURF MT NRI R1.18 Pipe-Pipe 13T-01 100 VOL-E UT GEOM 13T-02 7/8/2008 Detailed Inservice Inspection Bolts, Pumps, and Valves Listing (PSI) SYSTEM: Reactor Coolant System (RY) e" t~;ittir? X.i r-cn~irw AraL?3f NOT" EP3m &elejn- Byron ~~Station Unit 1 131 R15 ISI Outage Report NRI NRI Replacement of nut under WO 00966737. Page 1-1 7/8/2008 B-G-2 137.50 1RY038C-6/FLG 1-12 NA PFB-RY VT-1 Piping Flange Bolting B aseline ex a m for 1 RY8010C replacement. WO#009615450-08. B-G-2 87.50 1RY76A-2/FLG 1-8 NA VT-1 Piping Flange Bolting | |||
/!312008 Detailed Inservice Inspection Bolts, Pumps, and Valves Listing (PSI) SYSTEM: Steam Generator (SG) XI ID F}, ,~} ej Tcwi;r,;cai ~~xioai Results pert) I Q&C-" , ptiry.l pi" q-C'Sts Exelon- Byron V Station Unit 1 B1R15 ISI Outage Report Baseline exam of replacement manway stud #16, WO 00883690. 9/64' axial indication, acceptable per procedure. B-G-1 86.90 1RC-01-BA/STUDS-CL01-20 NA MT NRI Manway Studs 1-20 (Crossunder) | |||
B aseline exam of replac em ent manway st ud #15, WO 00880420. B-G-1 86.90 1RC-01-BA/STUDS-HL01-20 NA MT NRI Manway Studs 1-20 (Hot Leg) Baseline exam of replacement manway stud #19, WO 00880420. B-G-1 86.90 1RC-01-BC/STUDS-CL01-20 NA MT NRI Manway Studs 1-20 (Crossunder) | |||
Baseline exam of replacem ent manway stud #08, WO 00883690. B-G-1 B6.90 1 RC-01-BC/STUDS-HL 01-20 NA MT RI Manway Studs 1-20 (Hot Leg) 7,8/2008 Pressure Test Outage Summary SYSTEM: Auxiliary Feedwater System (AF) Cat. item , iTtti!entC NA NA 1-AF-2-1 NA NA 1-AF-2-2 T>" rhi+.tCasl ACtu'al, Rf-gtti7~'ts Notes F,Xj+/-t1 Exeloin- Byron _,... Station Unit 1 BIR15 ISI Outage Report VT-2 NRI VT-2 NRI Pressure Test Outage Summary SYSTEM: Containment Spray System (CS) t1~,; ei I(!Cr,r , , 4~4 ~iit-'Gi:CbtS ."v0t~-S Exelon- Byron Station Unit 1 B1 R15 ISi Outage Report NA NA 1-CS-2-1 VT-2 NRI NA NA 1-CS-2-2 VT-2 NRI NA NA 1-CS-2-3 VT-2 NRI NA NA 1-CS-2-4 VT-2 NRI NA NA 1-CS-2-5 VT-2 NRI 7/aI2008 Pressure Test Outage Summary SYSTEM: Chemical & Volume Control System (CV) t5 Exelein- Byron ~Station Unit 1 B1 R15 ISI Outage Report NA NA 1-CV-2-1 I3T-03 VT-2 13T-04 NRI NA NA 1-CV-2-10 VT-2 NRI NA NA 1-CV-2-2 VT-2 NRI NA NA 1-CV-2-3 VT-2 NRI NA NA 1-CV-2-4 VT-2 NRI NA NA 1-CV-2-5 VT-2 NRI NA NA 1-CV-2-7 VT-2 NRI 7/8/2008 Pressure Test Outage Summary SYSTEM: Fuel Pool Cooling System (AF) r.-~ f- gof ," s " ar,z s Exelein- ByronStation Unit 1 B1 R15 ISI Outage Report VT-2 NRI 7/812008 7/8/20NOB Pressure Test Outage Summary SYSTEM: Process Sampling System (PS) S -, I , XI cofllp~~(1 | |||
, 7 CA ZINTI Cans-.moms Exel6n- Byron siaiion Unit , 1 BIR15 ISI Outage Report NA NA 1-PS-2-1 VT-2 NRI NA NA 1-PS-2-2 VT-2 NRI NA NA 1-PS-2-3 VT-2 NRI NA NA 1-PS-2-4 VT-2 NRI NA NA 1-PS-2-5 VT-2 NF31 NA NA 1-PS-2-6 VT-2 NRI 7/8/2UGS Pressure Test Outage Summary SYSTEM: Reactor Coolant System (RC) NA NA 1-RC-1-1 MR* tmelein- r i B1RI5 ISI Outage Report R-" iipf n: "lop , , ! f, t 4 v xam VT-2 NRI 7/8/2008 Pressure Test Outage Summary SYSTEM: Residual Heat Removal System (RH) v Byron Station Unit 1 B1R15 ISI Outage Report Exelein- 7/8/2008 NA NA 1-RH-2-1 VT-2 NRI NA NA 1-RH-2-2 VT-2 NRI NA NA l-RH-2-3 VT-2 NRI NA NA 1-RH-2-6 VT-2 NRI 7/8/2008 Pressure Test Outage Summary SYSTEM: Reactor Coolant System (RY) NA NA 1-RY-2-1 Exelein_ Byron Station Unit 1 B1 R15 ISI Outage Report ical Asatztl f ;, `, ,u=;s c~,IS 'i02~'~ E:xaa'1 VT-2 NRI 7/8/2008 7,8/2008 Pressure Test Outage Summary SYSTEM: Safety Injection System (SI) Exelein_ - ByronStationUnit 1 B1 R15 ISI Outage Report NA NA 1-SI-2-1 VT-2 NRI NA NA 1-SI-2-2 VT-2 NRI NA NA 1-SI-2-3 VT-2 NRI NA NA 1-SI-2-4 VT-2 NRI NA NA 1-SI-2-6 VT-2 NRI NA NA 1-SI-2-7 VT-2 NRI 7/8/2008 Component Support Outage Summary SYSTEM: Auxiliary Feedwater System (AF) F-A F1.20 1AF02EA-4/1AF06001R 1AF02EA-4 VT-3 NRI Rigid &elejn- Byron _ Station Unit 1 B1R16 ISI Outage Report 7/8/2008 Component Support Outage Summary SYSTEM: Containment Spray System (CS) Exelein- Byron W Station Unit 1 B1R15 ISI Outage Report Mi nor surface rust only, no wast ag e F-A F1.20 1CS02AA-10/ICS03003V 1CS02AA-10 VT-3 NRI VARIABLE-Spring Can All welds painted F-A F1,20 1CS10AA-6/lCS03028X 1CS10AA-6 VT-3 NRI SEISMIC F-A F1.20 1CS10AA-6/lCS03089A 1CS10AA-6 VT-3 NRI ANCHOR 7/ar2ooa Component Support Outage Summary SYSTEM: Chemical & Volume Control System (CV) Exelon- Byron Station Unit 1 B1R15 ISI Outage Report F-A F1.20 1CV08BA-411CV01002X SEISMIC 1CV08BA-4 VT-3 NRI F-A F1.10 1CVA3B-2/1CV16024X 1CVA3B-2 VT-3 NRI SEISMIC F-A F1.10 1CVA3B-2/1CV16083X 1CVA3B-2 VT-3 NRI SEISMIC 7/8/2008 Component Support Outage Summary SYSTEM: Feedwater System (FW) Reference IR 757579, within allowable cold range. bcelcin_ Byron Station Unit 1 B1R15 ISI Outage Report F-A F1.20 1FW81AA-6/1AF06038R RIGID 1FW81AA-6 VT-3 NRI F-A F1.20 1FW81AA-6/lAF06039X 1FW81AA-6 VT-3 NRI SEISMIC Ins ulation removed for examination. F-A F1.20 1FW81BA-6/1AF060A0V 1FW81BA-6 VT-3 NRI VARIABLE VT-3 PMT NRI 7/8/2008 Component Support Outage Summary SYSTEM: Main Steam System (MS) C-xelein_ | |||
Byron Station Unit 1 B1R1S ISI Outage Report d i~-r rd, i nF ,.W;r,i(;J< t+c",ua! AAVk;as tL X i1 ~Y1 F-A F1.20 1 MS01 BB-30-3/4/1 PC-85A 1 MS01 BB-30.75 VT-3 NRI ANCHOR VT-3 NRI 03/30/2008 Exam performed on surfaces outside containment (Direct). 03/29/2008 Exam performed on surfaces inside containment (Direct and Remote). Surface rust ide ntif ied during both exams. No evidence of wastage or loss of materi al. | |||
7,$/2008 Component Support Outage Summary SYSTEM: Reactor Coolant System (RC) F-A F1.40 1 RC-01-BA/S I RC-01-BA VT-3 NRI SG A SUPPORT VT-3 NRI VT-3 NRI IR# 757 349, Written to address boric acid on all 4 SG support leg bases. After c le aning, no degradation identified. &elon- Byron - Station Unit 1 B1R15 ISI Outage Report 7/8/2008 Component Support Outage Summary SYSTEM: Residual Heat Removal System (RH) Exelon_ -Byron Station Unit 1 B1 R15 ISI Outage Report r_+/-u;0 4:aii(S t,'ortp F-A F1.40 1RH-01-PA/Ll 1RH-01-PA VT-3 NRI RH PUMP 1 A LUG 1 10-Minor surface rust, no degradation F-A F1.40 1 RH-01-PA/L2 1 RH-01-PA VT-3 NRI RH PUMP 1A LUG 2 10-Minor surface rust, no degradation F-A F1.40 1RH-01-PA/L3 1RH-01-PA VT-3 NRI RH PUMP 1 A LUG 3 10-Minor surface rust, no degradation F-A F1.20 1 RH02AA-8/1 RH07016V 1 RH02AA-8 VT-3 NRI VARIABLE-Spring Can All welds painted F-A F1.40 1 RH-02-AB/SKT 1 RH-02-AB VT-3 NRI RH HX B SKIRT All welds painted F-A F1.20 1 RH03AA-8/1 RH01003X 1 RH03AA-8 VT-3 NRI SEISMIC - Strut All welds painted 7/8/2008 Component Support Outage Summary SYSTEM: Reactor Coolant System (RY) F-A F1.40 1 RY-01-S/SKT 1 RY-01-S VT-3 NRI PRESSURIZER SKIRT Pressurizer Skirt / Base Exelon- Byron __Station Unit 1 BIR15 ISI Outage Report 7/8/2008 Component Support Outage Summary SYSTEM: Safety Injection System (SI) Exelein- Byron Station Unit 1 B1R15 ISI Outage Report NRI NRI NRI NRI NRI 03/21/08 Exam, Direct (Area 5 Outside Containment) 03/29/2008 Exam, Direct and Remote Inside Containment. Minor surface rust identified during both exams. No evidence of wastage or material loss. NRI NRI NRI F-A F1.20 1S104B-12/1RH02029X 1SI04B-12 VT-3 SEISMIC F-A F1.20 1 SI04C-8/1 RH02026X 1 SI04C-8 VT-3 SEISMIC F-A F1.10 1S104D-8/1RH02022X 1SI04D-8 VT-3 SEISMIC F-A F1.20 1 S105BA-8/1 PC-50A 1 SI05BA-8 VT-3 ANCHOR VT-3 F-A F1.20 1SI08CA-4/1SI07008X SEISMIC 1S108CA-4 VT-3 F-A F1.10 1SI08JA-1-1/2/1SI-CP1A 1SI08JA-1-1/2 VT-3 SEISMIC F-A F1.10 1SI098A-10/1S101001V 1SI09BA-10 VT-3 VARIABLE Component Support Outage Summary SYSTEM: Essential Service Water System (SX) F-A F1.20 1SX08BC-10/lSX06018X 1SX08BC-10 VT-3 NRI SEISMIC F-A F1.20 1SX08BC-10/lSX06020X 1SX08BC-10 VT-3 NRI SEISMIC Exelein- Byron ~~ Station Unit 1 B1 R15 ISI Outage Report 7/8/2008 SYSTEM: Chemical _& Volume Control S~(stem (CV) Snubber Outage Summary (Page 1 of 6) Initial Exam Note: Section XI Category numbers N/A-ed are exempt from IWF-1220 and IWF-2500 tables Byron Station Unit 1 Byron Station Outage B1R15 ~*,ri (: ai A~; wI ra,,co3 Exelc'm_ NA NA 1CV15AC-3/4/1CV29003S 1CV15AC-3/4 VT-3 NRI SNUBBER SR F-A F1.10 1CVA5AA-2/1CV15054S 1CVA5AA-2 VT-3 NRI SNUBBER SR FT PASS Initial Exam NA SNUB 1RC14AB-2/1CV15039-S1 1RC14AS-2 VT-3 NRI SNUBBER SR FT PASS Initial Exam NA SNUB 1RC14AB-2/1CV15039-S2 1RC14AB-2 VT-3 NRI SNUBBER SR FT PASS 7/8/2008 SYSTEM: Main Steam System (MS) Initial Exam Snubber Outage Summary (Page 2 of 6) Note: Section XI Category numbers N/A-ed are exempt from IWF-1220 and IWF-2500 tables 2 ~Byron Station Unit 1 Byron Station Outage B11115 Nk"tes - z :^i Exeiein_ NA SNUB 1MS01AC-32 | |||
.75 /1MS07006-S1 1MS01AC-32 | |||
.75 y VT-3 NRI SNUBBER 19 FT PASS NA SNUB 1MS01AC-32 | |||
.75 /1MS07006-S2 1MS01AC-32 | |||
.75 y VT-3 NRI SNUBBER 19 FT PASS Initial Exam 7/8/2008 SYSTEM: Reactor Coolant Svstem (RC) Snubber Outage Summary (Page 3 of 6) Exelesn_ Byron Station Unit 1 Byron Station Outage B1 R15 1., of A ,.Ii.,~i Re;i~+rs R;>,.~_osts Initial Exam Note: Section XI Category numbers N/A-ed are exempt from IWF-1220 and IWF-2500 tables 3 F-A F1.40 1RC01BA-1 A/1RC06S 1RC01BA-1A VT-3 NRI SNUBBER SR Reservoir Setting = 4-7/8, Minor weepage on reservoir piston seal. F-A F1.40 1 RC01 BA-1 A/1 RC07S 1 RC01 BA-1 A VT-3 NRI SNUBBER SR Reservoir Setting = 4-112. Minor weepage on reservoir piston seal. F-A F1.40 1 RC01 BB-1 B/1 RC08S 1 RC01 BB-1 B VT-3 NRI SNUBBER SR Reservoir Setting = 4-3/4. Minor weepage on reservoir piston seal. F-A F1 .40 1 RC01 BB-1 B/1 RC09S 1 RC01 BB-1 B VT-3 NRI SNUBBER SR Reservoir Setting = 4-1/2. Minor weepage on reservoir piston seal. F-A F1.40 1RC01BC-1C/1RC10S 1RC01BC-1C VT-3 NRI SNUBBER SR Reservoir Setting = 4-1/2. Minor weepage on reservoir piston seal. F-A F1.40 1 RC01 BC-1 C/1 RC11 S 1 RC01 BC-1 C VT-3 NRI SNUBBER SR Reservoir Setting = 4-5/8. Minor weepage on reservoir piston seal. F-A F1.40 1 RC01 BD-1 D/1 RC12S 1 RC01 BD-1 D VT-3 NRI SNUBBER SR FT PASS Reservoir Setting = 5-5/8. Minor weepage on reservoir piston seal. F-A F1.40 1 RC01 BD-1 D/1 RC13S 1 RC01 BD-1 D VT-3 NRI SNUBBER SR Reservoir Setting = 4. Minor weepage on reservoir piston seal. F-A FIA0 1RC14AB-2/1CV15053S 1AC14AB-2 VT-3 NRI SNUBBER SR FT PASS Initial Exam NA NA 1 RC20AB-3/4/1 RC17012S 1 RC20AB-3/4 VT-3 NRI SNUBBER SR FT PASS Initial Exam F-A F1.10 1 RC22AB-1.5/1 RC17015S 1 RC22AB-1.5 VT-3 NRI SNUBBER SR FT PASS Initial Exam F-A F1.10 1 RC22AB-1.5/1 RC170288 1 RC22AB-1.5 VT-3 NRI SNUBBER SR FT PASS Snubber Outage Summary (Page 4 of 6) SYSTEM: Residual Heat Removal System (RH) Byron Station Unit 1 Byron Station Outage B1R15 Note: Section XI Category numbers N/A-ed are exempt from IWF-1220 and IWF-2500 tables 4 Exelein_ F-A F1.10 1 RHOl AA-12/1 RH02054S 1 RH01AA-12 VT-3 NRI SNUBBER SR FT PASS Initial Exam F-A F1.20 1 RH02AB-8/1 RHO8015S 1 RH02AB-8 VT-3 NRI SNUBBER SR FT PASS 7/8/2008 SYSTEM: Reactor C oolan t Syste n RY) Snubber Outage Summary (Page 5 of 6) &elejn- Byron Station Unit 1 Byron Station Outage B1R15 Initial Exam Note: Section XI Category numbers N/A-ed are exempt from IWF-1220 and IWF-2500 tables 5 F-A F1.10 1RY01AA-4/lRY06066S 1RY01AA-4 VT-3 NRI SNUBBER SR FT PASS Initial Exam F-A F1.10 1 RY01 B-6/1 RY06022S 1 RY01 B-6 VT-3 NRI SNUBBER SR FT PASS 7/8/2008 SYSTEM: Safety Iniection Svstem (SIB Snubber Outage Summary (Page 6 of 6) F-A F1.20 1SI05CA-8/1SI02003S 1SI05CA-8 VT-3 NRI SNUBBER SR FT PASS Initial Exam Note: Section XI Category numbers N/A-ed are exempt from IWF-1220 and IWF-2500 tables 6 Exelein. ~Byron^StationUnit 1 Byron Station Outage B1R15 Category B-A Non-Deferred Exams 81.30 1 1 0 0 1 1 0 1 0 100.00% 0.00 0/0 0.00% 0.00 0/0 81.40 1 1 0 0 1 1 0 1 0 100.00 0/0 0.00 0/0 0.00 0/0 0.00 0/0 Totals: 2 2 0 0 1 1 0 1 0 100.00% 0.00% 0.00% 0.00 0/0 Category B-A Deferred Exams 81.11 3 3 N/A 0 N/A N/A 0 N/A 0 100.00% 0.00% 0.00% 0.00% B1.21 2 2 N/A 0 N/A N/A 0 N/A 0 100.00 0/0 0.00 0/0 0.00% 0.00% Totals: 5 5 N/A 0 N/A N/A 0 WA 0 100.00°.6 0.00% 0.00% 0.00% Category B-B Non-Deferred Exams 82.11 2 2 0 0 1 1 0 1 0 100.00% 0.00% 0.00% 0.00% 82.12 2 2 0 0 1 1 0 1 0 100.00% 0.00% 0.00% 0.00% 82.40 4 1 0 1 1 1 0 1 0 25.00% 100.00% 100.00 0/0 100.00% Totals: 8 5 1 1 2 2 0 2 0 62.50% 20.00% 20.00% 20.00% 1. (82.40) Per Examination Category B-B, Note 1, examinations maybe limited to one vessel among a group of vessels performing a similar function. Category B-D Non-Deferred Exams 83.110 6 6 1 5 3 -2 0 -1 0 100.00% 83.33% 83.33% 83.33% 83.120 6 6 1 5 3 -2 0 -1 0 100.00% 83.33% 83.33% 83.33% 83.140 8 8 2 0 4 4 0 6 0 100.00% 0.00% 0.00% 0.00% Totals: 20 20 4 10 10 0 0 5 0 100.00% 50.00% 50.00% 50.00 0/0 1. (B3.120& 83.140) 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, and requires that a visual examination with enhanced magnification may be performed on the inside radius section in place of an ultrasonic examination. Categ ory B-D Deferred Exams 83.90 8 8 N/A 0 N/A N/A 0 N/A 0 100.00 0/0 0.00 0/0 0.00% 0.00 0/0 8 3.100 8 8 N/A 0 N/A N/A 0 N/A 0 100.00% 0.00 0/0 0.00% 0.00% Totals: 16 16 N/A 0 N/A N/A 0 WA 0 100.00% 0.00% 0.00% 0.00% Section 3.0 Page 1 of 8 (This report is used to verify that the periodic BYRON STATION UNIT 1 AND UNIT COMMON - 3RD INTERVAL (The percentage requirements o¬ Tables IWx-- requirements of Tables IWx-2412-1 will be met by ASME SECTION XI EXAMINATION STATUS REPORT 2412-1 apply to the Category and were t h e in t e rval s chedu le. ay. led to each Item only when practical.) # of Total # Exams Completed | |||
% Exams Completed Item No. Com Selected Min Per 1 Max Min Per 2 Max Per 3 % Selected Period 1 Period 2 Period 3 | |||
: 1. (133.100) This Item Number requires a visual examination with enhanced magnification in lieu of volumetric examination, as allowed by Code Case N-648-1. 2. (133.90 & 133.100) Per Examination Category B-D, Note 5, for PWR's in the second and successive inspection intervals, these examinations maybe 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. Category B-G-1 Deferred Exams 1. (136.10 & 86.20 & 136.50) Single components representing one third of the 54 Reactor Vessel Closure Head Nuts, Closure Studs, and Closure Washers, Bushings. 2. (86.40) A single component representing all of the 54 Reactor Vessel Threads in Flange to be examined. 3. (136.90 & 136.100 & 136.110) 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 Steam Generator Manways. Each of the eight entries represents 20 bolts and associated parts for an individual manway. 4. (136.170) A single component represents the five sets of CETC column nuts. 5. (136.180) 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. 6. (136.190 & 136.200) Four components are tracked in the database, each representing all 24 associated Flange Surfaces and Nuts, Bushings, and Washers for one of the four Reactor Coolant Pumps (96 total) as reported in the ISI Program Plan. The visual examination of these components is limited to only one of the 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. Section 3.0 Page 2 of 8 (This report is used to verity that the periodic WY ON STATION UNIT 1 AND UNIT COMMON - 3RD INTERVAL (The percentage requirements of Tables IWx- requirements of Tables IWx-2412-1 will be met by ASME SECTION XI EXAMINATION STATUS REPORT 2412-1 apply to the Category and were the interval schedule. a,u died to each Item only when practical.) # of Total # Exams Completed | |||
% Exams Completed Item No. Com Selected Min Per 1 Max Min Per 2 Max Per 3 % Selected Period 1 Period 2 Period 3 136.10 3 3 NIA 1 N/A N/A 0 N/A 0 100.00% 33.33% 33.33% 33.33% 86.20 3 3 N/A 1 N/A N/A 0 N/A 0 100.00% 33.33% 33.33% 33.33% 66.40 1 1 N/A 0 N/A N/A 0 N/A 0 100.00 0/0 0.00% 0.00% 0.00% 136.50 3 3 N/A 1 N/A N/A 0 N/A 0 100.00% 33.33% 33.33% 33.33% 86.90 8 8 N/A 0 N/A N/A 0 N/A 0 100.00% 0.00% 0.00 0/0 0.00 0/0 136.100 8 8 N/A 8 N/A N/A 0 N/A 0 100.00% 100.00% 100.00% 100.00% 136.110 8 8 N/A 0 N/A N/A 0 N/A 0 100.00% 0.00% 0.00% 0.00% 136.170 1 1 N/A 0 N/A N/A 0 N/A 0 100.00% 0.00% 0.00% 0.00% 136.180 4 1 NIA 0 N/A N/A 0 N/A 0 25.00% 0.00% 0.00% 0.00% 136.190 4 0 N/A 0 N/A N/A 0 N/A 0 0.00 0/0 0.00 0/0 0.00% 0.00% 136.200 4 0 N/A 0 N/A N/A 0 N/A 0 0.00% 0.00% 0.00% 0.00% 86.210 8 2 N/A 0 N/A N/A 0 N/A 0 25.00% 0.00% 0.00% 0.00% 136.2 20 8 0 N/A 0 N/A N/A 0 NIA 0 0.00% 0.00% 0.00% 0.00% 136.230 8 0 NIA 0 N/A N/A 0 N/A 0 0.00 0/0 0.00 0/0 0.00 0/0 0.00% Totals: 71 38 N/A 11 N/A N/A 0 N/A 0 53.52% 28.95% 28-95% 28.95% | |||
: 7. (86.210) 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. 8. (86.220 & 86.230) 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 1. (87.10) Two components representing the CETC and RVLIS Clamp Bolts and associated Nuts as reported in the ISI Program Plan. 2. (87.20) A single component is scheduled in the first inspection period, representing all 16 Pressurizer Manway Bolts and associated Nuts as reported in the ISI Program Plan. 3. (87.50) 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. 4. (87.60) 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. 5. (87.70) 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 8 (This report is used to verify that the periodic BYRON STATION UNIT 1 AND UNIT COMMON - 3RD INTERVAL (The percentage requirements of Tables IWx- requirements of Tables IWx-2412-1 will be met by ASME SECTION Xt EXAMINATION STATUS REP!'IRT 2412-1 apply to the Category and were the interval schedule. a. flied to each Item on 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 87.10 2 2 N/A 0 N/A N/A 0 N/A 0 100.00% 0.00% 0.00% 0.00% 87.20 1 0 N/A 0 N/A N/A 0 N/A 0 0.00% 0.00% 0.00% 0.00% 87.50 20 3 N/A 2 N/A N/A 0 N/A 0 15.00% 66.67% 66.67% 66.67% 87.60 4 0 N/A 0 N/A N/A 0 N/A 0 0.00% 0.00% 0.00% 0.00% 87.70 26 1 N/A 1 N/A N/A 0 N/A 0 3.85% 100.00% 100.00% 100.00% Totals: 53 6 N/A 3 N/A N/A 0 N/A 0 11.32% 50.00°,6 50.00% 50.00% | |||
Category B-K Non-Deferred Exams 810.10 2 2 0 0 1 1 0 1 0 100.00% 0_00% 0.00% 0.00% B10.20 7 3 1 1 1 1 0 1 0 42.86% 33.33% 33.33% 33.33% Totals: 9 5 1 1 2 2 0 2 0 55.56% 20.00% 20.00% 20.00% 1. (B10.10) Per Examination Category B-K, Note 4, for multiple vessels of similar design, function and service, only one welded attachment of only one of the multiple vessels shall be selected for examination. Conservatively, a welded attachment of each type of welded attachment of one of multiple vessels will be `' examined. 2. (1310.20 & 810.30) 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 1. (812.20) The examination of pump casings is limited to only one of the pumps performing similar functions in the system per Examination Category B-L-2, Note 1. Also, 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. Category B-M-2 Deferred Exams 1. (1312.50) Per Examination Category B-M-2, Note 2, examination is required only when a valve is disassembled for maintenance, repair, or volumetric examination. Also, per Examination Category B-M-2, Note 3, examinations are limited to at least one valve within each group of valves that are of the same size, design, manufacturing method, and function. Examination is required only once per inspection interval within each valve group. Ca teg ory B-N-1 Non-Deferred Exams 81 3.10 2 1 0 1 1 1 0 1 0 50.00% 100.00 0/0 100.00% 100.00% Totals: 2 1 0 1 1 1 0 1 0 50.001% 100.00% 100.00% 100.00% 1. (1313.10) "% Completed" exceeds 100% since the vessel interior is selected for examination once each period (three times during the interval). Section 3.0 Page 4 of 8 (This report is used to verify that the periodic BYRON STATION UNIT 1 AND UNIT GIMMON - 3RD INTERVAL (The percentage requirements of Tables IWx- r eq uirem e nts of Tables IWx-2412-1 will be met by ASME SECTION XI EXAMINATION STATUS REPORT 2412-1 apply to the Category and were the interval schedule. a. elied 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 Item No. # of Comp Total Selected min Per 1 # Exams max min Completed Per 2 max Per 3 % Selected % Period 1 Exams Completed Period 2 Period 3 812.20 4 0 N/A 0 N/A N/A 0 N/A 0 0.00% 0.00% 0.00% 0.00% Totals: 4 0 WA 0 N/A WA 0 WA 0 0.00% 0.00% 0.00% 0.00% Item No. # of Comp Total Selected min Per 1 # Exams max min Completed Per 2 max Per 3 0 ,6 Selected % Exams Completed Period 1 Period 2 Period 3 81 2.50 37 2 N/A 2 N/A N/A 0 N/A 0 5.41% 100.00% 100.00% 100.00% Totals: 37 2 WA 2 WA N/A 0 WA 0 5.41 0 ,6 100.00% 100.00% 100.00% | |||
: 1. (814.10) 10% of the 45 CRD Housings (as reported in the ISI Program Plan) are required to be examined each interval per this Item Number. These 5 components represent that 10% population. Category B-P Non-Deferred Exams 815.10 5 5 N/A 0 N/A N/A 0 N/A 0 100.00% 0.00% 0.00% 0.00% Totals: 5 5 NIA 0 NIA N/A 0 NIA 0 100.00% 0.00% 0.00% 0.00% 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 maybe limited to one vessel or distributed among the vessels. Section 3.0 Page 5 of 8 (This report is used to verify that the periodic BYRON STATION UNIT 1 AND UNIT COMMON - 3RD INTERVAL (The percentage requirements of Tables IWx- requirements of Tables IWx-2412-1 will be met by ASME SECTR7:1C~*IN STATUS REPORT 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-N-2 Deferred Exams 8 13.50 1 1 N/A 0 N/A N/A 0 N/A 0 100.00% 0.000% 0.00% 0.000/0 813.60 1 1 N/A 0 N/A N/A 0 N/A 0 100.00 0/0 0.00% 0.00% 0.00% Totals: 2 2 NIA 0 N/A N/A 0 N/A 0 100.00% 0.00% 0.00% 0.00% Category B-N-3 Deferred Exams 813.70 1 1 N/A 0 N/A N/A 0 N/A 0 100.00% 0.00% 0.00% 0.00% Totals: 1 1 N/A 0 N/A N/A 0 N/A 0 100.00% 0.00% 0.00% 0.00% Category B-0 Deferred Exams 814.10 5 5 N/A 0 N/A N/A 0 N/A 0 100.00% 0.00% 0.00% 0.00% Totals: 5 5 NIA 0 N/A NIA 0 NIA 0 100.00% 0.00% 0.00% 0.00% 1. (815.10) "% Completed" exceeds 100% since Class 1 pressure tests are performed each refueling outage. 2. (1315.10) Five components representing the five systems in Class 1 as reported in the ISI Program Plan. Category C-A Non-Deferred Exams C1.10 6 2 0 1 1 1 0 1 0 33.33% 50.00% 50.00% 50.00% C1.20 6 2 0 1 1 1 0 1 0 33.33% 50.00% 50.00% 50.00% C 1.30 4 1 0 0 1 1 0 1 0 25.00% 0.00 0/0 0.00% 0.00% Totals: 16 5 1 2 2 1 0 1 0 31.25% 40.00% 40.00% 40.00% | |||
Category C-B Non-Deferred Exams C2.21 12 1 0 0 1 1 0 1 0 8.33% 0.00% 0.00% 0.00% C2.22 8 1 0 1 1 1 0 1 0 12.50% 100.00 0/0 100.00% 100.00% Totals: 20 2 0 1 1 1 0 1 0 10.00% 50.00 0/0 50.00% 50.00% 1. (C2.21 & C2.22) Per Examination Category C-B, Note 4, in the case of multiple vessels of similar design, size, and service, the required examinations may be limited to one vessel or distributed among the vessels. 2. (C2.22) Due to the unique configuration of the heat exchanger nozzle reinforcing pads being on the internal surface, the nozzle inner radius section is inaccessible for examination. (See Relief Request 13R-04). Category C-C Non-Deferred Exams 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. The interpretation is consistent with the previous NRC condition on the use of Code Case N-509. Category C-H Non-Deferred Exams C7.10 29 29 NIA 0 N/A N/A 0 N/A 0 100.00% 0.00% 0.00% 0.00% Totals: 29 29 N/A 0 N/A N/A 0 N/A 0 100.00% 0.00% 0.00% 0.00% 1. (D1.10& D1.20& D1.30) Unit 0 (Common) components are scheduled with and included in the Unit 1 counts. Section 3.0 Page 6 of 8 (This report is used to verify that the periodic BYRON STATION UNIT 1 AND UNIT COMMON - 3RD INTERVAL (The percentage requirements of Tables IWx- requirements of Tables IWx-2412-1 will be met by ASME SECTHJN Xl EXAMINATION STATUS REPORT 2412-1 apply to the Category and were t h e in terv a l sc h edu l e. applied to each Item only when practical.) # of Total # Exams Completed | |||
% Exams Completed Item No. Com Selected Min Per 1 Max Min Per 2 Max Per 3 % Selected Period 1 Period 2 Period 3 1. (C7.10) "% Completed" exceeds 100% si nc e Class 2 pressure tests are performed each inspection period. 2. (C7.10) Twenty-nine components repres e nting the twenty-nine systems in Class 2 as reported in the ISI Program Plan. Category Non-Deferred Exams D1.10 28 14 3 7 7 0 0 3 0 50.00% 50.00% 50.00% 50.00% D1.20 120 14 3 3 7 4 0 7 0 11.67% 21.43% 21.43% 21.43% D1.30 12 2 0 0 1 1 0 1 0 16.67% 0.00% 0.00% 0.00% Totals: 160 30 5 10 15 5 0 12 0 18.75% 33.33% 33.33% 33.33% C3.10 2 1 0 0 1 1 0 1 0 50.00% 0.00 0/0 0.00% 0.00% C3.20 61 7 2 2 3 2 0 3 0 11.48% 28.57% 28.57% 28.57% C3.30 20 2 0 0 1 1 0 1 0 10.00% 0.00% 0.00% 0.00% Totals: 83 10 2 2 5 3 0 5 0 12.05% 20.00% 20.00% 20.00% | |||
: 2. (D1.10) Per Examination Category, Note 3, for multiple vessels of similar design, function, and service, the welded attachments of only one of the multiple vessels shall be selected for examination. Conservatively, an integral attachment of each type of welded attachment of one of multiple vessels will be examined. 3. (D1.20) Per Examination Category, Note 3, for welded attachments of piping, pumps, and valves, a 10% sample shall be selected for examination. This requirement is conservatively interpreted to mean that 10% of the total Class 3 welded attachments shall be examined. The interpretation is consistent with the previous NRC condition on the use of Code Case N-509. Category D-B Non-Deferred Exams D2.10 20 20 N/A 0 N/A N/A 0 N/A 0 100.00% 0.00% 0.00% 0.00% Totals: 20 20 N/A 0 N/A N/A 0 WA 0 100.00% 0.00% 0.00% 0.00% 1. (F1.30 & F1.40) Unit 0 (Common) components are scheduled with and included in the Unit 1 counts. 2. (F1.40) Per Examination Category F-A, Note 3, for multiple components other than piping within a system of similar design, function, and service, the supports of only one of the multiple components are required to be examined. Category R-A Non-Socket Welds 1. (BER Welds) The # of Comp and # Selected include all BER welds which have been integrated into the RISI Program and are selected in accordance with the Risk Informed BER methodology. Section 3.0 Page 7 of 8 (This report is used to verity that the periodic BYRt~L_Ear- | |||
~X!7:AJ~`J1LI~T J 1'CW:7QW_Lf[-IN - 3RD INTERVAL (The percentage requirements of Tables IWx- requirements of Tables IWx-2412-1 will be met by th e interval sch ed ule. ASME SECTION XI EXAMINATION STATUS REPORT 2412-1 apply to the Category and were applied to each Item on when practical.) # of Total # Exams Completed | |||
% Exams Completed Item No. Com Selected Min Per 1 Max Min Per 2 Max Per 3 % Selected Period 1 Period 2 Period 3 1. (D2.10) "% Completed" exceeds 100% since Class 3 pressure tests are performed each inspection period. 2. (D2.10) Twenty components representing the twenty systems in Class 3 as reported in the ISI Program Plan. Category F-A Non-Deferred Exams F1.10 467 122 20 39 61 22 0 59 0 26.21% 31.97% 31.97% 31.97% F1.20 59 8 99 16 32 49 18 0 44 0 16.58% 32.32% 32.32% 32.32% F1.3 0 1007 103 17 34 51 18 0 43 0 10.23% 33.01% 33-01% 33.01 F1.40 74 35 6 7 17 11 0 19 0 47.30% 20.00% 20.00% 20.00% Totals: 2146 359 58 112 179 68 0 166 0 16.73% 31.20% 31.20% 31.20% 1 128 32 6 10 16 6 0 14 0 25.00% 31.25% 31.25% 31.25% 2 134 36 6 4 18 14 0 23 0 26.87% 11.11% 11.11% 11.11 4 1400 146 24 47 73 26 0 62 0 10.43% 32.19 0 10 32.19% 32.19% 5 65 10 2 0 5 5 0 7 0 15.38% 0.00 0/0 0.00% 0.00 0/0 Totals: 1727 224 36 61 112 51 0 107 0 12.97% 27.23% 27.23% 27.23% | |||
Category R-A Socket Welds 1. Socket welds for Examination Category R-A piping structural elements are listed separately from butt welds because socket welds are selected for examination in "each" refueling outage. Including socket welds in the # of Comp, Total Selected, and # Selected fields with the butt welds would misrepresent the % completed distributions for the remainder of the Examination Category. The "% Completed" exceeds 100% since they are examined each outage per ASME Code Case N-578-1, Table 1, footnote 12. Section 3.0 Page 8 of 8 (This report is used to verify that the periodic BYRON STATION UNIT 1 AND UNIT CIIMMON - 3RD INTERVAL (The percentage requirements of Tables lWx- requirements of Tables IWx-2412-1 will be met by ASME SECTION XI EXAMINATION STATUS REPORT 2412-1 apply to the Category and were t h e int erva l sc h ed ul e. a. tlied 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 2 93 38 N/A 76 N/A N/A 0 N/A 0 40.86% 200.00% 200.00% 200.00% 4 188 44 N/A 88 N/A N/A 0 N/A 0 23.40% 200.00°10 200.00% 200.00% 5 345 34 N/A 68 N/A N/A 0 N/A 0 9.86% 200.00% 200.00% 200.00% Totals: 626 116 N/A 232 N/A N/A 0 N/A 0 18.53% 200.00°!0 200.00°!0 200.00% | |||
FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS | |||
: 1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 (Name and Address W Owner) 2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 3. Plant Unit: 1 4. Owner Certificate Of Authorization (if required): N/A 5. Commercial Service Date: 09/16/85 6. National Board Number for Unit: N-198 T. Components Inspected: Auxiliary Feedwater System (AF) Note (1): Baseline Examination Note (2): Snubber examined as a Component Support Computer Generated Form As Required by the Provisions of the ASME Code Rules (Page 1 of 46) (Name and Address of Plant) Exelein- Byron Station Unit 1 BlR15 ISI Outage Report Note: Supplemental sheets in form of fists, 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. Component or Manufacturer Manufacturer State or National Appurtenance or Installer or Installer Province No. Board No. Serial No. 1-AF-2-1 Hunter Corp. N/A N/A N/A 1-AF-2-2 Hunter Corp. N/A N/A N/A | |||
: 1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 3. Plant Unit: 1 4. Owner Certificate Of Authorization (if required): N/A 5. Commercial Service Date: 09/16/85 6. National Board Number for Unit: N-198 7. Components Inspected: Auxiliary Feedwater System (AF) Note (1): Baseline Examination FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 2 of 46) Note (2): Snubber examined as a Component Support (Name and Address of Owner) (Name and Address of Plant) Exellloln_ | |||
Byron Station Unit 1 B1R15 ISI Outage Report 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 Component or Manufacturer Manufacturer State or National Appurtenance or Installer or Installer Province No. Board No. Serial No. 1 AF02EA- Hunter Corp. N/A N/A N/A 4/1 AF06001 R | |||
: 1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois Note (1): Baseline Examination Contputer Generated Form FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 3 of 46) Note (2): Snubber examined as a Component Support (Narne and Address of Owner) (Name and Address of Plant) 3. Plant Unit: 1 4. Owner Certificate Of Authorization (if required): 5. Commercial Service Date: 09/16/85 6. National Board Number for Unit: 7. Components Inspected: Containment Spray System (CS) Exelloin-Byron Station Unit 1 BiR15 ISI Outage Report 61010 N/A N-198 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. Component or Appurtenance Manufacturer or Installer Manufacturer or Installer Serial No. State or Province No. National Board No. 1-CS-2-1 Hunter Corp. N/A N/A N/A 1-CS-2-2 Hunter Corp. N/A N/A N/A 1-CS-2-3 Hunter Corp. N/A N/A N/A 1-CS-2-4 Hunter Corp. N/A N/A N/A 1-CS-2-5 Hunter Corp. N/A N/A N/A 6/26/2008 | |||
: 1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 3. Plant Unit: 1 4. Owner Certificate Of Authorization (If required): N/A 5. Commercial Service Date: 09/16/85 6. National Board Number for Unit: N-198 7. Components Inspected: Containment Spray System (CS) Note (1): Baseline Examination Note (2): Snubber examined as a Component Support Computer Generated Forth FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 4 of 46) (Name and Address of Owner) (Name and Address of Plant) &el6n- Byron Station Unit 1 B1 R15 ISI Outage Report 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. Component or Manufacturer Manufacturer State or National Appurtenance or Installer or Installer Province No. Board No. Serial No. 1 CS02AA- Hunter Corp. N/A N/A N/A 10/1 CS03003V 1 CS10AA- Hunter Corp. N/A N/A N/A 6/1 CS03028X 1CS10AA- Hunter Corp. NIA N/A N/A 6/1 CS03089A 6/2&2008 1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 Note (1): Baseline Examination Note (2): Snubber examined as a Component Support Computer Generated Form FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 5 of 46) (Narne and Address of owner) 2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois (Narne and Address of Plant) 3. Plant Unit: 1 4. Owner Certificate Of Authorization (if required): 5. Commercial Service Date: 09/16/85 6. National Board Number for Unit: 7. Components Inspected: Chemical & Volume Control System (CV) Exellibm Byron Station Unit 1 B1 R15 ISI Outage Report 61010 N/A N-198 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. Component or Manufacturer Manufacturer State or National Appurtenance or Installer or Installer Province No. Board No. Serial No. 1 RC14AB- Pacific Scientific 23835 NA NA 2/1 CV15039-S1 1 RC14AB- Pacific Scientific 7345 NA NA 2/1 CV15039-S2 6/26/2008 | |||
: 1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 Note (1): Baseline Examination Note (2): Snubber examined as a Component Support Computer Generated Form FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 6 of 46) (flame and Address of Owner) (Name and Address of Plant) Exelein- Byron Station Unit 1 B1 R15 ISI Outage Report 3. Plant Unit: 1 4. Owner Certificate Of Authorization (if required): N/A 5. Commercial Service Date: 09/16/85 6. National Board Number for Unit: N-198 7. Components Inspected: Chemical & Volume Control System (CV) 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. Component or Appurtenance Manufacturer or Installer Manufacturer or Installer Serial No. State or Province No. National Board No. 1-CV-2-1 Hunter Corp. N/A N/A N/A 1-CV-2-10 Hunter Corp. N/A N/A N/A 1-CV-2-2 Hunter Corp. N/A N/A N/A 1-CV-2-3 Hunter Corp. N/A N/A N/A 1-CV-2-4 Hunter Corp. N/A N/A N/A 1-CV-2-5 Hunter Corp. N/A N/A N/A 1-CV-2-7 Hunter Corp. N/A N/A N/A 6/2si20o8 Note (1): Baseline Examination Note (2): Snubber examined as a Component Support Computer Generated Form FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 7 of 46) (Narne and Address of Owner) (Name and Address of Plant) &elejn- Byron Station Unit 1 BiR15 ISI Outage Report 1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 3. Plant Unit: 1 4. Owner Certificate Of Authorization (if required): N/A 5. Commercial Service Date: 09/16/85 6. National Board Number for Unit: N-198 7. Components Inspected: Chemical & Volume Control System (CV) 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. Component or Manufacturer Manufacturer State or National Appurtenance or Installer or Installer Province No. Board No. Serial No. 1CV08BA- Hunter Corp. N/A N/A N/A 4/1 CV01002X 1 CVA3B- Hunter Corp. N/A N/A N/A 2/1 CV16024X 1CVA3B- Hunter Corp. N/A N/A N/A 2/1 CV16083X 6/26/2W8 Note (1): Baseline Examination FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 8 of 46) Note (2): Snubber examined as a Component Support Computer Generated Form (Narne and Address of Owner) Exelein- Byron Station Unit 1 B1 R15 ISI Outage Report 1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 (Narne and Address of Rant) 3. Plant Unit: 1 4. Owner Certificate Of Authorization (if required): N/A 5. Commercial Service Date: 09/16/85 6. National Board Number for Unit: N-198 7. Components Inspected: Chemical & Volume Control System (CV) 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. Component or Appurtenance Manufacturer or Installer Manufacturer or Installer Serial No. State or Province No. National Board No. 1CVA3AA-2/W-06 Hunter Corp. 1-CV-1-N5 NA NA 1CVA3AA-2/W-07 Hunter Corp. 1-CV-1-N5 NA NA 1CVA3B-2/W-74 Hunter Corp. 1-CV-1-N5 NA NA 1CVA38-2/W-75 Hunter Corp. 1-CV-1-N5 NA NA 1CVA3B-2/W-76 Hunter Corp. 1-CV-1-N5 NA NA 1CVA3B-2/W-77 Hunter Corp. 1-CV-1-N5 NA NA 1CVA3B-2/W-84 Hunter Corp. 1-CV-1-N5 NA NA 1CVA3B-2JW-85 Hunter Corp. 1-CV-1-N5 NA NA 1CVA5AA-2/W-04 Hunter Corp. 1-CV-1-N5 NA NA 1CVASAA-2/W-05 Hunter Corp. 1-CV-1-N5 NA NA 1CVA6AA-2/W-04 Hunter Corp. 1-CV-1-N5 NA NA 1CVA6AA-2/W-05 Hunter Corp. 1-CV-1-N5 NA NA 6/26/2008 | |||
: 1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 Note (1): Baseline Examination Note (2): Snubber examined as a Component Support Computer Generated Form FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 9 of 46) (Name and Address of Owner) (Name and Address of Plant) &elejn- Byron Station Unit 1 B1 R15 ISI Outage Report 2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 3. Plant Unit: 1 4. Owner Certificate Of Authorization (if required): N/A 5. Commercial Service Date: 09/16/85 6. National Board Number for Unit: N-198 7. Components Inspected: Chemical & Volume Control System (CV) 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. Component or Manufacturer Manufacturer State or National Appurtenance or Installer or Installer Province No. Board No. Serial No. 1 CVA7AA-2/W-08 Hunter Corp. 1-CV-1-N5 NA NA 1CVA7AA-2/W-09 Hunter Corp. 1-CV-1-N5 NA NA | |||
: 1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 Note (1): Baseline Examination Note (2): Snubber examined as a Component Support Comp~ Generated Ports FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 10 of 46) (Name and Address of Owner) (Name and Address of Plant) Exel6n- Byron Station Unit 1 B1 R15 ISI Outage Report 2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 3. Plant Unit: 1 4. Owner Certificate Of Authorization (if required): N/A 5. Commercial Service Date: 09/16/85 6. National Board Number for Unit: N-198 7. Components Inspected: Chemical & Volume Control System (CV) 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. Manufacturer Component or Manufacturer Installer State or National Appurtenance or Installer or Serial No. Province No. Board No. 1CV15AC- Pacific Scientific 1308 NA NA 3/4/1 CV29003S 1 CVA5AA- Pacific Scientific 22192 NA NA 2/1 CV15054S 6/2612008 Note (1): Baseline Examination FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 11 of 46) Note (2): Snubber examined as a Component Support Computer Generated Form Exelon- Byron Station Unit 1 B1R15 ISI Outage Report 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: 1 4. Owner Certificate Of Authorization (if required): N/A 5. Commercial Service Date: 09/16/85 6. National Board Number for Unit: N-198 7. Components Inspected: Fuel Pool Cooling System (AF) Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x t 1 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. Component or Manufacturer Manufacturer State or National Appurtenance or Installer or Installer Province No. Board No. Serial No. 1-FC-2-1 Hunter Corp. N/A N/A N/A 6/28/2008 FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 12 of 46) 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: 1 4. Owner Certificate Of Authorization (if required): N/A 5. Commercial Service Date: 09/16/85 6. National Board Number for Unit: N-198 7. Components Inspected: Feedwater System (FW) Note (1): Baseline Examination Note (2): Snubber examined as a Component Support Exelein- Byron Station Unit 1 B1 R15 ISI Outage Report 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 Component or Manufacturer Manufacturer State or National Appurtenance or Installer or Installer Province No. Board No. Serial No. 1 FW 81 AA- Hunter Corp. N/A N/A N/A 6/1 AF06038R 1 F W 81 AA- Hunter Corp. N/A N/A N/A 6/1 AF06039X 1 FW81 BA- Hunter Corp. N/A N/A N/A 6/1 AF06040V 6/28/2008 | |||
: 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 3. Plant Unit: 1 4. Owner Certificate Of Authorization (if required): N/A 5. Commercial Service Date: 09/16/85 6. National Board Number for Unit: N-198 7. Components Inspected: Feedwater System (FW) 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 FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 13 of 46) (Name and Address of Plant) Exelon- Byron Station Unit 1 Bi R15 ISI Outage Report Component or Manufacturer Manufacturer State or National Appurtenance or Installer or Installer Province No. Board No. Serial No. 1FW03DA-16/C01 | |||
.01 Hunter Corp. 1-FW-1-N5 NA NA 1FW03DA-16/C01B Hunter Corp. 1-FW-1-N5 NA NA 1FW87CA-6/C08A W. A. Pope Corp. 1-FW-1-N5 NA NA 6/2 6/2008 1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 Note (1): Baseline Examination Note (2): Snubber examined as a Component Support Computer Generated Form FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 14 of 46) (Narne and Address of Owner) 2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 (Name and Address of Plant) Exelein- Byron Station Unit 1 B1R15 ISI Outage Report 3. Plant Unit: 1 4. Owner Certificate Of Authorization (if required): N/A 5. Commercial Service Date: 09/16/85 6. National Board Number for Unit: N-198 7. Components Inspected: Main Steam System (MS) 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. Component or Manufacturer Manufacturer State or National Appurtenance or Installer or Installer Province No. Board No. Serial No. 1 MS01 AC-32.75 Pacific Scientific 10488 NA NA /1 MS07006-S1 1MS01AC-32 | |||
.75 Pacific Scientific 10489 NA NA /1 MS07006-S2 6/2 6/2008 FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 15 of 46) 1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 3. Plant Unit: 1 4. Owner Certificate Of Authorization (if required): N/A 5. Commercial Service Date: 09/16/85 6. National Board Number for Unit: N-198 7. Components Inspected: Main Steam System (MS) Note (1): Baseline Examination Note (2): Snubber examined as a Component Support Computer Generated Form (Name and Address of Owner) (Narne and Address of Plant) Exelon- Byron Station Unit 1 B1 R15 ISI Outage Report 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. Component or Manufacturer Manufacturer State or National Appurtenance or Installer or Installer Province No. Board No. Serial No. 1 MS01 BB-30-3/4/1 PC- Hunter Corp. N/A N/A N/A 85A 6/26/2008 (Name and Address of Owner) 2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois (Name and Address of Plant) 3. Plant Unit: 1 4. Owner Certificate Of Authorization (if required): 5. Commercial Service Date: 09/16/85 6. National Board Number for Unit: 7. Components Inspected: Process Sampling System (PS) Note (1): Baseline Examination FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 16 of 46) Note (2): Snubber examined as a Component Support Computer Genmrated Form Exelein- Byron Station Unit 1 B1 R15 ISI Outage Report 1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 61010 N/A N-198 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. Component or Appurtenance Manufacturer or Installer Manufacturer or Installer Serial No. State or Province No. National Board No. 1-PS-2-1 Hunter Corp. N/A N/A N/A 1-PS-2-2 Hunter Corp. N/A N/A N/A 1-PS-2-3 Hunter Corp. N/A NIA N/A 1-PS-2-4 Hunter Corp. N/A N/A N/A 1-PS-2-5 Hunter Corp. N/A N/A N/A 1-PS-2-6 Hunter Corp. N/A N/A N/A Note (1): Baseline Examination A Corrvwwr Generated Fonn FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 17 of 46) 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 Note (2): Snubber examined as a Component Support (flame and Address of Plant) Exelein- Byron Station Unit 1 B1R15 ISI Outage Report 3. Plant Unit: 1 4. Owner Certificate Of Authorization (if required): N/A 5. Commercial Service Date: 09/16/85 6. National Board Number for Unit: N-198 7. Components Inspected: Reactor Coolant System (RC) 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. Component or Manufacturer Manufacturer State or National Appurtenance or Installer or Installer Province No. Board No. Serial No. 1-RC-1-1 Hunter Corp. N/A N/A N/A 6/26/2008 Note (1): Baseline Examination Computer Generated Form FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 18 of 46) 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 Note (2): Snubber examined as a Component Support (Name and Address of Plant) Exelein- Byron Station Unit 1 B1 R15 ISI Outage Report 3. Plant Unit: 1 4. Owner Certificate Of Authorization (if required): N/A 5. Commercial Service Date: 09/16/85 6. National Board Number for Unit: N-198 7. Components Inspected: Reactor Coolant System (RC) 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. Component or Manufacturer Manufacturer State or National Appurtenance or installer or Installer Province No. Board No. Serial No. 1 RC-01 -BA/S Hunter Corp. N/A N/A N/A 6/26/2008 Note (1): Baseline Examination Note (2): Snubber examined as a Component Support computer Generated Form FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 19 of 46) (Name and Address of Plant) Exelon- Byron Station Unit 1 BIR15 ISI Outage Report 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 3. Plant Unit: 1 4. Owner Certificate Of Authorization (if required): N/A 5. Commercial Service Date: 09/16/85 6. National Board Number for Unit: N-198 7. Components Inspected: Reactor Coolant System (RC) 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. Component or Appurtenance Manufacturer or Installer Manufacturer or Installer Serial No. State or Province No. National Board No. 1RC PA/FLYWHEEL Westinghouse Corp. 1-115E121-G01 NA W25819 1 RC-01 -R/RPVS-A F-1 Westinghouse Corp. 640-0004-51 B-09061 N-198 1RC-01-R/RPVS-D F-1 Westinghouse Corp. 640-0004-51 B-09061 N-198 1RC-01-R/RPVS-E F-1 Westinghouse Corp. 640-0004-51 B-09061 N-198 1RC-01-R/RPVS-H F-1 Westinghouse Corp. 640-0004-51 B-09061 N-198 1 RC13AA-2/W-01 Hunter Corp. 1-RC-1-N5 NA NA 1 RC13AA-2/W-02 | |||
.01 W. A. Pope Corp. 1-RC-1-N5 NA NA 1RC13AA-2/W-03 Hunter Corp. 1-RC-1-N5 NA NA 1RC13AA-2/W-04 Hunter Corp. 1-RC-1-N5 NA NA 1 RC13AA-2/W-05 Hunter Corp. 1-RC-1-N5 NA NA 1 RC13AB-2/W-01 Hunter Corp. 1-RC-1-N5 NA NA 1RC13AB-2/W-09 Hunter Corp. 1-RC-1-N5 NA NA 6/26/2tNi8 As Required by the Provisions of the ASME Code Rules (Page 20 of 46) 1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 Note (1): Baseline Examination computer Generated Form FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS Note (2): Snubber examined as a Component Support (Name and Address of Owner) (Name and Address of Plant) 3. Plant Unit: 1 4. Owner Certificate Of Authorization (if required): 5. Commercial Service Date: 09/16/85 6. National Board Number for Unit: 7. Components Inspected: Reactor Coolant System (RC) Exelon- Byron Station Unit 1 B1 R15 ISI Outage Report 2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 N/A N-198 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. Component or Appurtenance Manufacturer or Installer Manufacturer or Installer Serial No. State or Province No. National Board No. 1 RC13AC-2/W-01 Hunter Corp. 1-RC-1-N5 NA NA 1RC13AD-2/W-01 Hunter Corp. 1-RC-1-N5 NA NA 1RC14AA-2/W-02 Hunter Corp. 1-RC-1-N5 NA NA 1 RC14AA-2/W-03 Hunter Corp. 1-RC-1-N5 NA NA 1RC14AA-2/W-03A Hunter Corp. 1-RC-1-N5 NA NA 1RC14AA-2/W-03B Hunter Corp. 1-RC-1-N5 NA NA 1RC14AA-2/W-03C Hunter Corp. 1-RC-1-N5 NA NA 1 RC14AA-2/W-04 Hunter Corp. 1-RC-1-N5 NA NA 1RC14AA-2/W-05 Hunter Corp. 1-RC-1-N5 NA NA 1 RC14AA-2/W-06 Hunter Corp. 1-RC-1-N5 NA NA 1RC14AA-2/W-07 Hunter Corp. 1-RC-1-N5 NA NA 1RC14AA-2/W-08 Hunter Corp. I 1-RC-1-N5 I NA I NA 6/28/2008 | |||
: 3. Plant Unit: 1 4. Owner Certificate Of Authorization (if required): 5. Commercial Service Date: 09/16/85 6. National Board Number for Unit: 7. Components Inspected: Reactor Coolant System (RC) Note (1): Baseline Examination Note (2): Snubber examined as a Component Support Computer Generated Form FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 21 of 46) (Name and Address of Owner) (Name and Address of Plant) Exelein- Byron Station Unit 1 B1 R15 ISI Outage Report 1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 N/A N-198 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. Component or Appurtenance Manufacturer or Installer Manufacturer or Installer Serial No. State or Province No. National Board No. 1 RC14AA-2/W-09 Hunter Corp. 1-RC-1-N5 NA NA 1 RC14AA-2/W-10 Hunter Corp. 1-RC-1-N5 NA NA 1RC14AA-2/W-11 Hunter Corp. 1-RC-1-N5 NA NA 1 RC14AA-2/W-12 Hunter Corp. 1-RC-1-N5 NA NA 1RC14AA-2/W-13 Hunter Corp. 1-RC-1-N5 NA NA 1RC14AB-2/W-07 Hunter Corp. 1-RC-1-N5 NA NA 1RC14AB-2/W-08 Hunter Corp. 1-RC-1-N5 NA NA 1RC14AB-2/W-09 Hunter Corp. 1-RC-1-N5 NA NA 1RC14AB-2/W-10 Hunter Corp. 1-RC-1-N5 NA NA 1RC14AB-2/W-11 Hunter Corp. 1-RC-1-N5 NA NA 1 RC14AC-2/W-08 Hunter Corp. 1-RC-1-N5 NA NA 1RC14AD-2/W-08 Hunter Corp. 1-RC-1-N5 NA NA 6/26/2008 Note (1): Baseline Examination Computer Generated Form FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS | |||
: 1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 Note (2): Snubber examined as a Component Support As Required by the Provisions of the ASME Code Rules (Page 22 of 46) (Name and Address d Owner) ByronStation Unit 1 B1R15 ISI Outage Report 2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 (Name and Address of Plant) Exelon- 3. Plant Unit: 1 4. Owner Certificate Of Authorization (if required): NIA 5. Commercial Service Date: 09/16/85 6. National Board Number for Unit: N-198 7. Components Inspected: Reactor Coolant System (RC) 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. Component or Appurtenance Manufacturer or Installer Manufacturer or Installer Serial No. State or Province No. National Board No. 1RC14AD-2/W-09 Hunter Corp. 1-RC-1-N5 NA NA 1RC14AD-2/W-10 Hunter Corp. 1-RC-1-N5 NA NA 1 RC14AD-2/W-11 Hunter Corp. 1-RC-1-N5 NA NA 1RC14AD-2/W-12 Hunter Corp. 1-RC-1-N5 NA NA IRC14AD-2/W-13 Hunter Corp. 1-RC-1-N5 NA NA 1RC16AA-2/W-02 Hunter Corp. 1-RC-1-N5 NA NA 1 RC16AA-2/W-03 Hunter Corp. 1-RC-1-N5 NA NA 1RC16AA-2/W-04 Hunter Corp. 1-RC-1-N5 NA NA 1 RC16AA-2/W-05 Hunter Corp. 1-RC-1-N5 NA NA 1 RC16AA-2/W-06 Hunter Corp. 1-RC-1-N5 NA NA 1 RC16AA-2/W-07 Hunter Corp. 1-RC-1-N5 NA NA 1RC16AA-2/W-08 Hunter Corp. 1-RC-1-N5 NA NA 6/26/2008 Note (1): Baseline Examination | |||
-- Computer Generated Form FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS Note (2): Snubber examined as a Component Support As Required by the Provisions of the ASME Code Rules (Page 23 of 46) (Name and Address of Owner) (Name and Address of Plant) &elejn- Byron Station Unit 1 BiR15 ISI Outage Report 1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 3. Plant Unit: 1 4. Owner Certificate Of Authorization (if required): N/A 5. Commercial Service Date: 09/16/85 6. National Board Number for Unit: N-198 7. Components Inspected: Reactor Coolant System (RC) 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. Component or Appurtenance Manufacturer or Installer Manufacturer or Installer Serial No. State or Province No. National Board No. 1 RC16AB-2/W-02 Hunter Corp. 1-RC-1-N5 NA NA 1 RC22AA-1.5/W-01 Hunter Corp. 1-RC-1-N5 NA NA 1 RC22AA-1.5/W-02 Hunter Corp. 1-RC-1-N5 NA NA 1RC22AA-1.5/W-03 Hunter Corp. 1-RC-1-N5 NA NA 1 RC22AA-1.5/W-04 Hunter Corp. 1-RC-1-N5 NA NA 1RC22AA-1.5/W-05 Hunter Corp. 1-RC-1-N5 NA NA 1 RC22AA-1.5/W-06 Hunter Corp. 1-RC-1-N5 NA NA 1 RC22AA-1.5/W-07 Hunter Corp. 1-RC-1-N5 NA NA 1RC22AA-1.5/W-08 Hunter Corp. 1-RC-1-N5 NA NA 1 RC22AA-1.5/W-09 Hunter Corp. 1-RC-1-N5 NA NA 1 RC22AA-1.5/W-10 Hunter Corp. 1-RC-1-N5 NA NA 1RC22AA-1.5/W-11 Hunter Corp. 1-RC-1-N5 NA NA j 6/26/2008 Note (1): Baseline Examination FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 24 of 46) Note (2): Snubber examined as a Component Support Computer Generated Form (Name and Address of Owner) Exelein- Byron Station Unit 1 B1 R15 ISI Outage Report 1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 (Name and Address of Plant) 3. Plant Unit: 1 4. Owner Certificate Of Authorization (if required): N/A 5. Commercial Service Date: 09/16/85 6. National Board Number for Unit: N-198 7. Components Inspected: Reactor Coolant System (RC) 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. Component or Appurtenance Manufacturer or Installer Manufacturer or Installer Serial No. State or Province No. National Board No. 1 RC22AA-1.5/W-12 Hunter Corp. 1-RC-1-N5 NA NA 1RC22AA-1.5/W-13.01 NPSW Venture Corp. 1-RC-1-N5 NA NA 1 RC22AA-1.5/W-14.01 NPSW Venture Corp. 1-RC-1-N5 NA NA 1RC22AA-1.5/W-15.01 NPSW Venture Corp. 1-RC-1-N5 NA NA 1RC22AA-1.5/W-16.01 NPSW Venture Corp. 1-RC-1-N5 NA NA 1RC22AA-1.5/W-17 Hunter Corp. 1-RC-1-N5 NA NA 1RC22AA-1.5/W-18 Hunter Corp. 1-RC-1-N5 NA NA 1RC22AA-1.5/W-19 Hunter Corp. 1-RC-1-N5 NA NA 1RC22AA-1.5/W-20 Hunter Corp. 1-RC-1-N5 NA NA 1RC22AA-1.5/W-21 Hunter Corp. 1-RC-1-N5 NA NA 1 RC22AA-1.5/W-22 Hunter Corp. 1-RC-1-N5 NA NA 1 RC22AA-1.5/W-23 Hunter Corp. 1-RC-1-N5 NA t NA 6/28/2b08 | |||
: 1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 3. Plant Unit: 1 4. Owner Certificate Of Authorization (if required): 5. Commercial Service Date: 09/16/85 6. National Board Number for Unit: 7. Components Inspected: Reactor Coolant System (RC) 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 FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 25 of 46) (Name and Address of Owner) (Name and Address of Plant) Exel6n- Byron Station Unit 1 B1 R15 ISI Outage Report 61010 N/A N-198 Component or Appurtenance Manufacturer or Installer Manufacturer or Installer Serial No. State or Province No. National Board No. 1 RC22AA-1.5/W-24 Hunter Corp. 1-RC-1-N5 NA NA 1RC22AA-1.5/W-25 Hunter Corp. 1-RC-1-N5 NA NA 1RC22AA-1.5/W-26 Hunter Corp. 1-RC-1-N5 NA NA 1RC22AA-1.5/W-27 Hunter Corp. 1-RC-1-N5 NA NA 1 RC22AA-1.5/W-28 Hunter Corp. 1-RC-1-N5 NA NA 1 RC22AA-1.5/W-29 Hunter Corp. 1-RC-1-N5 NA NA 1RC22AA-1.5/W-30 Hunter Corp. 1-RC-1-N5 NA NA 1RC22AA-1.5/W-31 Hunter Corp. 1-RC-1-N5 NA NA 1 RC22AA-1.5/W-32 Hunter Corp. 1-RC-1-N5 NA NA 1RC22AA-1.5/W-33 Hunter Corp. 1-RC-1-N5 NA NA 6/26/2008 | |||
: 1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 Note (1): Baseline Examination Note (2): Snubber examined as a Component Support Computer Generated Form FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 26 of 46) (Name and Address of Owner) (Name and Address of Plant) Exelon- Byron Station Unit 1 BlRl5 ISI Outage Report 2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 3. Plant Unit: 1 4. Owner Certificate Of Authorization (if required): N/A 5. Commercial Service Date: 09/16/85 6. National Board Number for Unit: N-198 7. Components Inspected: Reactor Coolant System (RC) 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. Component or Appurtenance Manufacturer or Installer Manufacturer or Installer Serial No. State or Province No. National Board No. 1 RC01 BA-1 A/1 RC06S Paul Munroe PD-1423-333 NA NA 1 RC01 BA-1 A/1 RC07S Paul Munroe PD-1423-322 NA NA 1 RC01 BB-1 B/1 RC08S Paul Munroe PD-1423-329 NA NA 1 RC01 BB-1 B/1 RC09S Paul Munroe PD-1423-327 NA NA 1 RC01 BC-1 C/1 RC10S Paul Munroe PD-1423-334 NA NA 1 RC01 BC-1 C/1 RC11 S Paul Munroe PD-1423-331 NA NA 1RC01BD-1D/1RC12S Paul Munroe PD-1423-321 NA NA 1 RC01 BD-1 D/1 RC13S Paul Munroe PD-1423-318 NA NA 1 RC14AB- 2/1 CV15053S Pacific Scientific 2193 NA NA 1 RC20AB- 3/4/1 RC17012S Pacific Scientific 14748 NA NA 1 RC22AB- 1.5/1 RC17015S Pacific Scientific 20437 NA NA 1 RC22AB- 1.5/1 RC17028S Pacific Scientific 5666 NA NA 6/26/2008 (Name and Address of Plant) 3. Plant Unit: 1 4. Owner Certificate Of Authorization (if required): 5. Commercial Service Date: 09/16/85 6. National Board Number for Unit: 7. Components Inspected: Residual Heat Removal System (RH) Note (1): Baseline Examination Note (2): Snubber examined as a Component Support "-- Computer Generated Form FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 27 of 46) Exelein- Byron Station Unit 1 B1R15 ISI Outage Report 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 N/A N-198 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. Component or Appurtenance Manufacturer or Installer Manufacturer or Installer Serial No. state or Province No. National Board No. 1-RH-2-1 Hunter Corp. N/A N/A N/A 1-RH-2-2 Hunter Corp. N/A N/A N/A 1-RH-2-3 Hunter Corp. N/A N/A N/A 1-RH-2-6 Hunter Corp. N/A N/A N/A 6/26/2008 FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 28 of 46) 1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 Note (1): Baseline Examination Note (2): Snubber examined as a Component Support Computer Generated Form (Name and Address of Owner) 2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois (Name and Address of Plant) 3. Plant Unit: 1 4. Owner Certificate Of Authorization (if required): 5. Commercial Service Date: 09/16/85 6. National Board Number for Unit: 7. Components Inspected: Residual Heat Removal System (RH) Exe-lon-ByronStation Unit 1 B1R15 ISI Outage Report 61010 N/A N-198 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. Component or Manufacturer Manufacturer State or National Appurtenance or Installer or Installer Province No. Board No. Serial No. 1 R H-01-PA/L 1 Hunter Corp. N/A N/A N/A 1 RH-01-PA/L2 Hunter Corp. N/A NIA N/A 1 RH-01-PA/L3 Hunter Corp. N/A N/A N/A 1 RH02AA- Hunter Corp. N/A N/A N/A 8/1 RH07016V 1 RH-02-AB/SKT Hunter Corp. N/A N/A N/A 1 RH03AA- Hunter Corp. N/A N/A N/A 8/1 RH01003X 6/26/2008 | |||
: 1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 3. Plant Unit: 1 4. Owner Certificate Of Authorization (if required): 5. Commercial Service Date: 09/16/85 6. National Board Number for Unit: 7. Components Inspected: Residual Heat Removal System (RH) 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 FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 29 of 46) (Narne and Address of Owner) (Name and Address of Plant) Exelon- Byron Station Unit 1 B1 R15 ISI Outage Report N/A N-198 Component or Manufacturer Manufacturer State or National Appurtenance or Installer or Installer Province No. Board No. Serial No. 1 R H01 AA- Pacific Scientific 9629 NA NA 12/1 RH02054S 1 RH02AB- Pacific Scientific 9892 NA NA 8/1 RH08015S 6/26/2008 | |||
: 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 (Name and Address of Plant) 3. Plant Unit: 1 4. Owner Certificate Of Authorization (if required): 5. Commercial Service Date: 09/16/85 6. National Board Number for Unit: 7. Components Inspected: Reactor Pressure Vessel (RPV) Note (1): Baseline Examination Computer Generated Form FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 30 of 46) Note (2): Snubber examined as a Component Support Exelein- Byron Station Unit 1 B1 R15 ISI Outage Report 61010 N/A N-198 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. Component or Manufacturer Manufacturer State or National Appurtenance or Installer or Installer Province No. Board No. Serial No. 1RC-01-R/N01-N18 Westinghouse Corp. 640-0004-52 B-09061 N-198 1RC-01-R/S01-S18 Westinghouse Corp. 640-0004-52 B-09061 N-198 1RC-01-R/W01-W18 Westinghouse Corp. 640-0004-52 B-09061 N-198 FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 31 of 46) &elon- Byron Station Unit 1 B1 R15 ISI Outage Report 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: 1 4. Owner Certificate Of Authorization (if required): N/A 5. Commercial Service Date: 09/16/85 6. National Board Number for Unit: N-198 T. Components Inspected: Reactor Pressure Vessel (RPV) 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 Component or Manufacturer Manufacturer State or National Appurtenance or Installer or Installer Province No. Board No. Serial No. 1 RC-01 -R/RPV Westinghouse Corp. 640-0004-51 B-09061 N-198 INTERIOR 6/26/2008 Note (1): Baseline Examination Computer Generated Form FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 32 of 46) 2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 3. Plant Unit: 1 4. Owner Certificate Of Authorization (if required): 5. Commercial Service Date: 09/16/85 6. National Board Number for Unit: 7. Components Inspected: Reactor Coolant System (RY) Note (2): Snubber examined as a Component Support (Name and Address of Owner) (Name and Address of Plant) Exelon- Byron Station Unit 1 B1R15 ISI Outage Report 1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 61010 N/A N-198 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. Component or Manufacturer Manufacturer State or National Appurtenance or Installer or Installer Serial No. Province No. Board No. 1 RY03BC-6/FLG 1-12 Hunter Corp. 1-RY-1-N5 NA NA 1RY76A-2/FLG 1-8 Hunter Corp. 1-RY-1-N5 NA NA 6126/2008 | |||
: 1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 Note (1): Baseline Examination Note (2): Snubber examined as a Component Support Computer Generated Form FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 33 of 46) (Name and Address of Owner) (Name and Address of Plant) 3. Plant Unit: 1 4. Owner Certificate Of Authorization (if required): 5. Commercial Service Date: 09/16/85 6. National Board Number for Unit: 7. Components Inspected: Reactor Coolant System (RY) Exelein- Byron Station Unit 1 B1R15 ISI Outage Report 2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 N/A N-198 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. Component or Manufacturer Manufacturer State or National Appurtenance or Installer or Installer Province No. Board No. Serial No. 1-RY-2-1 Hunter Corp. N/A N/A N/A 6/26/2008 Note (1): Baseline Examination Note (2): Snubber examined as a Component Support Computer Generated Form FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASIVIE Code Rules (Page 34 of 46) 1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 (Nerve and Address of Owner) 2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 (Name and Address of Plant) Euelun_ Byron Station Unit 1 BIR15 ISI Outage Report 3. Plant Unit: 1 4. Owner Certificate Of Authorization (if required): N/A 5. Commercial Service Date: 09/16/85 6. National Board Number for Unit: N-198 7. Components Inspected: Reactor Coolant System (RY) 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. Component or Manufacturer Manufacturer State or National Appurtenance or Installer or Installer Province No. Board No. Serial No. 1 RY-01-S/SKT Hunter Corp. N/A N/A N/A 6/26/2008 FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 35 of 46) Exelun_ Byron Station Unit 1 B1R15 ISI Outage Report 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 Fant) 3. Plant Unit: 1 4. Owner Certificate Of Authorization (If required): N/A 5. Commercial Service Date: 09/16/85 6. National Board Number for Unit: N-198 7. Components Inspected: Reactor Coolant System (RY) 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. x Computer Generated Form Component or Appurtenance Manufacturer or installer Manufacturer or Installer Serial No. State or Province No. National Board No. 1RY18A-2/W-05A Hunter Corp. 1-RC-1-N5 NA NA 1RY18A-2/W-06 Hunter Corp. 1-RC-1-N5 NA NA 1 RY18A-2/W-07 Hunter Corp. 1-RC-1-N5 NA NA 1RY18A-2/W-08 Hunter Corp. 1-RC-1-N5 NA NA 1RY18A-2/W-09 Hunter Corp. 1-RC-1-N5 NA NA 1 RY18A-2/W-10 Hunter Corp. 1-RC-1-N5 NA NA 6/26/2008 Note (1): Baseline Examination FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS Note (2): Snubber examined as a Component Support computer Generated Form As Required by the Provisions of the ASME Code Rules (Page 36 of 46) (Narne end Address of Owner) 2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois (Name and Address of Plant) 3. Plant Unit: 1 4. Owner Certificate Of Authorization (if required): 5. Commercial Service Date: 09/16/85 6. National Board Number for Unit: 7. Components Inspected: Reactor Coolant System (RY) Exelon- Byron Station Unit 1 B1 R15 ISI Outage Report 1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 61010 N/A N-198 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. Component or Manufacturer Manufacturer State or National Appurtenance or Installer or Installer Province No. Board No. Serial No. 1RY01AA- Pacific Scientific 20685 NA NA 4/1 RY06066S 1 RY01 B-6/1 RY06022S Pacific Scientific 10163 NA NA 6/26/2008 | |||
: 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 Note (1): Baseline Examination Computer Generated Form FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 37 of 46) Note (2): Snubber examined as a Component Support (Name and Address of Plant) Exelein_ Byron Station Unit 1 1311315 ISI Outage Report 3. Plant Unit: 1 4. Owner Certificate Of Authorization (if required): N/A 5. Commercial Service Date: 09/16/85 6. National Board Number for Unit: N-198 7. Components Inspected: Steam Generator (SG) 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. Component or Manufacturer Manufacturer State or National Appurtenance or Installer or Installer Province No. Board No. Serial No. 1 RC-01 -BA/FLG Babcock & Wilcox Industries 7722-02 ILU-242904 165 SURF-CL 1 RC-01 -BA/FLG Babcock & Wilcox Industries 7722-02 ILU-242904 165 SURF-HL 1RC-01-BA/STUDS-Babcock & Wilcox Industries 7722-02 ILU-242904 165 CL 01-20 1RC-01-BA/STUDS-Babcock & Wilcox Industries 7722-02 ILU-242904 165 HL 01-20 1 RC-01-BB/FLG Babcock & Wilcox Industries 7722-03 ILU-242903 166 SURF-CL 1RC-01-BB/FLG Babcock & Wilcox Industries 7722-03 ILU-242903 166 SURF-HL 1RC-01-BC/FLG Babcock & Wilcox Industries 7722-01 ILU-242902 164 SURF-CL 1RC-01-BC/FLG Babcock & Wilcox Industries 7722-01 ILU-242902 164 SURF-HL 1 RC-01-BC/STUDS-Babcock & Wilcox Industries 7722-01 ILU-242902 164 CL 01-20 1RC-01-BC/STUDS-Babcock & Wilcox Industries 7722-01 ILU-242902 164 HL 01-20 1RC-01-BD/FLG Babcock & Wilcox Industries 7722-04 ILU-242901 167 SURF-CL 1RC-01 -BD/FLG Babcock & Wilcox Industries 7722-04 ILU-242901 167 SURF-HL 6/26/2008 FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 38 of 46) 1. Owner: Exelon Generation Company, (EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 3. Plant Unit: 1 4. Owner Certificate Of Authorization (if required): N/A 5. Commercial Service Date: 09/16/85 6. National Board Number for Unit: N-198 7. Components Inspected: Steam Generator (SG) Note (1): Baseline Examination Note (2): Snubber examined as a Component Support (Name and Address of Owner) (Name and Address of Plant) Exel6n- Byron Station Unit 1 B1R15 ISI Outage Report 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 forth Component or Manufacturer Manufacturer State or National Appurtenance or Installer or Installer Province No. Board No. Serial No. 1 RC-01-BB/N-3-NIR Babcock & Wilcox Industries 7722-03 ILU-242903 166 6/26/2008 Note (1): Baseline Examination computer Generated Form FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 39 of 46) 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 Note (2): Snubber examined as a Component Support (Name and Address of Plant) Exelein- Byron Station Unit 1 B1R15 ISI Outage Report 3. Plant Unit: 1 4. Owner Certificate Of Authorization (if required): N/A 5. Commercial Service Date: 09/16/85 6. National Board Number for Unit: N-198 7. Components Inspected: Safety Injection System (SI) 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. Component or Manufacturer Manufacturer State or National Appurtenance or Installer or Installer Province No. Board No. Serial No. 1S108JA-1.5/FLG 1-4 Hunter Corp. 1-SI-1-N5 NA NA 6/26/2008 | |||
: 1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 Note (1): Baseline Examination Note (2): Snubber examined as a Component Support Computer Generated Form FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 40 of 46) (Name and Address of Owner) (Name and Address of Plant) Exelon- Byron Station Unit 1 B1 R15 ISI Outage Report 2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 3. Plant Unit: 1 4. Owner Certificate Of Authorization (if required): N/A 5. Commercial Service Date: 09/16/85 6. National Board Number for Unit: N-198 7. Components Inspected: Safety Injection System (SI) Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2 m. 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. Component or Appurtenance Manufacturer or Installer Manufacturer or Installer Serial No. State or Province No. National Board No. 1-SI-2-1 Hunter Corp. N/A N/A N/A 1-SI-2-2 Hunter Corp. N/A N/A N/A 1-SI-2-3 Hunter Corp. N/A N/A N/A 1-SI-2-4 Hunter Corp. N/A N/A N/A 1-SI-2-6 Hunter Corp. N/A N/A N/A F"l-2-7 Hunter Corp. N/A N/A N/A 6/28/2008 | |||
: 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 (Name and Address of Plant) 3. Plant Unit: 1 4. Owner Certificate Of Authorization (if required): 5. Commercial Service Date: 09/16/85 6. National Board Number for Unit: 7. Components Inspected: Safety Injection System (SI) Note (1): Baseline Examination FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 41 of 46) Note (2): Snubber examined as a Component Support Exelein- Byron Station Unit 1 B1 R15 ISI Outage Report 61010 NIA N-198 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 Component or Manufacturer Manufacturer State or National Appurtenance or installer or Installer Province No. Board No. Serial No. 1SI04B- Hunter Corp. N/A N/A N/A 12/1 RH02029X 1 S104C-8/1 RH02026X Hunter Corp. N/A N/A N/A 1SI04D-8/lRH02022X Hunter Corp. N/A N/A N/A 1 SI05BA-8/1 PC-50A Hunter Corp. N/A N/A N/A 1 SI08CA-4/1 S107008X Hunter Corp. N/A N/A N/A 1S108JA-1-1/2/lSI-Hunter Corp. N/A N/A N/A CP1A 1SI09BA- Hunter Corp. N/A N/A N/A 10/1 S101001 V 6/2 6/2008 FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS | |||
: 1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 3. Plant Unit: 1 4. Owner Certificate Of Authorization (if required): N/A 5. Commercial Service Date: 09/16/85 6. National Board Number for Unit: N-198 7. Components Inspected: Safety Injection System (SI) Note (1): Baseline Examination Note (2): Snubber examined as a Component Support Computer Generated Form As Required by the Provisions of the ASME Code Rules (Page 42 of 46) (Name and Address of Owner) (Name and Address ol Plant) Exel6n- Byron Station Unit 1 B1 R15 ISI Outage Report 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. Component or Appurtenance Manufacturer or Installer Manufacturer or Installer Serial No. State or Province No. National Board No. 1S103DA-2/W-09 Hunter Corp. 1-SI-1-N5 NA NA 1S105BA-8/C01A Hunter Corp. 1-SI-1-N5 NA NA 1Sl06BA-24/C02A Hunter Corp. 1-SI-1-N5 NA NA 1S108GC-1.5/W-01 Hunter Corp. 1-Si-1-N5 NA NA 1S108GC-1.5/W-02 Hunter Corp. 1-SI-1-N5 NA NA 1S108GC-1.5/W-03 Hunter Corp. 1-SI-1-N5 NA NA 1SI08GC-1.5/W-04 Hunter Corp. 1-SI-1-N5 NA NA IS108GC-1.5/W-05 Hunter Corp. 1-SI-1-N5 NA NA 1SI08HA-2/W-01 Hunter Corp. 1-SI-1-N5 NA NA 1S108HA-2/W-02 Hunter Corp. 1-SI-1-N5 NA NA IS108HA-2/W-03 Hunter Corp. 1-SI-1-N5 NA NA 1S108HA-2/W-04 Hunter Corp. 1-SI-1-N5 NA NA 6/26/2008 | |||
: 1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 Note (1): Baseline Examination Note (2): Snubber examined as a Component Support computer Generated Form FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 43 of 46) (Name and Address of Owner) (Name and Address of Plant) 3. Plant Unit: 1 4. Owner Certificate Of Authorization (if required): 5. Commercial Service Date: 09/16/85 6. National Board Number for Unit: 7. Components Inspected: Safety Injection System (SI) &elejn- Byron Station Unit 1 B1 R15 ISI Outage Report N/A N-198 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. Component or Appurtenance Manufacturer or Installer Manufacturer or Installer Serial No. State or Province No. National Board No. 1SI08JA-1.5/W-06 Hunter Corp. 1-SI-1-N5 NA NA 1SI08JA-1.5/W-07 Hunter Corp. 1-SI-1-N5 NA NA 1 SI08JA-1.5/W-08 Hunter Corp. 1-SI-1-N5 NA NA 1SI08JA-1.5fW-09 Hunter Corp. 1-SI-1-N5 NA NA 1 SI08JA-1.5/W-10 Hunter Corp. 1-SI-1-N5 NA NA 1SI08JA-1.5/W-11 Hunter Corp. 1-SI-1-N5 NA NA 1SI08JA-1.5/W-12 Hunter Corp. 1-SI-1-N5 NA NA IS108JA-1.5/W-13 Hunter Corp. 1-SI-1-N5 NA NA 1S108JA-1.5/W-14 Hunter Corp. 1-SI-1-N5 NA NA 1SI08JA-1.5/W-15 Hunter Corp. 1-SI-1-N5 NA NA 6/28/2008 | |||
: 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 (Narne and Address of Plant) 3. Plant Unit: 1 4. Owner Certificate Of Authorization (if required): N/A 5. Commercial Service Date: 09/16/85 6. National Board Number for Unit: N-198 7. Components Inspected: Safety Injection System (SI) Note (1): Baseline Examination FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provlslons of the ASME Code Rules (Page 44 of 46) Note (2): Snubber examined as a Component Support &elejn- Byron Station Unit 1 B1R15 ISI Outage Report 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 Component or Manufacturer Manufacturer State or National Appurtenance or Installer or Installer Province No. Board No. Serial No. 1 S105CA-8/1 S102003S Pacific Scientific 6923 NA NA 6/26!2008 | |||
: 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 Note (1): Baseline Examination Note (2): Snubber examined as a Component Support Computer Generated Form FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 45 of 46) (Name and Address of Plant) &elejn- Byron Station Unit 1 B1 R15 ISI Outage Report 3. Plant Unit: 1 4. Owner Certificate Of Authorization (if required): N/A 5. Commercial Service Date: 09/16/85 6. National Board Number for Unit: N-198 7. Components Inspected: Essential Service Water System (SX) 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. Component or Manufacturer Manufacturer State or National Appurtenance or Installer or Installer Serial No. Province No. Board No. 1 SX08BC- Hunter Corp. N/A N/A N/A 10/1 SX06018X 1SX08BC- Hunter Corp. N/A N/A N/A 10/1 SX06020X 7/9/2008 FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 46 of 46) (BACK) 8. Examination Dates: 10/16/06 to 04/14/08 9. Inspection Period Identification | |||
: 10. Inspection Interval Identification | |||
: 11. Applicable Edition of Section XI: - 2001 Addenda 2003 12. Date / Revision of Inspection Plan: 02/01/08 / Rev. 2 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 Third lnsoecti Q n lntetval 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: C? ~ D 9 ZD Signed for: Exelon Generation Company Computer Generated Form CERTIFICATE OF INSERVICE INSPECTION Exelein- Byron Station Unit 1 B1 R16 ISI Outage Report 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 10/16/06 to 04/14/08 , 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. 6-11 -Inspectors Signature Commissions | |||
: ILL-1254 Date: -~, 20 National Board, State, Province, and Endorsements}} | |||
Revision as of 10:36, 19 March 2019
| ML081930790 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 07/11/2008 |
| From: | Hoots D M Exelon Generation Co, Exelon Nuclear |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 1.10.0101, BYRON 2008-0067 | |
| Download: ML081930790 (109) | |
Text
Exelon Genernflon Company, L-C www.exeloneorp.co m Rvron Station 4450 North Ger=n,an Church Road Byron, IL 61010-9794 July 11, 2008 LTR: BYRON 2008-0067 FILE: 1.10.0101 United States Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Respectfully, Byron Station, Unit 1 Facility Operating License No. NPF-37 NRC Docket No, STNSO-.454
SUBJECT:
Byron Station Unit 1 90-Day Inservice Inspection Report for Interval 3, Period 1, Outage 2 (BIR15) The subject 90-Day Inservice Inspection Report for the Byron Station Unit 1, Refueling Outage Fifteen (BiR15) 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 1 Spring 2008 refueling outage. If there are any questions regarding this matter, please contact W. Grundmann, Regulatory Assurance Manager, at (815)-406-2800. vid M. Hoots Site Vice President Byron Generating Station DMH/RGM/TLH/jeh Attachment
- BlR15 Inservice Inspection Summary Report - Spring 2008 outage Exelon. Nuclear BYRON Exelon.-UNIT 1 Nuclear B1R15 Spring 2008 Outage INSERVICE INSPECTION
SUMMARY
REPORT For Inspection Activities from October 16, 2006 to April 14, 2008 Commercial Service Date September 16, 1985 Document Completion Date July 9, 2008 Exelon Generation Company (EGC, LLC) 4300 Winfield Rd Warrenville, IL 60555 Byron Nuclear Power Station 4450 North German Church Rd. Byron, I L 61010 BYRON UNIT 1 B1R15 Exelonrim Nuclear INSERVICE INSPECTION
SUMMARY
REPORT SECTION SECTION DESCRIPTION PAGES I [Cov er Page ii Table of Contents 1.0 Report introduction TOTAL PAGES IN REPORT] 253 ISI - Weld / Component Listing 16 _ _ ISI- Bolts, Pumps, and Valves Listing 3 Examination PSI - We ld / Component Listing 1 2.0 Summary PSI - Bolts, Pumps, and Valves Listing _ _ 2 Tables ISI - Pressure Tests _ 9 ISI - Component Supports 10 _ ISI - Snubbers 6 3.0 - Status of Examination Completion for the Program Plan 4.0 Form NIS-1: Preservice and Inservice Examinations 46 5.0 Form NIS-2: Repairs/ Modifications 145
1.0 INTRODUCTION
BYRON STATION UNIT 1 REFUELING OUTAGE 15 INSERVICE INSPECTION REPORT 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 October 16, 2006 through April 14, 2008. The majority of these inspections were performed during the fifteenth refueling outage (B1 R15) from March 23 through April 14, 2008. The examinations were performed in compliance with the rules and regulations of ASME Section XI, Division 1, Rules for Inservice Inspection of Nuclear Power Plant Components, (applicable edition and addenda), pursuant to the requirements of 10 CFR 50.55a, Codes and Standards. 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. See 7.0 in this section for a listing of referenced documents. The Nondestructive Examination (NDE) Inservice Inspection (ISI) Program Plan for Class 1, 2, and 3 components was developed in accordance with the requirements and intent of Section XI Subsections IWA, 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 ISI inspections were required. The Byron Station Unit 1 augmented ISI examination requirements include: a) Class 1 pressure boundary for leakage at nominal operating pressure, in accordance with NRC Generic Letter 88-05, Boric Acid Corrosion of Carbon Steel Reactor Pressure Boundary Components in PWR Plants; b) Class 2 and 3 pressure boundary for leakage at nominal operating pressure, in accordance with NUREG 0737, Clarification of TMI Action Plan Requirements c) Examination of RCP Flywheels in accordance with Regulatory Guide 1.14. 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. 1.1 Identification of Examination Requirements The Section 7.0 of the ISI Program Plan contains the examination program tables. These tables are presented in a tabular format consistent with the tables found in Subsections IWB, IWC, IWD, 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 Section 1.0 Page 1 of 5 of Subsection IWA, IWB, IWC, IWD, IWE, IWF, and IWL of Section XI of the ASME Code. For Class 1, 2, and certain non-class piping 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. 1.2 Identification of Exem pted Components BYRON STATION UNIT 1 REFUELING OUTAGE 15 INSERVICE INSPECTION REPORT 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 IWD-1200, Components Exempt from Examination, and Tables IWB-2500-1, IWC-2500-1, and IWD-2500-1, are identified in the NDE 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 of RI-ISI, welds evaluated as Risk Category 6 or 7 are not required to be subject to examination. 1.3 Implementation of the ISI Proqra m 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 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/ASNT CP-189, 1995 Edition and ASNT SNT-TC-1 A, 1984 Edition. Certified personnel performed and evaluated all NDE. Personnel were certified to the requirements of the ASNT SNT-TC-1 A, 1984 Edition. Additionally, ultrasonic examiners were certified in accordance with ANSI/ASNT CP-189, 1995 Revision. The NDE procedures were developed and certified in conformance with ASME Section V and XI as applicable. All ISI NDE, including evaluation of flaw indications, were performed in accordance with the requirements stipulated under Section XI, Subarticle IWA-2200 Examination Methods. 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. Section 1.0 Page 2 of 5
1.4 Significant
Section XI Activities Du rinQB1 R15 BYRON STATION UNIT 1 REFUELING OUTAGE 15 INSERVICE INSPECTION REPORT During the refueling outage, the Alloy 600 reactor vessel safe-end welds were visually examined for evidence of leakage per the requirements specified in EPRI MRP-139. 1.5 ASME Section XI Code Cases The following code case is incorporated into the current Byron Station ISI Program and were utilized during the 15"' fuel cycle. N-566-2 Corrective Action for Leakage Identified at Bolted Connections. The following code case is used for the implementation of the risk-informed program as described in relief request 13R-02. N-578-1 Risk-Informed Requirements for Class 1, 2, or 3 Piping, Method B. 1.6 Witness and Verification of Examination The inservice inspections were witnessed and/or verified by the Authorized Nuclear Inservice Inspectors (ANTI): 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. 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 Preservice Inspection - Weld / Component Listing Preservice Inspection - Bolts, Pumps, and Valves Listing " System Pressure Test Summaries " Component Support Examination Summary " Component Snubber Test Summary 3.0 UNIT 1 EXAMINATION COMPLETION STATUS A summary table of the examination status of Class 1, 2, and 3 components is contained in Section 3.0. Section 1.0 Page 3 of 5 4.0 FORM NIS-1 DATA SHEETS BYRON STATION UNIT 1 REFUELING OUTAGE 15 INSERVICE INSPECTION REPORT ASME Form NIS-1, Owners Report for Inservice Inspections, were filed during the cycle for Unit 1. See Section 4.0 for the reports. 5.0 FORM NIS-2 DATA SHEETS ASME Form NIS-2, Owners Report for Repairs or Replacements, were filed during the cycle for Unit 1. See Section 5.0 for the reports. 6.0 CONTAINMENT ISI PROGRAM No reportable conditions were identified for Class CC and Class MC components during this fuel cycle. 7.0 REFERENCED DOCUMENTS 7.1 Code of Federal Regulations, Title 10 Energy Part 50, Domestic Licensing of Production and Utilization Facilities 50.55a, Codes and Standards
7.2 American
Society of Mechanical Engineers (ASME) 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. 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
7.4 American
Society for Nondestructive Testing ASNT Recommended Practice No. SNT-TC-1 A, 1984 Edition, Personnel Qualification and Certification in Nondestructive Testing 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. Section 1.0 Page 4 of 5
7.6 Electric_
Power Research Institute BYRON STATION UNIT 1 REFUELING OUTAGE 15 INSERVICE INSPECTION REPORT Material Reliability Program Primary System Piping Butt Weld Inspection and Evaluation Guideline (MRP-139)
July 14, 2005. Topical Report TR112657 Revision B-A, Revised Risk-Informed Inservice Inspection Procedure, December 1999. Section 1.0 Page 5 of 5 7/812008 Weld / Component Outage Summary SYSTEM: Chemical & Volume Control System (CV) 1;;=ct;,nI c,'I I C{xie Aclua! Exelon- Byron ~Station Unit 1 BI R15 ISI Outage Report R-A A1.11 1CVA3AA-2/W-O6 1CVA3AA-2 13R-02 139.40 VT-2 NRI Pipe - Elbow 13T-01 13T-02 OBS15-001 R-A R1.11 1CVA3AA-2/W-07 1CVA3AA-2 13R-02 89.40 VT-2 NRI Elbow - Pipe 13T-01 13T-02 OBS15-002 R-A R1.11 1CVA3B-2/W-74 1CVA3B-2 13R-02 89.40 VT-2 NRI Pipe - Elbow 13T-01 13T-02 OBS15-003 R-A RIA1 1CVA3B-21W-75 1CVA3B-2 13R-02 89.40 VT-2 NRI Elbow - Pipe 13T-01 13T-02 OBS15-004 R-A 81,11 1 CVA3B-2/W-76 1 CVA38-2 13R-02 139.40 VT-2 NRI Pipe - Elbow 13T-01 13T-02 OBS15-005 R-A R1.11 1CVA3B-2M-77 1CVA3B-2 13R-02 139.40 VT-2 NRI Elbow - Pipe 13T-01 13T-02 OBS15-006 R-A R1.11 1CVA3B-2/W-84 1CVA38-2 13R-02 139.40 VT-2 NRI Pipe - Elbow 13T-01 13T-02 OBS15-007 R-A 81.11 1CVA3B-2/W-85 1CVA3B-2 13R-02 139.40 VT-2 NRI Elbow - Pipe 13T-01 13T-02 OBS15-008 R-A R1.11 1CVA5AA-2/W-04 1CVA5AA-2 138-02 139.40 VT-2 NRI Pipe - Elbow 13T-01 13T-02 OBS15-009 R-A R1.11 1CVASAA-2/W-05 1CVA5AA-2 13R-02 89.40 VT-2 NRI Elbow - Pipe 13T-01 13T-02 OBS15-010 R-A R1.11 1CVA6AA-2/W-04 1CVA6AA-2 13R-02 89.40 VT-2 NRI Pipe - Elbow 13T-01 13T-02 OBS15-011 7,8/2008 Weld / Component Outage Summary SYSTEM: Chemical & Volume Control System (CV) F ,.;., .. ? 3 f odP Actual t~c" p"."+art re°tip:. _.,~ t4o, - Over~lge Exam &elejn- Byron "Station Unit 1 B1 R15 ISI Outage Report R-A R1.11 OBS15-012 ICVA6AA-2IW-05 Elbow - Pipe 1CVA6AA-2 13R-02 139.40 13T-01 13T-02 VT-2 NRI R-A R1.11 1CVA7AA-21W-08 1CVA7AA-2 13R-02 89.40 VT-2 NRI Pipe - Elbow 13T-01 13T-02 OBS15-013 R-A R1.11 1CVA7AA-2/W-09 1CVA7AA-2 13R-02 139.40 VT-2 NRI Elbow - Pipe 13T-01 13T-02 OBS15-014 7,812008 Weld / Component Outage Summary SYSTEM: Feedwater System (FW) Cr-repo: " g:~2 , De"'c"Ipt
";n Rescan of B1R14 indication per 18 00756048. R-A R1.11 1FW87CA-61C08A 1FW87CA-6 13R-02 C5.51 UT IND 81.18 Pipe - SOL 13T-01 13T-02 _ByronStation Unit 1 B1 R15 ISI Outage Report P ,;,lr,? r~cf,-ic ,.Ii ;'~x , e :~ctu31 r?0" ga(T:as Ne'ces r0v"" ro-i'Ae Exam Exelein-7/8/2008 Weld / Component Outage Summary SYSTEM: Reactor Coolant System (RC) on x Ccr,~t~u;>n4 t. tiaarnut~~n NA RG1.14 1RC-01-PA/FLYWHEEL RCP Flywheel OBS15-153 1) 5/32" LI and 2) 1/16' AI. Acceptable. Ref: R-A 81.15 1RC-01-R/RPVS-A F-1 RPV Nozzle Safe-End HL OBS15-155 Bare-Metal examination per MRP-139 requir R-A 141.15 1 RC-01-R/RPVS-D F-1 RPV Nozzle Safe-End HL OBS15-156 B are-Metal examination per MRP-139 requ ir R-A 141.15 1RC-01-R/RPVS-E F-1 RPV Nozzle Safe-End HL OBS15-157 Bare-Metal examination p erMR P-139 requir OBS15-158 Bare-Metal examination per MRP-139 requir R-A 147.15 1RC-01-R/RPVS-H F-1 RPV Nozzle Safe-End HL R-A 141.20 1 RC13AA-2/W-01 SOL - Pipe OBS15-015 &elejn- Byron --~ Station Unit 1 B1R15 ISI Outage Report R-A 81.20 1 RC13AA-2/W-02
.01 Pipe - Tee OBS15-016 R-A 141.20 1AC13AA-2/W-03 Tee - Reducer OBS15-017 R-A 141.20 1 RC13AA-2/W-04 Tee - Pipe OBS15-018 R-A 141.20 1 RC13AA-2M-05 Pipe - Valve OBS15-019 1RC-01-PA PT IND AIR 2008-237. - _ 1RC-01-R 138-02 85.10 BMV NRI Loop C 13T-01 ments. 13T-02 1 RC-01-R 1314-02 B5.10 BMV NRI Loop D 13T-01 ments. 13T-02 1RC-01-R 1314-02 85.10 BMV NRI Loop A 13T-01 ments. 13T-02 1RC-01-R 1314-02 B5.10 BMV NRI oop B 13T-01 ments. 13T-02 1 RC13AA-2 1314-02 B9.40 VT-2 NRI 13T-01 13T-02 1 RC13AA-2 1314-02 B9.40 VT-2 NRI 13T-01 13T-02 1RC13AA-2 1314-02 B9.40 VT-2 NRI 13T-01 13T-02 1 RC13AA-2 1314-02 B9.40 VT-2 NRI 13T-01 13T-02 1 RC13AA-2 1314-02 89.40 VT-2 NRI 13T-01 13T-02 7,8/2008 Weld l Component Outage Summary SYSTEM: Reactor Coolant System (RC) OBS15-030 1,1"'1+"_ NUf"aDer Exel6n- Byron -Station Unit 1 B1 1415 ISI Outage Report ,,Gs? Arf,Ug; R P4tti~$ Exert? R-A 141.20 1 RC13AB-2/W-01 1 RC13AB-2 1314-02 89.40 VT-2 NRI SOL - Pipe 137-01 137-02 OBS15-020 R-A 81.20 1RC13AB-2/W-09 1RC13AB-2 1314-02 139.40 VT-2 NRI Pipe - Valve 137-01 137-02 OBS15-021 R-A 141.20 1RC13AC-2/W-01 1RC13AC-2 1314-02 89.40 VT-2 NRI SOL - Pipe 137-01 137-02 OBS15-022 R-A 141.20 1 RC13AD-2/W-01 1 RC13AD-2 1314-02 89.40 VT-2 NRI SOL - Pipe 137-01 137-02 OBS15-023 R-A 141.11 1 RC14AA-2/W-02 1 RC14AA-2 1314-02 139.40 VT-2 NRI Pipe - Elbow 137-01 137-02 OBS15-024 R-A 141.11 1RC14AA-2/W-03 1RC14AA-2 138-02 139.40 VT-2 NRI Elbow - Pipe 137-01 137-02 OBS15-025 R-A 141.11 1RC14AA-2/W-03A 1RC14AA-2 1314-02 139.40 VT-2 NRI Pipe - Tee 137-01 137-02 OBS15-026 R-A 141.11 1 RC14AA-2/W-0313 1 RC14AA-2 1314-02 89.40 VT-2 NRI Tee - Reducer 137-01 137-02 OBS15-027 R-A 141.11 1RC14AA-2JW-03C 1RC14AA-2 1314-02 139.40 VT-2 NRI Tee - Pipe 137-01 137-02 OBS15-028 R-A 81.11 1 RC14AA-2/W-04 1 RC14AA-2 1314-02 139.40 VT-2 NRI Pipe - Elbow 137-01 137-02 OBS15-029 R-A 141.11 1 RC14AA-2IW-05 1 RC14AA-2 1314-02 139.40 VT-2 NRI Elbow - Pipe 137-01 137-02 7/8/2008 Weld / Component Outage Summary SYSTEM: Reactor Coolant System (RC) <;r~,p~ : " rnt !iQ N::1 , 11 '11)0r P,y'ie! 1-t, Code At;l*ai r":ot;::n , iotes cxvf~ratle Exam &elejn- Byron Station Unit 1 B1 R15 ISI Outage Report R-A R1.11 1 RC14AA-2/W-06 1 RC14AA-2 13R-02 139.40 VT-2 NRI Pipe - Valve 137-01 137-02 OBS15-031 R-A RI A 1 1 RC14AA-2/W-07 1 RC14AA-2 13R-02 89.40 VT-2 NRI Valve - Pipe 137-01 137-02 OBS15-032 R-A R1.11 1 RC14AA-2/W-08 1 RC14AA-2 13R-02 139.40 VT-2 NRI Pipe - Tee 137-01 137-02 OBS15-033 R-A R1.11 1 RC14AA-2/W-09 1 RC14AA-2 13R-02 139.40 VT-2 NRI Tee - Reducer 137-01 137-02 OBS15-034 R-A R1.11 1RC14AA-2/W-10 1RC14AA-2 13R-02 139.40 VT-2 NRI Reducer - Pipe 137-01 137-02 OBS15-035 R-A R1.11 1 RC14AA-2/W-11 1 RC14AA-2 13R-02 139.40 VT-2 NRI Pipe - Valve 137-01 137-02 OBS15-036 R-A R1.11 1 RC14AA-2/W-12 1 RC14AA-2 13R-02 139.40 VT-2 NRI Pipe - Coupling 137-01 137-02 OBS15-037 R-A R1.11 IRC14AA-2/W-13 1RC14AA-2 13R-02 89.40 VT-2 NRI Coupling - Pipe 137-01 137-02 OBS15-038 R-A R1.11 1RC14AB-2/W-07 1RC14AB-2 13R-02 89.40 VT-2 NRI Coupling - Pipe 137-01 137-02 OBS15-039 R-A R1.11 1RC14AB-2/W-08 1RC14AB-2 13R-02 139.40 VT-2 NRI Pipe - Valve 137-01 137-02 OBS15-040 R-A R1.11 1 RC14AB-2/W-09 1 RC14AB-2 13R-02 89.40 VT-2 NRI Valve - Pipe 137-01 137-02 OBS15-041 7,8/2008 Weld / Component Outage Summary SYSTEM: Reactor Coolant System (RC) 6celein_ __ Byron Station Unit 1 B1R15 ISI Outage Report R-A 81.11 1 RC14AB-2/W-10 1 RC14AB-2 13R-02 139.40 VT-2 NRI Pipe - Tee 137-01 137-02 OBS15-042 R-A R1.11 1RC14AB-2JW-11 1RC14AB-2 13R-02 139.40 VT-2 NRI Tee - Reducer 137-01 137-02 OBS15-043 R-A R1.11 1 RC14AC-2/W-08 1 RC14AC-2 13R-02 89.40 VT-2 NRI Pipe - Valve 137-01 137-02 OBS15-044 R-A 81.11 1RC14AD-2fW-08 1RC14AD-2 13R-02 139.40 VT-2 NRI Pipe - Valve 137-01 137-02 OBS15-045 R-A R1.11 1 RC14AD-2/W-09 1 RC14AD-2 13R-02 139.40 VT-2 NRI Valve - Pipe 137-01 137-02 OBS15-046 R-A 81.11 1 RC14AD-2IW-10 1 RC14AD-2 13R-02 139.40 VT-2 NRI Pipe - Tee 137-01 137-02 OBS15-047 R-A R1.11 1 RC14AD-2/W-11 1 RC14AD-2 13R-02 139.40 VT-2 NRI Tee - Reducer 137-01 137-02 OBS15-048 R-A R1.11 1RC14AD-2JW-12 1RC14AD-2 13R-02 89.40 VT-2 NRI Tee - Pipe 137-01 137-02 OBS15-049 R-A R1.11 1RC14AD-21W-13 1RC14AD-2 13R-02 89.40 VT-2 NRI Pipe - Valve 137-01 137-02 OBS15-050 R-A R1.11 1RC16AA-2/W-02 1RC16AA-2 13R-02 89.40 VT-2 NRI Pipe - Valve 137-01 137-02 OBS15-051 R-A R1.11 1 RC16AA-2IW-03 1 RC16AA-2 138-02 139.40 VT-2 NRI Valve - Pipe 137-01 137-02 OBS15-052 7,8/2008 Weld / Component Outage Summary SYSTEM: Reactor Coolant System (RC) bcelein_ Byron Station Unit 1 B1R15 ISI Outage Report !t t' . .,..^F+.S :r?..;.p A,c;2li 1t. F$e c;:.:!2:a tuf-M 14" , ';!L'S R-A R1.11 1RC16AA-2/W-04 1RC16AA-2 13R-02 139.40 VT-2 NRI Pipe - Elbow 13T-01 13T-02 OBS 15-0 53 R-A R1.11 1 RC16AA-2/W-05 1 RC16AA-2 13R-02 139.40 VT-2 NRI Elbow - Pipe 13T-01 13T-02 OBS15-054 R-A R1.11 1 RC16AA-2/W-06 1 RC16AA-2 13R-02 139.40 VT-2 NRI Pipe - Elbow 13T-01 13T-02 O BS 15-0 55 R-A R1.20 1RC16AA-2/W-07 1RC16AA-2 13R-02 89.40 VT-2 NRI Elbow - Pipe 13T-01 13T-02 OBS15-056 R-A R1.20 1RC16AA-2/W-08 1RC16AA-2 13R-02 139.40 VT-2 NRI Pipe - SOL 13T-01 13T-02 OBS15-057 R-A R1.11 1 RC16AB-2/W-02 1 RC16AB-2 13R-02 89.40 VT-2 NRI Pipe - Elbow 13T-01 13T-02 OBS15-058 R-A 81.20 1 RC22AA-1.5/W-01 1 RC22AA-1.5 13R-02 139.40 VT-2 NRI Reducer - Coupling 13T-01 13T-02 OBS15-059 R-A R1.20 1 RC22AA-1.5/W-02 1 RC22AA-1.5 13R-02 139.40 VT-2 NRI Coupling - Pipe 13T-01 13T-02 OBS15-060 R-A R1.20 1RC22AA-1.5/W-03 IRC22AA-1.5 13R-02 139.40 VT-2 NRI Pipe - Elbow 13T-01 13T-02 OBS15-061 R-A R1.20 1 RC22AA-1.5/W-04 1 RC22AA-1.5 13R-02 139.40 VT-2 NRI Elbow - Pipe 13T-01 13T-02 OBS15-062 R-A R1.20 1 RC22AA-1.5/W-05 1 RC22AA-1.5 13R-02 89.40 VT-2 NRI Pipe - Elbow 13T-01 13T-02 OBS15-063 7,11/2008 Weld / Component Outage Summary SYSTEM: Reactor Coolant System (RC) ~": r~:e. :~1~ors Exelein_ Byron W Station Unit t B1 R16 ISI Outage Report cxAe Ar , ,:~al He ~,,uIt; R-A R1.20 1 RC22AA-1.51W-06 1 RC22AA-1.5 13R-02 139.40 VT-2 NRI Elbow - Pipe 13T-01 13T-02 OBS15-064 R-A R1.20 1 RC22AA-1.51W-07 1 RC22AA-1.5 13R-02 89.40 VT-2 NRI Pipe - Elbow 13T-01 13T-02 OBS15-065 R-A R1.20 1 RC22AA-1.5/W-08 1 RC22AA-1.5 138-02 139.40 VT-2 NRI Elbow - Pipe 13T-01 13T-02 OB S 15-0 66 R-A 81.20 1 RC22AA-1.5PN-09 1 RC22AA-1.5 13R-02 139.40 VT-2 NRI Pipe - Elbow 13T-01 13T-02 OBS15-067 R-A Rt20 1RC22AA-1.5/W-10 1RC22AA-1.5 13R-02 139.40 VT-2 NRI Elbow - Pipe 13T-01 13T-02 OBS15-068 R-A Rt20 1 RC22AA-1.5/W-11 1 RC22AA-1.5 13R-02 89.40 VT-2 NRI Pipe - Elbow 13T-01 13T-02 OBS15-069 R-A R1.20 1RC22AA-1.5/W-12 1RC22AA-1.5 13R-02 89.40 VT-2 NRI Elbow - Pipe 13T-01 13T-02 OBS15-070 8-A R1.20 1 RC22AA-1.5/W-13.01 1 RC22AA-1.5 13R-02 139.40 VT-2 NRI Pipe - Valve I3T-01 13T-02 OBS15-071 R-A R1.20 1 RC22AA-1.5/W-14.01 1 RC22AA-1.5 13R-02 139.40 VT-2 NRI Valve - Pipe 13T-01 13T-02 OBS15-072 R-A R1.20 IRC22AA-1.5/W-15.01 1RC22AA-1.5 13R-02 139.40 VT-2 NRI Pipe - Elbow 13T-01 13T-02 OBS15-073 R-A R1.20 1 RC22AA-1.5/W-16.01 1 RC22AA-1.5 13R-02 139.40 VT-2 NRI Elbow - Pipe 13T-01 13T-02 OBS15-074 7/812008 Weld / Component Outage Summary SYSTEM: Reactor Coolant System (RC) C=at. (~aolr+rE , rw Exelein- Byron ~Station Unit 1 B1R15 ISI Outage Report OBS15-085 10 R-A 131.20 1 RC22AA-1.5/W-17 1 RC22AA-1.5 1313-02 139.40 VT-2 NRI Pipe - Coupling 137-01 137-02 O BS 15-0 75 R-A 131.20 1RC22AA-1.5/W-18 1RC22AA-1.5 1313-02 89.40 VT-2 NRI Coupling - Pipe 137-01 137-02 OBS15-076 R-A 131.20 1 RC22AA-1.5/W-19 1 RC22AA-1.5 1313-02 139.40 VT-2 NRI Pipe - Flange 137-01 137-02 OB S15-077 R-A 131.20 1 RC22AA-1.5/W-20 1 RC22AA-1.5 1313-02 139.40 VT-2 NRI Flange - Pipe 137-01 137-02 OBS15-078 R-A 131.20 1 RC22AA-1.5/W-21 1 RC22AA-1.5 1313-02 139.40 VT-2 NRI Pipe - Tee 137-01 137-02 OBS15-079 R-A 131.20 1 RC22AA-1.5/W-22 1 RC22AA-1.5 1313-02 139.40 VT-2 NRI Tee - Reducer 137-01 137-02 OBS15-080 R-A 131.20 1 RC22AA-1.5/W-23 1 RC22AA-1.5 138-02 139.40 VT-2 NRI Tee - Pipe 137-01 137-02 OBS15-081 R-A 131.20 1 RC22AA-1.5/W-24 1 RC22AA-1.5 1313-02 89.40 VT-2 NRI Pipe - Tee 137-01 137-02 OBS15-082 R-A 131.20 1 RC22AA-1.5/W-25 1 RC22AA-1.5 1313-02 139.40 VT-2 NRI Tee - Reducer 137-01 137-02 OBS15-083 R-A 131.20 1 RC22AA-1.5/W-26 1 RC22AA-1.5 1313-02 89.40 VT-2 NRI Tee - Pipe 137-01 137-02 OBS15-084 R-A 131.20 1 RC22AA-1.5/W-27 1 RC22AA-1.5 1313-02 139.40 VT-2 NRI Pipe - Valve 137-01 137-02 7,812008 Weld / Component Outage Summary SYSTEM: Reactor Coolant System (RC) eqj{',,18 N,+t"'S &elejn- Byron __Station Unit 1 131 R15 ISI Outage Report OBS15-091 R-A 111.20 1 RC22AA-1.5/W-28 1 RC22AA-1.5 1311-02 139.40 VT-2 NRI Valve - Pipe 13T-01 13T-02 OBS15-086 R-A 81.20 1 RC22AA-1.5/W-29 1 RC22AA-1.5 1311-02 139.40 VT-2 NRI Pipe - Elbow 13T-01 13T-02 OBS15-087 R-A 111.20 1 RC22AA-1.5/W-30 1 RC22AA-1.5 138-02 139.40 VT-2 NRI Elbow - Pipe 13T-01 13T-02 OBS15-088 R-A 111.20 1RC22AA-1.5/W-31 1RC22AA-1
.5 1311-02 139.40 VT-2 NRI Pipe - Elbow 13T-01 13T-02 OBS15-089 R-A 111.20 1 RC22AA-1.5/W-32 1 RC22AA-1.5 1311-02 139.40 VT-2 NRI Elbow - Pipe 13T-01 13T-02 OBS15-090 R-A 111.20 1 RC22AA-1.5/W-33 1 RC22AA-1.5 1311-02 B9.40 VT-2 NRI Pipe - WOL 13T-01 13T-02 7/8/2008 Weld / Component Outage Summary SYSTEM: Reactor Pressure Vessel (RPV) Fw:xf C, ;,de Arl wi ) Xquys VT-3 RI OBS15-144 IR 00757175 for foreign m aterial on flange surface. All other conditions NRI. Exelon_ Byron Station Unit t B1R15 ISI Outage Report Pj l .'W's x I f ,.1 via L qa_ ~ c 3t bswov= cv" ,:~ws B-N-1 813.10 IRC-01-R/RPV 1 RC-01 -R INTERIOR RPV Interior Surfaces 7,8/2008 Weld / Component Outage Summary SYSTEM: Reactor Coolant System (RY) Exelon- Byron ~Station Unit 1 B1 R15 ISI Outage Report ^,ra;~~at .f19 !', ui,n OBS15-097 R-A 81.11 1RY18A-2/W-05A 1RY18A-2 1311-02 139.40 VT-2 NRI Valve - Pipe 13T-01 13T-02 OBS15-092 R-A 111.11 1 RY18A-21W-06 I RY18A-2 1311-02 139.40 VT-2 NRI Pipe - Elbow 13T-01 13T-02 OBS15-093 R-A 111.11 1 RY18A-27W-07 1 RY18A-2 1311-02 139.40 VT-2 NRI Elbow- Pipe 13T-01 13T-02 OBS15-094 R-A 111.11 1RY18A-21W-08 1RY18A-2 1311-02 89.40 VT-2 NRI Pipe - Elbow 13T-01 13T-02 OBS15-095 R-A 111.11 1 RY18A-2/W-09 1 RY18A-2 1311-02 139.40 VT-2 NRI Elbow - Pipe 13T-01 13T-02 OBS15-096 R-A 111.11 1 RY18A-2/VV-10 1 RY18A-2 1311-02 139.40 VT-2 NRI Pipe - WOL 13T-01 13T-02 7/8(20NO8 Weld / Component Outage Summary SYSTEM: Steam Generator (SG) Liri, 1.1 , m~~,r C-B C2.22 1RC-01-BB/N-3-NIR 1RC-01-BB UT NRI FW Nozzle Inner Radius OBS 15 -151 Roiqlf c 1, F ,!,: w cc-(~e Act , ,;a Exelon. BI R1 5 ISI Outage Report 7/8/2008 Weld / Component Outage Summary SYSTEM: Safety Injection System (SI) PT NRI PT NRI PT NRI Exelein- 11----"-.,----, Byron Station Unit 1 B1 R15 ISI Outage Report Cr>4 r- Actu:ii pa : , ,jIts OBS15-152 Welded Attachment (VALVE ENC. 1S18811A)
R-A 81.11 1 SI08GC-1.5/W-01 1 SI08GC-1 .5 13R-02 89.40 VT-2 NRI Reducer - Coupling 137-01 137-02 OBS15-098 R-A R1.11 1SI08GC-1.5/W-02 1S108GC-1.5 13R-02 B9.40 VT-2 NRI Coupling - Pipe 137-01 137-02 OBS15-099 R-A R1.11 1S108GC-1.5/W-03 1SI08GC-1.5 13R-02 89.40 VT-2 NRI Pipe - Elbow 137-01 137-02 OBS15-100 R-A R1.11 1SI08GC-1.5/W-04 1S108GC-1.5 13R-02 59.40 VT-2 NRI Elbow - Pipe 137-01 137-02 OBS15-101 R-A R1.11 1S108GC-1.5/W-05 1SI08GC-1.5 13R-02 B9.40 VT-2 NRI Pipe - Reducer 137-01 137-02 OBS15-102 R-A 81.11 1SI08HA-2/W-01 1SI08HA-2 13R-02 B9.40 VT-2 NRI Reducer - Pipe 137-01 137-02 OBS15-103 R-A 81.11 1SI08HA-2/W-02 1SI08HA-2 13R-02 89.40 VT-2 NRI Pipe - Flange 137-01 137-02 OBS15-104 R-A R1.11 1SI08HA-2/W-03 1SI08HA-2 13R-02 B9.40 VT-2 NRI Flange - Pipe 137-01 137-02 OBS15-105 B-K B10.20 1S103DA-2/W-09 1SI03DA-2 100 Closure Plate 1RB-61A OBS15-149 C-C C3.20 1SI05BA-8/C01A 1SI05BA-8 NA 100 Closure Plate 1 PC-50 OBS15-123 C-C C3.20 1SI06BA-24/C02A 1S106BA-24 100 7,8/2008 Weld / Component Outage Summary SYSTEM: Safety Injection System (SI) Exelon- Byron Station Unit 1 B1 R15 ISI Outage Report {7 ( ".n , N c, {° OW apt 1 o ,~, e Actual OBS15-116 1 6 R-A 81.11 1SI08HA-2/W-04 1SI08HA-2 1311-02 89.40 VT-2 NRI Pipe - Reducer 13T-01 13T-02 OBS15-106 R-A 111.11 1SI08JA-1.5/W-06 1SI08JA-1.5 1311-02 89.40 VT-2 NRI Pipe - Valve 13T-01 13T-02 CBS15-107 R-A 111.11 1 $I08JA-1.5/W-07 1 SI08JA-1.5 1311-02 B9.40 VT-2 NRI Valve - Pipe 13T-01 13T-02 OBS15-108 R-A 111.11 1S108JA-1.5/W-08 1SI08JA-1.5 1311-02 139.40 VT-2 NRI Pipe - Coupling 13T-01 13T-02 OBS15-109 R-A 111.11 1 SI08JA-1.5/W-09 1 SI08JA-1.5 1311-02 139.40 VT-2 NRI Coupling - Pipe 13T-Ot 13T-02 OBS15-110 R-A 111.11 1SI08JA-t5/W-10 1SI08JA-1.5 1311-02 139.40 VT-2 NRI Pipe - Flange 13T-01 13T-02 OBS15-111 R-A 81.11 1SI08JA-1.5/W-11 1SI08JA-1.5 1311-02 89.40 VT-2 NRI Flange - Pipe 13T-01 13T-02 OBS15-112 R-A 111.11 1SI08JA-1.5/W-12 1SI08JA-1.5 1311-02 139.40 VT-2 NRI Pipe - Elbow 13T-01 13T-02 OBS15-113 R-A 81.11 1Sl08JA-t5/W-13 1SI08JA-1.5 1311-02 139.40 VT-2 NRI Elbow - Pipe I3T-01 13T-02 OBS15-114 R-A 111.11 1SI08JA-1.5/W-14 1SI08JA-1.5 1311-02 89.40 VT-2 NRI Pipe - Elbow 13T-01 13T-02 OBS15-115 R-A 111.11 1SI08JA-1.51W-15 IS108JA-1.5 1311-02 139.40 VT-2 NRI Elbow - Pipe 13T-01 13T-02 7/a/2008 Bolts, Pumps, and Valves Outage Summary SYSTEM: Reactor Pressure Vessel (RPV) Cat, ;teal Co,,Crlpl; in OBS15-148 Washe rs 3 to 11, 13 to 18, 55, 56, and 60. !:M Fit:que ils Exelein- Byron Station Unit 1 131 R15 ISI Outage Report I r'urrtjai ~+t; ults Exam Co%~;r`~t>rtE s B-G-1 136.10 1 RC-01-R/N01-N18 NA VT-1 NRI RPV Closure Head Nuts OBS15-145 N16 d ent on OD surface. B-G-1 136.20 1RC-01-R/S01-S18 NA UT NRI RPV Closure Head Studs OBS15-146 Studs 01 to 07, 9, 11, 12, 14 to 18, 55, 56, and 57. B-G-1 136.50 1RC-01-R(W01-W18 NA VT-1 NRI Closure Washers 7/8/2008 Bolts, Pumps, and Valves Outage Summary SYSTEM: Steam Generator (SG) ._ "-.f t aJr3 (.7t. Cc_, ,* ^eplt$ ~zc:r ;tour, &elejn- --- Byron~Station Unit 1 B1 R15 ISI Outage Report Fsr:i at '"" ci,n-cal Actua, Rofautls FiW1t.rPStg OBS15-137 B-G-1 136.100 1RC-01-BA/FLG SURF-CL NA VT-1 NRI Manway Flange Surface (Crossunder)
OBS15-130 El-G-1 86.100 1RC-01-BA/FLG SURF-HL NA VT-1 NRI Manway Flange Surface (Hot Leg) OBS15-131 B-G-1 136.100 1RC-01-BB/FLG SURF-CL NA VT-1 NRI Manway Flange Surface (Crossunder)
OBS15-132 B-G-1 136.100 1RC-01-BB/FLG SURF-HL NA VT-1 NRI Manway Flange Surface (Hot Leg) OBS15-133 B-G-1 136.100 1RC-01-BC/FLG SURF-CL NA VT-1 NRI Manway Flange Surface (Crossunder)
OBS15-134 B-G-1 136.100 1RC-01-BC/FLG SURF-HL NA VT-1 NRI Manway Flange Surface (Hot Leg) OBS15-135 B-G-1 136.100 1RC-01-BD/FLG SURF-CL NA VT-1 NRI Manway Flange Surface (Crossunder)
OBS15-136 B-G-1 136.100 1RC-01-BD/FLG SURF-HL NA VT-1 NRI Manway Flange Surface (Hot Leg) 7/8/2008 Bolts, Pumps, and Valves Outage Summary SYSTEM: Safety Injection System (SI) B-G-2 B7.50 IS108JA-1.5/FLG 1-4 NA PFB-S1-2 VT-1 NAI Piping Flange Bolting OBS15-154 Dissassembled under WO 1042252. Exelon- Byron Station Unit 1 B1R15 ISI Outage Report P1 TtchtItC.l; 4GIU39 Heg"tiIs E isa*tq 7/ar2008 Weld / Component Outage Summary (Preservice Inspections)
SYSTEM: Feedwater System (FW) IttaY? ?;zf~rtCtlihfl rtrn1s Baseline exam of replacement pipe weld W-4, WO 00955081. rb~, t (V" htot "er~h~~caa~
t:; Rg~uirf, iucsis Note,S ^.tir"`tat. f-x jeh Exelein- Byron Station Unit 1 B1 R1 S ISI Outage Report F t,Bults R-A R1.11 1FW03DA-16/C01
.01 1FW03DA-16 13R-02 C5.51 100 SURF MT NRI R1.18 Valve-Pipe 13T-01 100 VOL-E UT GEOM 13T-02 Baseline exam of replacement pipe weld W-1, WO 00955081. R-A R1.11 1FW03DA-16/C01B 1FW03DA-16 13R-02 C5.51 100 SURF MT NRI R1.18 Pipe-Pipe 13T-01 100 VOL-E UT GEOM 13T-02 7/8/2008 Detailed Inservice Inspection Bolts, Pumps, and Valves Listing (PSI) SYSTEM: Reactor Coolant System (RY) e" t~;ittir? X.i r-cn~irw AraL?3f NOT" EP3m &elejn- Byron ~~Station Unit 1 131 R15 ISI Outage Report NRI NRI Replacement of nut under WO 00966737. Page 1-1 7/8/2008 B-G-2 137.50 1RY038C-6/FLG 1-12 NA PFB-RY VT-1 Piping Flange Bolting B aseline ex a m for 1 RY8010C replacement. WO#009615450-08. B-G-2 87.50 1RY76A-2/FLG 1-8 NA VT-1 Piping Flange Bolting
/!312008 Detailed Inservice Inspection Bolts, Pumps, and Valves Listing (PSI) SYSTEM: Steam Generator (SG) XI ID F}, ,~} ej Tcwi;r,;cai ~~xioai Results pert) I Q&C-" , ptiry.l pi" q-C'Sts Exelon- Byron V Station Unit 1 B1R15 ISI Outage Report Baseline exam of replacement manway stud #16, WO 00883690. 9/64' axial indication, acceptable per procedure. B-G-1 86.90 1RC-01-BA/STUDS-CL01-20 NA MT NRI Manway Studs 1-20 (Crossunder)
B aseline exam of replac em ent manway st ud #15, WO 00880420. B-G-1 86.90 1RC-01-BA/STUDS-HL01-20 NA MT NRI Manway Studs 1-20 (Hot Leg) Baseline exam of replacement manway stud #19, WO 00880420. B-G-1 86.90 1RC-01-BC/STUDS-CL01-20 NA MT NRI Manway Studs 1-20 (Crossunder)
Baseline exam of replacem ent manway stud #08, WO 00883690. B-G-1 B6.90 1 RC-01-BC/STUDS-HL 01-20 NA MT RI Manway Studs 1-20 (Hot Leg) 7,8/2008 Pressure Test Outage Summary SYSTEM: Auxiliary Feedwater System (AF) Cat. item , iTtti!entC NA NA 1-AF-2-1 NA NA 1-AF-2-2 T>" rhi+.tCasl ACtu'al, Rf-gtti7~'ts Notes F,Xj+/-t1 Exeloin- Byron _,... Station Unit 1 BIR15 ISI Outage Report VT-2 NRI VT-2 NRI Pressure Test Outage Summary SYSTEM: Containment Spray System (CS) t1~,; ei I(!Cr,r , , 4~4 ~iit-'Gi:CbtS ."v0t~-S Exelon- Byron Station Unit 1 B1 R15 ISi Outage Report NA NA 1-CS-2-1 VT-2 NRI NA NA 1-CS-2-2 VT-2 NRI NA NA 1-CS-2-3 VT-2 NRI NA NA 1-CS-2-4 VT-2 NRI NA NA 1-CS-2-5 VT-2 NRI 7/aI2008 Pressure Test Outage Summary SYSTEM: Chemical & Volume Control System (CV) t5 Exelein- Byron ~Station Unit 1 B1 R15 ISI Outage Report NA NA 1-CV-2-1 I3T-03 VT-2 13T-04 NRI NA NA 1-CV-2-10 VT-2 NRI NA NA 1-CV-2-2 VT-2 NRI NA NA 1-CV-2-3 VT-2 NRI NA NA 1-CV-2-4 VT-2 NRI NA NA 1-CV-2-5 VT-2 NRI NA NA 1-CV-2-7 VT-2 NRI 7/8/2008 Pressure Test Outage Summary SYSTEM: Fuel Pool Cooling System (AF) r.-~ f- gof ," s " ar,z s Exelein- ByronStation Unit 1 B1 R15 ISI Outage Report VT-2 NRI 7/812008 7/8/20NOB Pressure Test Outage Summary SYSTEM: Process Sampling System (PS) S -, I , XI cofllp~~(1
, 7 CA ZINTI Cans-.moms Exel6n- Byron siaiion Unit , 1 BIR15 ISI Outage Report NA NA 1-PS-2-1 VT-2 NRI NA NA 1-PS-2-2 VT-2 NRI NA NA 1-PS-2-3 VT-2 NRI NA NA 1-PS-2-4 VT-2 NRI NA NA 1-PS-2-5 VT-2 NF31 NA NA 1-PS-2-6 VT-2 NRI 7/8/2UGS Pressure Test Outage Summary SYSTEM: Reactor Coolant System (RC) NA NA 1-RC-1-1 MR* tmelein- r i B1RI5 ISI Outage Report R-" iipf n: "lop , , ! f, t 4 v xam VT-2 NRI 7/8/2008 Pressure Test Outage Summary SYSTEM: Residual Heat Removal System (RH) v Byron Station Unit 1 B1R15 ISI Outage Report Exelein- 7/8/2008 NA NA 1-RH-2-1 VT-2 NRI NA NA 1-RH-2-2 VT-2 NRI NA NA l-RH-2-3 VT-2 NRI NA NA 1-RH-2-6 VT-2 NRI 7/8/2008 Pressure Test Outage Summary SYSTEM: Reactor Coolant System (RY) NA NA 1-RY-2-1 Exelein_ Byron Station Unit 1 B1 R15 ISI Outage Report ical Asatztl f ;, `, ,u=;s c~,IS 'i02~'~ E:xaa'1 VT-2 NRI 7/8/2008 7,8/2008 Pressure Test Outage Summary SYSTEM: Safety Injection System (SI) Exelein_ - ByronStationUnit 1 B1 R15 ISI Outage Report NA NA 1-SI-2-1 VT-2 NRI NA NA 1-SI-2-2 VT-2 NRI NA NA 1-SI-2-3 VT-2 NRI NA NA 1-SI-2-4 VT-2 NRI NA NA 1-SI-2-6 VT-2 NRI NA NA 1-SI-2-7 VT-2 NRI 7/8/2008 Component Support Outage Summary SYSTEM: Auxiliary Feedwater System (AF) F-A F1.20 1AF02EA-4/1AF06001R 1AF02EA-4 VT-3 NRI Rigid &elejn- Byron _ Station Unit 1 B1R16 ISI Outage Report 7/8/2008 Component Support Outage Summary SYSTEM: Containment Spray System (CS) Exelein- Byron W Station Unit 1 B1R15 ISI Outage Report Mi nor surface rust only, no wast ag e F-A F1.20 1CS02AA-10/ICS03003V 1CS02AA-10 VT-3 NRI VARIABLE-Spring Can All welds painted F-A F1,20 1CS10AA-6/lCS03028X 1CS10AA-6 VT-3 NRI SEISMIC F-A F1.20 1CS10AA-6/lCS03089A 1CS10AA-6 VT-3 NRI ANCHOR 7/ar2ooa Component Support Outage Summary SYSTEM: Chemical & Volume Control System (CV) Exelon- Byron Station Unit 1 B1R15 ISI Outage Report F-A F1.20 1CV08BA-411CV01002X SEISMIC 1CV08BA-4 VT-3 NRI F-A F1.10 1CVA3B-2/1CV16024X 1CVA3B-2 VT-3 NRI SEISMIC F-A F1.10 1CVA3B-2/1CV16083X 1CVA3B-2 VT-3 NRI SEISMIC 7/8/2008 Component Support Outage Summary SYSTEM: Feedwater System (FW) Reference IR 757579, within allowable cold range. bcelcin_ Byron Station Unit 1 B1R15 ISI Outage Report F-A F1.20 1FW81AA-6/1AF06038R RIGID 1FW81AA-6 VT-3 NRI F-A F1.20 1FW81AA-6/lAF06039X 1FW81AA-6 VT-3 NRI SEISMIC Ins ulation removed for examination. F-A F1.20 1FW81BA-6/1AF060A0V 1FW81BA-6 VT-3 NRI VARIABLE VT-3 PMT NRI 7/8/2008 Component Support Outage Summary SYSTEM: Main Steam System (MS) C-xelein_
Byron Station Unit 1 B1R1S ISI Outage Report d i~-r rd, i nF ,.W;r,i(;J< t+c",ua! AAVk;as tL X i1 ~Y1 F-A F1.20 1 MS01 BB-30-3/4/1 PC-85A 1 MS01 BB-30.75 VT-3 NRI ANCHOR VT-3 NRI 03/30/2008 Exam performed on surfaces outside containment (Direct). 03/29/2008 Exam performed on surfaces inside containment (Direct and Remote). Surface rust ide ntif ied during both exams. No evidence of wastage or loss of materi al.
7,$/2008 Component Support Outage Summary SYSTEM: Reactor Coolant System (RC) F-A F1.40 1 RC-01-BA/S I RC-01-BA VT-3 NRI SG A SUPPORT VT-3 NRI VT-3 NRI IR# 757 349, Written to address boric acid on all 4 SG support leg bases. After c le aning, no degradation identified. &elon- Byron - Station Unit 1 B1R15 ISI Outage Report 7/8/2008 Component Support Outage Summary SYSTEM: Residual Heat Removal System (RH) Exelon_ -Byron Station Unit 1 B1 R15 ISI Outage Report r_+/-u;0 4:aii(S t,'ortp F-A F1.40 1RH-01-PA/Ll 1RH-01-PA VT-3 NRI RH PUMP 1 A LUG 1 10-Minor surface rust, no degradation F-A F1.40 1 RH-01-PA/L2 1 RH-01-PA VT-3 NRI RH PUMP 1A LUG 2 10-Minor surface rust, no degradation F-A F1.40 1RH-01-PA/L3 1RH-01-PA VT-3 NRI RH PUMP 1 A LUG 3 10-Minor surface rust, no degradation F-A F1.20 1 RH02AA-8/1 RH07016V 1 RH02AA-8 VT-3 NRI VARIABLE-Spring Can All welds painted F-A F1.40 1 RH-02-AB/SKT 1 RH-02-AB VT-3 NRI RH HX B SKIRT All welds painted F-A F1.20 1 RH03AA-8/1 RH01003X 1 RH03AA-8 VT-3 NRI SEISMIC - Strut All welds painted 7/8/2008 Component Support Outage Summary SYSTEM: Reactor Coolant System (RY) F-A F1.40 1 RY-01-S/SKT 1 RY-01-S VT-3 NRI PRESSURIZER SKIRT Pressurizer Skirt / Base Exelon- Byron __Station Unit 1 BIR15 ISI Outage Report 7/8/2008 Component Support Outage Summary SYSTEM: Safety Injection System (SI) Exelein- Byron Station Unit 1 B1R15 ISI Outage Report NRI NRI NRI NRI NRI 03/21/08 Exam, Direct (Area 5 Outside Containment) 03/29/2008 Exam, Direct and Remote Inside Containment. Minor surface rust identified during both exams. No evidence of wastage or material loss. NRI NRI NRI F-A F1.20 1S104B-12/1RH02029X 1SI04B-12 VT-3 SEISMIC F-A F1.20 1 SI04C-8/1 RH02026X 1 SI04C-8 VT-3 SEISMIC F-A F1.10 1S104D-8/1RH02022X 1SI04D-8 VT-3 SEISMIC F-A F1.20 1 S105BA-8/1 PC-50A 1 SI05BA-8 VT-3 ANCHOR VT-3 F-A F1.20 1SI08CA-4/1SI07008X SEISMIC 1S108CA-4 VT-3 F-A F1.10 1SI08JA-1-1/2/1SI-CP1A 1SI08JA-1-1/2 VT-3 SEISMIC F-A F1.10 1SI098A-10/1S101001V 1SI09BA-10 VT-3 VARIABLE Component Support Outage Summary SYSTEM: Essential Service Water System (SX) F-A F1.20 1SX08BC-10/lSX06018X 1SX08BC-10 VT-3 NRI SEISMIC F-A F1.20 1SX08BC-10/lSX06020X 1SX08BC-10 VT-3 NRI SEISMIC Exelein- Byron ~~ Station Unit 1 B1 R15 ISI Outage Report 7/8/2008 SYSTEM: Chemical _& Volume Control S~(stem (CV) Snubber Outage Summary (Page 1 of 6) Initial Exam Note: Section XI Category numbers N/A-ed are exempt from IWF-1220 and IWF-2500 tables Byron Station Unit 1 Byron Station Outage B1R15 ~*,ri (: ai A~; wI ra,,co3 Exelc'm_ NA NA 1CV15AC-3/4/1CV29003S 1CV15AC-3/4 VT-3 NRI SNUBBER SR F-A F1.10 1CVA5AA-2/1CV15054S 1CVA5AA-2 VT-3 NRI SNUBBER SR FT PASS Initial Exam NA SNUB 1RC14AB-2/1CV15039-S1 1RC14AS-2 VT-3 NRI SNUBBER SR FT PASS Initial Exam NA SNUB 1RC14AB-2/1CV15039-S2 1RC14AB-2 VT-3 NRI SNUBBER SR FT PASS 7/8/2008 SYSTEM: Main Steam System (MS) Initial Exam Snubber Outage Summary (Page 2 of 6) Note: Section XI Category numbers N/A-ed are exempt from IWF-1220 and IWF-2500 tables 2 ~Byron Station Unit 1 Byron Station Outage B11115 Nk"tes - z :^i Exeiein_ NA SNUB 1MS01AC-32
.75 /1MS07006-S1 1MS01AC-32
.75 y VT-3 NRI SNUBBER 19 FT PASS NA SNUB 1MS01AC-32
.75 /1MS07006-S2 1MS01AC-32
.75 y VT-3 NRI SNUBBER 19 FT PASS Initial Exam 7/8/2008 SYSTEM: Reactor Coolant Svstem (RC) Snubber Outage Summary (Page 3 of 6) Exelesn_ Byron Station Unit 1 Byron Station Outage B1 R15 1., of A ,.Ii.,~i Re;i~+rs R;>,.~_osts Initial Exam Note: Section XI Category numbers N/A-ed are exempt from IWF-1220 and IWF-2500 tables 3 F-A F1.40 1RC01BA-1 A/1RC06S 1RC01BA-1A VT-3 NRI SNUBBER SR Reservoir Setting = 4-7/8, Minor weepage on reservoir piston seal. F-A F1.40 1 RC01 BA-1 A/1 RC07S 1 RC01 BA-1 A VT-3 NRI SNUBBER SR Reservoir Setting = 4-112. Minor weepage on reservoir piston seal. F-A F1.40 1 RC01 BB-1 B/1 RC08S 1 RC01 BB-1 B VT-3 NRI SNUBBER SR Reservoir Setting = 4-3/4. Minor weepage on reservoir piston seal. F-A F1 .40 1 RC01 BB-1 B/1 RC09S 1 RC01 BB-1 B VT-3 NRI SNUBBER SR Reservoir Setting = 4-1/2. Minor weepage on reservoir piston seal. F-A F1.40 1RC01BC-1C/1RC10S 1RC01BC-1C VT-3 NRI SNUBBER SR Reservoir Setting = 4-1/2. Minor weepage on reservoir piston seal. F-A F1.40 1 RC01 BC-1 C/1 RC11 S 1 RC01 BC-1 C VT-3 NRI SNUBBER SR Reservoir Setting = 4-5/8. Minor weepage on reservoir piston seal. F-A F1.40 1 RC01 BD-1 D/1 RC12S 1 RC01 BD-1 D VT-3 NRI SNUBBER SR FT PASS Reservoir Setting = 5-5/8. Minor weepage on reservoir piston seal. F-A F1.40 1 RC01 BD-1 D/1 RC13S 1 RC01 BD-1 D VT-3 NRI SNUBBER SR Reservoir Setting = 4. Minor weepage on reservoir piston seal. F-A FIA0 1RC14AB-2/1CV15053S 1AC14AB-2 VT-3 NRI SNUBBER SR FT PASS Initial Exam NA NA 1 RC20AB-3/4/1 RC17012S 1 RC20AB-3/4 VT-3 NRI SNUBBER SR FT PASS Initial Exam F-A F1.10 1 RC22AB-1.5/1 RC17015S 1 RC22AB-1.5 VT-3 NRI SNUBBER SR FT PASS Initial Exam F-A F1.10 1 RC22AB-1.5/1 RC170288 1 RC22AB-1.5 VT-3 NRI SNUBBER SR FT PASS Snubber Outage Summary (Page 4 of 6) SYSTEM: Residual Heat Removal System (RH) Byron Station Unit 1 Byron Station Outage B1R15 Note: Section XI Category numbers N/A-ed are exempt from IWF-1220 and IWF-2500 tables 4 Exelein_ F-A F1.10 1 RHOl AA-12/1 RH02054S 1 RH01AA-12 VT-3 NRI SNUBBER SR FT PASS Initial Exam F-A F1.20 1 RH02AB-8/1 RHO8015S 1 RH02AB-8 VT-3 NRI SNUBBER SR FT PASS 7/8/2008 SYSTEM: Reactor C oolan t Syste n RY) Snubber Outage Summary (Page 5 of 6) &elejn- Byron Station Unit 1 Byron Station Outage B1R15 Initial Exam Note: Section XI Category numbers N/A-ed are exempt from IWF-1220 and IWF-2500 tables 5 F-A F1.10 1RY01AA-4/lRY06066S 1RY01AA-4 VT-3 NRI SNUBBER SR FT PASS Initial Exam F-A F1.10 1 RY01 B-6/1 RY06022S 1 RY01 B-6 VT-3 NRI SNUBBER SR FT PASS 7/8/2008 SYSTEM: Safety Iniection Svstem (SIB Snubber Outage Summary (Page 6 of 6) F-A F1.20 1SI05CA-8/1SI02003S 1SI05CA-8 VT-3 NRI SNUBBER SR FT PASS Initial Exam Note: Section XI Category numbers N/A-ed are exempt from IWF-1220 and IWF-2500 tables 6 Exelein. ~Byron^StationUnit 1 Byron Station Outage B1R15 Category B-A Non-Deferred Exams 81.30 1 1 0 0 1 1 0 1 0 100.00% 0.00 0/0 0.00% 0.00 0/0 81.40 1 1 0 0 1 1 0 1 0 100.00 0/0 0.00 0/0 0.00 0/0 0.00 0/0 Totals: 2 2 0 0 1 1 0 1 0 100.00% 0.00% 0.00% 0.00 0/0 Category B-A Deferred Exams 81.11 3 3 N/A 0 N/A N/A 0 N/A 0 100.00% 0.00% 0.00% 0.00% B1.21 2 2 N/A 0 N/A N/A 0 N/A 0 100.00 0/0 0.00 0/0 0.00% 0.00% Totals: 5 5 N/A 0 N/A N/A 0 WA 0 100.00°.6 0.00% 0.00% 0.00% Category B-B Non-Deferred Exams 82.11 2 2 0 0 1 1 0 1 0 100.00% 0.00% 0.00% 0.00% 82.12 2 2 0 0 1 1 0 1 0 100.00% 0.00% 0.00% 0.00% 82.40 4 1 0 1 1 1 0 1 0 25.00% 100.00% 100.00 0/0 100.00% Totals: 8 5 1 1 2 2 0 2 0 62.50% 20.00% 20.00% 20.00% 1. (82.40) Per Examination Category B-B, Note 1, examinations maybe limited to one vessel among a group of vessels performing a similar function. Category B-D Non-Deferred Exams 83.110 6 6 1 5 3 -2 0 -1 0 100.00% 83.33% 83.33% 83.33% 83.120 6 6 1 5 3 -2 0 -1 0 100.00% 83.33% 83.33% 83.33% 83.140 8 8 2 0 4 4 0 6 0 100.00% 0.00% 0.00% 0.00% Totals: 20 20 4 10 10 0 0 5 0 100.00% 50.00% 50.00% 50.00 0/0 1. (B3.120& 83.140) 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, and requires that a visual examination with enhanced magnification may be performed on the inside radius section in place of an ultrasonic examination. Categ ory B-D Deferred Exams 83.90 8 8 N/A 0 N/A N/A 0 N/A 0 100.00 0/0 0.00 0/0 0.00% 0.00 0/0 8 3.100 8 8 N/A 0 N/A N/A 0 N/A 0 100.00% 0.00 0/0 0.00% 0.00% Totals: 16 16 N/A 0 N/A N/A 0 WA 0 100.00% 0.00% 0.00% 0.00% Section 3.0 Page 1 of 8 (This report is used to verify that the periodic BYRON STATION UNIT 1 AND UNIT COMMON - 3RD INTERVAL (The percentage requirements o¬ Tables IWx-- requirements of Tables IWx-2412-1 will be met by ASME SECTION XI EXAMINATION STATUS REPORT 2412-1 apply to the Category and were t h e in t e rval s chedu le. ay. led to each Item only when practical.) # of Total # Exams Completed
% Exams Completed Item No. Com Selected Min Per 1 Max Min Per 2 Max Per 3 % Selected Period 1 Period 2 Period 3
- 1. (133.100) This Item Number requires a visual examination with enhanced magnification in lieu of volumetric examination, as allowed by Code Case N-648-1. 2. (133.90 & 133.100) Per Examination Category B-D, Note 5, for PWR's in the second and successive inspection intervals, these examinations maybe 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. Category B-G-1 Deferred Exams 1. (136.10 & 86.20 & 136.50) Single components representing one third of the 54 Reactor Vessel Closure Head Nuts, Closure Studs, and Closure Washers, Bushings. 2. (86.40) A single component representing all of the 54 Reactor Vessel Threads in Flange to be examined. 3. (136.90 & 136.100 & 136.110) 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 Steam Generator Manways. Each of the eight entries represents 20 bolts and associated parts for an individual manway. 4. (136.170) A single component represents the five sets of CETC column nuts. 5. (136.180) 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. 6. (136.190 & 136.200) Four components are tracked in the database, each representing all 24 associated Flange Surfaces and Nuts, Bushings, and Washers for one of the four Reactor Coolant Pumps (96 total) as reported in the ISI Program Plan. The visual examination of these components is limited to only one of the 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. Section 3.0 Page 2 of 8 (This report is used to verity that the periodic WY ON STATION UNIT 1 AND UNIT COMMON - 3RD INTERVAL (The percentage requirements of Tables IWx- requirements of Tables IWx-2412-1 will be met by ASME SECTION XI EXAMINATION STATUS REPORT 2412-1 apply to the Category and were the interval schedule. a,u died to each Item only when practical.) # of Total # Exams Completed
% Exams Completed Item No. Com Selected Min Per 1 Max Min Per 2 Max Per 3 % Selected Period 1 Period 2 Period 3 136.10 3 3 NIA 1 N/A N/A 0 N/A 0 100.00% 33.33% 33.33% 33.33% 86.20 3 3 N/A 1 N/A N/A 0 N/A 0 100.00% 33.33% 33.33% 33.33% 66.40 1 1 N/A 0 N/A N/A 0 N/A 0 100.00 0/0 0.00% 0.00% 0.00% 136.50 3 3 N/A 1 N/A N/A 0 N/A 0 100.00% 33.33% 33.33% 33.33% 86.90 8 8 N/A 0 N/A N/A 0 N/A 0 100.00% 0.00% 0.00 0/0 0.00 0/0 136.100 8 8 N/A 8 N/A N/A 0 N/A 0 100.00% 100.00% 100.00% 100.00% 136.110 8 8 N/A 0 N/A N/A 0 N/A 0 100.00% 0.00% 0.00% 0.00% 136.170 1 1 N/A 0 N/A N/A 0 N/A 0 100.00% 0.00% 0.00% 0.00% 136.180 4 1 NIA 0 N/A N/A 0 N/A 0 25.00% 0.00% 0.00% 0.00% 136.190 4 0 N/A 0 N/A N/A 0 N/A 0 0.00 0/0 0.00 0/0 0.00% 0.00% 136.200 4 0 N/A 0 N/A N/A 0 N/A 0 0.00% 0.00% 0.00% 0.00% 86.210 8 2 N/A 0 N/A N/A 0 N/A 0 25.00% 0.00% 0.00% 0.00% 136.2 20 8 0 N/A 0 N/A N/A 0 NIA 0 0.00% 0.00% 0.00% 0.00% 136.230 8 0 NIA 0 N/A N/A 0 N/A 0 0.00 0/0 0.00 0/0 0.00 0/0 0.00% Totals: 71 38 N/A 11 N/A N/A 0 N/A 0 53.52% 28.95% 28-95% 28.95%
- 7. (86.210) 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. 8. (86.220 & 86.230) 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 1. (87.10) Two components representing the CETC and RVLIS Clamp Bolts and associated Nuts as reported in the ISI Program Plan. 2. (87.20) A single component is scheduled in the first inspection period, representing all 16 Pressurizer Manway Bolts and associated Nuts as reported in the ISI Program Plan. 3. (87.50) 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. 4. (87.60) 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. 5. (87.70) 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 8 (This report is used to verify that the periodic BYRON STATION UNIT 1 AND UNIT COMMON - 3RD INTERVAL (The percentage requirements of Tables IWx- requirements of Tables IWx-2412-1 will be met by ASME SECTION Xt EXAMINATION STATUS REP!'IRT 2412-1 apply to the Category and were the interval schedule. a. flied to each Item on 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 87.10 2 2 N/A 0 N/A N/A 0 N/A 0 100.00% 0.00% 0.00% 0.00% 87.20 1 0 N/A 0 N/A N/A 0 N/A 0 0.00% 0.00% 0.00% 0.00% 87.50 20 3 N/A 2 N/A N/A 0 N/A 0 15.00% 66.67% 66.67% 66.67% 87.60 4 0 N/A 0 N/A N/A 0 N/A 0 0.00% 0.00% 0.00% 0.00% 87.70 26 1 N/A 1 N/A N/A 0 N/A 0 3.85% 100.00% 100.00% 100.00% Totals: 53 6 N/A 3 N/A N/A 0 N/A 0 11.32% 50.00°,6 50.00% 50.00%
Category B-K Non-Deferred Exams 810.10 2 2 0 0 1 1 0 1 0 100.00% 0_00% 0.00% 0.00% B10.20 7 3 1 1 1 1 0 1 0 42.86% 33.33% 33.33% 33.33% Totals: 9 5 1 1 2 2 0 2 0 55.56% 20.00% 20.00% 20.00% 1. (B10.10) Per Examination Category B-K, Note 4, for multiple vessels of similar design, function and service, only one welded attachment of only one of the multiple vessels shall be selected for examination. Conservatively, a welded attachment of each type of welded attachment of one of multiple vessels will be `' examined. 2. (1310.20 & 810.30) 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 1. (812.20) The examination of pump casings is limited to only one of the pumps performing similar functions in the system per Examination Category B-L-2, Note 1. Also, 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. Category B-M-2 Deferred Exams 1. (1312.50) Per Examination Category B-M-2, Note 2, examination is required only when a valve is disassembled for maintenance, repair, or volumetric examination. Also, per Examination Category B-M-2, Note 3, examinations are limited to at least one valve within each group of valves that are of the same size, design, manufacturing method, and function. Examination is required only once per inspection interval within each valve group. Ca teg ory B-N-1 Non-Deferred Exams 81 3.10 2 1 0 1 1 1 0 1 0 50.00% 100.00 0/0 100.00% 100.00% Totals: 2 1 0 1 1 1 0 1 0 50.001% 100.00% 100.00% 100.00% 1. (1313.10) "% Completed" exceeds 100% since the vessel interior is selected for examination once each period (three times during the interval). Section 3.0 Page 4 of 8 (This report is used to verify that the periodic BYRON STATION UNIT 1 AND UNIT GIMMON - 3RD INTERVAL (The percentage requirements of Tables IWx- r eq uirem e nts of Tables IWx-2412-1 will be met by ASME SECTION XI EXAMINATION STATUS REPORT 2412-1 apply to the Category and were the interval schedule. a. elied 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 Item No. # of Comp Total Selected min Per 1 # Exams max min Completed Per 2 max Per 3 % Selected % Period 1 Exams Completed Period 2 Period 3 812.20 4 0 N/A 0 N/A N/A 0 N/A 0 0.00% 0.00% 0.00% 0.00% Totals: 4 0 WA 0 N/A WA 0 WA 0 0.00% 0.00% 0.00% 0.00% Item No. # of Comp Total Selected min Per 1 # Exams max min Completed Per 2 max Per 3 0 ,6 Selected % Exams Completed Period 1 Period 2 Period 3 81 2.50 37 2 N/A 2 N/A N/A 0 N/A 0 5.41% 100.00% 100.00% 100.00% Totals: 37 2 WA 2 WA N/A 0 WA 0 5.41 0 ,6 100.00% 100.00% 100.00%
- 1. (814.10) 10% of the 45 CRD Housings (as reported in the ISI Program Plan) are required to be examined each interval per this Item Number. These 5 components represent that 10% population. Category B-P Non-Deferred Exams 815.10 5 5 N/A 0 N/A N/A 0 N/A 0 100.00% 0.00% 0.00% 0.00% Totals: 5 5 NIA 0 NIA N/A 0 NIA 0 100.00% 0.00% 0.00% 0.00% 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 maybe limited to one vessel or distributed among the vessels. Section 3.0 Page 5 of 8 (This report is used to verify that the periodic BYRON STATION UNIT 1 AND UNIT COMMON - 3RD INTERVAL (The percentage requirements of Tables IWx- requirements of Tables IWx-2412-1 will be met by ASME SECTR7:1C~*IN STATUS REPORT 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-N-2 Deferred Exams 8 13.50 1 1 N/A 0 N/A N/A 0 N/A 0 100.00% 0.000% 0.00% 0.000/0 813.60 1 1 N/A 0 N/A N/A 0 N/A 0 100.00 0/0 0.00% 0.00% 0.00% Totals: 2 2 NIA 0 N/A N/A 0 N/A 0 100.00% 0.00% 0.00% 0.00% Category B-N-3 Deferred Exams 813.70 1 1 N/A 0 N/A N/A 0 N/A 0 100.00% 0.00% 0.00% 0.00% Totals: 1 1 N/A 0 N/A N/A 0 N/A 0 100.00% 0.00% 0.00% 0.00% Category B-0 Deferred Exams 814.10 5 5 N/A 0 N/A N/A 0 N/A 0 100.00% 0.00% 0.00% 0.00% Totals: 5 5 NIA 0 N/A NIA 0 NIA 0 100.00% 0.00% 0.00% 0.00% 1. (815.10) "% Completed" exceeds 100% since Class 1 pressure tests are performed each refueling outage. 2. (1315.10) Five components representing the five systems in Class 1 as reported in the ISI Program Plan. Category C-A Non-Deferred Exams C1.10 6 2 0 1 1 1 0 1 0 33.33% 50.00% 50.00% 50.00% C1.20 6 2 0 1 1 1 0 1 0 33.33% 50.00% 50.00% 50.00% C 1.30 4 1 0 0 1 1 0 1 0 25.00% 0.00 0/0 0.00% 0.00% Totals: 16 5 1 2 2 1 0 1 0 31.25% 40.00% 40.00% 40.00%
Category C-B Non-Deferred Exams C2.21 12 1 0 0 1 1 0 1 0 8.33% 0.00% 0.00% 0.00% C2.22 8 1 0 1 1 1 0 1 0 12.50% 100.00 0/0 100.00% 100.00% Totals: 20 2 0 1 1 1 0 1 0 10.00% 50.00 0/0 50.00% 50.00% 1. (C2.21 & C2.22) Per Examination Category C-B, Note 4, in the case of multiple vessels of similar design, size, and service, the required examinations may be limited to one vessel or distributed among the vessels. 2. (C2.22) Due to the unique configuration of the heat exchanger nozzle reinforcing pads being on the internal surface, the nozzle inner radius section is inaccessible for examination. (See Relief Request 13R-04). Category C-C Non-Deferred Exams 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. The interpretation is consistent with the previous NRC condition on the use of Code Case N-509. Category C-H Non-Deferred Exams C7.10 29 29 NIA 0 N/A N/A 0 N/A 0 100.00% 0.00% 0.00% 0.00% Totals: 29 29 N/A 0 N/A N/A 0 N/A 0 100.00% 0.00% 0.00% 0.00% 1. (D1.10& D1.20& D1.30) Unit 0 (Common) components are scheduled with and included in the Unit 1 counts. Section 3.0 Page 6 of 8 (This report is used to verify that the periodic BYRON STATION UNIT 1 AND UNIT COMMON - 3RD INTERVAL (The percentage requirements of Tables IWx- requirements of Tables IWx-2412-1 will be met by ASME SECTHJN Xl EXAMINATION STATUS REPORT 2412-1 apply to the Category and were t h e in terv a l sc h edu l e. applied to each Item only when practical.) # of Total # Exams Completed
% Exams Completed Item No. Com Selected Min Per 1 Max Min Per 2 Max Per 3 % Selected Period 1 Period 2 Period 3 1. (C7.10) "% Completed" exceeds 100% si nc e Class 2 pressure tests are performed each inspection period. 2. (C7.10) Twenty-nine components repres e nting the twenty-nine systems in Class 2 as reported in the ISI Program Plan. Category Non-Deferred Exams D1.10 28 14 3 7 7 0 0 3 0 50.00% 50.00% 50.00% 50.00% D1.20 120 14 3 3 7 4 0 7 0 11.67% 21.43% 21.43% 21.43% D1.30 12 2 0 0 1 1 0 1 0 16.67% 0.00% 0.00% 0.00% Totals: 160 30 5 10 15 5 0 12 0 18.75% 33.33% 33.33% 33.33% C3.10 2 1 0 0 1 1 0 1 0 50.00% 0.00 0/0 0.00% 0.00% C3.20 61 7 2 2 3 2 0 3 0 11.48% 28.57% 28.57% 28.57% C3.30 20 2 0 0 1 1 0 1 0 10.00% 0.00% 0.00% 0.00% Totals: 83 10 2 2 5 3 0 5 0 12.05% 20.00% 20.00% 20.00%
- 2. (D1.10) Per Examination Category, Note 3, for multiple vessels of similar design, function, and service, the welded attachments of only one of the multiple vessels shall be selected for examination. Conservatively, an integral attachment of each type of welded attachment of one of multiple vessels will be examined. 3. (D1.20) Per Examination Category, Note 3, for welded attachments of piping, pumps, and valves, a 10% sample shall be selected for examination. This requirement is conservatively interpreted to mean that 10% of the total Class 3 welded attachments shall be examined. The interpretation is consistent with the previous NRC condition on the use of Code Case N-509. Category D-B Non-Deferred Exams D2.10 20 20 N/A 0 N/A N/A 0 N/A 0 100.00% 0.00% 0.00% 0.00% Totals: 20 20 N/A 0 N/A N/A 0 WA 0 100.00% 0.00% 0.00% 0.00% 1. (F1.30 & F1.40) Unit 0 (Common) components are scheduled with and included in the Unit 1 counts. 2. (F1.40) Per Examination Category F-A, Note 3, for multiple components other than piping within a system of similar design, function, and service, the supports of only one of the multiple components are required to be examined. Category R-A Non-Socket Welds 1. (BER Welds) The # of Comp and # Selected include all BER welds which have been integrated into the RISI Program and are selected in accordance with the Risk Informed BER methodology. Section 3.0 Page 7 of 8 (This report is used to verity that the periodic BYRt~L_Ear-
~X!7:AJ~`J1LI~T J 1'CW:7QW_Lf[-IN - 3RD INTERVAL (The percentage requirements of Tables IWx- requirements of Tables IWx-2412-1 will be met by th e interval sch ed ule. ASME SECTION XI EXAMINATION STATUS REPORT 2412-1 apply to the Category and were applied to each Item on when practical.) # of Total # Exams Completed
% Exams Completed Item No. Com Selected Min Per 1 Max Min Per 2 Max Per 3 % Selected Period 1 Period 2 Period 3 1. (D2.10) "% Completed" exceeds 100% since Class 3 pressure tests are performed each inspection period. 2. (D2.10) Twenty components representing the twenty systems in Class 3 as reported in the ISI Program Plan. Category F-A Non-Deferred Exams F1.10 467 122 20 39 61 22 0 59 0 26.21% 31.97% 31.97% 31.97% F1.20 59 8 99 16 32 49 18 0 44 0 16.58% 32.32% 32.32% 32.32% F1.3 0 1007 103 17 34 51 18 0 43 0 10.23% 33.01% 33-01% 33.01 F1.40 74 35 6 7 17 11 0 19 0 47.30% 20.00% 20.00% 20.00% Totals: 2146 359 58 112 179 68 0 166 0 16.73% 31.20% 31.20% 31.20% 1 128 32 6 10 16 6 0 14 0 25.00% 31.25% 31.25% 31.25% 2 134 36 6 4 18 14 0 23 0 26.87% 11.11% 11.11% 11.11 4 1400 146 24 47 73 26 0 62 0 10.43% 32.19 0 10 32.19% 32.19% 5 65 10 2 0 5 5 0 7 0 15.38% 0.00 0/0 0.00% 0.00 0/0 Totals: 1727 224 36 61 112 51 0 107 0 12.97% 27.23% 27.23% 27.23%
Category R-A Socket Welds 1. Socket welds for Examination Category R-A piping structural elements are listed separately from butt welds because socket welds are selected for examination in "each" refueling outage. Including socket welds in the # of Comp, Total Selected, and # Selected fields with the butt welds would misrepresent the % completed distributions for the remainder of the Examination Category. The "% Completed" exceeds 100% since they are examined each outage per ASME Code Case N-578-1, Table 1, footnote 12. Section 3.0 Page 8 of 8 (This report is used to verify that the periodic BYRON STATION UNIT 1 AND UNIT CIIMMON - 3RD INTERVAL (The percentage requirements of Tables lWx- requirements of Tables IWx-2412-1 will be met by ASME SECTION XI EXAMINATION STATUS REPORT 2412-1 apply to the Category and were t h e int erva l sc h ed ul e. a. tlied 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 2 93 38 N/A 76 N/A N/A 0 N/A 0 40.86% 200.00% 200.00% 200.00% 4 188 44 N/A 88 N/A N/A 0 N/A 0 23.40% 200.00°10 200.00% 200.00% 5 345 34 N/A 68 N/A N/A 0 N/A 0 9.86% 200.00% 200.00% 200.00% Totals: 626 116 N/A 232 N/A N/A 0 N/A 0 18.53% 200.00°!0 200.00°!0 200.00%
FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS
- 1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 (Name and Address W Owner) 2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 3. Plant Unit: 1 4. Owner Certificate Of Authorization (if required): N/A 5. Commercial Service Date: 09/16/85 6. National Board Number for Unit: N-198 T. Components Inspected: Auxiliary Feedwater System (AF) Note (1): Baseline Examination Note (2): Snubber examined as a Component Support Computer Generated Form As Required by the Provisions of the ASME Code Rules (Page 1 of 46) (Name and Address of Plant) Exelein- Byron Station Unit 1 BlR15 ISI Outage Report Note: Supplemental sheets in form of fists, 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. Component or Manufacturer Manufacturer State or National Appurtenance or Installer or Installer Province No. Board No. Serial No. 1-AF-2-1 Hunter Corp. N/A N/A N/A 1-AF-2-2 Hunter Corp. N/A N/A N/A
- 1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 3. Plant Unit: 1 4. Owner Certificate Of Authorization (if required): N/A 5. Commercial Service Date: 09/16/85 6. National Board Number for Unit: N-198 7. Components Inspected: Auxiliary Feedwater System (AF) Note (1): Baseline Examination FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 2 of 46) Note (2): Snubber examined as a Component Support (Name and Address of Owner) (Name and Address of Plant) Exellloln_
Byron Station Unit 1 B1R15 ISI Outage Report 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 Component or Manufacturer Manufacturer State or National Appurtenance or Installer or Installer Province No. Board No. Serial No. 1 AF02EA- Hunter Corp. N/A N/A N/A 4/1 AF06001 R
- 1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois Note (1): Baseline Examination Contputer Generated Form FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 3 of 46) Note (2): Snubber examined as a Component Support (Narne and Address of Owner) (Name and Address of Plant) 3. Plant Unit: 1 4. Owner Certificate Of Authorization (if required): 5. Commercial Service Date: 09/16/85 6. National Board Number for Unit: 7. Components Inspected: Containment Spray System (CS) Exelloin-Byron Station Unit 1 BiR15 ISI Outage Report 61010 N/A N-198 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. Component or Appurtenance Manufacturer or Installer Manufacturer or Installer Serial No. State or Province No. National Board No. 1-CS-2-1 Hunter Corp. N/A N/A N/A 1-CS-2-2 Hunter Corp. N/A N/A N/A 1-CS-2-3 Hunter Corp. N/A N/A N/A 1-CS-2-4 Hunter Corp. N/A N/A N/A 1-CS-2-5 Hunter Corp. N/A N/A N/A 6/26/2008
- 1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 3. Plant Unit: 1 4. Owner Certificate Of Authorization (If required): N/A 5. Commercial Service Date: 09/16/85 6. National Board Number for Unit: N-198 7. Components Inspected: Containment Spray System (CS) Note (1): Baseline Examination Note (2): Snubber examined as a Component Support Computer Generated Forth FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 4 of 46) (Name and Address of Owner) (Name and Address of Plant) &el6n- Byron Station Unit 1 B1 R15 ISI Outage Report 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. Component or Manufacturer Manufacturer State or National Appurtenance or Installer or Installer Province No. Board No. Serial No. 1 CS02AA- Hunter Corp. N/A N/A N/A 10/1 CS03003V 1 CS10AA- Hunter Corp. N/A N/A N/A 6/1 CS03028X 1CS10AA- Hunter Corp. NIA N/A N/A 6/1 CS03089A 6/2&2008 1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 Note (1): Baseline Examination Note (2): Snubber examined as a Component Support Computer Generated Form FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 5 of 46) (Narne and Address of owner) 2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois (Narne and Address of Plant) 3. Plant Unit: 1 4. Owner Certificate Of Authorization (if required): 5. Commercial Service Date: 09/16/85 6. National Board Number for Unit: 7. Components Inspected: Chemical & Volume Control System (CV) Exellibm Byron Station Unit 1 B1 R15 ISI Outage Report 61010 N/A N-198 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. Component or Manufacturer Manufacturer State or National Appurtenance or Installer or Installer Province No. Board No. Serial No. 1 RC14AB- Pacific Scientific 23835 NA NA 2/1 CV15039-S1 1 RC14AB- Pacific Scientific 7345 NA NA 2/1 CV15039-S2 6/26/2008
- 1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 Note (1): Baseline Examination Note (2): Snubber examined as a Component Support Computer Generated Form FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 6 of 46) (flame and Address of Owner) (Name and Address of Plant) Exelein- Byron Station Unit 1 B1 R15 ISI Outage Report 3. Plant Unit: 1 4. Owner Certificate Of Authorization (if required): N/A 5. Commercial Service Date: 09/16/85 6. National Board Number for Unit: N-198 7. Components Inspected: Chemical & Volume Control System (CV) 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. Component or Appurtenance Manufacturer or Installer Manufacturer or Installer Serial No. State or Province No. National Board No. 1-CV-2-1 Hunter Corp. N/A N/A N/A 1-CV-2-10 Hunter Corp. N/A N/A N/A 1-CV-2-2 Hunter Corp. N/A N/A N/A 1-CV-2-3 Hunter Corp. N/A N/A N/A 1-CV-2-4 Hunter Corp. N/A N/A N/A 1-CV-2-5 Hunter Corp. N/A N/A N/A 1-CV-2-7 Hunter Corp. N/A N/A N/A 6/2si20o8 Note (1): Baseline Examination Note (2): Snubber examined as a Component Support Computer Generated Form FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 7 of 46) (Narne and Address of Owner) (Name and Address of Plant) &elejn- Byron Station Unit 1 BiR15 ISI Outage Report 1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 3. Plant Unit: 1 4. Owner Certificate Of Authorization (if required): N/A 5. Commercial Service Date: 09/16/85 6. National Board Number for Unit: N-198 7. Components Inspected: Chemical & Volume Control System (CV) 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. Component or Manufacturer Manufacturer State or National Appurtenance or Installer or Installer Province No. Board No. Serial No. 1CV08BA- Hunter Corp. N/A N/A N/A 4/1 CV01002X 1 CVA3B- Hunter Corp. N/A N/A N/A 2/1 CV16024X 1CVA3B- Hunter Corp. N/A N/A N/A 2/1 CV16083X 6/26/2W8 Note (1): Baseline Examination FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 8 of 46) Note (2): Snubber examined as a Component Support Computer Generated Form (Narne and Address of Owner) Exelein- Byron Station Unit 1 B1 R15 ISI Outage Report 1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 (Narne and Address of Rant) 3. Plant Unit: 1 4. Owner Certificate Of Authorization (if required): N/A 5. Commercial Service Date: 09/16/85 6. National Board Number for Unit: N-198 7. Components Inspected: Chemical & Volume Control System (CV) 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. Component or Appurtenance Manufacturer or Installer Manufacturer or Installer Serial No. State or Province No. National Board No. 1CVA3AA-2/W-06 Hunter Corp. 1-CV-1-N5 NA NA 1CVA3AA-2/W-07 Hunter Corp. 1-CV-1-N5 NA NA 1CVA3B-2/W-74 Hunter Corp. 1-CV-1-N5 NA NA 1CVA38-2/W-75 Hunter Corp. 1-CV-1-N5 NA NA 1CVA3B-2/W-76 Hunter Corp. 1-CV-1-N5 NA NA 1CVA3B-2/W-77 Hunter Corp. 1-CV-1-N5 NA NA 1CVA3B-2/W-84 Hunter Corp. 1-CV-1-N5 NA NA 1CVA3B-2JW-85 Hunter Corp. 1-CV-1-N5 NA NA 1CVA5AA-2/W-04 Hunter Corp. 1-CV-1-N5 NA NA 1CVASAA-2/W-05 Hunter Corp. 1-CV-1-N5 NA NA 1CVA6AA-2/W-04 Hunter Corp. 1-CV-1-N5 NA NA 1CVA6AA-2/W-05 Hunter Corp. 1-CV-1-N5 NA NA 6/26/2008
- 1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 Note (1): Baseline Examination Note (2): Snubber examined as a Component Support Computer Generated Form FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 9 of 46) (Name and Address of Owner) (Name and Address of Plant) &elejn- Byron Station Unit 1 B1 R15 ISI Outage Report 2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 3. Plant Unit: 1 4. Owner Certificate Of Authorization (if required): N/A 5. Commercial Service Date: 09/16/85 6. National Board Number for Unit: N-198 7. Components Inspected: Chemical & Volume Control System (CV) 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. Component or Manufacturer Manufacturer State or National Appurtenance or Installer or Installer Province No. Board No. Serial No. 1 CVA7AA-2/W-08 Hunter Corp. 1-CV-1-N5 NA NA 1CVA7AA-2/W-09 Hunter Corp. 1-CV-1-N5 NA NA
- 1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 Note (1): Baseline Examination Note (2): Snubber examined as a Component Support Comp~ Generated Ports FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 10 of 46) (Name and Address of Owner) (Name and Address of Plant) Exel6n- Byron Station Unit 1 B1 R15 ISI Outage Report 2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 3. Plant Unit: 1 4. Owner Certificate Of Authorization (if required): N/A 5. Commercial Service Date: 09/16/85 6. National Board Number for Unit: N-198 7. Components Inspected: Chemical & Volume Control System (CV) 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. Manufacturer Component or Manufacturer Installer State or National Appurtenance or Installer or Serial No. Province No. Board No. 1CV15AC- Pacific Scientific 1308 NA NA 3/4/1 CV29003S 1 CVA5AA- Pacific Scientific 22192 NA NA 2/1 CV15054S 6/2612008 Note (1): Baseline Examination FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 11 of 46) Note (2): Snubber examined as a Component Support Computer Generated Form Exelon- Byron Station Unit 1 B1R15 ISI Outage Report 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: 1 4. Owner Certificate Of Authorization (if required): N/A 5. Commercial Service Date: 09/16/85 6. National Board Number for Unit: N-198 7. Components Inspected: Fuel Pool Cooling System (AF) Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x t 1 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. Component or Manufacturer Manufacturer State or National Appurtenance or Installer or Installer Province No. Board No. Serial No. 1-FC-2-1 Hunter Corp. N/A N/A N/A 6/28/2008 FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 12 of 46) 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: 1 4. Owner Certificate Of Authorization (if required): N/A 5. Commercial Service Date: 09/16/85 6. National Board Number for Unit: N-198 7. Components Inspected: Feedwater System (FW) Note (1): Baseline Examination Note (2): Snubber examined as a Component Support Exelein- Byron Station Unit 1 B1 R15 ISI Outage Report 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 Component or Manufacturer Manufacturer State or National Appurtenance or Installer or Installer Province No. Board No. Serial No. 1 FW 81 AA- Hunter Corp. N/A N/A N/A 6/1 AF06038R 1 F W 81 AA- Hunter Corp. N/A N/A N/A 6/1 AF06039X 1 FW81 BA- Hunter Corp. N/A N/A N/A 6/1 AF06040V 6/28/2008
- 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 3. Plant Unit: 1 4. Owner Certificate Of Authorization (if required): N/A 5. Commercial Service Date: 09/16/85 6. National Board Number for Unit: N-198 7. Components Inspected: Feedwater System (FW) 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 FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 13 of 46) (Name and Address of Plant) Exelon- Byron Station Unit 1 Bi R15 ISI Outage Report Component or Manufacturer Manufacturer State or National Appurtenance or Installer or Installer Province No. Board No. Serial No. 1FW03DA-16/C01
.01 Hunter Corp. 1-FW-1-N5 NA NA 1FW03DA-16/C01B Hunter Corp. 1-FW-1-N5 NA NA 1FW87CA-6/C08A W. A. Pope Corp. 1-FW-1-N5 NA NA 6/2 6/2008 1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 Note (1): Baseline Examination Note (2): Snubber examined as a Component Support Computer Generated Form FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 14 of 46) (Narne and Address of Owner) 2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 (Name and Address of Plant) Exelein- Byron Station Unit 1 B1R15 ISI Outage Report 3. Plant Unit: 1 4. Owner Certificate Of Authorization (if required): N/A 5. Commercial Service Date: 09/16/85 6. National Board Number for Unit: N-198 7. Components Inspected: Main Steam System (MS) 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. Component or Manufacturer Manufacturer State or National Appurtenance or Installer or Installer Province No. Board No. Serial No. 1 MS01 AC-32.75 Pacific Scientific 10488 NA NA /1 MS07006-S1 1MS01AC-32
.75 Pacific Scientific 10489 NA NA /1 MS07006-S2 6/2 6/2008 FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 15 of 46) 1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 3. Plant Unit: 1 4. Owner Certificate Of Authorization (if required): N/A 5. Commercial Service Date: 09/16/85 6. National Board Number for Unit: N-198 7. Components Inspected: Main Steam System (MS) Note (1): Baseline Examination Note (2): Snubber examined as a Component Support Computer Generated Form (Name and Address of Owner) (Narne and Address of Plant) Exelon- Byron Station Unit 1 B1 R15 ISI Outage Report 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. Component or Manufacturer Manufacturer State or National Appurtenance or Installer or Installer Province No. Board No. Serial No. 1 MS01 BB-30-3/4/1 PC- Hunter Corp. N/A N/A N/A 85A 6/26/2008 (Name and Address of Owner) 2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois (Name and Address of Plant) 3. Plant Unit: 1 4. Owner Certificate Of Authorization (if required): 5. Commercial Service Date: 09/16/85 6. National Board Number for Unit: 7. Components Inspected: Process Sampling System (PS) Note (1): Baseline Examination FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 16 of 46) Note (2): Snubber examined as a Component Support Computer Genmrated Form Exelein- Byron Station Unit 1 B1 R15 ISI Outage Report 1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 61010 N/A N-198 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. Component or Appurtenance Manufacturer or Installer Manufacturer or Installer Serial No. State or Province No. National Board No. 1-PS-2-1 Hunter Corp. N/A N/A N/A 1-PS-2-2 Hunter Corp. N/A N/A N/A 1-PS-2-3 Hunter Corp. N/A NIA N/A 1-PS-2-4 Hunter Corp. N/A N/A N/A 1-PS-2-5 Hunter Corp. N/A N/A N/A 1-PS-2-6 Hunter Corp. N/A N/A N/A Note (1): Baseline Examination A Corrvwwr Generated Fonn FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 17 of 46) 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 Note (2): Snubber examined as a Component Support (flame and Address of Plant) Exelein- Byron Station Unit 1 B1R15 ISI Outage Report 3. Plant Unit: 1 4. Owner Certificate Of Authorization (if required): N/A 5. Commercial Service Date: 09/16/85 6. National Board Number for Unit: N-198 7. Components Inspected: Reactor Coolant System (RC) 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. Component or Manufacturer Manufacturer State or National Appurtenance or Installer or Installer Province No. Board No. Serial No. 1-RC-1-1 Hunter Corp. N/A N/A N/A 6/26/2008 Note (1): Baseline Examination Computer Generated Form FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 18 of 46) 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 Note (2): Snubber examined as a Component Support (Name and Address of Plant) Exelein- Byron Station Unit 1 B1 R15 ISI Outage Report 3. Plant Unit: 1 4. Owner Certificate Of Authorization (if required): N/A 5. Commercial Service Date: 09/16/85 6. National Board Number for Unit: N-198 7. Components Inspected: Reactor Coolant System (RC) 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. Component or Manufacturer Manufacturer State or National Appurtenance or installer or Installer Province No. Board No. Serial No. 1 RC-01 -BA/S Hunter Corp. N/A N/A N/A 6/26/2008 Note (1): Baseline Examination Note (2): Snubber examined as a Component Support computer Generated Form FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 19 of 46) (Name and Address of Plant) Exelon- Byron Station Unit 1 BIR15 ISI Outage Report 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 3. Plant Unit: 1 4. Owner Certificate Of Authorization (if required): N/A 5. Commercial Service Date: 09/16/85 6. National Board Number for Unit: N-198 7. Components Inspected: Reactor Coolant System (RC) 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. Component or Appurtenance Manufacturer or Installer Manufacturer or Installer Serial No. State or Province No. National Board No. 1RC PA/FLYWHEEL Westinghouse Corp. 1-115E121-G01 NA W25819 1 RC-01 -R/RPVS-A F-1 Westinghouse Corp. 640-0004-51 B-09061 N-198 1RC-01-R/RPVS-D F-1 Westinghouse Corp. 640-0004-51 B-09061 N-198 1RC-01-R/RPVS-E F-1 Westinghouse Corp. 640-0004-51 B-09061 N-198 1RC-01-R/RPVS-H F-1 Westinghouse Corp. 640-0004-51 B-09061 N-198 1 RC13AA-2/W-01 Hunter Corp. 1-RC-1-N5 NA NA 1 RC13AA-2/W-02
.01 W. A. Pope Corp. 1-RC-1-N5 NA NA 1RC13AA-2/W-03 Hunter Corp. 1-RC-1-N5 NA NA 1RC13AA-2/W-04 Hunter Corp. 1-RC-1-N5 NA NA 1 RC13AA-2/W-05 Hunter Corp. 1-RC-1-N5 NA NA 1 RC13AB-2/W-01 Hunter Corp. 1-RC-1-N5 NA NA 1RC13AB-2/W-09 Hunter Corp. 1-RC-1-N5 NA NA 6/26/2tNi8 As Required by the Provisions of the ASME Code Rules (Page 20 of 46) 1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 Note (1): Baseline Examination computer Generated Form FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS Note (2): Snubber examined as a Component Support (Name and Address of Owner) (Name and Address of Plant) 3. Plant Unit: 1 4. Owner Certificate Of Authorization (if required): 5. Commercial Service Date: 09/16/85 6. National Board Number for Unit: 7. Components Inspected: Reactor Coolant System (RC) Exelon- Byron Station Unit 1 B1 R15 ISI Outage Report 2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 N/A N-198 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. Component or Appurtenance Manufacturer or Installer Manufacturer or Installer Serial No. State or Province No. National Board No. 1 RC13AC-2/W-01 Hunter Corp. 1-RC-1-N5 NA NA 1RC13AD-2/W-01 Hunter Corp. 1-RC-1-N5 NA NA 1RC14AA-2/W-02 Hunter Corp. 1-RC-1-N5 NA NA 1 RC14AA-2/W-03 Hunter Corp. 1-RC-1-N5 NA NA 1RC14AA-2/W-03A Hunter Corp. 1-RC-1-N5 NA NA 1RC14AA-2/W-03B Hunter Corp. 1-RC-1-N5 NA NA 1RC14AA-2/W-03C Hunter Corp. 1-RC-1-N5 NA NA 1 RC14AA-2/W-04 Hunter Corp. 1-RC-1-N5 NA NA 1RC14AA-2/W-05 Hunter Corp. 1-RC-1-N5 NA NA 1 RC14AA-2/W-06 Hunter Corp. 1-RC-1-N5 NA NA 1RC14AA-2/W-07 Hunter Corp. 1-RC-1-N5 NA NA 1RC14AA-2/W-08 Hunter Corp. I 1-RC-1-N5 I NA I NA 6/28/2008
- 3. Plant Unit: 1 4. Owner Certificate Of Authorization (if required): 5. Commercial Service Date: 09/16/85 6. National Board Number for Unit: 7. Components Inspected: Reactor Coolant System (RC) Note (1): Baseline Examination Note (2): Snubber examined as a Component Support Computer Generated Form FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 21 of 46) (Name and Address of Owner) (Name and Address of Plant) Exelein- Byron Station Unit 1 B1 R15 ISI Outage Report 1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 N/A N-198 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. Component or Appurtenance Manufacturer or Installer Manufacturer or Installer Serial No. State or Province No. National Board No. 1 RC14AA-2/W-09 Hunter Corp. 1-RC-1-N5 NA NA 1 RC14AA-2/W-10 Hunter Corp. 1-RC-1-N5 NA NA 1RC14AA-2/W-11 Hunter Corp. 1-RC-1-N5 NA NA 1 RC14AA-2/W-12 Hunter Corp. 1-RC-1-N5 NA NA 1RC14AA-2/W-13 Hunter Corp. 1-RC-1-N5 NA NA 1RC14AB-2/W-07 Hunter Corp. 1-RC-1-N5 NA NA 1RC14AB-2/W-08 Hunter Corp. 1-RC-1-N5 NA NA 1RC14AB-2/W-09 Hunter Corp. 1-RC-1-N5 NA NA 1RC14AB-2/W-10 Hunter Corp. 1-RC-1-N5 NA NA 1RC14AB-2/W-11 Hunter Corp. 1-RC-1-N5 NA NA 1 RC14AC-2/W-08 Hunter Corp. 1-RC-1-N5 NA NA 1RC14AD-2/W-08 Hunter Corp. 1-RC-1-N5 NA NA 6/26/2008 Note (1): Baseline Examination Computer Generated Form FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS
- 1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 Note (2): Snubber examined as a Component Support As Required by the Provisions of the ASME Code Rules (Page 22 of 46) (Name and Address d Owner) ByronStation Unit 1 B1R15 ISI Outage Report 2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 (Name and Address of Plant) Exelon- 3. Plant Unit: 1 4. Owner Certificate Of Authorization (if required): NIA 5. Commercial Service Date: 09/16/85 6. National Board Number for Unit: N-198 7. Components Inspected: Reactor Coolant System (RC) 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. Component or Appurtenance Manufacturer or Installer Manufacturer or Installer Serial No. State or Province No. National Board No. 1RC14AD-2/W-09 Hunter Corp. 1-RC-1-N5 NA NA 1RC14AD-2/W-10 Hunter Corp. 1-RC-1-N5 NA NA 1 RC14AD-2/W-11 Hunter Corp. 1-RC-1-N5 NA NA 1RC14AD-2/W-12 Hunter Corp. 1-RC-1-N5 NA NA IRC14AD-2/W-13 Hunter Corp. 1-RC-1-N5 NA NA 1RC16AA-2/W-02 Hunter Corp. 1-RC-1-N5 NA NA 1 RC16AA-2/W-03 Hunter Corp. 1-RC-1-N5 NA NA 1RC16AA-2/W-04 Hunter Corp. 1-RC-1-N5 NA NA 1 RC16AA-2/W-05 Hunter Corp. 1-RC-1-N5 NA NA 1 RC16AA-2/W-06 Hunter Corp. 1-RC-1-N5 NA NA 1 RC16AA-2/W-07 Hunter Corp. 1-RC-1-N5 NA NA 1RC16AA-2/W-08 Hunter Corp. 1-RC-1-N5 NA NA 6/26/2008 Note (1): Baseline Examination
-- Computer Generated Form FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS Note (2): Snubber examined as a Component Support As Required by the Provisions of the ASME Code Rules (Page 23 of 46) (Name and Address of Owner) (Name and Address of Plant) &elejn- Byron Station Unit 1 BiR15 ISI Outage Report 1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 3. Plant Unit: 1 4. Owner Certificate Of Authorization (if required): N/A 5. Commercial Service Date: 09/16/85 6. National Board Number for Unit: N-198 7. Components Inspected: Reactor Coolant System (RC) 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. Component or Appurtenance Manufacturer or Installer Manufacturer or Installer Serial No. State or Province No. National Board No. 1 RC16AB-2/W-02 Hunter Corp. 1-RC-1-N5 NA NA 1 RC22AA-1.5/W-01 Hunter Corp. 1-RC-1-N5 NA NA 1 RC22AA-1.5/W-02 Hunter Corp. 1-RC-1-N5 NA NA 1RC22AA-1.5/W-03 Hunter Corp. 1-RC-1-N5 NA NA 1 RC22AA-1.5/W-04 Hunter Corp. 1-RC-1-N5 NA NA 1RC22AA-1.5/W-05 Hunter Corp. 1-RC-1-N5 NA NA 1 RC22AA-1.5/W-06 Hunter Corp. 1-RC-1-N5 NA NA 1 RC22AA-1.5/W-07 Hunter Corp. 1-RC-1-N5 NA NA 1RC22AA-1.5/W-08 Hunter Corp. 1-RC-1-N5 NA NA 1 RC22AA-1.5/W-09 Hunter Corp. 1-RC-1-N5 NA NA 1 RC22AA-1.5/W-10 Hunter Corp. 1-RC-1-N5 NA NA 1RC22AA-1.5/W-11 Hunter Corp. 1-RC-1-N5 NA NA j 6/26/2008 Note (1): Baseline Examination FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 24 of 46) Note (2): Snubber examined as a Component Support Computer Generated Form (Name and Address of Owner) Exelein- Byron Station Unit 1 B1 R15 ISI Outage Report 1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 (Name and Address of Plant) 3. Plant Unit: 1 4. Owner Certificate Of Authorization (if required): N/A 5. Commercial Service Date: 09/16/85 6. National Board Number for Unit: N-198 7. Components Inspected: Reactor Coolant System (RC) 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. Component or Appurtenance Manufacturer or Installer Manufacturer or Installer Serial No. State or Province No. National Board No. 1 RC22AA-1.5/W-12 Hunter Corp. 1-RC-1-N5 NA NA 1RC22AA-1.5/W-13.01 NPSW Venture Corp. 1-RC-1-N5 NA NA 1 RC22AA-1.5/W-14.01 NPSW Venture Corp. 1-RC-1-N5 NA NA 1RC22AA-1.5/W-15.01 NPSW Venture Corp. 1-RC-1-N5 NA NA 1RC22AA-1.5/W-16.01 NPSW Venture Corp. 1-RC-1-N5 NA NA 1RC22AA-1.5/W-17 Hunter Corp. 1-RC-1-N5 NA NA 1RC22AA-1.5/W-18 Hunter Corp. 1-RC-1-N5 NA NA 1RC22AA-1.5/W-19 Hunter Corp. 1-RC-1-N5 NA NA 1RC22AA-1.5/W-20 Hunter Corp. 1-RC-1-N5 NA NA 1RC22AA-1.5/W-21 Hunter Corp. 1-RC-1-N5 NA NA 1 RC22AA-1.5/W-22 Hunter Corp. 1-RC-1-N5 NA NA 1 RC22AA-1.5/W-23 Hunter Corp. 1-RC-1-N5 NA t NA 6/28/2b08
- 1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 3. Plant Unit: 1 4. Owner Certificate Of Authorization (if required): 5. Commercial Service Date: 09/16/85 6. National Board Number for Unit: 7. Components Inspected: Reactor Coolant System (RC) 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 FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 25 of 46) (Name and Address of Owner) (Name and Address of Plant) Exel6n- Byron Station Unit 1 B1 R15 ISI Outage Report 61010 N/A N-198 Component or Appurtenance Manufacturer or Installer Manufacturer or Installer Serial No. State or Province No. National Board No. 1 RC22AA-1.5/W-24 Hunter Corp. 1-RC-1-N5 NA NA 1RC22AA-1.5/W-25 Hunter Corp. 1-RC-1-N5 NA NA 1RC22AA-1.5/W-26 Hunter Corp. 1-RC-1-N5 NA NA 1RC22AA-1.5/W-27 Hunter Corp. 1-RC-1-N5 NA NA 1 RC22AA-1.5/W-28 Hunter Corp. 1-RC-1-N5 NA NA 1 RC22AA-1.5/W-29 Hunter Corp. 1-RC-1-N5 NA NA 1RC22AA-1.5/W-30 Hunter Corp. 1-RC-1-N5 NA NA 1RC22AA-1.5/W-31 Hunter Corp. 1-RC-1-N5 NA NA 1 RC22AA-1.5/W-32 Hunter Corp. 1-RC-1-N5 NA NA 1RC22AA-1.5/W-33 Hunter Corp. 1-RC-1-N5 NA NA 6/26/2008
- 1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 Note (1): Baseline Examination Note (2): Snubber examined as a Component Support Computer Generated Form FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 26 of 46) (Name and Address of Owner) (Name and Address of Plant) Exelon- Byron Station Unit 1 BlRl5 ISI Outage Report 2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 3. Plant Unit: 1 4. Owner Certificate Of Authorization (if required): N/A 5. Commercial Service Date: 09/16/85 6. National Board Number for Unit: N-198 7. Components Inspected: Reactor Coolant System (RC) 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. Component or Appurtenance Manufacturer or Installer Manufacturer or Installer Serial No. State or Province No. National Board No. 1 RC01 BA-1 A/1 RC06S Paul Munroe PD-1423-333 NA NA 1 RC01 BA-1 A/1 RC07S Paul Munroe PD-1423-322 NA NA 1 RC01 BB-1 B/1 RC08S Paul Munroe PD-1423-329 NA NA 1 RC01 BB-1 B/1 RC09S Paul Munroe PD-1423-327 NA NA 1 RC01 BC-1 C/1 RC10S Paul Munroe PD-1423-334 NA NA 1 RC01 BC-1 C/1 RC11 S Paul Munroe PD-1423-331 NA NA 1RC01BD-1D/1RC12S Paul Munroe PD-1423-321 NA NA 1 RC01 BD-1 D/1 RC13S Paul Munroe PD-1423-318 NA NA 1 RC14AB- 2/1 CV15053S Pacific Scientific 2193 NA NA 1 RC20AB- 3/4/1 RC17012S Pacific Scientific 14748 NA NA 1 RC22AB- 1.5/1 RC17015S Pacific Scientific 20437 NA NA 1 RC22AB- 1.5/1 RC17028S Pacific Scientific 5666 NA NA 6/26/2008 (Name and Address of Plant) 3. Plant Unit: 1 4. Owner Certificate Of Authorization (if required): 5. Commercial Service Date: 09/16/85 6. National Board Number for Unit: 7. Components Inspected: Residual Heat Removal System (RH) Note (1): Baseline Examination Note (2): Snubber examined as a Component Support "-- Computer Generated Form FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 27 of 46) Exelein- Byron Station Unit 1 B1R15 ISI Outage Report 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 N/A N-198 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. Component or Appurtenance Manufacturer or Installer Manufacturer or Installer Serial No. state or Province No. National Board No. 1-RH-2-1 Hunter Corp. N/A N/A N/A 1-RH-2-2 Hunter Corp. N/A N/A N/A 1-RH-2-3 Hunter Corp. N/A N/A N/A 1-RH-2-6 Hunter Corp. N/A N/A N/A 6/26/2008 FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 28 of 46) 1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 Note (1): Baseline Examination Note (2): Snubber examined as a Component Support Computer Generated Form (Name and Address of Owner) 2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois (Name and Address of Plant) 3. Plant Unit: 1 4. Owner Certificate Of Authorization (if required): 5. Commercial Service Date: 09/16/85 6. National Board Number for Unit: 7. Components Inspected: Residual Heat Removal System (RH) Exe-lon-ByronStation Unit 1 B1R15 ISI Outage Report 61010 N/A N-198 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. Component or Manufacturer Manufacturer State or National Appurtenance or Installer or Installer Province No. Board No. Serial No. 1 R H-01-PA/L 1 Hunter Corp. N/A N/A N/A 1 RH-01-PA/L2 Hunter Corp. N/A NIA N/A 1 RH-01-PA/L3 Hunter Corp. N/A N/A N/A 1 RH02AA- Hunter Corp. N/A N/A N/A 8/1 RH07016V 1 RH-02-AB/SKT Hunter Corp. N/A N/A N/A 1 RH03AA- Hunter Corp. N/A N/A N/A 8/1 RH01003X 6/26/2008
- 1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 3. Plant Unit: 1 4. Owner Certificate Of Authorization (if required): 5. Commercial Service Date: 09/16/85 6. National Board Number for Unit: 7. Components Inspected: Residual Heat Removal System (RH) 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 FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 29 of 46) (Narne and Address of Owner) (Name and Address of Plant) Exelon- Byron Station Unit 1 B1 R15 ISI Outage Report N/A N-198 Component or Manufacturer Manufacturer State or National Appurtenance or Installer or Installer Province No. Board No. Serial No. 1 R H01 AA- Pacific Scientific 9629 NA NA 12/1 RH02054S 1 RH02AB- Pacific Scientific 9892 NA NA 8/1 RH08015S 6/26/2008
- 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 (Name and Address of Plant) 3. Plant Unit: 1 4. Owner Certificate Of Authorization (if required): 5. Commercial Service Date: 09/16/85 6. National Board Number for Unit: 7. Components Inspected: Reactor Pressure Vessel (RPV) Note (1): Baseline Examination Computer Generated Form FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 30 of 46) Note (2): Snubber examined as a Component Support Exelein- Byron Station Unit 1 B1 R15 ISI Outage Report 61010 N/A N-198 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. Component or Manufacturer Manufacturer State or National Appurtenance or Installer or Installer Province No. Board No. Serial No. 1RC-01-R/N01-N18 Westinghouse Corp. 640-0004-52 B-09061 N-198 1RC-01-R/S01-S18 Westinghouse Corp. 640-0004-52 B-09061 N-198 1RC-01-R/W01-W18 Westinghouse Corp. 640-0004-52 B-09061 N-198 FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 31 of 46) &elon- Byron Station Unit 1 B1 R15 ISI Outage Report 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: 1 4. Owner Certificate Of Authorization (if required): N/A 5. Commercial Service Date: 09/16/85 6. National Board Number for Unit: N-198 T. Components Inspected: Reactor Pressure Vessel (RPV) 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 Component or Manufacturer Manufacturer State or National Appurtenance or Installer or Installer Province No. Board No. Serial No. 1 RC-01 -R/RPV Westinghouse Corp. 640-0004-51 B-09061 N-198 INTERIOR 6/26/2008 Note (1): Baseline Examination Computer Generated Form FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 32 of 46) 2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 3. Plant Unit: 1 4. Owner Certificate Of Authorization (if required): 5. Commercial Service Date: 09/16/85 6. National Board Number for Unit: 7. Components Inspected: Reactor Coolant System (RY) Note (2): Snubber examined as a Component Support (Name and Address of Owner) (Name and Address of Plant) Exelon- Byron Station Unit 1 B1R15 ISI Outage Report 1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 61010 N/A N-198 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. Component or Manufacturer Manufacturer State or National Appurtenance or Installer or Installer Serial No. Province No. Board No. 1 RY03BC-6/FLG 1-12 Hunter Corp. 1-RY-1-N5 NA NA 1RY76A-2/FLG 1-8 Hunter Corp. 1-RY-1-N5 NA NA 6126/2008
- 1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 Note (1): Baseline Examination Note (2): Snubber examined as a Component Support Computer Generated Form FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 33 of 46) (Name and Address of Owner) (Name and Address of Plant) 3. Plant Unit: 1 4. Owner Certificate Of Authorization (if required): 5. Commercial Service Date: 09/16/85 6. National Board Number for Unit: 7. Components Inspected: Reactor Coolant System (RY) Exelein- Byron Station Unit 1 B1R15 ISI Outage Report 2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 N/A N-198 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. Component or Manufacturer Manufacturer State or National Appurtenance or Installer or Installer Province No. Board No. Serial No. 1-RY-2-1 Hunter Corp. N/A N/A N/A 6/26/2008 Note (1): Baseline Examination Note (2): Snubber examined as a Component Support Computer Generated Form FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASIVIE Code Rules (Page 34 of 46) 1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 (Nerve and Address of Owner) 2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 (Name and Address of Plant) Euelun_ Byron Station Unit 1 BIR15 ISI Outage Report 3. Plant Unit: 1 4. Owner Certificate Of Authorization (if required): N/A 5. Commercial Service Date: 09/16/85 6. National Board Number for Unit: N-198 7. Components Inspected: Reactor Coolant System (RY) 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. Component or Manufacturer Manufacturer State or National Appurtenance or Installer or Installer Province No. Board No. Serial No. 1 RY-01-S/SKT Hunter Corp. N/A N/A N/A 6/26/2008 FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 35 of 46) Exelun_ Byron Station Unit 1 B1R15 ISI Outage Report 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 Fant) 3. Plant Unit: 1 4. Owner Certificate Of Authorization (If required): N/A 5. Commercial Service Date: 09/16/85 6. National Board Number for Unit: N-198 7. Components Inspected: Reactor Coolant System (RY) 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. x Computer Generated Form Component or Appurtenance Manufacturer or installer Manufacturer or Installer Serial No. State or Province No. National Board No. 1RY18A-2/W-05A Hunter Corp. 1-RC-1-N5 NA NA 1RY18A-2/W-06 Hunter Corp. 1-RC-1-N5 NA NA 1 RY18A-2/W-07 Hunter Corp. 1-RC-1-N5 NA NA 1RY18A-2/W-08 Hunter Corp. 1-RC-1-N5 NA NA 1RY18A-2/W-09 Hunter Corp. 1-RC-1-N5 NA NA 1 RY18A-2/W-10 Hunter Corp. 1-RC-1-N5 NA NA 6/26/2008 Note (1): Baseline Examination FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS Note (2): Snubber examined as a Component Support computer Generated Form As Required by the Provisions of the ASME Code Rules (Page 36 of 46) (Narne end Address of Owner) 2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois (Name and Address of Plant) 3. Plant Unit: 1 4. Owner Certificate Of Authorization (if required): 5. Commercial Service Date: 09/16/85 6. National Board Number for Unit: 7. Components Inspected: Reactor Coolant System (RY) Exelon- Byron Station Unit 1 B1 R15 ISI Outage Report 1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 61010 N/A N-198 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. Component or Manufacturer Manufacturer State or National Appurtenance or Installer or Installer Province No. Board No. Serial No. 1RY01AA- Pacific Scientific 20685 NA NA 4/1 RY06066S 1 RY01 B-6/1 RY06022S Pacific Scientific 10163 NA NA 6/26/2008
- 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 Note (1): Baseline Examination Computer Generated Form FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 37 of 46) Note (2): Snubber examined as a Component Support (Name and Address of Plant) Exelein_ Byron Station Unit 1 1311315 ISI Outage Report 3. Plant Unit: 1 4. Owner Certificate Of Authorization (if required): N/A 5. Commercial Service Date: 09/16/85 6. National Board Number for Unit: N-198 7. Components Inspected: Steam Generator (SG) 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. Component or Manufacturer Manufacturer State or National Appurtenance or Installer or Installer Province No. Board No. Serial No. 1 RC-01 -BA/FLG Babcock & Wilcox Industries 7722-02 ILU-242904 165 SURF-CL 1 RC-01 -BA/FLG Babcock & Wilcox Industries 7722-02 ILU-242904 165 SURF-HL 1RC-01-BA/STUDS-Babcock & Wilcox Industries 7722-02 ILU-242904 165 CL 01-20 1RC-01-BA/STUDS-Babcock & Wilcox Industries 7722-02 ILU-242904 165 HL 01-20 1 RC-01-BB/FLG Babcock & Wilcox Industries 7722-03 ILU-242903 166 SURF-CL 1RC-01-BB/FLG Babcock & Wilcox Industries 7722-03 ILU-242903 166 SURF-HL 1RC-01-BC/FLG Babcock & Wilcox Industries 7722-01 ILU-242902 164 SURF-CL 1RC-01-BC/FLG Babcock & Wilcox Industries 7722-01 ILU-242902 164 SURF-HL 1 RC-01-BC/STUDS-Babcock & Wilcox Industries 7722-01 ILU-242902 164 CL 01-20 1RC-01-BC/STUDS-Babcock & Wilcox Industries 7722-01 ILU-242902 164 HL 01-20 1RC-01-BD/FLG Babcock & Wilcox Industries 7722-04 ILU-242901 167 SURF-CL 1RC-01 -BD/FLG Babcock & Wilcox Industries 7722-04 ILU-242901 167 SURF-HL 6/26/2008 FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 38 of 46) 1. Owner: Exelon Generation Company, (EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 3. Plant Unit: 1 4. Owner Certificate Of Authorization (if required): N/A 5. Commercial Service Date: 09/16/85 6. National Board Number for Unit: N-198 7. Components Inspected: Steam Generator (SG) Note (1): Baseline Examination Note (2): Snubber examined as a Component Support (Name and Address of Owner) (Name and Address of Plant) Exel6n- Byron Station Unit 1 B1R15 ISI Outage Report 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 forth Component or Manufacturer Manufacturer State or National Appurtenance or Installer or Installer Province No. Board No. Serial No. 1 RC-01-BB/N-3-NIR Babcock & Wilcox Industries 7722-03 ILU-242903 166 6/26/2008 Note (1): Baseline Examination computer Generated Form FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 39 of 46) 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 Note (2): Snubber examined as a Component Support (Name and Address of Plant) Exelein- Byron Station Unit 1 B1R15 ISI Outage Report 3. Plant Unit: 1 4. Owner Certificate Of Authorization (if required): N/A 5. Commercial Service Date: 09/16/85 6. National Board Number for Unit: N-198 7. Components Inspected: Safety Injection System (SI) 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. Component or Manufacturer Manufacturer State or National Appurtenance or Installer or Installer Province No. Board No. Serial No. 1S108JA-1.5/FLG 1-4 Hunter Corp. 1-SI-1-N5 NA NA 6/26/2008
- 1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 Note (1): Baseline Examination Note (2): Snubber examined as a Component Support Computer Generated Form FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 40 of 46) (Name and Address of Owner) (Name and Address of Plant) Exelon- Byron Station Unit 1 B1 R15 ISI Outage Report 2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 3. Plant Unit: 1 4. Owner Certificate Of Authorization (if required): N/A 5. Commercial Service Date: 09/16/85 6. National Board Number for Unit: N-198 7. Components Inspected: Safety Injection System (SI) Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2 m. 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. Component or Appurtenance Manufacturer or Installer Manufacturer or Installer Serial No. State or Province No. National Board No. 1-SI-2-1 Hunter Corp. N/A N/A N/A 1-SI-2-2 Hunter Corp. N/A N/A N/A 1-SI-2-3 Hunter Corp. N/A N/A N/A 1-SI-2-4 Hunter Corp. N/A N/A N/A 1-SI-2-6 Hunter Corp. N/A N/A N/A F"l-2-7 Hunter Corp. N/A N/A N/A 6/28/2008
- 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 (Name and Address of Plant) 3. Plant Unit: 1 4. Owner Certificate Of Authorization (if required): 5. Commercial Service Date: 09/16/85 6. National Board Number for Unit: 7. Components Inspected: Safety Injection System (SI) Note (1): Baseline Examination FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 41 of 46) Note (2): Snubber examined as a Component Support Exelein- Byron Station Unit 1 B1 R15 ISI Outage Report 61010 NIA N-198 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 Component or Manufacturer Manufacturer State or National Appurtenance or installer or Installer Province No. Board No. Serial No. 1SI04B- Hunter Corp. N/A N/A N/A 12/1 RH02029X 1 S104C-8/1 RH02026X Hunter Corp. N/A N/A N/A 1SI04D-8/lRH02022X Hunter Corp. N/A N/A N/A 1 SI05BA-8/1 PC-50A Hunter Corp. N/A N/A N/A 1 SI08CA-4/1 S107008X Hunter Corp. N/A N/A N/A 1S108JA-1-1/2/lSI-Hunter Corp. N/A N/A N/A CP1A 1SI09BA- Hunter Corp. N/A N/A N/A 10/1 S101001 V 6/2 6/2008 FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS
- 1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 3. Plant Unit: 1 4. Owner Certificate Of Authorization (if required): N/A 5. Commercial Service Date: 09/16/85 6. National Board Number for Unit: N-198 7. Components Inspected: Safety Injection System (SI) Note (1): Baseline Examination Note (2): Snubber examined as a Component Support Computer Generated Form As Required by the Provisions of the ASME Code Rules (Page 42 of 46) (Name and Address of Owner) (Name and Address ol Plant) Exel6n- Byron Station Unit 1 B1 R15 ISI Outage Report 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. Component or Appurtenance Manufacturer or Installer Manufacturer or Installer Serial No. State or Province No. National Board No. 1S103DA-2/W-09 Hunter Corp. 1-SI-1-N5 NA NA 1S105BA-8/C01A Hunter Corp. 1-SI-1-N5 NA NA 1Sl06BA-24/C02A Hunter Corp. 1-SI-1-N5 NA NA 1S108GC-1.5/W-01 Hunter Corp. 1-Si-1-N5 NA NA 1S108GC-1.5/W-02 Hunter Corp. 1-SI-1-N5 NA NA 1S108GC-1.5/W-03 Hunter Corp. 1-SI-1-N5 NA NA 1SI08GC-1.5/W-04 Hunter Corp. 1-SI-1-N5 NA NA IS108GC-1.5/W-05 Hunter Corp. 1-SI-1-N5 NA NA 1SI08HA-2/W-01 Hunter Corp. 1-SI-1-N5 NA NA 1S108HA-2/W-02 Hunter Corp. 1-SI-1-N5 NA NA IS108HA-2/W-03 Hunter Corp. 1-SI-1-N5 NA NA 1S108HA-2/W-04 Hunter Corp. 1-SI-1-N5 NA NA 6/26/2008
- 1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 Note (1): Baseline Examination Note (2): Snubber examined as a Component Support computer Generated Form FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 43 of 46) (Name and Address of Owner) (Name and Address of Plant) 3. Plant Unit: 1 4. Owner Certificate Of Authorization (if required): 5. Commercial Service Date: 09/16/85 6. National Board Number for Unit: 7. Components Inspected: Safety Injection System (SI) &elejn- Byron Station Unit 1 B1 R15 ISI Outage Report N/A N-198 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. Component or Appurtenance Manufacturer or Installer Manufacturer or Installer Serial No. State or Province No. National Board No. 1SI08JA-1.5/W-06 Hunter Corp. 1-SI-1-N5 NA NA 1SI08JA-1.5/W-07 Hunter Corp. 1-SI-1-N5 NA NA 1 SI08JA-1.5/W-08 Hunter Corp. 1-SI-1-N5 NA NA 1SI08JA-1.5fW-09 Hunter Corp. 1-SI-1-N5 NA NA 1 SI08JA-1.5/W-10 Hunter Corp. 1-SI-1-N5 NA NA 1SI08JA-1.5/W-11 Hunter Corp. 1-SI-1-N5 NA NA 1SI08JA-1.5/W-12 Hunter Corp. 1-SI-1-N5 NA NA IS108JA-1.5/W-13 Hunter Corp. 1-SI-1-N5 NA NA 1S108JA-1.5/W-14 Hunter Corp. 1-SI-1-N5 NA NA 1SI08JA-1.5/W-15 Hunter Corp. 1-SI-1-N5 NA NA 6/28/2008
- 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 (Narne and Address of Plant) 3. Plant Unit: 1 4. Owner Certificate Of Authorization (if required): N/A 5. Commercial Service Date: 09/16/85 6. National Board Number for Unit: N-198 7. Components Inspected: Safety Injection System (SI) Note (1): Baseline Examination FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provlslons of the ASME Code Rules (Page 44 of 46) Note (2): Snubber examined as a Component Support &elejn- Byron Station Unit 1 B1R15 ISI Outage Report 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 Component or Manufacturer Manufacturer State or National Appurtenance or Installer or Installer Province No. Board No. Serial No. 1 S105CA-8/1 S102003S Pacific Scientific 6923 NA NA 6/26!2008
- 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 Note (1): Baseline Examination Note (2): Snubber examined as a Component Support Computer Generated Form FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 45 of 46) (Name and Address of Plant) &elejn- Byron Station Unit 1 B1 R15 ISI Outage Report 3. Plant Unit: 1 4. Owner Certificate Of Authorization (if required): N/A 5. Commercial Service Date: 09/16/85 6. National Board Number for Unit: N-198 7. Components Inspected: Essential Service Water System (SX) 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. Component or Manufacturer Manufacturer State or National Appurtenance or Installer or Installer Serial No. Province No. Board No. 1 SX08BC- Hunter Corp. N/A N/A N/A 10/1 SX06018X 1SX08BC- Hunter Corp. N/A N/A N/A 10/1 SX06020X 7/9/2008 FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 46 of 46) (BACK) 8. Examination Dates: 10/16/06 to 04/14/08 9. Inspection Period Identification
- 10. Inspection Interval Identification
- 11. Applicable Edition of Section XI: - 2001 Addenda 2003 12. Date / Revision of Inspection Plan: 02/01/08 / Rev. 2 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 Third lnsoecti Q n lntetval 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: C? ~ D 9 ZD Signed for: Exelon Generation Company Computer Generated Form CERTIFICATE OF INSERVICE INSPECTION Exelein- Byron Station Unit 1 B1 R16 ISI Outage Report 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 10/16/06 to 04/14/08 , 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. 6-11 -Inspectors Signature Commissions
- ILL-1254 Date: -~, 20 National Board, State, Province, and Endorsements