Text

Day Inservice Inspection Report for Interval 3, Period 1, Outage 2 (B1R15)
	ML081930790
Person / Time
Site:	Byron
Issue date:	07/11/2008
From:	Hoots D; Exelon Generation Co, Exelon Nuclear
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	1.10.0101, BYRON 2008-0067
	Download: ML081930790 (109)
	v • d • e

Exelon.

Exelon Genernflon Company, L-C Rvron Station www.exeloneorp.com Nuclear 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 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 .

Respectfully, vid M. Hoots Site Vice President Byron Generating Station DMH/RGM/TLH/jeh

Attachment:

BlR15 Inservice Inspection Summary Report - Spring 2008 outage

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 Exelonrim Nuclear B1R15 INSERVICE INSPECTION

SUMMARY

REPORT SECTION SECTION DESCRIPTION PAGES I [CoverPage ii Table of Contents 1 .0 Report introduction

__ ISI - Weld / Component Listing 16 ISI- Bolts, Pumps, and Valves Listing 3 Examination PSI - Weld / 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 TOTAL PAGES IN REPORT] 253

BYRON STATION UNIT 1 REFUELING OUTAGE 15 INSERVICE INSPECTION REPORT 1 .0 INTRODUCTION Inservice inspections of American Society of Mechanical Engineers (ASME) Class 1, 2, 3, CC, and MC components were conducted at Byron Station Unit 1 from 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

BYRON STATION UNIT 1 REFUELING OUTAGE 15 INSERVICE INSPECTION REPORT 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 Exempted Components ASME Class 1, 2, and 3 components, or parts of components, that are not included in the examination tables and that are exempt from examination, as specified in Section XI Paragraphs IWB, IWC, and 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

BYRON STATION UNIT 1 REFUELING OUTAGE 15 INSERVICE INSPECTION REPORT 1 .4 Significant Section XI Activities Du rinQB1 R15 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

BYRON STATION UNIT 1 REFUELING OUTAGE 15 INSERVICE INSPECTION REPORT 4.0 FORM NIS-1 DATA SHEETS 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

BYRON STATION UNIT 1 REFUELING OUTAGE 15 INSERVICE INSPECTION REPORT 7.6 Electric_Power Research Institute 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 Exelon-

~Station Byron Unit 1 BI R15 ISI Outage Report Weld / Component Outage Summary SYSTEM: Chemical & Volume Control System (CV) 1 ; =ct;,nI c,'I I C{xie Aclua!

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

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"Station Byron Unit 1 B1 R15 ISI Outage Report 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 R-A R1 .11 ICVA6AA-2IW-05 1CVA6AA-2 13R-02 139 .40 VT-2 NRI Elbow - Pipe 13T-01 13T-02 OBS15-012 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

_ Exelein-ByronStation Unit 1 B1 R15 ISI Outage Report Weld / Component Outage Summary SYSTEM : Feedwater System (FW)

Cr- repo : "g :~2 , P ,;,lr,? r~cf,-ic, .Ii ;'~x, e :~ctu31 De"'c"Ipt ";n r?0"ga(T:as Ne'ces r0v "" ro-i'Ae Exam R-A R1 .11 1FW87CA-61C08A 1FW87CA-6 13R-02 C5.51 UT IND 81 .18 Pipe - SOL 13T-01 13T-02 Rescan of B1R14 indication per 18 00756048 .

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t. tiaarnut~~n NA RG1 .14 1RC-01-PA/FLYWHEEL 1RC-01-PA PT IND RCP Flywheel OBS15-153

1) 5/32" LI and 2) 1/16' AI . Acceptable . Ref: AIR 2008-237 . - _

R-A 81 .15 1RC-01-R/RPVS-A F-1 1RC-01-R 138-02 85 .10 BMV NRI RPV Nozzle Safe-End HL Loop C 13T-01 13T-02 OBS15-155 Bare-Metal examination per MRP-139 requir ments .

R-A 141 .15 1 RC-01-R/RPVS-D F-1 1 RC-01-R 1314-02 B5 .10 BMV NRI RPV Nozzle Safe-End HL Loop D 13T-01 13T-02 OBS15-156 Bare-Metal examination per MRP-139 requ ir ments .

R-A 141 .15 1RC-01-R/RPVS-E F-1 1RC-01-R 1314-02 85 .10 BMV NRI RPV Nozzle Safe-End HL Loop A 13T-01 13T-02 OBS15-157 Bare-Metal examination perMRP-139 requir ments .

R-A 147 .15 1RC-01-R/RPVS-H F-1 1RC-01-R 1314-02 B5 .10 BMV NRI RPV Nozzle Safe-End HL oop B 13T-01 13T-02 OBS15-158 Bare-Metal examination per MRP-139 requir ments .

R-A 141 .20 1 RC13AA-2/W-01 1 RC13AA-2 1314-02 B9.40 VT-2 NRI SOL - Pipe 13T-01 13T-02 OBS15-015 R-A 81 .20 1 RC13AA-2/W-02 .01 1 RC13AA-2 1314-02 B9 .40 VT-2 NRI Pipe - Tee 13T-01 13T-02 OBS15-016 R-A 141 .20 1AC13AA-2/W-03 1RC13AA-2 1314-02 B9 .40 VT-2 NRI Tee - Reducer 13T-01 13T-02 OBS15-017 R-A 141 .20 1 RC13AA-2/W-04 1 RC13AA-2 1314-02 B9 .40 VT-2 NRI Tee - Pipe 13T-01 13T-02 OBS15-018 R-A 141 .20 1 RC13AA-2M-05 1 RC13AA-2 1314-02 89 .40 VT-2 NRI Pipe - Valve 13T-01 13T-02 OBS15-019

Exel6n-7,8/2008 Byron Station Unit 1 B1 1415 ISI Outage Report Weld l Component Outage Summary SYSTEM: Reactor Coolant System (RC) 1,1 "'1+"_ NUf"aDer ,,Gs? Arf,Ug ; R P4tti~$

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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 OBS15-030

&elejn-7/8/2008 Byron Station Unit 1 B1 R15 ISI Outage Report Weld / Component Outage Summary SYSTEM: Reactor Coolant System (RC)

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N : :1 11 '11)0r P,y'ie! 1-t, Code At;l*ai r " :ot ; : :n , iotes cxvf~ratle Exam 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

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Byron Station Unit 1 B1R15 ISI Outage Report Weld / Component Outage Summary SYSTEM : Reactor Coolant System (RC)

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 bcelein_

Byron Station Unit 1 B1R15 ISI Outage Report Weld / Component Outage Summary SYSTEM : Reactor Coolant System (RC)

!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- 053 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 OBS15-055 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

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7,11/2008 Byron Station Unit t W

B1 R16 ISI Outage Report Weld / Component Outage Summary SYSTEM: Reactor Coolant System (RC) cxAe ,

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~": r~:e . :~1~ors 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 S15-066 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

Exelein-7/812008

~Byron Station Unit 1 B1R15 ISI Outage Report Weld / Component Outage Summary SYSTEM : Reactor Coolant System (RC)

C=at .

(~aolr+r E, rw 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 OBS 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 OBS15-077 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 OBS15-085 10

7,812008

&elejn-

__Station Byron Unit 1 131 R15 ISI Outage Report Weld / Component Outage Summary SYSTEM : Reactor Coolant System (RC) eqj{',,18 N,+t "'S 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 OBS15-091

7/8/2008 Exelon_

Byron Station Unit t B1R15 ISI Outage Report Weld / Component Outage Summary SYSTEM: Reactor Pressure Vessel (RPV) x I f ,.1 via L qa_~ Fw :xf C, ;,de Arl wi )

c 3t bswov= Xquys Pj l.'W's cv" , :~ws B-N-1 813 .10 IRC-01-R/RPV 1 RC-01 -R VT-3 RI INTERIOR RPV Interior Surfaces OBS15-144 IR 00757175 for foreign m aterial on flange surface . All other conditions NRI .

7,8/2008 Exelon-

~Station Byron Unit 1 B1 R15 ISI Outage Report Weld / Component Outage Summary SYSTEM: Reactor Coolant System (RY)

^,ra;~~at .f19

!' ,ui,n 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 OBS15-097

7/8(20NO8 Exelon.

BI R1 5 ISI Outage Report Weld / Component Outage Summary SYSTEM : Steam Generator (SG)

Liri, 1 m~~,r

1. , Roiqlf c 1, , ! ,: w F cc-(~e Act ,, ;a C-B C2 .22 1RC-01-BB/N-3-NIR 1RC-01-BB UT NRI FW Nozzle Inner Radius OBS15-151

Exelein-11----"-.,----,

7/8/2008 Byron Station Unit 1 B1 R15 ISI Outage Report Weld / Component Outage Summary SYSTEM: Safety Injection System (SI)

Cr>4 r- Actu :ii pa : ,,jIts B-K B10 .20 1S103DA-2/W-09 1SI03DA-2 100 PT NRI Closure Plate 1RB-61A OBS15-149 C-C C3 .20 1SI05BA-8/C01A 1SI05BA-8 NA 100 PT NRI Closure Plate 1 PC-50 OBS15-123 C-C C3 .20 1SI06BA-24/C02A 1S106BA-24 100 PT NRI Welded Attachment (VALVE ENC . 1S18811A)

OBS15-152 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

7,8/2008 Exelon-Byron Station Unit 1 B1 R15 ISI Outage Report Weld / Component Outage Summary SYSTEM : Safety Injection System (SI)

{7 ( ",N n

. c, {° OW apt 1 o,~, e Actual 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 OBS15-116 16

Exelein-7/a/2008 Byron Station Unit 1 131 R15 ISI Outage Report Bolts, Pumps, and Valves Outage Summary SYSTEM: Reactor Pressure Vessel (RPV)

! :M I r'urrtjai ~+t; ults Cat, ;teal Co,,Crlpl ; in Fit:que ils 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 dent 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 OBS15-148 Washers 3 to 11, 13 to 18, 55, 56, and 60.

&elejn-7/8/2008

--- Byron~Station Unit 1 B1 R15 ISI Outage Report Bolts, Pumps, and Valves Outage Summary SYSTEM: Steam Generator (SG)

._ "-.f t aJr3 Fsr:i at ' "" ci,n-cal Actua, Rofautls

(.7t . ~zc :r ;tour, FiW1t.rPStg Cc_, ,* ^eplt$

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)

OBS15-137

7/8/2008 Exelon-Byron Station Unit 1 B1R15 ISI Outage Report Bolts, Pumps, and Valves Outage Summary SYSTEM: Safety Injection System (SI)

P1 TtchtItC .l ; 4GIU39 Heg"tiIs E isa*tq 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 .

7/ar2008 Exelein-Byron Station Unit 1 B1 R1 S ISI Outage Report Weld / Component Outage Summary (Preservice Inspections)

SYSTEM: Feedwater System (FW) rb~,t (V" htot "er~h~~caa~ t: ; Rg~uirf, F t,Bults IttaY? ?;zf~rtCtlihfl iucsis Note,S ^.tir " `tat. f-x jeh rtrn1s 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 Baseline exam of replacement pipe weld W-4, WO 00955081 .

&elejn-7/8/2008

~ Byron ~Station Unit 1 131 R15 ISI Outage Report 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 B-G-2 137 .50 1RY038C-6/FLG 1-12 NA PFB-RY VT-1 NRI Piping Flange Bolting Baseline exa m for 1 RY8010C replacement . WO#009615450-08 .

B-G-2 87 .50 1RY76A-2/FLG 1-8 NA VT-1 NRI Piping Flange Bolting Replacement of nut under WO 00966737.

Page 1-1 7/8/2008

/!312008 Exelon-Byron VStation Unit 1 B1R15 ISI Outage Report 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 B-G-1 86.90 1RC-01-BA/STUDS-CL01-20 NA MT NRI Manway Studs 1-20 (Crossunder)

B aseline exam of replacem ent manway stud #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)

Baseline exam of replacement manway stud #16, WO 00883690 . 9/64' axial indication, acceptable per procedure .

Exeloin-7,8/2008 Byron Station Unit 1 BIR15 ISI Outage Report Pressure Test Outage Summary SYSTEM: Auxiliary Feedwater System (AF)

T>"rhi+.tCasl ACtu'al, Cat . item Rf-gtti7~'ts Notes F,Xj+/-t1

, iTtti!entC NA NA 1-AF 1 VT-2 NRI NA NA 1-AF- 2-2 VT-2 NRI

Exelon-Byron Station Unit 1 B1 R15 ISi Outage Report Pressure Test Outage Summary SYSTEM: Containment Spray System (CS) t1~, ; ei I(!Cr,r , 4~4

~iit-'Gi :CbtS ."v0t~-S 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 Exelein-

~Station Byron Unit 1 B1 R15 ISI Outage Report Pressure Test Outage Summary SYSTEM : Chemical & Volume Control System (CV) t5 NA NA 1-CV-2-1 I3T-03 VT-2 NRI 13T-04 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

Exelein-7/8/2008 ByronStation Unit 1 B1 R15 ISI Outage Report Pressure Test Outage Summary SYSTEM : Fuel Pool Cooling System (AF) r.-~ f-gof, " s "ar,z s VT-2 NRI 7/812008

Exel6n-7/8/20NOB Byron siaiion Unit 1 BIR15 ISI Outage Report Pressure Test Outage Summary SYSTEM : Process Sampling System (PS)

S -, I, XI cofllp~~(1 ,7 CA ZINTI

.moms Cans-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

tmelein-MR*

r i 7/8/2UGS B1RI5 ISI Outage Report Pressure Test Outage Summary SYSTEM : Reactor Coolant System (RC)

R- " iipf n:

"lop

, , ! f, t4 v xam NA NA 1-RC-1-1 VT-2 NRI

7/8/2008 Exelein-v Byron Station Unit 1 B1R15 ISI Outage Report Pressure Test Outage Summary SYSTEM : Residual Heat Removal System (RH)

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

7/8/2008 Exelein_

Byron Station Unit 1 B1 R15 ISI Outage Report Pressure Test Outage Summary SYSTEM : Reactor Coolant System (RY) ical Asatztl f;,`, ,u= ;s c~,IS 'i02~'~ E:xaa'1 NA NA 1-RY-2-1 VT-2 NRI 7/8/2008

Exelein_

7,8/2008

- ByronStationUnit 1 B1 R15 ISI Outage Report Pressure Test Outage Summary SYSTEM : Safety Injection System (SI)

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

&elejn-7/8/2008 ByronStation Unit 1 B1R16 ISI Outage Report Component Support Outage Summary SYSTEM : Auxiliary Feedwater System (AF)

F-A F1 .20 1AF02EA-4/1AF06001R 1AF02EA-4 VT-3 NRI Rigid

7/8/2008 Exelein-W Byron Station Unit 1 B1R15 ISI Outage Report Component Support Outage Summary SYSTEM: Containment Spray System (CS)

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 Mi nor surface rust only, no wast ag e

7/ar2ooa Exelon-Byron Station Unit 1 B1R15 ISI Outage Report Component Support Outage Summary SYSTEM: Chemical & Volume Control System (CV)

F-A F1 .20 1CV08BA-411CV01002X 1CV08BA-4 VT-3 NRI SEISMIC 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 bcelcin_

Byron Station Unit 1 B1R15 ISI Outage Report Component Support Outage Summary SYSTEM: Feedwater System (FW)

F-A F1 .20 1FW81AA-6/1AF06038R 1FW81AA-6 VT-3 NRI RIGID 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 Reference IR 757579, within allowable cold range .

7/8/2008 C-xelein_

Byron Station Unit 1 B1R1S ISI Outage Report Component Support Outage Summary SYSTEM: Main Steam System (MS) d i~-r rd, i nF , .W;r,i(;J< t+c",ua! AAVk;as tL Xi1 ~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 identif ied during both exams . No evidence of wastage or loss of material .

&elon-7,$/2008

- Byron Station Unit 1 B1R15 ISI Outage Report 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 .

7/8/2008 Exelon_

- Byron Station Unit 1 B1 R15 ISI Outage Report Component Support Outage Summary SYSTEM: Residual Heat Removal System (RH) 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

__ Exelon-Byron Station Unit 1 BIR15 ISI Outage Report 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

Exelein-7/8/2008 Byron Station Unit 1 B1R15 ISI Outage Report Component Support Outage Summary SYSTEM: Safety Injection System (SI)

F-A F1 .20 1S104B-12/1RH02029X 1SI04B-12 VT-3 NRI SEISMIC F-A F1 .20 1 SI04C-8/1 RH02026X 1 SI04C-8 VT-3 NRI SEISMIC F-A F1 .10 1S104D-8/1RH02022X 1SI04D-8 VT-3 NRI SEISMIC F-A F1 .20 1 S105BA-8/1 PC-50A 1 SI05BA-8 VT-3 NRI ANCHOR VT-3 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 .

F-A F1 .20 1SI08CA-4/1SI07008X 1S108CA-4 VT-3 NRI SEISMIC F-A F1 .10 1SI08JA-1-1/2/1SI-CP1A 1SI08JA-1-1/2 VT-3 NRI SEISMIC F-A F1 .10 1SI098A-10/1S101001V 1SI09BA-10 VT-3 NRI VARIABLE

Exelein-

~~ Byron Station Unit 1 B1 R15 ISI Outage Report 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

7/8/2008 Exelc'm_

Byron Station Unit 1 Byron Station Outage B1R15 Snubber Outage Summary (Page 1 of 6)

SYSTEM: Chemical _& Volume Control S~(stem (CV)

~*,ri (: ai A~ ; wI ra,,co3 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 Initial Exam Note : Section XI Category numbers N/A-ed are exempt from IWF-1220 and IWF-2500 tables

Exeiein_

7/8/2008

~Byron Station Unit 1 Byron Station Outage B11115 Snubber Outage Summary (Page 2 of 6)

SYSTEM : Main Steam System (MS)

Nk"tes - z :^i NA SNUB 1MS01AC-32 .75 /1MS07006-S1 1MS01AC-32 .75 y VT-3 NRI SNUBBER 19 FT PASS Initial Exam NA SNUB 1MS01AC-32 .75 /1MS07006-S2 1MS01AC-32.75 y VT-3 NRI SNUBBER 19 FT PASS Initial Exam Note : Section XI Category numbers N/A-ed are exempt from IWF-1220 and IWF-2500 tables 2

7/8/2008 Exelesn_

Byron Station Unit 1 Byron Station Outage B1 R15 Snubber Outage Summary (Page 3 of 6)

SYSTEM: Reactor Coolant Svstem (RC) 1 ., of A , .Ii .,~i Re ;i~+rs R;>,.~_osts 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 Initial Exam Note: Section XI Category numbers N/A-ed are exempt from IWF-1220 and IWF-2500 tables 3

Exelein_

Byron Station Unit 1 Byron Station Outage B1R15 Snubber Outage Summary (Page 4 of 6)

SYSTEM : Residual Heat Removal System (RH)

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 Note : Section XI Category numbers N/A-ed are exempt from IWF-1220 and IWF-2500 tables 4

7/8/2008

&elejn-Byron Station Unit 1 Byron Station Outage B1R15 Snubber Outage Summary (Page 5 of 6)

SYSTEM: Reactor Coolan t Syste n RY)

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 Initial Exam Note : Section XI Category numbers N/A-ed are exempt from IWF-1220 and IWF-2500 tables 5

7/8/2008 Exelein.

~Byron^ StationUnit 1 Byron Station Outage B1R15 Snubber Outage Summary (Page 6 of 6)

SYSTEM : Safety Iniection Svstem (SIB 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

(This report is used to verify that the periodic BYRON STATION UNIT 1 AND UNIT COMMON - 3RD INTERVAL (The percentage requirements o¬ TablesIWx--

requirements of Tables IWx-2412-1 will be met by 2412-1 apply to the Category and were ASME SECTION XI EXAMINATION STATUS REPORT ay . led to each Item only when practical .)

t he in terval schedu le .

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 Category B-A Non-Deferred Exams 81 .30 1 1 0 0 1 1 0 1 0 100.00% 0.000/0 0.00% 0.000/0 81 .40 1 1 0 0 1 1 0 1 0 100.000/0 0.000/0 0.000/0 0.000/0 Totals : 2 2 0 0 1 1 0 1 0 100.00% 0.00% 0.00% 0.000/0 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 0 100.000/0 0.000/0 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% 100.000/0 100 .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% 50.000/0 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 .

Category B-D Deferred Exams 83 .90 8 8 N/A 0 N/A N/A 0 N/A 0 100.000/0 0.000/0 0 .00% 0.000/0 8 3.100 8 8 N/A 0 N/A N/A 0 N/A 0 100.00% 0.000/0 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 verity that the periodic WY ON STATION UNIT 1 AND UNIT COMMON - 3RD INTERVAL (The percentage requirements ofTables IWx-requirements of Tables IWx-2412-1 will be met by 2412-1 apply to the Category and were the interval schedule .

ASME SECTION XI EXAMINATION STATUS REPORT 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

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 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 0 100.000/0 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% 0.000/0 0.000/0 136 .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 0.000/0 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 .220 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 0.000/0 0.00 0/0 0.000/0 0.00%

Totals : 71 38 N/A 11 N/A N/A 0 N/A 0 53.52% 28.95% 28-95% 28.95%

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 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 2412-1 apply to the Category and were the interval schedule . ASME SECTION Xt EXAMINATION STATUS REP!'IRT 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

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 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%

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 GIMMON - 3RD INTERVAL (The percentage requirements of Tables IWx-req uirem ents of Tables IWx-2412-1 will be met by 2412-1 apply to the Category and were ASME SECTION XI EXAMINATION STATUS REPORT a . elied to each Item only when practical .)

the interval schedule.

of Total # Exams Completed % Exams Completed Item No. Comp Selected Min Per 1 Max Min Per 2 Max Per 3 % Selected Period 1 Period 2 Period 3 Category B-K Non-Deferred Exams 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

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 3 812 .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%

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

of Total # Exams Completed % Exams Completed Item No. Comp Selected min Per 1 max min Per 2 max Per 3 0,6 Selected 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 . (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 .

Categ ory B-N-1 Non-Deferred Exams 81 3.10 2 1 0 1 1 1 0 1 0 50.00% 100.000/0 100.00% 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 COMMON - 3RD INTERVAL (The percentage requirements of Tables IWx-requirements of Tables IWx-2412-1 will be met by 2412-1 apply to the Category and were the interval schedule .

ASME SECTR7:1C~*IN -

STATUS REPORT 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 0 100.000/0 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 . (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 . (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%

C1 .30 4 1 0 0 1 1 0 1 0 25.00% 0.000/0 0.00% 0.00%

Totals : 16 5 1 2 2 1 0 1 0 31 .25% 40.00% 40.00% 40.00%

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 2412-1 apply to the Category and were ASME SECTHJN Xl EXAMINATION STATUS REPORT applied to each Item only when practical .)

th e interva l sch edu le .

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 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% 100.000/0 100.00% 100.00%

Totals : 20 2 0 1 1 1 0 1 0 10.00% 50.000/0 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 C3 .10 2 1 0 0 1 1 0 1 0 50 .00% 0.000/0 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%

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 . (C7.10) "% Completed" exceeds 100% si nce Class 2 pressure tests are performed each inspection period.

2. (C7.10) Twenty-nine components representing 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%

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 verity that the periodic BYRt~L_Ear- ~X!7:AJ~`J1LI~T J1'CW:7QW_Lf[-IN - 3RD INTERVAL (The percentage requirements of Tables IWx-requirements of Tables IWx-2412-1 will be met by 2412-1 apply to the Category and were th e interval sched ule.

ASME SECTION XI EXAMINATION STATUS REPORT 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

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 . (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 .30 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 . (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 1 128 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% 32.19010 32.19% 32.19%

5 65 10 2 0 5 5 0 7 0 15.38% 0.000/0 0.00% 0.000/0 Totals: 1727 224 36 61 112 51 0 107 0 12.97% 27.23% 27.23% 27.23%

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 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 2412-1 apply to the Category and were th e interval schedul e . ASME SECTION XI EXAMINATION STATUS REPORT 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 Category R-A Socket Welds 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%

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

Exelein-Byron Station Unit 1 BlR15 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 1 of 46) 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 (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: Auxiliary Feedwater System (AF)

Manufacturer Component or Manufacturer State or National or Installer Appurtenance or Installer Serial No. Province No. Board 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 Note (1) : Baseline Examination Note (2) : Snubber examined as a Component Support 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 .

Computer Generated Form

Exellloln_

Byron Station Unit 1 B1R15 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 2 of 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 : Auxiliary Feedwater System (AF)

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

Appurtenance or Installer Serial No.

1 AF02EA- Hunter Corp. N/A N/A N/A 4/1 AF06001 R Note (1) : Baseline Examination Note (2) : Snubber examined as a Component Support Note : Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in . x 11 in ., (2) information in items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form .

Computer Generated form

Exelloin-Byron Station Unit 1 BiR15 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 3 of 46) 1 . Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 (Narne 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: Containment Spray System (CS)

Manufacturer Component or Manufacturer State or National or Installer Appurtenance or Installer Serial No.

Province No . 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 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 .

Contputer Generated Form

&el6n-6/26/2008 Byron Station Unit 1 B1 R15 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 4 of 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: Containment Spray System (CS)

Manufacturer Component or Manufacturer State or National or Installer Appurtenance 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 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 Forth

Exellibm 6/2&2008 Byron Station Unit 1 B1 R15 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 5 of 46) 1 . Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 (Narne 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: Chemical & Volume Control System (CV)

Manufacturer Component or Manufacturer State or National or Installer Appurtenance or Installer Serial No. Province No. Board No.

1 RC14AB- Pacific Scientific 23835 NA NA 2/1 CV15039-S1 1 RC14AB- Pacific Scientific 7345 NA NA 2/1 CV15039-S2 Note (1) : Baseline Examination Note (2) : Snubber examined as a Component Support Note : Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in . x 11 in ., (2) 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

Exelein-6/26/2008 Byron Station Unit 1 B1 R15 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 6 of 46) 1 . Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 (flame 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 : Chemical & Volume Control System (CV)

Manufacturer Component or Manufacturer State or National or Installer Appurtenance or Installer Province No. Board No.

Serial 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 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

&elejn-6/2si20o8 Byron Station Unit 1 BiR15 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 7 of 46) 1 . Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 (Narne 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: Chemical & Volume Control System (CV)

Manufacturer Component or Manufacturer State or National or Installer Province No.

Appurtenance or Installer Serial No. Board 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 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

Exelein-6/26/2W8 Byron Station Unit 1 B1 R15 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 8 of 46) 1 . Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 (Narne and Address of Owner)

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)

Manufacturer Component or Manufacturer State or National or Installer Appurtenance or Installer Province No. Board No.

Serial 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 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

&elejn-6/26/2008 Byron Station Unit 1 B1 R15 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 9 of 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: Chemical & Volume Control System (CV)

Manufacturer Component or 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 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

Exel6n-Byron Station Unit 1 B1 R15 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 10 of 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: Chemical & Volume Control System (CV)

Component or Manufacturer Manufacturer or Installer State or National Appurtenance or Installer Province No. Board No.

Serial No.

1CV15AC- Pacific Scientific 1308 NA NA 3/4/1 CV29003S 1 CVA5AA- Pacific Scientific 22192 NA NA 2/1 CV15054S 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 .

Comp~ Generated Ports

6/2612008 Exelon-Byron Station Unit 1 B1R15 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 11 of 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: Fuel Pool Cooling System (AF)

Manufacturer Manufacturer Component or or Installer State or National Appurtenance or Installer Province No. Board No.

Serial No.

1-FC-2-1 Hunter Corp. N/A N/A N/A Note (1) : Baseline Examination Note (2) : Snubber examined as a Component Support Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in . x 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 .

Computer Generated Form

Exelein-6/28/2008 Byron Station Unit 1 B1 R15 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 12 of 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)

Manufacturer Component or Manufacturer State or National or Installer Appurtenance or Installer Province No. Board No.

Serial No.

1 FW 81 AA- Hunter Corp. N/A N/A N/A 6/1 AF06038R 1 FW 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 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

6/28/2008 Exelon-Byron Station Unit 1 Bi R15 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 13 of 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)

Manufacturer Component or Manufacturer State or National or Installer Appurtenance or Installer Serial No. Province No. Board 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 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

6/26/2008 Exelein-Byron Station Unit 1 B1R15 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 14 of 46) 1 . Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 (Narne 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 : Main Steam System (MS)

Manufacturer Component or Manufacturer State or National or Installer Appurtenance 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 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

6/26/2008 Exelon-Byron Station Unit 1 B1 R15 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 15 of 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 (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: Main Steam System (MS)

Manufacturer Component or Manufacturer State or National or Installer Appurtenance or Installer Serial No. Province No. Board No.

1 MS01 BB-30-3/4/1 PC- Hunter Corp . N/A N/A N/A 85A 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

Exelein-6/26/2008 Byron Station Unit 1 B1 R15 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 16 of 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 : Process Sampling System (PS)

Manufacturer Component or Manufacturer State or National or Installer Appurtenance or Installer Province No. Board No.

Serial 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 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 Genmrated Form

Exelein-Byron Station Unit 1 B1R15 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 17 of 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 (flame 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)

Manufacturer Component or Manufacturer State or National or Installer Appurtenance or Installer Province No. Board No.

Serial No.

1-RC-1-1 Hunter Corp. N/A N/A N/A Note (1) : Baseline Examination Note (2) : Snubber examined as a Component Support Note : Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in . x 11 in ., (2) information in items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form .

A Corrvwwr Generated Fonn

6/26/2008 Exelein-Byron Station Unit 1 B1 R15 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 18 of 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 : Reactor Coolant System (RC)

Manufacturer Component or Manufacturer State or National or Installer Appurtenance or installer Serial No. Province No. Board No.

1 RC-01 -BA/S Hunter Corp . N/A N/A N/A Note (1): Baseline Examination Note (2) : Snubber examined as a Component Support Note : Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in . x 11 in ., (2) information in items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form .

Computer Generated Form

6/26/2008 Exelon-Byron Station Unit 1 BIR15 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 19 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 : Reactor Coolant System (RC)

Manufacturer Component or Manufacturer State or National or Installer Appurtenance or Installer Province No . Board No.

Serial No.

1RC Westinghouse Corp. 1-115E121-G01 NA W25819 PA/FLYWHEEL 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 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

Exelon-6/26/2tNi8 Byron Station Unit 1 B1 R15 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 20 of 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 : Reactor Coolant System (RC)

Manufacturer Component or Manufacturer State or National or Installer Appurtenance or Installer Serial No. Province No. 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 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

6/28/2008 Exelein-Byron Station Unit 1 B1 R15 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 21 of 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 : Reactor Coolant System (RC)

Manufacturer Component or Manufacturer State or National or Installer Appurtenance or Installer Province No. Board No.

Serial 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 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

6/26/2008 Exelon-ByronStation Unit 1 B1R15 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 22 of 46) 1 . Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 (Name and Address d 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) : NIA

5. Commercial Service Date: 09/16/85 6. National Board Number for Unit : N-198

7. Components Inspected : Reactor Coolant System (RC)

Manufacturer Component or Manufacturer State or National or Installer Appurtenance or Installer Province No. Board No.

Serial 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 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

6/26/2008

&elejn-Byron Station Unit 1 BiR15 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 23 of 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 : Reactor Coolant System (RC)

Manufacturer Component or Manufacturer State or National or Installer Appurtenance or Installer Province No. Board No.

Serial 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 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

Exelein-6/26/2008 Byron Station Unit 1 B1 R15 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 24 of 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 : Reactor Coolant System (RC)

Component or Manufacturer Manufacturer State or National or Installer Appurtenance or Installer Province No. Board No.

Serial 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 t

1 RC22AA-1 .5/W-23 Hunter Corp. 1-RC-1-N5 NA NA Note (1): Baseline Examination Note (2): Snubber examined as a Component Support Note : Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in . x 11 in ., (2) information in items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form .

Computer Generated Form

Exel6n-6/28/2b08 Byron Station Unit 1 B1 R15 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 25 of 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 : Reactor Coolant System (RC)

Manufacturer Component or Manufacturer State or National or Installer Appurtenance or Installer Province No. Board No.

Serial 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 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

6/26/2008 Exelon-Byron Station Unit 1 BlRl5 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 26 of 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 : Reactor Coolant System (RC)

Manufacturer Component or Manufacturer State or National or Installer Appurtenance or Installer Province No. Board No.

Serial 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- Pacific Scientific 2193 NA NA 2/1 CV15053S 1 RC20AB- Pacific Scientific 14748 NA NA 3/4/1 RC17012S 1 RC22AB- Pacific Scientific 20437 NA NA 1 .5/1 RC17015S 1 RC22AB- Pacific Scientific 5666 NA NA 1 .5/1 RC17028S 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

Exelein-6/26/2008 Byron Station Unit 1 B1R15 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 27 of 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 : Residual Heat Removal System (RH)

Component or Manufacturer Manufacturer state or National Appurtenance or Installer or Installer Province No. Board No.

Serial 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 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

6/26/2008 Exe-lon-ByronStation Unit 1 B1R15 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 28 of 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 : Residual Heat Removal System (RH)

Manufacturer Component or Manufacturer State or National or Installer Appurtenance 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 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

6/26/2008 Exelon-Byron Station Unit 1 B1 R15 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 29 of 46) 1 . Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 (Narne 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 : Residual Heat Removal System (RH)

Manufacturer Component or Manufacturer State or National or Installer Appurtenance 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 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

Exelein-6/26/2008 Byron Station Unit 1 B1 R15 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 30 of 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 : Reactor Pressure Vessel (RPV)

Manufacturer Component or 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 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

&elon-Byron Station Unit 1 B1 R15 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 31 of 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 T. Components Inspected : Reactor Pressure Vessel (RPV)

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 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

6/26/2008 Exelon-Byron Station Unit 1 B1R15 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 32 of 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 : Reactor Coolant System (RY)

Manufacturer Component or Manufacturer State or National or Installer Appurtenance or Installer Province No . Board No.

Serial 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 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

Exelein-6126/2008 Byron Station Unit 1 B1R15 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 33 of 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 : Reactor Coolant System (RY)

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 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

Euelun_

6/26/2008 Byron Station Unit 1 BIR15 ISI Outage Report 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)

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)

Component or Manufacturer Manufacturer or Installer State or National Appurtenance or Installer Province No. Board No.

Serial No.

1 RY-01-S/SKT Hunter Corp . N/A N/A N/A Note (1) : Baseline Examination Note (2) : Snubber examined as a Component Support Note : Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in . x 11 in ., (2) information in items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form .

Computer Generated Form

Exelun_

6/26/2008 Byron Station Unit 1 B1R15 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 35 of 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 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)

Manufacturer Component or Manufacturer State or National Appurtenance or Installer or installer Province No. Board No.

Serial 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 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

Exelon-6/26/2008 Byron Station Unit 1 B1 R15 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 36 of 46) 1 . Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 (Narne end 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: Reactor Coolant System (RY)

Component or Manufacturer Manufacturer or Installer State or National Appurtenance 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 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

Exelein_

6/26/2008 Byron Station Unit 1 1311315 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 37 of 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: Steam Generator (SG)

Manufacturer Component or 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 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

Exel6n-6/26/2008 Byron Station Unit 1 B1R15 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 38 of 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: Steam Generator (SG)

Manufacturer Component or Manufacturer State or National or Installer Province No.

Appurtenance or Installer Serial No. Board No.

1 RC-01-BB/N-3-NIR Babcock & Wilcox Industries 7722-03 ILU-242903 166 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 forth

6/26/2008 Exelein-Byron Station Unit 1 B1R15 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 39 of 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 : Safety Injection System (SI)

Manufacturer Component or Manufacturer State or National or Installer Appurtenance or Installer Province No. Board No.

Serial No.

1S108JA-1 .5/FLG 1-4 Hunter Corp . 1-SI-1-N5 NA NA Note (1) : Baseline Examination Note (2) : Snubber examined as a Component Support Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in . x 11 in ., (2) information in items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form .

computer Generated Form

6/26/2008 Exelon-Byron Station Unit 1 B1 R15 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 40 of 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 : Safety Injection System (SI)

Manufacturer Component or Manufacturer State or National or Installer Appurtenance or Installer Province No. Board No.

Serial 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 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 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 .

Computer Generated Form

Exelein-6/28/2008 Byron Station Unit 1 B1 R15 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 41 of 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) : NIA

5. Commercial Service Date: 09/16/85 6. National Board Number for Unit: N-198

7. Components Inspected : Safety Injection System (SI)

Manufacturer Component or Manufacturer State or National or Installer Appurtenance 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 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

Exel6n-6/26/2008 Byron Station Unit 1 B1 R15 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 42 of 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 ol 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)

Manufacturer Component or Manufacturer State or National or Installer Appurtenance or Installer Province No. Board No.

Serial 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 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

&elejn-6/26/2008 Byron Station Unit 1 B1 R15 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 43 of 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 : Safety Injection System (SI)

Manufacturer Component or Manufacturer State or National or Installer Appurtenance or Installer Province No. Board No.

Serial 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 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

&elejn-6/28/2008 Byron Station Unit 1 B1R15 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provlslons of the ASME Code Rules (Page 44 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 (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)

Manufacturer Component or Manufacturer State or National or Installer Appurtenance or Installer Serial No.

Province No. Board No.

1 S105CA-8/1 S102003S Pacific Scientific 6923 NA NA Note (1) : Baseline Examination Note (2) : Snubber examined as a Component Support Note : Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in . x 11 in ., (2) information in items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form .

computer Generated Form

6/26!2008

&elejn-Byron Station Unit 1 B1 R15 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 45 of 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 : Essential Service Water System (SX)

Manufacturer Component or Manufacturer State or National Appurtenance or Installer or Installer Province No. Board No.

Serial 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 Note (1) : Baseline Examination Note (2) : Snubber examined as a Component Support Note : Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in . x 11 in ., (2) information in items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form .

Computer Generated Form

7/9/2008 Exelein-Byron Station Unit 1 B1 R16 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 46 of 46)

(BACK)

8. Examination Dates: 10/16/06 to 04/14/08

9. Inspection Period Identification :

10 . Inspection Interval Identification : Third lnsoecti Qn lntetval 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 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 CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Illinois and employed by HSB CT of Hartford CT. have inspected the components described in this Owner's Report during the period 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 Computer Generated Form

BYRON 2008-0067, Day Inservice Inspection Report for Interval 3, Period 1, Outage 2 (B1R15)

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BYRON 2008-0067, Day Inservice Inspection Report for Interval 3, Period 1, Outage 2 (B1R15)

Text

Attachment:

SUMMARY

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