BYRON 2005-0073, Day Inservice Inspection Report for Interval 2, Period 3, Outage 1 (B1R13). Part 1

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Day Inservice Inspection Report for Interval 2, Period 3, Outage 1 (B1R13). Part 1
ML051720481
Person / Time
Site: Byron Constellation icon.png
Issue date: 06/20/2005
From: Kuczynski S
Exelon Generation Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
BYRON 2005-0073
Download: ML051720481 (49)
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Text

EXeI~:~:~nSM Exelon Generation Company, LLC www.exeloncorp.com N uclear Byron Station 4450 North German Church Road Byron, IL 61010-~9794 June 20, 2005 LTR: BYRON 2005-0073 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. STN 50-454

SUBJECT:

Byron Station Unit 1 90-Day Inservice Inspection Report for Interval 2, Period 3, Outage 1 (B1R13)

The subject 90-day Inservice Inspection Report for the Byron Station Unit 1, Refueling Outage Thirteen (i.e., Bi R13) is being submitted pursuant to the requirements of Article IWA-6000, Records and Reports of Section Xl, Rules for lnservice Inspection of Nuclear Power Plant Components, of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, 1989 Edition. The report covers the inservice inspections conducted prior to and during the Unit 1 Spring 2005 refueling outage.

If there are any questions regarding this matter, please contact W. Grundmann, Regulatory Assurance Manager, at (815) 406-2800.

Respectfully, 5~L)~I Stephen E. Kuczynski Site Vice President Byron Nuclear Generating Station SEK/TLF/rah

Attachment:

B1R13 Inservice Inspection Summary Report Spring 2005 Outage

BYRON EXkflSM UNIT I Nuclear B1R13 Spring 2005 Outage INSERVICE INSPECTION

SUMMARY

REPORT For Inspection Activities from October 14, 2003 to March 25, 2005 Commercial Service Date September 16, 1985 Document Completion Date June 1, 2005 Exelon Generation Company, LLC 4300 Winfield Rd Warrenville, IL 60555 Byron Nuclear Power Station 4450 North German Church Rd.

Byron, IL 61010

BYRON UNIT 1 Exekn5~

Nuclear B1R13 INSERVICE INSPECTION

SUMMARY

REPORT ESECTION SECTION DESCRIPTION PAGES 1 f i fCover Page j I

[~ ii liable of Contents I I I I I JReport Introduction I 8 I Welds & Components 13 Obstructed Examinations I Examination Summary Tables Pressure Tests 4 2

Containment Structure I Component Supports 9 Snubbers 4 Welds & Components 12 Pressure Tests 6 Containment Structure I ASME Form NIS-1 Signature Page I 3

Component Supports 9 Signature Page I Sn ubbers 5 Signature Page I I 4 IASME Form NIS-2 Repairs I Modificationsf 86 I I TOTALPAGESINREPORTI 164 I

BYRON STATION UNIT I REFUELING OUTAGE 13 INSERVICE INSPECTION REPORT

1.0 INTRODUCTION

lnservice 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 14, 2003 through March 25, 2005. The majority of these inspections were performed during the thirteenth refueling outage (Bi Ri 3) from February 27 through March 25, 2005. The 20th Year tendon surveillance on the concrete containment was performed between June 1 and July 28, 2004. The examinations were performed in compliance with the rules and regulations of ASME Section Xl, 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. This report also includes inspection results of components for Class 3,CC, MC, and Augmented Programs. See Section 3.0 for a listing of referenced documents.

The Nondestructive Examination (NDE) Inservice Inspection (lSl) 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, and IWF, 1989 Edition, No Addenda, and Subsections IWA, IWE, and IWL, 1998 Edition, No Addenda for Class CC and MC components. In addition to the ASME Section XI requirements of examination, certain Nuclear Regulatory Commission (NRC) augmented ISI inspections were required. The Byron Station Unit I augmented ISI examination requirements include:

a) Class I 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; Note: Specific requests for relief were developed and submitted for the NRCs 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 ISI Program contains the NDE 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 NDE tables include the corresponding code category, item number, and component/weld selection in conformance with examination requirements and intent of Subsection IWA, IWB, IWC, IWD, IWE, IWF, and IWL of Section Xl of the ASME Code. Program notes, relief requests, and additional information are identified in the remarks column.

Page 1 of 8

BYRON STATION UNIT I REFUELING OUTAGE 13 INSERVICE INSPECTION REPORT For Class 1 and 2 piping, the requirements of Risk Informed Inservice Inspection (RI-ISI) are followed using Table I of ASME Code Case N-578-1, and EPRI Topical Report TRI 12657 Revision B-A, Revised Risk-Informed Inservice Inspection Procedure. This alternate selection and examination method was approved for use with Byron Stations Request for Relief I2R-40 and was incorporated into the program plan (currently Revision 5, dated February 7, 2004). This request was granted by a Safety Evaluation (SER) dated February 5, 2002.

1.2 Identification of Exempted components ASME Class 1, 2, and 3 components, or parts of components, that are not included in the NDE tables and that are exempt from examination, as specified in Section Xl Paragraphs IWB, IWC, and IWD-1200, Components Exempt from Examination, and Table IWD-2500-1, are identified in the NDE Program Plan in conjunction with technical justification(s) for exempting the component/system. Class I 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-i, 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 Program Exelon Nuclear, or its designee, visually examined ASME components utilizing the following test methods: VT-I, VT-2, and VT-3. The components examined comply with the lSl Program Schedule, Byron Station Technical Specifications, and/or comply with the ASME Section Xl Repair/Replacement Program.

Certified personnel performed and evaluated visual examinations (i.e., VT-i, VT-2, and VT-3) of Class 1, 2, and 3 components, and supports. Exelon Nuclear personnel certification procedures comply with the requirements ofANSI/ASNT CP-189, 1991 Edition and ASNT SNT-TC-IA, 1984 Edition.

Certified personnel performed and evaluated all NDE. Personnel were certified to the requirements of the ASNT SNT-TC-IA, 1984 Edition. Additionally, ultrasonic examiners were certified in accordance with ANSI/ASNT CP-189, 1991 Revision.

The NDE procedures were developed and certified in conformance with ASME Section V and XI, 1989 Edition, and the 1995 Edition with the 1996 Addenda as applicable.

All lSl 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 Page 2 of 8

BYRON STATION UNIT I REFUELING OUTAGE 13 INSERVICE INSPECTION REPORT by the EPRI Topical Report while the guidance for the examination method is provided by Code Case N-578-1.

All lSl NDE, including evaluation of flaw indications, were performed in accordance with the requirements stipulated under Section XI, Subarticle IWA-2200 Examination Methods.

I .4 Witness and Verification of Examination The inservice inspections were witnessed and/or verified by the Authorized Nuclear Inservice Inspectors (ANII), J. Hendricks and L. Malabanan. These inspectors are associated with Hartford Steam Boiler Inspection and Insurance Company of Connecticut, Chicago Branch, at 2443 Warrenville Rd., Suite 500, Lisle, Illinois 60532.

Page 3 of 8

BYRON STATION UNIT I REFUELING OUTAGE 13 INSERVICE INSPECTION REPORT 2.0 EXAMINATION SUMMARIES The following section contains summaries of examinations performed during the refueling outage. Refer to each summary table for additional information or for specific tests and examinations conducted during this term.

2.1 Welds & Components Summary _________________________________

PIPING AND PUMPS VESSEL WELDS

> r z > CZ COMPONENT! SYSTEM ~ m ~ ~ ~ ~

BASIC DESCRIPTION PRESSURE RETAINING WELDS 2~ ~

m ci

~ ~ 2 Z~~ BOLTING I > ~

~ ~ ~ ~ STUDS ~

~l ~ 0 >0 m ~ Z ~

~n r ~

EXAMINATION METHOD SUR VOL VT SUR SUR VOL VT VOL SUR VOL VOL VIS SUR VOL SUR VOL VT VT SURFACE, VOLUMETRIC, VISUAL CS-Containment 6 Spray CV-Chem. & Vol. 14 Control FW-Feedwater 13 MS-Main Steam RY-Pressurizer 7 7 3 Piping PZR-Pressurizer 2 Vessel RC-Reactor Coolant 10 77 RPV-RX Pressure 8 8 2 5 4 RH-Res. Heat 4 2 Removal SD-St. Gen.

Blowdown SG-Steam 3 5 2 1 1 1 Generators SI-Safety Injection 3 19 SX-Essential Ser.

2 Water EXAM TYPE TOTAL 43 117 2 9 3 9 1 8 3 7 14 COMPONENT/EXAM 162 ~ 24 ~

TOTAL OUTAGE EXAM TOTAL 2

Page 4 of 8

BYRON STATION UNIT I REFUELING OUTAGE 13 INSERVICE INSPECTION REPORT 2.2 System Pressure Test Summary EXAMINATION AREA j LEAK FUNCTIONAL INSERVICE PNEUMATIC Class 1 Vessel Pressure Retaining Boundary 6 Class 1 Piping, Pressure Retaining Boundary 1 Class 1 Pumps, Pressure Retaining Boundary 4 Class 1 Valves, Pressure Retaining Boundary 1 Class 2 Vessel Pressure Retaining Boundary 4 6 Class 2 Piping, Pressure Retaining Boundary 17 13 2 Class 2 Pumps, Pressure Retaining Boundary 6 3 Class 2 Valves, Pressure Retaining Boundary 18 9 2 TOTALS 12 45 31 4 2.3 Containment Examination Summary EXAMINATION ITEM* / AREA COMMENTS El. 11 Containment Liner 100% of Accessible Surfaces Examined L2.30 Anchorage Hardware L2.40 Protection Medium L2.40 Protection Medium Grease Replacement

  • Examination item number from Table IWE/IWL 2500-1 Page 5 of 8

BYRON STATION UNIT I REFUELING OUTAGE 13 INSERVICE INSPECTION REPORT 2.4 Component Support Examination Summary SYSTEM EXAMINED VT-3 CS-Containment Spray 3 CV-Chemical & Volume Control 9 FW-Feedwater 5 MS-Main Steam 1 RC-Reactor Coolant 3 RH-Residual Heat Removal 1 RY- Pressurizer Surge and Piping 3 SX-Essential Service Water 4 VQ-Primary Containment Purge 1 TOTAL 30 2.5 Component Snubber Test Summary SYSTEM EXAMINED VT-3 EXAMINED FUNCTIONAL TEST CV-Chemical & Volume Control 3 3 RC-Reactor Coolant 14 7 RY-Pressurizer Surge and Piping 2 2 SI-Safety Injection 1 2 TOTALS 20 14 Page 6 of 8

BYRON STATION UNIT I REFUELING OUTAGE 13 INSERVICE INSPECTION REPORT 2.6 Repair/Replacement Summary _________________________________________

A total of 73 ASME Form NIS-2, Owners Report for Repairs or Replacements, were filed during Byron Station Unit 1 Cycle 13. The following is a system summary of NIS-2s generated:

SYSTEM TOTAL NIS-2 FORMS NUMBER OF PAGES AF-Auxiliary Feedwater 3 4 CC-Component Cooling 2 2 CS-Containment Spray 1 1 CV-Chemical Volume Control 12 12 DG-Diesel Generator 3 3 DO-Diesel Fuel Oil 1 1 FP-Fire Protection 1 1 MS-Main Steam 9 16 RC-Reactor Coolant 4 5 RH-Residual Heat Removal 1 1 RY-Pressurizer and Pressurizer Piping 5 5 SA-Station Air 4 4 SD-Steam Generator Blowdown 1 1 SI-Safety Injection 1 1 SX-Essential Service Water 17 21 VQ-Primary Containment Purge 2 2 WE-Auxiliary Building Equipment Drains 1 1 WO-Chilled Water 3 3 Spare Components 2 2 TOTAL 73 86 Page 7 of 8

BYRON STATION UNIT I REFUELING OUTAGE 13 INSERVICE INSPECTION REPORT 3.0 REFERENCED DOCUMENTS 3.1 Code of Federal Regulations, Title 10 Energy Part 50, Domestic Licensing of Production and Utilization Facilities 50.55a, Codes and Standards 3.2 American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code Section V, Nondestructive Examination, 1989 Edition, No Addenda,Section V, Nondestructive Examination, 1995 Edition, with the 1996 Addenda, Section Xl, Rules for Inservice Inspection of Nuclear Power Plant Components, 1989 Edition, No Addenda,Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components, 1995 Edition, 1996 Addenda,Section XI, Rules for lnservice Inspection of Nuclear Power Plant Components, 1998 Edition, No Addenda, Cases of ASME Boiler and Pressure Vessel Code Case N-578-i Risk-Informed Requirements for Class 1, 2, or 3 Piping, Method B, Section Xl, Division 1 3.3 American National Standards Institute / American Society for Nondestructive Testing ANSI/ASNT CP-I89, 1991 Edition, Standard for Qualification and Certification of Nondestructive Testing Personnel 3.4 American Society for Nondestructive Testing ASNT Recommended Practice No. SNT-TC-IA, 1984 Edition, Personnel Qualification and Certification in Nondestructive Testing 3.5 Miscellaneous NRC Documents Approval of Relief Request l2R-40 for Application of Risk-Informed Inservice Inspection Program as an Alternative to the ASME Boiler and Pressure Vessel Code Section Xl Requirements for Class I and 2 Piping Welds for Byron Station, Units 1 and 2 (TAC NOS. MB0567 AND MB0568).

Safety Evaluation by the Office of Nuclear Reactor Regulation, Risk Informed Inservice Inspection Program Relief Request, Exelon Generation Company, Byron Station Units 1 and 2, Docket Nos. STN 50-454 and STN 50-455 Evaluation of Second 10-Year Interval lnservice Inspection Program Plan and Associated Request for Relief for Byron Station, Units 1 and 2 (TAC Nos. M94830 and M94831).

Safety Evaluation by the Office of Nuclear Reactor Regulation, Related to the Second 10-Year Interval Inservice Inspection Program Plan and Associated Request for Relief, Commonwealth Edision Company, Byron Station Units 1 and 2, Docket Nos. STN 50-454 and STN 50-455.

Page 8 of 8

Exelon Byron Unit I Welds I Components B1R13 OUTAGE INSPECTION

SUMMARY

SYSTEM: INTERVAL: PERIOD:

Containment Spray (CS) Second Third 088 CODE ISOMETRIC COMPONENT/LINE COMPONENT I WELD E ~.MT E RE t.

CODE ITEM - .~- SU TS NUMBER CATEGORY IDENTIFICATION NUMBER 13-069 R-A4 R1.20 1CS-03 1CSO1AA-16 C06 X ID. Geometry 360°Intermittent.13-070 R-A 4 Ri.20 1CS-03 1CSO1AA-16 C21 X No Recordable Indications.13-071 R-A4 R1.20 1CS-04 1CSO1AB-16 C14 X No Recordable Indications.13-072 R-A4 R1.20 1CS-05 1CSO2AB-1O C07 X No Recordable Indications.13-073 R-A 4 Ri .20 1CS-05 1CSO2AB-iO ClO X No Recordable Indications.13-074 R-A4 Ri.20 1CS-05 1CSO2AB-10 C20 X No Recordable Indications.

Page 1 of 13

Exelon Byron Unit 1 Welds I Components B1R13 OUTAGE INSPECTION

SUMMARY

I I

SYSTEM: INTERVAL: PERIOD:

I Chemical Volume Control (CV) Second Third 13-031 R-A5 R1.1i 1RC-361CVA3AA-2 W-07______ X *No_Recordable Indications.13-003 R-A5 Ri.il 1CV-05 1CVA3B-2 W-74 X No Recordable Indications.13-004 R-A5 R1.i 1 1 CV-05 1 CVA3B-2 W-75 X No Recordable Indications.13-005 R-A5 Ri. ii I CV-05 1 CVA3B-2 W-76_______ X No Recordable Indications.13-006 R-A5 RI.i1 1CV-05 ICVA3B-2 W-77_______ X No Recordable Indications.13-007 R-A5 RI.l1 ICV-05 1CVA3B-2 W-84 X No Recordable Indications.13-008 R-A 5 RI .11 I CV-05 I CVA3B-2 W-85 X No Recordable Indications.13-009 R-A 5 RI.li 1CV-08 1CVA5AA-2 W-04 X No Recordable Indications.13-010 R-A5 RI.1l ICV-08 1CVA5AA-2 W-05 - X No Recordable Indications.13-011 R-A5 RI.1i 1CV-1l 1CVA6AA-2 W-04 X No Recordable Indications.13-012 R-A5 RI.ll 1CV-ll ICVA6AA-2 W-05 X No Recordable Indications.13-046 R-A5 RI.11 IRC-37 1CVA7AA-2 W-08 X No Recordable Indications.13-047 R-A5 Ri. 11 1 RC-37 1 CVA7AA-2 W-09 X No Recordable Indications.

Page 2 of 13

Exelon Byron Unit 1 Welds / Components B1R13 OUTAGE INSPECTION

SUMMARY

SYSTEM: INTERVAL: PERIOD:

Feedwater_(FW) Second Third msi*imum~

13-084 R-A 1 R1.lI IFW-03 1FWO3DB-16 C02 X No Recordable Indications.13-248 R-A 1 RI.1I 1FW-03 1FWO3DB-16 CIl.Oi x No Recordable Indications.13-249 R-A 1 RI.1l 1FW-03 1FWO3DB-l6 C12.0l X No Recordable Indications.13-086 R-A 1 R1.Ii 1FW-04 1FWO3DC-16 COi X No Recordable Indications.- 13-088 R-A 1 Rl.Il IFW-04 1FWO3DC-16 C02 X No Recordable Indications.13-252 R-A I Rl.II 1FW-0l 1FWO3DD-i6 C16 X No Recordable Indications.13-253 R-A 1 RI.iI 1FW-01 IFWO3DD-16 C17 X No Recordable Indications.- 13-306 R-A 1 RI.lI IFW-0I IFWO3DD-16 C19.01 X No Recordable Indications.13-307 R-A 1 Rl.ll 1FW-0l IFWO3DD-16 C20.01 X No Recordable Indications.13-107 R-A 1 Rl.lI 1FW-05 IFW87CB-6 CO7A X No Recordable lndica~ons.13-108 R-A 1 R1.11 1FW-05 1FW87CB-6 CO8A x I.D. Geometry 360°Intermittent.13-118 R-A 1 Rl.1l 1FW-l0 1FW87CC-6 CO7A X No Recordable_Indications.

Page 3 of 13

Exelon Byron Unit 1 Welds I Components OUTAGE INSPECTION

SUMMARY

B1R13 SYSTEM: INTERVAL: PERIOD:

Pressurizer (RY) Second Third

~13-I I-RI.20 I ~ - -~ X Recordae Indications.13-311 R-A4 RI .20 IRC-35 IRYO2B-3 J05______ X ~LD.Geometry. Initial data.13-312 R-A4 Rl.20 1RC-35 1RYO2B-3 J06 X l.D. Geometry. Initial data.13-176 R-A 4 RI .20 1 RC-32 1 RYO3AA-6 J04 X No Recordable Indications.13-177 R-A 4 RI .20 I RC-32 1 RYO3AB-6 J02 X No Recordable Indications.13-178 R-A4 Rl.20 IRC-32 IRYO3AC-6 J04 X I.D. Geometry 360°fritermittent.13-179 R-A 4 RI .20 I RC-32 I RYO3BA-6 JOl X No Recordable Indications.13-173 R-A 4 RI .20 1 RC-32 I RYO3BC-6 JOl X l.D. Geometry 360°Intermittent.13-001 R-A2 RI.II ICV-02 IRY18A-2 W-05A X No Recordable Indications.- 13-258 R-A 2 Rl.1l ICV-02 IRY18A-2 ~ W-06 X No Recordable Indications.13-259 R-A 2 RI.1I ICV-02 IRY18A-2 W-07 X No Recordable Indications.- 13-260 R-A2 Rl.ll 1CV-02 1RY18A-2 W-08 X No Recordable Indications.13-261 R-A 2 RI .11 1 CV-02 I RYI 8A-2 W-09 X No Recordable Indications.13-002 R-A2 R1.II 1CV-02 1RY18A-2 W-l0 X No Recordable Indications.

- B-G-1 B7.70 I RC-32 1 RYO3BA-6 FLG 1-12 X No Recordable Indications.

Baseline exam of replacement.

- B-G-1 B7.70 IRC-32 1RYO3BB-6 FLG 1-12 X No Recordable Indications.

Baseline exam of replacement.

- B-G-l B7.70 IRC-32 IRYO3BC-6 FLG 1-12 X No Recordable Indications.

Baseline exam of replacement.

Page 4 of 13

Exelon Byron Unit 1 Welds I Components B1R13 OUTAGE INSPECTION

SUMMARY

SYSTEM: INTERVAL: PERIOD:

Pressurizer Vessel (PZR) Second Third

  • ~ecori .,le Inc,~

l3-1~ B-B B2.i2 1PZR-1 1RY-Oi-S PL-04 X No Recordable Indications.13-169 R-A2 R1.i5 1PZR-i IRY-Oi-S PN-04-F4 X No Recordable Indications.

Page 5 of 13

Exelon Byron Unit 1 Welds / Components B1R13 OUTAGE INSPECTION

SUMMARY

SYSTEM: INTERVAL: PERIOD:

Reactor Coolant (RC) Second Third 4~ TMT N1~?~R ~A~ORY ICODE ITEM ~ ISOMETRICf c0MN~M~p ~j~$T~ ~EXA YPE~f~ RESU4~~IIIf 13-019 R-A4 Ri.20 1RC-30 IRC13AA-2 W-01 X No Recordable Indications.13-289 R-A4 Rl.20 1RC-30 1RC13AA-2 W-02.01 X No Recordable Indications.13-290 R-A4 Ri.20 1RC-30 1RC13AA-2 W-03 X No Recordable Indications.13-291 R-A4 Rl.20 1RC-30 1RC13AA-2 W-04 X No Recordable Indications.13-020 R-A4 R1.20 1RC-30 1RC13AA-2° W-05 X No Recordable Indications.13-021 R-A 4 Ri .20 1 RC-30 1 RC1 3AB-2° W-01 X No Recordable Indications.13-022 R-A 4 Ri .20 1RC-30 1RCI3AB-2 W-09 X No Recordable Indications.13-023 R-A 4 Ri.20 IRC-30 1RC13AC-2 W-0I X No Recordable Indications.13-024 R-A4 RI.20 1RC-30 1RC13AD-2 W-0i X No Recordable Indications.13-032 R-A 2 R1.II IRC-36 IRCI4AA-2 W-02 X No Recordable Indications.13-033 R-A 2 Ri.ii 1RC-36 1RC14AA-2 W-03 X No_Recordable Indications.13-034 R-A 2 R1.11 IRC-36 IRC14AA-2 W-03A X No Recordable Indications.13-035 R-A 2 Ri.il 1RC-36 1RC14AA-2 W-03B X No Recordable Indications.13-036 R-A 2 R1.il 1RC-36 IRC14AA-2 W-03C X No Recordable Indications.13-037 R-A 2 R1.Ii IRC-36 IRCI4AA-2 W-04 X No Recordable Indications.13-038 R-A 2 RI.II IRC-36 1RC14AA-2 W-05 X No Recordable Indications.13-292 R-A 2 R1.1i 1RC-36 IRC14AA-2 W-06 X No Recordable Indications.13-039 R-A 2 Ri .11 1 RC-36 1 RC14AA-2 W-07 X No Recordable Indications.13-040 R-A 2 Rl.Il 1RC-36 1RC14AA-2 W-08 X No Recordable Indications.13-041 R-A 2 RI.ll IRC-36 IRCI4AA-2 W-09 X No Recordable Indications.13-042 R-A 2 R1.il 1RC-36 1RCI4AA-2 W-I0 X No Recordable Indications.13-043 R-A 2 Rl.ll 1RC-36 1RC14AA-2 W-li X No Recordable Indications.13-044 R-A 2 Rl.il 1RC-36 1RC14AA-2 W-12 X No Recordable Indications.13-045 R-A 2 Rl.1I 1RC-36 IRC14AA-2 W-13 X No Recordable Indications.13-025 R-A2 Rl.ii IRC-3I IRC14AB-2 W-07 X No Recordable Indications.13-026 R-A 2 RI.II 1 RC-31 I RC14AB-2 W-08 X No Recordable Indications.13-027 R-A2 R1.II 1RC-3I 1RC14AB-2 W-09 X No Recordable Indications.13-028 R-A 2 R1.li 1RC-31 1RC14AB-2° W-I0 X No Recordable Indications.13-029 R-A2 RI.II IRC-3I IRC14AB-2 W-il X No Recordable Indications._____

13-059 R-A 2 Ri.li 1RC-42 1RC14AC-2 W-08 X No Recordable Indications.13-048 R-A 2 Ri .11 1 RC-37 I RC1 4AD-2 W-08 x No Recordable_Indications.13-049 R-A 2 Ri .11 1 RC-37 1 RC14AD-2 W-09 X No Recordable Indications.13-050 R-A 2 Ri.ii 1RC-37 1RC14AD-2 W-iO X No Recordable_Indications.13-051 R-A 2 Ri.ii 1RC-37 1RC14AD-2 W-11 X No Recordable Indications.13-052 R-A 2 Ri.ii 1RC-37 1RC14AD-2 W-12 X No Recordable Indications.13-053 R-A2 Ri.ii 1RC-37 1RC14AD-2 W-i3 X No_Recordable Indications.13-293 R-A 5 Ri.ii 1RC-41 1RC16AA-2 W-02 X No Recordable Indications.13-054 R-A 2 Ri.ii 1RC-4i 1RC16AA-2 W-03 X No Recordable Indications.13-055 R-A 2 Ri .11 1 RC-4i 1RC16AA-2 W-04 x No Recordable Indications.13-056 R-A 2 Ri.ii 1RC-4i 1RC16AA-2 W-05 x No Recordable Indications.- 13-057 - R-A 2 Ri .11 1 RC-41 1 RC1 6AA-2 W-06 X No Recordable_Indications. -

13 294 R A4 Ri ii 1 RC-4i 1 RC16AA-2 W-07 X No Recordable Indications 13295 R A4 Ri ii 1RC 41 1RC16AA 2 W 08 X No Recordable Indications -

Page 6 of 13

Exelon Byron Unit 1 Welds / Components B1R13 OUTAGE INSPECTION

SUMMARY

SYSTEM: INTERVAL: PERIOD:

Reactor_Coolant_(contd) Second Third

~ ~___________

13-058 R-A 2 RI .11 1 RC-41 1 RC16AB-2 W-02 X No Recordable Indications.13-013 R-A4 Ri.20 iRC-23 1RC22AA-I% W-Oi_______ X No Recordable_Indications.13-262 R-A4 Ri,20 1RC-23 1RC22AA-iW W-02 X No Recordable_Indications.13-263 R-A 4 Ri .20 i RC-23 1 RC22AA-i 1/2k W-03 X No Recordable_Indications.13-264 R-A4 Ri.20 1RC-23 IRC22AA-iW W-04 X No Recordable Indications.13-265 R-A4 Ri.20 1RC-23 IRC22AA-iW W-05 X No Recordable Indications.13-266 R-A 4 Rl.20 1RC-23 IRC22AA-i% W-06 X No Recordable Indications.13-267 R-A4 RI.20 1RC-23 1RC22AA-i% W-07 X No Recordable Indication~

13-014 R-A4 Ri.20 IRC-23 IRC22AA-iW W-08 X No Recordable Indications.13-268 R-A4 Rl.20 1RC-23 1RC22AA-i% W-09 X No Recordable Indications.13-269 R-A4 Ri.20 1RC-23 IRC22AA-iW W-iO X No Recordable Indications.13-270 R-A4 Ri,20 1RC-23 1RC22AA-i% W-il X No Recordable Indications.13-271 R-A 4 Ri.20 1RC-23 1RC22AA-iW W-i2 X No Recordable Indications.13-272 R-A4 Ri.20 1RC-23 1RC22AA-iW W-i3.Oi X No Recordable Indications.13-273 R-A4 Ri.20 1RC-23 IRC22AA-IW W-i4.Oi X No Recordable Indications.13-274 R-A4 Ri.20 1RC-23 1RC22AA-iW W-15.Oi X No Recordable Indications.13-275 R-A4 Ri.20 IRC-23 1RC22AA-iW W-i6.0l X No Recordable Indications.13-276 R-A 4 RI.20 IRC-23 1RC22AA-1W W-I7 - X No Recordable Indications.13-277 R-A 4 R1.20 IRC-23 IRC22AA-IW W-i8 X No Recordable Indications.13-015 R-A 4 Rl .20 1 RC-23 I RC22AA-I 1/zn W-i 9 X No Recordable Indications.13-016 R-A4 RI.20 IRC-23 1RC22AA-1W W-20 X No Recordable Indications.13-278 R-A4 RI.20 IRC-23 IRC22AA-11/2 W-2i X No Recordable Indications.13-279 R-A4 Ri.20 IRC-23 IRC22AA-1W W-22 X No Recordable Indications.13-280 R-A 4 RI.20 1RC-27 1RC22AA-IY2 W-23 X No Recordable Indications.13-281 R-A4 Ri.20 1RC-27 IRC22AA-iW W-24 X No Recordable Indications.13-282 R-A4 Rl.20 1RC-27 IRC22AA-I% W-25 X No Recordable Indications.13-283 R-A 4 Rl.20 1RC-27 1RC22AA-IW W-26 X No Recordable Indications.13-284 R-A4 RI.20 IRC-27 IRC22AA-i% W-27 X No Recordable Indications.13-285 R-A 4 Ri .20 1 RC-27 I RC22AA-i~ W-28 X No Recordable Indications.13-286 R-A4 RI.20 1RC-27 1RC22AA-i1/2 W-29 X No Recordable Indications.13-287 R-A4 Ri.20 1RC-27 1RC22AA-iW W-30 X No Recordable_Indications.13-288 R-A 4 Ri .20 1 RC-27 I RC22AA-iW W-3i X No Recordable Indications.13-017 R-A4 Ri.20 1RC-27 1RC22AA-iW W-32 X No Recordable Indications.13-018 R-A 4 Ri.20 1RC-27 1RC22AA-i% W-33 x No Recordable Indications.13-254 R-A4 Ri.20 1RC-i4 1RC24AB-4 J16 X No Recordable Indications.13-255 R-A4 Ri.20 iRC-i4 1RC24AB-4 Ji7 X l.D. Geometry 360°Intermittent.

Page 7 of 13

Byron Unit 1 Exelon B1R13 Welds / Components OUTAGE INSPECTION

SUMMARY

SYSTEM: INTERVAL: PERIOD:

Reactor Pressure Vessel (RPV) Second Third

~ IINI1~*~IIIIIS~*

13-190 B-N-i Bi3.iO iRPV-i 1RC-Oi-R INTERIOR x No Recordable Indications.13-187 B-N-2 Bi3.50 1RPV-i 1RC-0i-R INT ATTACH X No Recordable Indications.

BELTLINE 13-188 B-N-2 613.60 iRPV-i 1RC-OI-R INT ATTACH X No Recordable Indications.

NONBELT 13-189 B-N-3 Bi3.70 1RPV-i 1RC-Oi-R CORE SUPP X No Recordable Indications.

STRUCT i3-22i B-G-i B6.I0 1RPV-3 1RC-Oi-R Ni9 N36

- X No Recordable Indications.13-222 B-G-i B6.iO 1RPV-3 IRC-0I-R - N37 N54

- X No Recordable lndication~

13-223 B-G-i B6.20 1RPV-3 IRC-Oi-R Si9 S36

- X No Recordable Indications.13-224 B-G-i B6.20 1RPV-3 IRC-0l-R_____ S37 S54 - X No Recordable Indications.13-225 B-G-i B6.50 1RPV-3 1RC-Oi-R Wi9 W36- X No Recordable Indications.13-226 B-G-i - B6.50 1RPV-3 1RC-Oi-R W37 W54- X No Recordable Indications.13-191 B-D B3.90 1RPV-l 1RC-OI-R RPVN-A X 2 Mid-wall indications, acceptable per code.13-192 B-D B3.I00 1RPV-I 1RC-Oi-R -- RPVN-A-IR X No Recordable Indications13-193 B-D B3.90 IRPV-i 1RC-0l-R RPVN-B X 29 Mid-wall indications, acceptable per code.13-194 B-D B3.I00 1RPV-l IRC-OI-R RPVN-B-lR X No Recordable Indications13-195 B-D B3.90 1RPV-1 IRC-OI-R RPVN-C X No Recordable Indications.13-196 B-D B3.iOO IRPV-i 1RC-0I-R RPVN-C-IR X No Recordable Indications.13-197 B-D B3.90 1RPV-l 1RC-OI-R RPVN-D X 2 Mid-waIl indications, acceptable per code.13-198 B-D 63.100 1RPV-l 1RC-OI-R RPVN-D-IR X No Recordable Indications.13-199 B-D B3.90 1RPV-I 1RC-OI-R - RPVN-E X No Recordable Indications.13-200 B-D 63.100 IRPV-1 1RC-0l-R RPVN-E-lR X No Recordable Indications.13-201 - B-D B3.90 IRPV-l 1RC-0i-R RPVN-F X 2 Mid-wall indications, acceptable per code.13-202 B-D B3.iOO 1RPV-I IRC-Oi-R RPVN-F-IR X No Recordable Indications.13-203 B-D B3.90 iRPV-1 1RC-Oi-R RPVN-G X No Recordable Indications.13-204 B-D B3.l00 iRPV-i 1RC-Oi-R RPVN-G-IR X No Recordable Indications.13-205 B-D B3.90 1RPV-l 1RC-0i-R - RPVN-H X No Recordable Indications.13-206 B-D B3.100 1RPV-i 1RC-0i-R RPVN-H-IR X No Recordable Indications i3-207 R-A2 Ri.15 iRPV-i iRC-Oi-R RPVS-A-Fi X No Recordable Indications.13-208 R-A2 Ri.i5 1RPV-i 1RC-Oi-R RPVS-B-Fi X No Recordable Indications.13-209 R-A2 Ri.15 iRPV-i iRC-Oi-R RPVS-C-Fi X No Recordable Indications.13-210 R-A2 Ri.i5 1RPV-i 1RC-Oi-R RPVS-D-Fi X No Recordable Indications.

i3-2ii R-A2 Ri.15 1RPV-i 1RC-Oi-R_____ RPVS-E-Fi X No Recordable Indications.13-212 R-A2 Ri.i5 IRPV-i 1 RC-Oi-R RPVS-F-Fi X No Recordable Indications.

i3-2i3 R-A 2 R1.I5 iRPV-i RC-Oi-R RPVS-G-Fi X No Recordable Indications.

i3-2i4 R-A2 RI.i5 1RPV-i i RC-Oi-R RPVS-H-Fi X No_Recordable_Indications.

Page 8 of 13

Exelon Byron Unit 1 Welds / Components B1R13 OUTAGE INSPECTION

SUMMARY

I SYSTEM: INTERVAL: PERIOD:

Reactor Pressure Vessel (RPV) Second Third J~T .~.i . -j, .. ~-i . i r.,.... ......i indicaton, acc

. per code.13-215 B-A Bi.ii 1RPV-i 1RC-Oi-R WR-i8 X 1 Mid-waIl indication, acceptable per code.13-216 B-A Bill 1RPV-l 1RC-Oi-R WR-29 X No Recordable Indications.13-217 B-A 61.11 1RPV-l 1RC-Oi-R WR-34 X 1 Mid-waIl indication, acceptable per code.13-219 B-A 61.21 IRPV-2 1RC-0i-R WR-i6 X NoRecordablekidications.

- B-G-i B6.i70 IRPV-3 1RC-Oi-R CETC NUTS X No Recordable Indications.

1-5 Baseline exam of replacement.

Page 9 of 13

Exelon Byron Unit 1 Welds / Components B1R13 OUTAGE INSPECTION

SUMMARY

SYSTEM: INTERVAL: PERIOD:

Residual Heat Removal (RH) Second Third

~

13-185 AUG TRACK 1RHX-i 1RH-02-AB RHXN-Oi X 5 Rounded Indications, acceptable per code.13-186 AUG TRACK 1RHX-i 1RH-02-AB RHXN-02 X No Recordable Indications.13-183 R-A4 Ri.20 1RH-03 1RHO3AA-8° COl X No Recordable Indications.13-181 R-A 4 RI .20 i RH-03 1 RHO3AA-8 C05 X No Recordable Indications.13-182 R-A 4 Ri.20 IRH-03 1RHO3AA-8 C06 X No Recordable Indications.13-184 R-A4 Rl.20 1RH-03 1RHO3AA-8 C07 X No Recordable Indications. I Page 10 of 13

Exelon Byron Unit 1 Welds I Components B1R13 OUTAGE INSPECTION

SUMMARY

SYSTEM: INTERVAL: PERIOD:

Q - ,ction (SI) Second Third

~l3-2~f R-A4 Ri.2j 3 iE~-~. C03 X l..~Jeometry~E.i° Intermittent.13-257 R-A4 Ri.20 1SI-38 1SIO8B-4 C06 X l.D. Geometry 360°Intermittent.

i3-068 R-A 5 Ri.ii iSl-20 1SIO8GC-1W W-OI_____ X No Recordable Indications.13-302 R-A5 Ri.ii iSl-20 1SIO8GC-iW W-02 X No Recordable Indications.13-303 R-A5 Ri.ii 1SI-20 1SIO8GC-1W W-03 X No Recordable Indications.13-304 R-A 5 Ri.ii iSl-20 1SIO8GC-iW W-04 X No Recordable Indications.13-305 R-A 5 R1.ii iSl-20 1SIO8GC-1W W-05 X No Recordable Indications.13-060 R-A5 Ri.ii ISI-19 ISIO8HA-2 W-0l - X No Recordable Indication~

13-061 R-A 5 Ri.il ISI-I9 1SIO8HA-2 W-02 X No Recordable_Indications.13-062 R-A5 Ri.iI iSl-19 ISIO8HA-2 W-03 X No Recordable Indications.13-296 R-A 5 Ri.ii iSI-i9 1SIO8HA-2 W-04 X No Recordable Indications.13-063 R-A 5 Ri.il iSI-i9 ISIO8JA-i% W-06 X No Recordable Indications.13-064 R-A 5 RI.ii 1SI-i9 1SIO8JA-i% W-07 X No Recordable Indications.13-065 R-A 5 Ri.ii 1SI-i9 1SIO8JA-1W W-08 X No Recordable Indications.13-066 R-A 5 Ri.ii ISI-i9 ISIO8JA-i% W-09 X No Recordable Indications.

R-A 5 - RI.Ii lSl-19 ISIO8JA-1W W-iO X No Recordable Indications.

R-A 5 Ri.il iSl-19 ISIO8JA-iW W-li X No Recordable Indications.

R-A 5 RI.Ii iSI-I9 ISIO8JA-1W W-12 X No Recordable Indications.

R-A 5 Rl.Ii 1SI-I9 1SIO8JA-iW W-13 X No Recordable Indications.

R-A5 Rl.ii iSI-I9 ISIO8JA-1W W-14 X No Recordable Indications.

R-A 5 RI.II iSl-19 ISIO8JA-l% W-15 X No Recordable Indications.

R-A 4 RI .20 1SI-36 1SIF9A-8 C03 X No Recordable Indications.

Page 11 of 13

Exelon Byron Unit 1 Welds / Components B1R13 OUTAGE INSPECTION

SUMMARY

i SYSTEM: INTERVAL: PERIOD:

Steam Generators_(SG) Second Third 1~_ I0~A~

i3-232 C-A Ci.20 1SG-05 1RC-Oi-BA SGW-08 X - No Recordable Indications.13-308 C-B C2.2i 1SG-06 1RC-Oi-BB N-3 X X No Recordable Indications.13-309 C-B C2.22 1SG-06 1RC-0l-BB N-3-NIR X No Recordable Indications.13-247 B-G-l B6.90 1SG-06 1RC-OI-BB SH-04 X MTd due to stuck elongation rod.

No Record. Ind. Other studs examined in B1R11.13-310 C-A Ci.l0 1SG-06 1RC-OI-BB SGW-06 X No Recordable Indications.13-234 B-G-i B6.iiO 1SG-07 1RC-0l-BC NC-UI thru 20 X No Recordable Indications.13-235 B-G-i B6.iiO 1SG-07 IRC-OI-BC NH-Ui_thru 20 X No Recordable Indications.13-236 B-G-i B6.90 iSG-07 1RC-Oi-BC SC-0i thru 20 X X No Recordable Indications. Studs 01, 07, i8 MTd due to stuck elongation rod.13-237 B-G-i B6.90 1SG-07 1RC-Oi-BC SH-0i thru 20 X No Recordable Indications.13-238 B-G-I B6.iOO 1SG-08 1RC-0i-BD FLG_SURF-CL X No Recordable Indications.13-239 B-G-i B6.i0O 1SG-08 1RC-OI-BD FLG_SURF-HL X No Recordable Indications.13-240 B-G-i B6.IIO 1SG-08 1RC-Oi-BD NC-Oi thru 20 X No Recordable Indications.13-241 B-G-i B6.iiO 1SG-08 1RC-0l-BD NH-UI thru 20 X No Recordable Indications.13-242 B-G-l B6.90 1SG-08 1RC-0l-BD SC-Ol thru 20 X X No Recordable Indications. Stud 04 MTd due to stuck elongation rod.13-243 B-G-1 B6.90 1SG-08 IRC-0l-BD SH-0I thru 20 X No Recordable Indications.

- B-G-i 86.90 1SG-06 1 RC-01-BC Replacements X NRI. Baseline of replacement studs 4,6,8,9,10,12, and 13.

Page 12 of 13

Exelon Byron Unit 1 Welds / Components OUTAGE INSPECTION

SUMMARY

B1R13 I SYSTEM:

Essential Service Water (SX)

INTERVAL:

Second PERIOD:

Third C3.20 iSX~04uiSX06BB~iJ C01A *No Recordable Indications.

~13-246 C-C X

  • 13-245 C C C3.20 1SX-10 1SXO7FA-16 C1iA X No Recordable Indications.

ii Page 13 of 13

Exelon Byron Unit 1 B1R13

~O8S# ~ ¶~

13-072 1 CSO2AB-l 0 C07 Ri .20 UT Adjacent gamma plug. I 95.0% - lBl Ri 3-UT-003 Pipe to elbow weld.13-308 1RC-0l-BB N-3 C2.21 UT ceobstructed by 94.6% - 81 RI 3-UT-024 Feedwater nozzle to shell weld.13-310 1 RC-01 -BB SGW-06 Cl. 10 UT Adjacent small instrument nozzles 99.5% - 81 Ri 3-UT-026 Transistion cone to upper steam drum circumferential weld.

restrict scanning from shell side.13-191 1RC-01-R }RPVN-A 83.90 UT Nozzle geometry. 91.1% See Note W-6 RPV outlet nozzle to shell weld @22° 1 below 13-193 1RC-01-R RPVN-B UT Nozzle geometry. 95.3% - W-10 RPV inlet nozzle to shell weld @67°13-195 1 RC-01 -R RPVN-C 83.90 UT Nozzle geometry. 95.3% - W-l I RPV inlet nozzle to shell weld @ 113°13-197 1RC-01-R RPVN-D UT Nozzle geometry. 91.1% See Note W-7 RPV outlet nozzle to shell weld @ 158° 1 below 13-199 1 RC-01 -R RPVN-E 83.90 UT Nozzle geometry. 91.1% See Note W-8 RPV outlet nozzle to shell weld @ 202° 1 below 13-201 1RC-01-R RPVN-F 83.90 UT Nozzle geometry. 95.3% - W-12 RPV inlet nozzle to shell weld @247°13-203 1RC-01-R RPVN-G 83.90 UT Nozzle geometry. 95.3% - W-13 RPV inlet nozzle to shell weld @293°13-205 1RC-01-R RPVN-F-I B3.90 UT Nozzle geometry. 91.1% See Note W-9 RPV outlet nozzle to shell weld @ 338° 1 below 13-218 1 RC-01-R WR-7 UT Scan obstructed by core barrel 99.6°h - W-1 Flange to Nozzle Belt (Upper Shell) keyways.13-216 1RC-01-R WR-29 Bill UT Scan obstructed by core support lugs. 86.2% See Note W-4 Lower Shell to Bottom Head Torus 2 below 13-219 1 RC-01-R WR-16 - B 1.21 ~5i~ obstructed by adjacent bottom 93.7% See Note W-5 Bottom Head Torus to Bottom Head Dome mounted instrumentation nozzles. 2 below 13-166 1 RY-Ol -S PC-05 B2.l1 UT Adjacent insulation pads restrict shell- 96.0% - 81 RI 3-UT-Ol 4 Shell to upper head circumferential weld.

side scanning surface.13-246 1SXO6BB-16 COlA C3.20 MT Inside surface of containment 100.0% 12R-22 B1R13-MT-00l Closure head penetration to pipe weld. Listed obtained penetration inaccessable. coverage for outside surface only.13-245 1SXO7FA-16 Cl IA C3.20 MT Inside surface of containment 100.0% l2R-22 B1R13-MT-002 Closure head penetration to pipe weld. Listed obtained penetration inaccossable, coverage for outside surface only.

.~

Note 1: Relief request l2R-02 was prepared and submitted at the beginning of the Second Inspection Interval. Granted per SER dated 12/30/98. The identified coverage for the examinations was based on the obtained coverage during the previous 10-year vessel examination in B1RO7. The identified coverage in 12R-02 was 81.0%. Changes in the examination techniques and equipment resulted in the increased coverage obtained in BI RI 3.

Note 2: Relief request l2R-0i was prepared and submitted at the beginning ofthe Second Inspection Interval. Granted per SER dated 12/30/98. The identified coverage for the examinations was based on the obtained coverage during the previous 10-year vessel examination in B1RO7. The identified coverage in I2R.0l was 57.0% for WR-29 and 81.0% for WR-16. Changes in the examination techniques and equipment resulted in the increased coverage obtained in 81 Ri 3.

Obstructed Examinations Page 1 of I

Exelon Byron Unit 1 Components / Examinations B1R13 OUTAGE INSPECTION

SUMMARY

I SYSTEM: INTERVAL: PERIOD:

Pressure Tests, All Systems I Second Third i~~* EXAMINATiON TYP~~W -

NUMBER ~ (NOTE~-~~ ~LEA~i~4 FUNCTIONAL 1 INSERV1CE ~ PNEUMATIC~~ NQTE~,

CLASS I COMPONENTS Bi5.iO Reactor Vessel Pressure Retaining Boundary IRCO1RJ X J I I I Bi5.20 Pressurizer Pressure Retaining Boundary 1RYO1SI X f I I I I Bi5.30 Steam Generator Pressure Retaining Boundary IRCOIBA X I 1RCO1BB X - I 1RCOIBC X 1 1RCOIBD X J I 815.50 Class 1 Piping Pressure Retaining Boundary Pipingi x I )_______ I 1,5 Bi5.60 Class 1 Pumps Pressure Retaining Boundary 1RCOIPA X I______

1RCOIPB X 1 1 1 RCO1 PC X I 1RCO1PD X 1 815.70 Class 1 Valves Pressure Retaining Boundary Valvesi X I I I 1,5 CLASS 2 COMPONENTS C2.33 Nozzle-to-Shell (or Head) When Inside of Vessel is Inaccessible Residual Heat Removal:

1RHO2AA RH-2-l X 1 RHO2AB RH-2-.2 X C7. 10 Pressure Vessels Pressure Retaining Compo nents Chemical & Volume Control:

1CVO2F CV-2-4 X 1 CVO2A CV-2-4 X _____

iCVOi FA CV-2-4 X 1CVO1FB CV-2-4 X 1CVO4AA CV-2-5 X 1cvo4ABçv-2-5 X Residual Heat Removal:

iRHO2AA RH-2-i X IRHU2AB RH-2-2 X C7.30 Piping, Pressure Retaining Boundary Auxiliary Feedwater:

AF-2-i X AF-2-2 X Containment Spray:

CS-2-i X CS-2-2 X CS-2-3 X CS-2-4 X

-~ CS-2-5 - -- X Page 1 of 4

Exelon Byron Unit 1 Components / Examinations B 1 Ri 3 OUTAGE INSPECTION

SUMMARY

SYSTEM: IINTERVAL: PERIOD:

Pressure Tests, All Systems I Second Third

~

CLASS 2 COMPONENTS C7.30 Piping, Pressure Retaining Boundary (contd)

Chemical & Volume Control:

CV-2-i X X

X 3 CV-2-4 X CV-2-5 X CV-2-7 X CV-2-iO X 4 Fuel Pool Cooling:

FC-2-i X Process Sampling:

-_______ x PS-2-2 x PS-2-3 X PS-2-4 X PS-2-5 X PS-2-6 Residual Heat Removal:

RH-2-1 X RH-2-2 X RH-2-3 X RH-2-6 X Reactor Coolant Pressurizer:

RY-2-i X Safety Injection:

Sl-2-1 X Sl-2-2 X SI-2-3 X S1-2-4 X S 1-2-6 X SI-2-7 X Page 2 of 4

Exelon Byron Unit 1 Components/Examinations B1R13 OUTAGE INSPECTION

SUMMARY

SYSTEM:

Pressure Tests, All Systems I INTERVAL:

Second PERIOD:

Third

~ ~

CLASS 2 COMPONENTS C7.50 Pumps, Pressure Retaining Boundary Containment Spray: I iCSO1PA_CS-2-i X 1CSO1PB_CS-2-2 X Chemical & Volume Control:

ICVO1PA CV-2-i X 1CVOIPB CV-2-2 . x 1CVO2PCV-2-3 X 3 Residual Heat Removal:

1RHO1PA RH-2-i x 1RHO1PB_RH-2-2 X Safety Injection:

1SIO1PA SI-2-i X 1SIO1PB_S1-2-2 X C7.70 Valves, Pressure Retaining Boundary Auxiliary Feedwater:

AF-2-i X AF-2-2 X Contaiment Spray:

CS-2-i X CS2-2 X Chemical and Volume Control:

CV-2-i CV-2-2 x CV-2-3 X 3 CV-2-4 x CV-2-5 x CV-2-7 X CV-2-iO x Fuel Pool Cooling:

FC-2-i x Process Sampling:

PS-2-i X PS-2-2 x X

PS-2-4 X PS-2-5 X PS-2-6 X Page 3 of 4

Exelon Byron Unit 1 Components / Examinations B 1 Ri 3 OUTAGE INSPECTION

SUMMARY

SYSTEM: INTERVAL: PERIOD:

CQD~iT~M f Pressure Tests, All Systems

~

I Second

~ ATiO+~P~

Third

~

NUMBER ~. ~NOTE2) L~AX ~ FUNCTIONAL I INSERVICE I PNEUMA~C I MOTE ~,

CLASS 2 COMPONENTS C7.70 Valves, Pressure Retaining Boundary (contd)

Residual Heat Removal:

X RH-2-2 X RH-2-3 X RH-2-6 X Reactor Coolant Pressurizer:

RY-2-1 X Safety Injection:

Sl-2-i X SI-2-2 X 5 1-2-3 X Sl-2-4 x S 1-2-6 X SI-2-7 X NOTE I The ASME Class 1 Pressure Boundary Leakage Test (VT-2) was performed on 2/27/05 and 3/23/05 to correspond to the pre- and post- refueling outage inspections.

NOTE 2 Refer to the System Pressure Test Summary for Subsystem Descriptions.

NOTE 3 The Inservice Inspection (VT-2) of CV-2-3 was performed with the exception of the Chemical Volume Control Positive Displacement Pump (1CVO2P) and its associated piping and valves between the suction and discharge manual isolation valves. This Class 2 pump has been indefinitely taken out of service per Byron On-Site reviews92-088 and 93-006.

NOTE 4 Pneumatic test is conducted normal operating pressure, and is not a hydro test.

NOTE 5 Boundary extended out to last isolation valve as part of end of interval testing requirements.

Page 4 of 4

Exelon Byron Unit 1 B1R13 Containment Structure OUTAGE INSPECTION

SUMMARY

  • SYSTEM: INTERVAL: PERIOD:

CODE ITEM CONTAINMENT STRUCTURE EXAMINATION ITEtIIA~EA rEXAM TYPE~ ~

Second Third El ii Accessible Surface Areas of VT Relief Request l2R 38 approved for use by NRC Disassembled Pentrations, Fuel current code used is ASME Section XI, 1998 Edition Transfer Canal, and Equipment Hatch (MC Components), 100% of accessible surfaces examined.

L2.30 Anchorage Hardware VT Two protruding wires in shop end anchor head for V47 L2.40 Protection Meduim - Gease Leakage at various vertical tendons

~ At Top: V85 At Bottom: Vi9, V21, V22, V24, V26, V28, V30, V33, V34, V37, V40, V45, V48, V49, V5i, V53, V56 V64, V66, V67, V70, V73, V74, V77 -V79, V81 V87, V89 V9i, V94 V98, Vl00, V103, V106 Vi08, V113, Vii6, V120, Vi22 Vi25, V127 VI3O, V132, Vl33, Vi36, V137, VI39, Vi4i, Vi42, VI47, V149, VlSI, Vi55, and VI56 L2.40 Protection Meduim - Replacement grease volume at V-47 tendon exceeds 10%

Page 1 of I

EI~n~

Byron Station Unit I Byron Station Outage BIRI3 Snubber Outage Summary (Page 1 of 4)

SYSTEM: Chemical & Volume Control System (CV~

Section xl isi identifier Line Number I EPN Exam Results Comments Cat. Comments Summary F-A 1 CVO8O1 iS 1 CVO5CB-6/l CVO8O1 15 VT-3 NRI F.TEST PASS F-A 1CVO8OI3S 1 CVO5CB-6/1 CVO8O1 3S VT-3 NRI

.F.TEST PASS F-A 1 CV08027S 1CV98C-8/1CVO8O27S VT-3 NRI F.TEST PASS Note: Relief Request l2-Rl3, applies to all Technical Requirement Manual Snubbers Note: Section Xl Category numbers N/A-ed are exempt from IWF-1220 and IWF-2500 tables

  • Byron ExekitStation Unit I Byron Station Outage BIRI3 Snubber Outage Summary (Page 2 of 4)

SYSTEM: Reactor Coolant System (RC)

L Section Xl Cat.

F-A ISi identifier Comments 1CV11O23S Line Number / EPN 1RC14AA-2/1CV11O23S I Exam Summary

\JT-3 Results NRI Comments I

F.TEST PASS F-A 1CV24026S 1RC16AB-2/1CV24026S VT-3 NRI F.TEST PASS F-A 1RCO6S 1RCO1BA-1N1RCO6S VT-3 NRI F.TEST PASS F-A 1RCO7S 1RCO1BA-1N1RCO7S - VT-3 NRI VT-3 NRI F-A 1RCO8S 1RcO1BB-1B/1RCO8S VT-3 NRI VT-3 NRI F-A 1RCO9S - 1RCO1BB-1B/1RCO9S VT-3 NRI VT-3 NRI F-A -- 1RC1OS 1RCO1BC-iC/1RCIOS VT-3 - NRI VT-3 NRI F-A 1RCIIS 1RcOIBC-IC/1RC11S VT-3 NRI VT-3 NRI F-A 1RC12S 1RCO1BD-1D/1RCI2S - VT-3 NRI - ____-~

VT-3 NRI F-A 1RC13S 1RCOIBD-ID/1RC13S VT-3 - NRI ________________

VT-3 NRI NA 1 RC1 7025S 1 RCO8AB-3/4/1 RC1 7025S VT-3 NRI F.TEST PASS F-A 1RC18O1OS 1RC22AC-l.5/1RC18O1OS VT-3 NRI F.TEST PASS NA 1RC19O24S 1RC2OAD-3/4/1RC19O24S VT-3 NRI F.TEST PASS F-A 1RYO6O15S 1RC24AA-4/1RYO6O15S VT-3 NRI F.TEST PASS Note: Relief Request l2-R13, applies to all Technical Requirement Manual Snubbers Note: Section XI Category numbers N/A-ed are exempt from IWF-1220 and IWF-2500 tables

Exekn~

Byron Station Unit I Byron Station Outage BIRI3 Snubber Outage Summary (Page 3 of 4)

SYSTEM: Reactor Coolant System (RY)

Section Xi iSi identifier Line Numbe r I EPN Exam Results Comments Cat. Comments Summary F-A 1 RY06076S 1 RYO1 8-6/1RY06076S VT-3 NRI F.TEST PASS F-A 1RYO6121S 1RYO1AA-4/IRYO6121S VT-3 NRI

  • F.TEST PASS Note: Relief Request 12-R13, applies to all Technical Requirement Manual Snubbers Note: Section Xl Category numbers N/A-ed are exempt from IWF-1220 and IWF-2500 tables

Exeknt Byron Station Unit I Byron Station Outage BIRI3 Snubber Outage Summary (Page 4 of 4)

SYSTEM: Safety Injection System (SI)

J Section Xl lsi Identifier Line Numb en EPN Exam Results Comments f Cat. Comments Summary F-A 1S1O9024S 1 SIO9BC-lO/1S109O24S F.TEST NRI F.TEST PASS NA 1S116037S 1 SI18ED-2/1S116037S VT-3 NRI F.TEST PASS Note: Relief Request l2-R13, applies to all Technical Requirement Manual Snubbers Note: Section XI Category numbers N/A-ed are exempt from IWF-1220 and IWF-2500 tables

Byron Station Unit I BIRI3 ISI Outage Summary Report Support Outage Summary (Page 1 of 9)

SYSTEM: Containment Spray System (CS)

Section Xl iSI identifier Line Number! EPN Exam Results Comments Cat. Item Comments Summary F-A F1.20 1CSO3007X 1 CSO2AA-10/1 CSO3007X - VT-3 NRI F-A F1.20 1C503008X 1 CSO2AA-i 0/1CSO3008X VT-3 NRI Minor rust on weld (rear bracket to wide flange). No sign of degradation.

F-A Fl.20 1CSO3O13R 1 CSO2AA-i 0/i CSO3OI 3R VT-3 NRI Component Supports examined in accordance with Code Case N-491-1

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Byron Station Unit I BIRI3 ISl Outage Summary Report Support Outage Summary (Page 2 of 9)

SYSTEM: Chemical & Volume Control System (CV)

Section Xi Cat. item F-A Fl .20 ISI identifier Comments 1 CVO1 005X Line Number / EPN 1 CVO8BA-4/i CVO1 005X Exam Summary VT-3 Results NRI Comments Remote examination performed on top I

(Structural attachment) portion of support uSing pole camera.

F-A Fi.2O1CVO1II4X 1CVO9A-4/1CVO1114X

  • VT-3 NRI F-A Fib 1CVO2O1OX 1CV1ODB-3/1CVO2O1OX VT-3 NRI Insulation removed for examination.

F-A Fl.10 1CV22005X 1 CV45B-2/l CV22005X VT-3 NRI F-A Fib 1CV22016X 1 CV45B-2/l CV22016X VT-3 NRI F-A Fib 1CV16O36X 1 CVA3B-2/i Cvi 6036X VT-3 NR1 Insulation removed from pipe clamp for examination.

F-A Fi.bO 1CV16O4OX 1 cVA3B-21i Cvi 6040X VT-3 NRI Insulation removed from pipe clamp for examination.

F-A F1.i0 1CV16O41X 1CVA3B-2/1CVI6O41X VT-3 NR1 Insulation removed from pipe attachment for examination.

F-A Ella 1CV15O31X 1CVA5AA-2/1CV15O31X VT-3 NRI Component Supports examined in accordance with Code Case N-491-l

  • Exek~n~

Byron Station Unit I BIRI3 ISI Outage Summary Report Support Outage Summary (Page 3 of 9)

SYSTEM: Feedwater System (FW)

Section Xl ISI Identifier Line Number! EPN Exam Results Comments Cat. item Comments Summary F-A Fi.20 IFWO4O16X 1FWO3DC-l6/1FWO4O16X VT-3 NRI Replaces 1EWO2O2OX due to interference with Steam Generator Work F-A Fi.20 1PC-76A 1FWO3DD-i6/1PC-76A - VT-3 NRI F-A Fi.20 1AF04069R 1FW81BB-6/iAFO4O69R VT-3 NRI _____ -

F-A El.20 1AE04074R 1FW81BB-6/1AF04074R VT-3 NRI F-A Fl.20 1AFO4O81G 1FW81BB-6/1AFO4O81G VT-3 NRI Component Supports examined in accordance with Code Case N-49l-b

  • *xk~n~~

Byron Station Unit I BIRI3 ISI Outage Summary Report Support Outage Summary (Page 4 of 9)

SYSTEM: Main Steam System (MS)

Section Xi ISi identifier Line Numbe r I EPN Exam Results Comments Cat. Item Comments Summary F-A Fi.20 iMSO12O6R 1MSO7AA-28/1MSOI2O6R VT-3 NRI Insulation pulled back for examination of component suport pipe clamp.

Component Supports examined in accordance with Code Case N-491-1

Exeknt Byron Station Unit I BIRI3 ISI Outage Summary Report Support Outage Summary (Page 5 of 9)

SYSTEM: Reactor Coolant System (RC)

Sec tion XI ISi Identifier Line Number! EPN Exam Results Comments Cat. item Comments Summary F-A Fl.40 S 1RC-Oi-R/S VT-3 NRI F-A Fi .10 1 CV12002X 1 RCi6AA-2/b cvi 2002X VT-3 NRI Insulation removed for examination.

F-A Fb.l0 1RC16002X 1RC22AA-i-i/2/iRC16002X VT-3 NRI Insulation removed for examination.

Component Supports examined in accordance with Code Case N-491-b

  • E,ek~n~

Byron Station Unit I BIRI3 ISI Outage Summary Report Support Outage Summary (Page 6 of 9)

SYSTEM: Residual Heat Removal System (RH)

Section Xl ISI identifier Line Number! EPN Exam Results Comments Cat. Item Comments Summary F-A Fib 1RH02049X iRHO1AA-i2/1RHO2O49X vT-3 NRI Insulation removed for examination.

Component Supports examined in accordance with Code Case N-49i-l

Exekn~

Byron Station Unit I BIRI3 ISI Outage Summary Report Support Outage Summary (Page 7 of 9)

SYSTEM: Reactor Coolant System (RY)

Section Xl ISi Identifier Line Number! EPN Exam Results Comments Cat. item Comments Summary F-A Fb.iO 1RYO611OX 1RYO1B-6/iRYO6ibOX vT-3 NRI Insulation removed from clamp for examination.

F-A Fb.40 L2 1 RY-Oi-S/L2 VT-3 NRI Insulation removed for examination.

F-A

  • F1.40 L4 1 RY-Oi -S!L4 JT-3 NRI Examination performed remotely.

Component Supports examined in accordance with Code Case N-491-i

  • Exekn~.

Byron Station Unit I BIRI3 ISI Outage Summary Report Support Outage Summary (Page 8 of 9)

SYSTEM: Essential Service Water System (SX)

Section Xl ISI identifier Line Number! EPN Exam Results Comments Cat. Item Comments Summary F-A Fl.20 iSXO600iX 1SXO6BA-i6/1SXO6001X \/T-3 NRI F-A Fi.20 1SXO6007X 1SXO6CA-i4/iSXO6007X vT-3 NRI F-A Fb.20 1SXO6008X 1SXO6CA-i4/1SXO6008X

  • VT-3 NRI F-A Fb.20 1SX06022X 1SXO6DC-iO/1SXO6O22X VT-3 NRI Component Supports examined in accordance with Code Case N-491-1
  • Exeknt Byron Station Unit I BIRI3 ISI Outage Summary Report Support Outage Summary (Page 9 of 9)

SYSTEM: Primary Containment Purae System (VQ)

[ Section XI IS1 Identifier Line Number! EPN Exam Results Comments Cat. item Comments Summary

~

F-A F1.20 iVQO300iX ivQo5A-8/bvQo300iX VT-3 NRI Component Supports examined in accordance with Code Case N-491-b

B1R13 FORM NIS-1 OWNERS REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules I. Owner: Exelon Generation Company (EGC, LLC) 4300 Winfield Road Warrenville, IL 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: One (1) 4. Owner Certificate of Authorization: N/A
5. Comercial Service Date: 09/16/85 6. National Board Number of Unit: N-I98
7. Components Inspected: Containment Spray System Piping Welds & Components (CS)

Component or 1 Manufacturer or Manufacturer or 1 State or Province National Board Appurtenance J Installer Installer Serial No. I Number Number Cat. 4/Rl .20 Hunter Corporation l-CS-5-N5 Not Applicable Not Applicable 1CSO1AA-16 Cat. 4/RI .20 l-CS-5-N5 Hunter Corporation Not Applicable Not Applicable I CSO1AB-l6 Cat. 4/Rl .20 Hunter Corporation l-CS-5-N5 Not Applicable Not Applicable 1CSO2AB-l 0 Computer Generated Form Page 1 of 20

B1R13 FORM NIS-1 OWNERS REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules I. Owner: Exelon Generation Company (EGC, LLC) 4300 Winfield Road Warrenville, IL 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: One (1) 4. Owner Certificate of Authorization: N/A
5. Comercial Service Date: 09/16/85 6. National Board Number of Unit: N-I 98
7. Components Inspected: Chemical & Volume Control System Piping Welds & Components (CV) or 1 Manufacturer or Manufacturer or 1 State or Province 1 National Board Appurtenance J installer Installer Serial No. J Number J Number

.11 Hunter Corporation 1-CV-1-N5 Not Applicable Not Applicable CVA3AA-2

.11 Hunter Corporation l-CV-l-N5 Not Applicable Not Applicable CVA3B-2

.11 Hunter Corporation I-CV-l-N5 Not Applicable Not Applicable CVA5AA-2 Hunter Corporation I-CV-l-N5 Not Applicable Not Applicable CVA6AA-2 11 Hunter Corporation 1-CV-l-N5

  • Not Applicable Not Applicable CVA7AA-2 Computer Generated Form Page 2 of 20

B1R13 FORM NIS-1 OWNERS REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules I. Owner: Exelon Generation Company (EGC, LLC) 4300 Winfield Road Warrenville, IL 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: One (1) 4. Owner Certificate of Authorization: N/A
5. Comercial Service Date: 09/16/85 6. National Board Number of Unit: N-198
7. Components Inspected: Feedwater System Piping Welds & Components (FW)

Component or Manufacturer or Manufacturer or State or Province National Board Appurtenance Installer Installer Serial No. Number Number Cat. 1/Ri.1i-R1.18 Hunter Corporation 1-FW-1-N5 Not Applicable Not Applicable Cat. 1/R1.11-R1.18 W.A. Pope Corp. 1-FW-I-N5 Not Applicable Not Applicable 1 FWO3DB-1 6 Cat. 1/RI .11-RI .18 Hunter Corporation 1-FW-1-N5 Not Applicable Not Applicable I FWO3DC-I 6 Cat. 1/RI .11-RI .18 Hunter Corporation l-FW-I-N5 Not Applicable Not Applicable 1 FWO3DD-l6 Cat. 1/RI .11-RI.18 W.A. Pope Corp. I-FW-I-N5 Not Applicable Not Applicable 1 FWO3DD-16 Cat. 1/Ri .11-RI .18 W.A. Pope Corp. 1-FW-1-N5 Not Applicable Not Applicable 1 FW87CB-6 Cat. I/Ri .11-Ri .18 W.A. Pope Corp. 1-FW-1-N5 Not Applicable Not Applicable 1 FW87CC-6 Computer Generated Form Page 3 of 20

B1R13 FORM NIS.~1OWNERS REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules I. Owner: Exelon Generation Company (EGC, LLC) 4300 Winfield Road Warrenville, IL 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: One (1) 4. Owner Certificate of Authorization: N/A
5. Comercial Service Date: 09/16/85 6. National Board Number of Unit: N-198
7. Components Inspected: Reactor Coolant System Piping Welds & Components (RC)

Appurtenance or 1 Manufacturer or installer Manufacturer or Installer 5eriaI No.

J State or Province Number

} National Board Number

.20 Hunter Corporation 1-RC-1-N5 Not Applicable Not Applicable RC 1 3AA-2

.20 1-RC-1-N5 Hunter Corporation Not Applicable Not Applicable RCI3AB-2

.20 Hunter Corporation I-RC-I-N5 Not Applicable Not Applicable RC 13AC-2

.20 Hunter Corporation 1-RC-1-N5 Not Applicable Not Applicable RC 1 3AD-2 Hunter Corporation i-RC-l-N5 Not Applicable Not Applicable RC14AA-2 Hunter Corporation 1-RC-l-N5 Not Applicable Not Applicable RC I4AB-2

.11 Hunter Corporation l-RC-1-N5 Not Applicable Not Applicable RC 1 4AC-2

.11 Hunter Corporation 1-RC-1-N5 Not Applicable Not Applicable RC I4AD-2 Hunter Corporation l-RC-1-N5 Not Applicable Not Applicable RC16AA-2 Hunter Corporation 1-RC-1-N5 Not Applicable Not Applicable RC1 6AA-2 Hunter Corporation 1-RC-1-N5 Not Applicable Not Applicable RC 1 6AB-2

.20 Hunter Corporation 1-RC-1-N5 Not Applicable Not Applicable RC22AA-i %

.20 Hunter Corporation 1-RC-1-N5 Not Applicable Not Applicable RC24AB-4 Computer Generated Form Page 4 of 20

B1R13 FORM NIS-1 OWNERS REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules I. Owner: Exelon Generation Company (EGC, LLC) 4300 Winfield Road Warrenville, IL 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: One (1) 4. Owner Certificate of Authorization: N/A
5. Comercial Service Date: 09/16/85 6. National Board Number of Unit: N-198
7. Components Inspected: Residual Heat Removal Heat System Piping Welds & Components (RH)

Component or Manufacturer or Manufacturer or State or Province National Board Appurtenance Installer Installer Serial No. Number Number Cat.4 / Ri .20 . . .

1-RH-2-N5 Not Applicable Not Applicable 1 RHO3AA8 Hunter Corporation Computer Generated Form Page 5 of 20

B1R13 FORM NIS-1 OWNERS REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules

1. Owner: Exelon Generation Company (EGC, LLC) 4300 Winfield Road Warrenville, IL 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: One (1) 4. Owner Certificate of Authorization: N/A
5. Comercial Service Date: 09/16/85 6. National Board Number of Unit: N-198
7. Components Inspected: Residual Heat Removal Heat Exchanger (RHX)

I Component or Manufacturer or Manufacturer or 1 State or Province I National Board Appurtenance Installer Installer Serial No. J Number J Number C2.32 Joseph Oat 2267-lB U122327 837 1 RH-02-AB Corporation Computer Generated Form Page 6 of 20

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