ML080180437

Thirteenth Refueling Outage Steam Generator Inservice Inspection Summary Report

ML080180437
Person / Time
Site:	Braidwood
Issue date:	01/18/2008
From:	Coutu T Exelon Corp, Exelon Generation Co, Exelon Nuclear
To:	Office of Nuclear Reactor Regulation
References
BW080003
Download: ML080180437 (74)

Text

January 18, 2008 BW080003 U.S.Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C.20555-0001 Braidwood Station, Unit 1 Facility Operating License No, NPF 72 NRC Docket No.STN 50-456

Subject:

Braidwood Station, Unit 1 Thirteenth Refueling Outage Steam Generator!nservice Inspection Summary Report In accordance with Technical Specification 5.6.9,"Steam Generator (SG)Tube Insoection Report"Exelon Generation Company, LLC is reporting the results of the SG inspections, which were completed during the Braidwood Station, Unit 1 thirteenth refueling outage (Al Ri 3).The attached report is also being submitted in accordance with the requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, 1989 Edition, Section Xl,"Rules for Inservice Inspection of Nuclear Power Plant Components,"

Article IWA-6000,"Records and Reports,"and Article lV-7000,"Report of Examination,"

of Mandatory Appendix IV,"Eddy Current Examination of Non-Ferromagnetic Steam Generator Heat Exchanger Tubing."If there are any questions regarding this submittal, please contact Mr.David Gullott, Regulatory Assurance Manager, at (815)417-2800.Respectfully, Thomas Coutu Site Vice President Braidwood Station

Attachment:

Exelon Braidwood Station Unit 1 Thirteenth Refueling Outage Steam Generator lnservice Inspection Summary Report Exelon Nuclear BRAIDWOOD STATION UNIT 1 35100 South Rte.53, Suite 84 Braceville, IL 60407 COMMERCIAL OPERATION:

July 29, 1988 STEAM GENERATOR EDDY CURRENT INSPECTION REPORT THIRTEENTH REFUELING OUTAGE (A1R13)October 2007 Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555 Document Completion Date: January 11, 2008 TABLE OF CONTENTS

1.0 INTRODUCTION

2.0

SUMMARY

3.0 CERTIFICATIONS 3.1 Procedures/Examinations/Equipment 3.2 Personnel 4.0 EXAMINATION TECHNIQUES AND EXAMINATION SCOPE 4.1 Examination Techniques 4.2 Steam Generator Inspection Scope 4.3 Recording of Examination Data 4.4 Witness and Verification of Examination 5.0 EXAMINATION RESULTS 5.1 Eddy Current Inspection 5.2 Other Inspection Results 6.0 RESULTS OF CONDITION MONITORING 6.1 Fan BarWear 6.2 Lattice Grid Wear 6.3 Foreign Object Wear 7.0 REPAIR

SUMMARY

8.0 DOCUMENTATION 9.0 FIGURES/TABLES/ATTACHMENTS January 18, 2008 BW080003 U.S.Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C.20555-0001 Braidwood Station, Unit 1 Facility Operating License No, NPF 72 NRC Docket No.STN 50-456

Subject:

Braidwood Station, Unit 1 Thirteenth Refueling Outage Steam Generator!nservice Inspection Summary Report In accordance with Technical Specification 5.6.9,"Steam Generator (SG)Tube Insoection Report"Exelon Generation Company, LLC is reporting the results of the SG inspections, which were completed during the Braidwood Station, Unit 1 thirteenth refueling outage (Al Ri 3).The attached report is also being submitted in accordance with the requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, 1989 Edition, Section Xl,"Rules for Inservice Inspection of Nuclear Power Plant Components,"

Article IWA-6000,"Records and Reports,"and Article lV-7000,"Report of Examination,"

of Mandatory Appendix IV,"Eddy Current Examination of Non-Ferromagnetic Steam Generator Heat Exchanger Tubing."If there are any questions regarding this submittal, please contact Mr.David Gullott, Regulatory Assurance Manager, at (815)417-2800.Respectfully, Thomas Coutu Site Vice President Braidwood Station

Attachment:

Exelon Braidwood Station Unit 1 Thirteenth Refueling Outage Steam Generator lnservice Inspection Summary Report Exelon Nuclear BRAIDWOOD STATION UNIT 1 35100 South Rte.53, Suite 84 Braceville, IL 60407 COMMERCIAL OPERATION:

July 29, 1988 STEAM GENERATOR EDDY CURRENT INSPECTION REPORT THIRTEENTH REFUELING OUTAGE (A1R13)October 2007 Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555 Document Completion Date: January 11, 2008 TABLE OF CONTENTS

1.0 INTRODUCTION

2.0

SUMMARY

3.0 CERTIFICATIONS 3.1 Procedures/Examinations/Equipment 3.2 Personnel 4.0 EXAMINATION TECHNIQUES AND EXAMINATION SCOPE 4.1 Examination Techniques 4.2 Steam Generator Inspection Scope 4.3 Recording of Examination Data 4.4 Witness and Verification of Examination 5.0 EXAMINATION RESULTS 5.1 Eddy Current Inspection 5.2 Other Inspection Results 6.0 RESULTS OF CONDITION MONITORING 6.1 Fan BarWear 6.2 Lattice Grid Wear 6.3 Foreign Object Wear 7.0 REPAIR

SUMMARY

8.0 DOCUMENTATION 9.0 FIGURES/TABLES/ATTACHMENTS