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| {{#Wiki_filter:January 27, 2006Mr. Christopher M. Crane, President and Chief Nuclear Officer Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555 | | {{#Wiki_filter:January 27, 2006 Mr. Christopher M. Crane, President and Chief Nuclear Officer Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| BRAIDWOOD STATION, UNIT 1 - EVALUATION OF STEAM GENERATORINSERVICE INSPECTION | | BRAIDWOOD STATION, UNIT 1 - EVALUATION OF STEAM GENERATOR INSERVICE INSPECTION |
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| ==SUMMARY== | | ==SUMMARY== |
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| ==Dear Mr. Crane:== | | ==Dear Mr. Crane:== |
| By letters to the Nuclear Regulatory Commission (NRC) dated October 29, 2004 andJanuary 20, 2005, Exelon Generation Company, LLC (the licensee), submitted information pertaining to the steam generator tube inspection summary reports for the fall 2004 outage at the Braidwood Station, Unit 1 (Braidwood), in accordance with the plant's technical specifications (TSs).The NRC staff has completed its review of these reports and concludes that the licenseeprovided the information required by the Braidwood TSs and that no additional follow-up is required at this time.Sincerely,/RA/Mahesh L. Chawla, Project ManagerPlant Licensing Branch III-2 Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket No. STN 50-456 | | |
| | By letters to the Nuclear Regulatory Commission (NRC) dated October 29, 2004 and January 20, 2005, Exelon Generation Company, LLC (the licensee), submitted information pertaining to the steam generator tube inspection summary reports for the fall 2004 outage at the Braidwood Station, Unit 1 (Braidwood), in accordance with the plants technical specifications (TSs). |
| | The NRC staff has completed its review of these reports and concludes that the licensee provided the information required by the Braidwood TSs and that no additional follow-up is required at this time. |
| | Sincerely, |
| | /RA/ |
| | Mahesh L. Chawla, Project Manager Plant Licensing Branch III-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. STN 50-456 |
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| ==Enclosure:== | | ==Enclosure:== |
| Evaluation of SG Inspection Reportscc w/encl: See next page Mr. Christopher M. Crane, PresidentJanuary 27, 2006 and Chief Nuclear Officer Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555 | | |
| | Evaluation of SG Inspection Reports cc w/encl: See next page |
| | |
| | Mr. Christopher M. Crane, President January 27, 2006 and Chief Nuclear Officer Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| BRAIDWOOD STATION, UNIT 1 - EVALUATION OF STEAM GENERATORINSERVICE INSPECTION | | BRAIDWOOD STATION, UNIT 1 - EVALUATION OF STEAM GENERATOR INSERVICE INSPECTION |
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| ==SUMMARY== | | ==SUMMARY== |
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| ==Dear Mr. Crane:== | | ==Dear Mr. Crane:== |
| By letters to the Nuclear Regulatory Commission (NRC) dated October 29, 2004 andJanuary 20, 2005, Exelon Generation Company, LLC (the licensee), submitted information pertaining to the steam generator tube inspection summary reports for the fall 2004 outage at the Braidwood Station, Unit 1 (Braidwood), in accordance with the plant's technical specifications (TSs).The NRC staff has completed its review of these reports and concludes that the licenseeprovided the information required by the Braidwood TSs and that no additional follow-up is required at this time.Sincerely,/RA/Mahesh L. Chawla, Project ManagerPlant Licensing Branch III-2 Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket No. STN 50-456 | | |
| | By letters to the Nuclear Regulatory Commission (NRC) dated October 29, 2004 and January 20, 2005, Exelon Generation Company, LLC (the licensee), submitted information pertaining to the steam generator tube inspection summary reports for the fall 2004 outage at the Braidwood Station, Unit 1 (Braidwood), in accordance with the plants technical specifications (TSs). |
| | The NRC staff has completed its review of these reports and concludes that the licensee provided the information required by the Braidwood TSs and that no additional follow-up is required at this time. |
| | Sincerely, |
| | /RA/ |
| | Mahesh L. Chawla, Project Manager Plant Licensing Branch III-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. STN 50-456 |
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| ==Enclosure:== | | ==Enclosure:== |
| Evaluation of SG Inspection Reportscc w/encl: See next pageDISTRIBUTION | | |
| :PUBLICLPLIII/2 r/fRidsNrrPMMChawlaMMurphy RidsOGCRpDHills, RIIIKKarwoskiRidsNrrDlrRIra RidsNrrDorlLplfRidsAcrsAcnwMailCenterYDiazRidsNrrDciCsgb RidsNrrLADClarkeRSkokowski, RIIIADAMS Accession Number: ML053490064OFFICEPM:LPL3-2LA:LPL3-2BC:CSGB(A)BC:LPLIII-2NAMEMChawla:mwDClarkeAHiserM LandauDATE1/26/061/26/061/27/061/27/06OFFICIAL RECORD COPY EnclosureOFFICE OF NUCLEAR REACTOR REGULATIONEVALUATION OF STEAM GENERATOR INSPECTION REPORTSFROM 2004 REFUELING OUTAGEBRAIDWOOD STATION, UNIT 1DOCKET NO. STN 50-456INTRODUCTIONBy letters to the Nuclear Regulatory Commission (NRC) dated October 29, 2004 (AgencywideDocuments Access and Management System Accession No. ML043090549) and January 20, 2005 (ADAMS Accession No. ML050280208), Exelon Generation Company, LLC (the licensee),
| | Evaluation of SG Inspection Reports cc w/encl: See next page DISTRIBUTION: |
| submitted information pertaining to the steam generator (SG) tube inspection summary reports for the fall 2004 outage at the Braidwood Station, Unit 1 (Braidwood) in accordance with theplant's technical specifications. In addition, the NRC staff summarized some of the inspectionresults in a letter dated December 21, 2004 (ADAMS Accession No. ML043240231).BACKGROUNDThe four SGs at Braidwood were replaced in 1998 with the SGs fabricated by Babcock andWilcox International. Each SG contains 6633 thermally treated Alloy 690 tubes. Each tube hasa nominal outside diameter of 0.6875-inch and a nominal wall thickness of 0.040-inch. The tubes were hydraulically expanded at both ends for the full length of the tubesheet and aresupported by a number of stainless steel tube supports (lattice grid). The tubes installed in rows 1 through 21 were thermally stress relieved after bending. RESULTS OF FALL 2004 INSPECTIONThe licensee provided the scope, extent, methods and results of their SG tube inspections inthe documents referenced above. In addition, the licensee described corrective actions (i.e., | | PUBLIC LPLIII/2 r/f RidsNrrPMMChawla MMurphy RidsOGCRp DHills, RIII KKarwoski RidsNrrDlrRIra RidsNrrDorlLplf RidsAcrsAcnwMailCenter YDiaz RidsNrrDciCsgb RidsNrrLADClarke RSkokowski, RIII ADAMS Accession Number: ML053490064 OFFICE PM:LPL3-2 LA:LPL3-2 BC:CSGB (A)BC:LPLIII-2 NAME MChawla:mw DClarke AHiser MLandau DATE 1/26/06 1/26/06 1/27/06 1/27/06 OFFICIAL RECORD COPY |
| tube plugging) taken in response to the inspection findings.The licensee included information regarding the examination and evaluation procedures usedduring the SG eddy current inspection which included two independent analyses of the eddy current data, using automat ed data screening analysis systems. As a result of the SG tube inspections, the licensee identified five tubes with indications ofsecondary side foreign object wear at the lattice grid elevations in SGs B, C and D. All of these tubes were plugged. In a conference call with the licensee, it was indicated that the foreignobjects causing the wear could be spiral wound gasket material. During this inspection, the licensee continued to monitor the potential for tubes to be in closeproximity as part of the 100-percent full length bobbin coil inspection in SG B. The licensee did not identify any tube degradation associated with the tubes being in close proximity. Thelicensee stated that this condition will be monitored in all four SGs during the next refueling outage.In its report dated July 29, 2003 (ADAMS Accession No. ML032190155), the licensee indicatedthat the tube in row 70 column 41 in SG D had a 6-percent through-wall indication which was attributed to wear at the lattice grid. In its report dated January 20, 2005 (ADAMS Accession No. ML050280208), the licensee indicated that the indication was 25-percent through-wall. In an NRC summary dated December 21, 2004, the NRC staff indicated that the indication inR70C41 (actually, the NRC staff incorrectly identified the tube as R70C2 in the summary)measured 25-percent through-wall and was attributed to wear from a foreign object and that there was no change in the signal between 2003 and 2004 SG tube inspections. In a conference call on August 4, 2005, the licensee clarified that originally (in 2003) the indicationswas classified as lattice grid wear, but based on the overall 2004 inspection results, they reviewed the 2003 indication at this location and concluded that this indication was a result of wear from a foreign object. The licensee also clarified that there was no growth in the indication rather the apparent change in depth (from 6 percent to 25 percent) was a result of using a different sizing method (i.e., instead of sizing the indication with a technique for lattice grid wear, the indication was sized with a foreign object wear sizing technique). The wear scar was at the bottom edge of the tube support slightly adjacent to the tube-to-lattice gridintersection.CONCLUSIONS AND FUTURE INSPECTION PLANSBased on a review of the information provided, the NRC staff concludes that the licenseeprovided the information required by Braidwood TSs. In addition, the NRC staff concludes thatthere are no technical issues that warrant follow-up action at this time since the inspections appear to be consistent with the objective of detecting potential tube degradation and theinspection results appear to be consistent with industry operating experience at similarly designed and operated units.Principle Contributor: Y. DiazDate: January 26, 2006 Braidwood Station Units 1 and 2 cc: | | |
| Regional Administrator, Region IIIU.S. Nuclear Regulatory Commission 801 Warrenville RoadLisle, IL 60532-4351Document Control Desk - LicensingExelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555Mr. Dwain W. Alexander, Project ManagerWestinghouse Electric Corporation Energy Systems Business Unit Post Office Box 355 Pittsburgh, PA 15230Joseph GalloGallo & Ross 1025 Connecticut Ave., NW, Suite 1014 Washington, DC 20036Ms. Bridget Little RoremAppleseed Coordinator 117 N. Linden Street Essex, IL 60935Howard A. LearnerEnvironmental Law and Policy Center of the Midwest 35 East Wacker Dr., Suite 1300 Chicago, IL 60601-2110U.S. Nuclear Regulatory CommissionBraidwood Resident Inspectors Office 35100 S. Rt. 53, Suite 79 Braceville, IL 60407Ms. Lorraine CreekRR 1, Box 182 Manteno, IL 60950Illinois Emergency Management Agency Division of Disaster Assistance & | | OFFICE OF NUCLEAR REACTOR REGULATION EVALUATION OF STEAM GENERATOR INSPECTION REPORTS FROM 2004 REFUELING OUTAGE BRAIDWOOD STATION, UNIT 1 DOCKET NO. STN 50-456 INTRODUCTION By letters to the Nuclear Regulatory Commission (NRC) dated October 29, 2004 (Agencywide Documents Access and Management System Accession No. ML043090549) and January 20, 2005 (ADAMS Accession No. ML050280208), Exelon Generation Company, LLC (the licensee), |
| Preparedness 110 East Adams Street Springfield, IL 62701-1109County Executive Will County Office Building 302 N. Chicago Street Joliet, IL 60432Attorney General500 S. Second Street Springfield, IL 62701George L. EdgarMorgan, Lewis and Bockius 1111 Pennsylvania Ave, NW Washington, DC 20004Braidwood Station Plant ManagerExelon Generation Company, LLC 35100 S. Rt. 53, Suite 84 Braceville, IL 60407-9619 Site Vice President - BraidwoodExelon Generation Company, LLC 35100 S. Rt. 53, Suite 84 Braceville, IL 60407-9619Senior Vice President of OperationsExelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555Chairman, Ogle County BoardPost Office Box 357 Oregon, IL 61061 Braidwood Station Units 1 and 2- 2 -Regulatory Assurance Manager - BraidwoodExelon Generation Company, LLC 35100 S. Rt. 53, Suite 84 Braceville, IL 60407-9619Director - Licensing and Regulatory AffairsExelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555Assistant General CounselExelon Generation Company, LLC 200 Exelon Way Kennett Square, PA 19348Vice President - Licensing and Regulatory AffairsExelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555Manager Licensing - Braidwood, Byron and LaSalleExelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555}}
| | submitted information pertaining to the steam generator (SG) tube inspection summary reports for the fall 2004 outage at the Braidwood Station, Unit 1 (Braidwood) in accordance with the plants technical specifications. In addition, the NRC staff summarized some of the inspection results in a letter dated December 21, 2004 (ADAMS Accession No. ML043240231). |
| | BACKGROUND The four SGs at Braidwood were replaced in 1998 with the SGs fabricated by Babcock and Wilcox International. Each SG contains 6633 thermally treated Alloy 690 tubes. Each tube has a nominal outside diameter of 0.6875-inch and a nominal wall thickness of 0.040-inch. The tubes were hydraulically expanded at both ends for the full length of the tubesheet and are supported by a number of stainless steel tube supports (lattice grid). The tubes installed in rows 1 through 21 were thermally stress relieved after bending. |
| | RESULTS OF FALL 2004 INSPECTION The licensee provided the scope, extent, methods and results of their SG tube inspections in the documents referenced above. In addition, the licensee described corrective actions (i.e., |
| | tube plugging) taken in response to the inspection findings. |
| | The licensee included information regarding the examination and evaluation procedures used during the SG eddy current inspection which included two independent analyses of the eddy current data, using automated data screening analysis systems. |
| | As a result of the SG tube inspections, the licensee identified five tubes with indications of secondary side foreign object wear at the lattice grid elevations in SGs B, C and D. All of these tubes were plugged. In a conference call with the licensee, it was indicated that the foreign objects causing the wear could be spiral wound gasket material. |
| | Enclosure |
| | |
| | During this inspection, the licensee continued to monitor the potential for tubes to be in close proximity as part of the 100-percent full length bobbin coil inspection in SG B. The licensee did not identify any tube degradation associated with the tubes being in close proximity. The licensee stated that this condition will be monitored in all four SGs during the next refueling outage. |
| | In its report dated July 29, 2003 (ADAMS Accession No. ML032190155), the licensee indicated that the tube in row 70 column 41 in SG D had a 6-percent through-wall indication which was attributed to wear at the lattice grid. In its report dated January 20, 2005 (ADAMS Accession No. ML050280208), the licensee indicated that the indication was 25-percent through-wall. In an NRC summary dated December 21, 2004, the NRC staff indicated that the indication in R70C41 (actually, the NRC staff incorrectly identified the tube as R70C2 in the summary) measured 25-percent through-wall and was attributed to wear from a foreign object and that there was no change in the signal between 2003 and 2004 SG tube inspections. In a conference call on August 4, 2005, the licensee clarified that originally (in 2003) the indications was classified as lattice grid wear, but based on the overall 2004 inspection results, they reviewed the 2003 indication at this location and concluded that this indication was a result of wear from a foreign object. The licensee also clarified that there was no growth in the indication rather the apparent change in depth (from 6 percent to 25 percent) was a result of using a different sizing method (i.e., instead of sizing the indication with a technique for lattice grid wear, the indication was sized with a foreign object wear sizing technique). The wear scar was at the bottom edge of the tube support slightly adjacent to the tube-to-lattice grid intersection. |
| | CONCLUSIONS AND FUTURE INSPECTION PLANS Based on a review of the information provided, the NRC staff concludes that the licensee provided the information required by Braidwood TSs. In addition, the NRC staff concludes that there are no technical issues that warrant follow-up action at this time since the inspections appear to be consistent with the objective of detecting potential tube degradation and the inspection results appear to be consistent with industry operating experience at similarly designed and operated units. |
| | Principle Contributor: Y. Diaz Date: January 26, 2006 |
| | |
| | Braidwood Station Units 1 and 2 cc: |
| | Regional Administrator, Region III Illinois Emergency Management U.S. Nuclear Regulatory Commission Agency 801 Warrenville Road Division of Disaster Assistance & |
| | Lisle, IL 60532-4351 Preparedness 110 East Adams Street Document Control Desk - Licensing Springfield, IL 62701-1109 Exelon Generation Company, LLC 4300 Winfield Road County Executive Warrenville, IL 60555 Will County Office Building 302 N. Chicago Street Mr. Dwain W. Alexander, Project Manager Joliet, IL 60432 Westinghouse Electric Corporation Energy Systems Business Unit Attorney General Post Office Box 355 500 S. Second Street Pittsburgh, PA 15230 Springfield, IL 62701 Joseph Gallo George L. Edgar Gallo & Ross Morgan, Lewis and Bockius 1025 Connecticut Ave., NW, Suite 1014 1111 Pennsylvania Ave, NW Washington, DC 20036 Washington, DC 20004 Ms. Bridget Little Rorem Braidwood Station Plant Manager Appleseed Coordinator Exelon Generation Company, LLC 117 N. Linden Street 35100 S. Rt. 53, Suite 84 Essex, IL 60935 Braceville, IL 60407-9619 Howard A. Learner Site Vice President - Braidwood Environmental Law and Policy Exelon Generation Company, LLC Center of the Midwest 35100 S. Rt. 53, Suite 84 35 East Wacker Dr., Suite 1300 Braceville, IL 60407-9619 Chicago, IL 60601-2110 Senior Vice President of Operations U.S. Nuclear Regulatory Commission Exelon Generation Company, LLC Braidwood Resident Inspectors Office 4300 Winfield Road 35100 S. Rt. 53, Suite 79 Warrenville, IL 60555 Braceville, IL 60407 Chairman, Ogle County Board Ms. Lorraine Creek Post Office Box 357 RR 1, Box 182 Oregon, IL 61061 Manteno, IL 60950 |
| | |
| | Braidwood Station Units 1 and 2 Regulatory Assurance Manager - Braidwood Exelon Generation Company, LLC 35100 S. Rt. 53, Suite 84 Braceville, IL 60407-9619 Director - Licensing and Regulatory Affairs Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555 Assistant General Counsel Exelon Generation Company, LLC 200 Exelon Way Kennett Square, PA 19348 Vice President - Licensing and Regulatory Affairs Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555 Manager Licensing - Braidwood, Byron and LaSalle Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555}} |
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Category:Letter
MONTHYEARIR 05000456/20230042024-02-0202 February 2024
Integrated Inspection Report 05000456/2023004 and 05000457/2023004
ML24025C7242024-01-29029 January 2024
Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000456/2024002; 05000457/2024002
IR 05000457/20230112024-01-25025 January 2024
2B Auxiliary Feedwater Pump Diesel Fuel Oil Dilution Report 05000457/2023011 and Preliminary Greater than Green Finding and Apparent Violation
ML24018A0362024-01-17017 January 2024
Paragon Energy Solutions, Defect with Detroit Diesel/Mtu Fuel Injectors P/N R5229660 Cat Id 0001390618
RS-24-004, Proposed Alternative to the Distribution Requirements of ASME Code Table IWC-2411-1 for the Steam Generators2024-01-11011 January 2024
Proposed Alternative to the Distribution Requirements of ASME Code Table IWC-2411-1 for the Steam Generators
ML23348A2162023-12-15015 December 2023
Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0030 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting))
IR 05000456/20200232023-12-15015 December 2023
Baseline Security Inspection Document; 05000456/2023/402; 05000457/2023/402
ML23277A0032023-12-11011 December 2023
Issuance of Amendments Regarding Adoption of TSTF-370
ML23339A0452023-12-0505 December 2023
Request for Information for an NRC Post-Approval Site Inspection for License Renewal Inspection Report 05000546/2024010
ML23313A1552023-12-0101 December 2023
Review of the Fall 2022 Steam Generator Tube Inspection Report
ML23331A8922023-11-22022 November 2023
Supplement - Braidwood Security Rule Exemption Request ISFSI Docket No. Reference
05000457/LER-2023-001, Submittal of LER 2023-001-00 for Braidwood Station, Unit 2, Train B Auxiliary Feedwater Pump Was Inoperable Due to Degraded Oil in the Crank Case2023-11-17017 November 2023
Submittal of LER 2023-001-00 for Braidwood Station, Unit 2, Train B Auxiliary Feedwater Pump Was Inoperable Due to Degraded Oil in the Crank Case
ML23321A0442023-11-17017 November 2023
Notification of Deviation from Electric Power Research Institute (EPRI) Topical Report MRP-227, Revision 1-A, Materials Reliability Program: Pressurized Water Reactor Internals Inspection and Evaluation Guideline
RS-23-118, Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information2023-11-10010 November 2023
Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information
ML23317A1192023-11-10010 November 2023
Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums
RS-23-114, Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds2023-11-0101 November 2023
Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds
IR 05000456/20234012023-10-18018 October 2023
Security Baseline Inspection Report 05000456/2023401 and 05000457/2023401
IR 05000456/20230102023-10-18018 October 2023
Functional Engineering Inspection Commercial Grade Dedication Report 05000456/2023010 and 05000457/2023010
RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023
Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans
RS-23-108, Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles2023-10-11011 October 2023
Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles
RS-23-105, Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections2023-10-10010 October 2023
Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections
RS-23-093, License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel.2023-09-29029 September 2023
License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel.
ML23226A0062023-09-19019 September 2023
Review of License Renewal Commitment Number 10 Submittal
ML23180A1692023-09-11011 September 2023
Calvert Cliff Units 1 & 2, and R.E. Ginna Plant - Withdrawal of Proposed Alternatives to American Society of Mechanical Engineers (ASME) Requirements (Epids L-2022-LRR-0074, 0076, 0079, 0091, 0092, 0093 and 0094)
IR 05000456/20230052023-08-30030 August 2023
Updated Inspection Plan for Braidwood Station Report 05000456/2023005 and 05000457/2023005
ML23234A2462023-08-25025 August 2023
Confirmation of Initial License Examination
IR 05000456/20230022023-08-0303 August 2023
Integrated Inspection Report 05000456/2023002 and 05000457/2023002
ML23188A1292023-07-26026 July 2023
Issuance of Amendment Nos. 233 and 233 Adoption of TSTF-577, Revised Frequencies for Steam Generator Tube Inspections, Revision 1
ML23087A0762023-07-13013 July 2023
Issuance of Amendment Nos. 232 and 232 Revision of Technical Specifications for the Ultimate Heat Sink
ML23191A8442023-07-10010 July 2023
05000456; 05000457 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information
ML23178A2422023-06-28028 June 2023
Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch III
RS-23-083, Withdrawal - Proposed Alternatives Related to the Steam Generators2023-06-27027 June 2023
Withdrawal - Proposed Alternatives Related to the Steam Generators
RS-23-077, Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-06-16016 June 2023
Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations
ML23110A1152023-06-12012 June 2023
Environmental Assessment and Finding of No Significant Impact Related to a Requested Increase in Ultimate Heat Sink Temperature (EPID L-2023-LLA-0042) (Letter)
RS-23-074, Supplement to Application for License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink2023-06-0909 June 2023
Supplement to Application for License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink
RS-23-075, Application for Technical Specification Improvement to Extend the Completion Time for Condition B of Technical Specification 3.5.1, Accumulators, Using the Consolidated Line Item Improvement Process2023-06-0707 June 2023
Application for Technical Specification Improvement to Extend the Completion Time for Condition B of Technical Specification 3.5.1, Accumulators, Using the Consolidated Line Item Improvement Process
RS-23-050, Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube.2023-05-22022 May 2023
Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube.
ML23138A1342023-05-18018 May 2023
Information Meeting with a Question and Answer Session to Discuss NRC 2022 End-Of-Cycle Plant Performance Assessment of Braidwood Station and Byron Station
ML23132A0472023-05-12012 May 2023
Submittal of 2022 Annual Radiological Environmental Operating Report
ML23130A0072023-05-10010 May 2023
Submittal of Core Operating Limits Report Cycle 24, Rev. 16
IR 05000456/20230012023-05-0808 May 2023
Integrated Inspection Report 05000456/2023001 and 05000457/2023001
ML23114A2522023-04-28028 April 2023
Request to Use a Provision of a Later Edition of the ASME Boiler & Pressure Vessel Code, Section XI
ML23118A0202023-04-28028 April 2023
Submittal of 2022 Annual Radioactive Effluent Release Report
ML23110A3202023-04-21021 April 2023
Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection
RS-23-056, Response to Request for Additional Information to Braidwood Station, Unit 1, and Byron Station, Unit 1, for Steam Generator License Renewal Response to Commitment 102023-04-20020 April 2023
Response to Request for Additional Information to Braidwood Station, Unit 1, and Byron Station, Unit 1, for Steam Generator License Renewal Response to Commitment 10
RS-23-055, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2023-04-10010 April 2023
Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors
ML23095A1292023-04-0505 April 2023
Steam Generator Tube Inspection Report for Refueling Outage 23
ML23094A1352023-04-0404 April 2023
Request for Information for Nrc Commercial Grade Dedication Inspection Inspection Report 05000456/2023010 05000457/2023010
RS-23-052, License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink2023-03-24024 March 2023
License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink
RS-23-049, Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-23023 March 2023
Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations
2024-02-02
[Table view]
Category:Report
MONTHYEARBW230054, Attachment 2: MDMP Deviation Form2023-11-17017 November 2023
Attachment 2: MDMP Deviation Form
ML23321A0452023-11-17017 November 2023
EC 639996 (Byron), Revision 1 and 640160 (Braidwood), Revision 0, Technical Evaluation for NEI 03-08 Deviation of Baffle-Former Bolts Volumetric Examinations for Byron and Braidwood
RS-23-056, Response to Request for Additional Information to Braidwood Station, Unit 1, and Byron Station, Unit 1, for Steam Generator License Renewal Response to Commitment 102023-04-20020 April 2023
Response to Request for Additional Information to Braidwood Station, Unit 1, and Byron Station, Unit 1, for Steam Generator License Renewal Response to Commitment 10
BW220062, Pressure and Temperature Limits Report (Ptlr), Revision 92022-10-20020 October 2022
Pressure and Temperature Limits Report (Ptlr), Revision 9
NMP1L3469, Constellation Energy Company, LLC, Request for Use of Honeywell Mururoa V4F1 R Supplied Air Suits2022-06-30030 June 2022
Constellation Energy Company, LLC, Request for Use of Honeywell Mururoa V4F1 R Supplied Air Suits
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License Renewal Response to Commitment 10 - Evaluation of Possible PWSCC Crack Initiation and Propagation in the Steam Generator Channel Head Assembly and Tube-to-Tubesheet Welds
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Justification for the Deviation from MRP 2019-008, Technical Evaluation 635273
BW210065, Pressure and Temperature Limits Report, Revision 82021-10-27027 October 2021
Pressure and Temperature Limits Report, Revision 8
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Updated 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors
RS-21-093, R. E. Ginna, Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections2021-09-0101 September 2021
R. E. Ginna, Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections
BW210047, ER-BR-330-1008, Revision 0, Snubber Program Plan for the Fourth 10-Year Interval2021-06-30030 June 2021
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Revised Proposed Alternative to Utilize Code Cases N-878 and N-880 for Carbon Steel Piping
RS-20-154, Application for Revision to TS 5.5.9, Steam Generator (SG) Program for a One-Time Deferral of Steam Generator Tube Inspections2020-12-16016 December 2020
Application for Revision to TS 5.5.9, Steam Generator (SG) Program for a One-Time Deferral of Steam Generator Tube Inspections
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Proposed Relief Request from Section XI Repair/Replacement Documentation for Bolting Replacement of Pressure Retaining Bolting
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Attachment 11 - SG-SGMP-17-25-NP, Revision 1, Foreign Object Limits Analysis for the Byron and Braidwood Unit 2 Steam Generators June 2020
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Proposed Alternative to Utilize Code Case N-879
ML18348A9792018-12-14014 December 2018
Transmittal of 10 CFR 50.59 Summary Report
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Submittal of Analytical Evaluation in Accordance with ASME Code Section XI
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Operating Data Report for 2016
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Report of Full Compliance with March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)
RS-16-174, High Frequency Supplement to Seismic Hazard Screening Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review...2016-11-0303 November 2016
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Areva, 51-9263014-000, PWSCC Evaluation of Uhp Cavitation Peening for Byron and Braidwood Reactor Vessel Head Penetrations.
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51-9263014-000, PWSCC Evaluation of Uhp Cavitation Peening for Byron and Braidwood Reactor Vessel Head Penetrations.
ML17360A1742016-10-0707 October 2016
Attachment 6: Areva Document 51-9263014-000, PWSCC Evaluation of Uhp Cavitation Peening for Byron and Braidwood Reactor Vessel Head Penetrations (Non-Proprietary)
RS-17-039, Attachment 6, Areva Document 51-9263014-000, PWSCC Evaluation of Uhp Cavitation Peening for Byron and Braidwood Reactor Vessel Head Penetrations.2016-10-0707 October 2016
Attachment 6, Areva Document 51-9263014-000, PWSCC Evaluation of Uhp Cavitation Peening for Byron and Braidwood Reactor Vessel Head Penetrations.
ML17095A2692016-10-0707 October 2016
Attachment 6, Areva Document 51-9263014-000, PWSCC Evaluation of Uhp Cavitation Peening for Byron and Braidwood Reactor Vessel Head Penetrations.
ML16236A2082016-08-23023 August 2016
Report of Backfit Appeal Review Panel
ML16214A1992016-08-11011 August 2016
an Assessment of Core Damage Frequency for Byron/Braidwood Backit Appeal Review
RS-16-099, Mitigating Strategies Flood Hazard Assessment (Msfha) Submittal2016-06-30030 June 2016
Mitigating Strategies Flood Hazard Assessment (Msfha) Submittal
ML16250A5182016-04-30030 April 2016
Technical Evaluation Report Related to the Exelon Generation Company, LLC, License Amendment Request to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink. Docket Nos. Stn 50-456 & 457
RS-16-073, Submittal of Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2016-04-0707 April 2016
Submittal of Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors
RS-16-057, Supplement to Response to Requests for Additional Information for Relief for Alternate Requirements for Repair of Reactor Vessel Head Penetrations with Nozzles Having Pressure-Retaining Partial-Penetration J-Groove Welds2016-03-15015 March 2016
Supplement to Response to Requests for Additional Information for Relief for Alternate Requirements for Repair of Reactor Vessel Head Penetrations with Nozzles Having Pressure-Retaining Partial-Penetration J-Groove Welds
ML16014A1882016-01-22022 January 2016
Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50 Section 50.54(f) Seismic Hazard Reevaluations for Recommendation 2.1of the Near-Term Task Force Review of Insights
ML15344A1592015-12-10010 December 2015
Submittal of Pressure and Temperature Limits Reports (Ptlrs), Revision 8 and Braidwood, Unit 2 - Pressure and Temperature Limits Reports (Ptlrs), Revision 7
ML15322A3172015-11-18018 November 2015
Record of Decision
ML15237A3822015-10-15015 October 2015
Pressure and Temperature Limits Report for Measurement Uncertainty Recapture Power Uprate
RS-15-259, Final Report: Five Year Post-Construction Monitoring of the Unionid Community Near the Braidwood Station Kankakee River Discharge.2015-09-30030 September 2015
Final Report: Five Year Post-Construction Monitoring of the Unionid Community Near the Braidwood Station Kankakee River Discharge.
RS-15-129, Westinghouse Report CCE-15-27, Revision 1, Braidwood Units 1 and 2 - Responses to NRC Request for Additional Information (Rai)Regarding Ultimate Heat Sink Temperature Increase License Amendment Request, April 20152015-04-30030 April 2015
Westinghouse Report CCE-15-27, Revision 1, Braidwood Units 1 and 2 - Responses to NRC Request for Additional Information (Rai)Regarding Ultimate Heat Sink Temperature Increase License Amendment Request, April 2015
ML14349A6572014-12-15015 December 2014
CFR 50.59 Changes, Tests, and Experiments, Paragraph (d)(2), Summary Report
RS-14-348, Comments on the Safety Evaluation Report with Open Items, Related to the License Renewal Application2014-12-15015 December 2014
Comments on the Safety Evaluation Report with Open Items, Related to the License Renewal Application
RS-14-277, Proposed Alternative to Utilize Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 12014-09-24024 September 2014
Proposed Alternative to Utilize Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 1
ML14141A1332014-06-30030 June 2014
Staff Assessment of the Flooding Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima DAI-ICHI Nuclear Power Plant Accident
ML14178B2222014-06-24024 June 2014
Technical Review of TIA 2013-02, Single Spurious Assumptions for Braidwood and Byron Stations Safe-Shutdown Methodology
ML14101A4452014-06-0404 June 2014
Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident (Tac No. MF0095)
ML14101A3522014-06-0404 June 2014
Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-ichi Nuclear Power Plant Accident
ML14127A1742014-05-0707 May 2014
Startup Report for the Measurement Uncertainty Recapture Power Uprate
ML14120A0392014-04-24024 April 2014
Units 1 & 2 - License Amendment Request to Install New Low Degraded Voltage Relays & Timers on the 4.16 Kv Engineered Safety Features (ESF) Buses
2023-04-20
[Table view]
Category:Miscellaneous
MONTHYEARBW230054, Attachment 2: MDMP Deviation Form2023-11-17017 November 2023
Attachment 2: MDMP Deviation Form
ML23321A0452023-11-17017 November 2023
EC 639996 (Byron), Revision 1 and 640160 (Braidwood), Revision 0, Technical Evaluation for NEI 03-08 Deviation of Baffle-Former Bolts Volumetric Examinations for Byron and Braidwood
RS-22-071, License Renewal Response to Commitment 10 - Evaluation of Possible PWSCC Crack Initiation and Propagation in the Steam Generator Channel Head Assembly and Tube-to-Tubesheet Welds2022-06-0707 June 2022
License Renewal Response to Commitment 10 - Evaluation of Possible PWSCC Crack Initiation and Propagation in the Steam Generator Channel Head Assembly and Tube-to-Tubesheet Welds
RS-22-047, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2022-04-0808 April 2022
Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors
ML21349A1062021-12-15015 December 2021
Justification for the Deviation from MRP 2019-008, Technical Evaluation 635273
RS-21-112, Updated 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2021-10-22022 October 2021
Updated 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors
ML20303A1752020-10-23023 October 2020
Proposed Relief Request from Section XI Repair/Replacement Documentation for Bolting Replacement of Pressure Retaining Bolting
RS-17-048, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2017-04-0707 April 2017
Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors
ML17024A0362016-12-31031 December 2016
Operating Data Report for 2016
RS-16-174, High Frequency Supplement to Seismic Hazard Screening Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review...2016-11-0303 November 2016
High Frequency Supplement to Seismic Hazard Screening Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review...
RS-17-039, Attachment 6, Areva Document 51-9263014-000, PWSCC Evaluation of Uhp Cavitation Peening for Byron and Braidwood Reactor Vessel Head Penetrations.2016-10-0707 October 2016
Attachment 6, Areva Document 51-9263014-000, PWSCC Evaluation of Uhp Cavitation Peening for Byron and Braidwood Reactor Vessel Head Penetrations.
ML17170A1472016-10-0707 October 2016
Areva, 51-9263014-000, PWSCC Evaluation of Uhp Cavitation Peening for Byron and Braidwood Reactor Vessel Head Penetrations.
ML17095A2692016-10-0707 October 2016
Attachment 6, Areva Document 51-9263014-000, PWSCC Evaluation of Uhp Cavitation Peening for Byron and Braidwood Reactor Vessel Head Penetrations.
ML16236A2082016-08-23023 August 2016
Report of Backfit Appeal Review Panel
ML16214A1992016-08-11011 August 2016
an Assessment of Core Damage Frequency for Byron/Braidwood Backit Appeal Review
RS-16-099, Mitigating Strategies Flood Hazard Assessment (Msfha) Submittal2016-06-30030 June 2016
Mitigating Strategies Flood Hazard Assessment (Msfha) Submittal
RS-16-073, Submittal of Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2016-04-0707 April 2016
Submittal of Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors
ML16014A1882016-01-22022 January 2016
Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50 Section 50.54(f) Seismic Hazard Reevaluations for Recommendation 2.1of the Near-Term Task Force Review of Insights
ML15344A1592015-12-10010 December 2015
Submittal of Pressure and Temperature Limits Reports (Ptlrs), Revision 8 and Braidwood, Unit 2 - Pressure and Temperature Limits Reports (Ptlrs), Revision 7
ML15322A3172015-11-18018 November 2015
Record of Decision
ML15237A3822015-10-15015 October 2015
Pressure and Temperature Limits Report for Measurement Uncertainty Recapture Power Uprate
RS-15-129, Westinghouse Report CCE-15-27, Revision 1, Braidwood Units 1 and 2 - Responses to NRC Request for Additional Information (Rai)Regarding Ultimate Heat Sink Temperature Increase License Amendment Request, April 20152015-04-30030 April 2015
Westinghouse Report CCE-15-27, Revision 1, Braidwood Units 1 and 2 - Responses to NRC Request for Additional Information (Rai)Regarding Ultimate Heat Sink Temperature Increase License Amendment Request, April 2015
ML14349A6572014-12-15015 December 2014
CFR 50.59 Changes, Tests, and Experiments, Paragraph (d)(2), Summary Report
RS-14-348, Comments on the Safety Evaluation Report with Open Items, Related to the License Renewal Application2014-12-15015 December 2014
Comments on the Safety Evaluation Report with Open Items, Related to the License Renewal Application
ML14141A1332014-06-30030 June 2014
Staff Assessment of the Flooding Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima DAI-ICHI Nuclear Power Plant Accident
ML14101A4452014-06-0404 June 2014
Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident (Tac No. MF0095)
ML14101A3522014-06-0404 June 2014
Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-ichi Nuclear Power Plant Accident
ML14127A1742014-05-0707 May 2014
Startup Report for the Measurement Uncertainty Recapture Power Uprate
ML14120A0392014-04-24024 April 2014
Units 1 & 2 - License Amendment Request to Install New Low Degraded Voltage Relays & Timers on the 4.16 Kv Engineered Safety Features (ESF) Buses
ML14066A4792014-03-0404 March 2014
Clarification of Licensing Basis Assumptions for a Natural Circulation Cooldown Event
ML14059A1242014-02-28028 February 2014
Pressure and Temperature Limits Reports (Ptlrs)
IR 05000272/20132012013-01-31031 January 2013
Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee
IR 05000456/20132022013-01-31031 January 2013
Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee
ML13008A2192013-01-31031 January 2013
U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee
IR 05000454/20132022013-01-31031 January 2013
Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee
IR 05000461/20132012013-01-31031 January 2013
Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee
IR 05000237/20132022013-01-31031 January 2013
Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee
IR 05000373/20132012013-01-31031 January 2013
Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee
IR 05000289/20132012013-01-31031 January 2013
Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee
IR 05000254/20132012013-01-31031 January 2013
Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee
IR 05000277/20132012013-01-31031 January 2013
Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee
IR 05000219/20132012013-01-31031 January 2013
Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee
IR 05000352/20132012013-01-31031 January 2013
Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee
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10 CFR 50.59 Summary Report for June 19, 2010 Through June 18, 2012
ML12339A2172012-11-16016 November 2012
12Q0108.10-R-001, Revision 0, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the Braidwood Station, Unit 1. Part 1 of 5
ML12339A2182012-11-16016 November 2012
12Q0108.10-R-002, Revision 0, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the Braidwood Station, Unit 2. Part 5 of 5
ML12339A2192012-11-16016 November 2012
12Q0108.10-R-001, Revision 0, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the Braidwood Station, Unit 1. Part 2 of 5
ML12339A2202012-11-16016 November 2012
12Q0108.10-R-001, Revision 0, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the Braidwood Station, Unit 1. Part 3 of 5
ML12339A2212012-11-16016 November 2012
12Q0108.10-R-001, Revision 0, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the Braidwood Station, Unit 1. Part 4 of 5
ML12339A2222012-11-16016 November 2012
12Q0108.10-R-001, Revision 0, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the Braidwood Station, Unit 1. Part 5 of 5
2023-11-17
[Table view] |
Text
January 27, 2006 Mr. Christopher M. Crane, President and Chief Nuclear Officer Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
BRAIDWOOD STATION, UNIT 1 - EVALUATION OF STEAM GENERATOR INSERVICE INSPECTION
SUMMARY
REPORT (TAC NO. MC7014)
Dear Mr. Crane:
By letters to the Nuclear Regulatory Commission (NRC) dated October 29, 2004 and January 20, 2005, Exelon Generation Company, LLC (the licensee), submitted information pertaining to the steam generator tube inspection summary reports for the fall 2004 outage at the Braidwood Station, Unit 1 (Braidwood), in accordance with the plants technical specifications (TSs).
The NRC staff has completed its review of these reports and concludes that the licensee provided the information required by the Braidwood TSs and that no additional follow-up is required at this time.
Sincerely,
/RA/
Mahesh L. Chawla, Project Manager Plant Licensing Branch III-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. STN 50-456
Enclosure:
Evaluation of SG Inspection Reports cc w/encl: See next page
Mr. Christopher M. Crane, President January 27, 2006 and Chief Nuclear Officer Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
BRAIDWOOD STATION, UNIT 1 - EVALUATION OF STEAM GENERATOR INSERVICE INSPECTION
SUMMARY
REPORT (TAC NO. MC7014)
Dear Mr. Crane:
By letters to the Nuclear Regulatory Commission (NRC) dated October 29, 2004 and January 20, 2005, Exelon Generation Company, LLC (the licensee), submitted information pertaining to the steam generator tube inspection summary reports for the fall 2004 outage at the Braidwood Station, Unit 1 (Braidwood), in accordance with the plants technical specifications (TSs).
The NRC staff has completed its review of these reports and concludes that the licensee provided the information required by the Braidwood TSs and that no additional follow-up is required at this time.
Sincerely,
/RA/
Mahesh L. Chawla, Project Manager Plant Licensing Branch III-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. STN 50-456
Enclosure:
Evaluation of SG Inspection Reports cc w/encl: See next page DISTRIBUTION:
PUBLIC LPLIII/2 r/f RidsNrrPMMChawla MMurphy RidsOGCRp DHills, RIII KKarwoski RidsNrrDlrRIra RidsNrrDorlLplf RidsAcrsAcnwMailCenter YDiaz RidsNrrDciCsgb RidsNrrLADClarke RSkokowski, RIII ADAMS Accession Number: ML053490064 OFFICE PM:LPL3-2 LA:LPL3-2 BC:CSGB (A)BC:LPLIII-2 NAME MChawla:mw DClarke AHiser MLandau DATE 1/26/06 1/26/06 1/27/06 1/27/06 OFFICIAL RECORD COPY
OFFICE OF NUCLEAR REACTOR REGULATION EVALUATION OF STEAM GENERATOR INSPECTION REPORTS FROM 2004 REFUELING OUTAGE BRAIDWOOD STATION, UNIT 1 DOCKET NO. STN 50-456 INTRODUCTION By letters to the Nuclear Regulatory Commission (NRC) dated October 29, 2004 (Agencywide Documents Access and Management System Accession No. ML043090549) and January 20, 2005 (ADAMS Accession No. ML050280208), Exelon Generation Company, LLC (the licensee),
submitted information pertaining to the steam generator (SG) tube inspection summary reports for the fall 2004 outage at the Braidwood Station, Unit 1 (Braidwood) in accordance with the plants technical specifications. In addition, the NRC staff summarized some of the inspection results in a letter dated December 21, 2004 (ADAMS Accession No. ML043240231).
BACKGROUND The four SGs at Braidwood were replaced in 1998 with the SGs fabricated by Babcock and Wilcox International. Each SG contains 6633 thermally treated Alloy 690 tubes. Each tube has a nominal outside diameter of 0.6875-inch and a nominal wall thickness of 0.040-inch. The tubes were hydraulically expanded at both ends for the full length of the tubesheet and are supported by a number of stainless steel tube supports (lattice grid). The tubes installed in rows 1 through 21 were thermally stress relieved after bending.
RESULTS OF FALL 2004 INSPECTION The licensee provided the scope, extent, methods and results of their SG tube inspections in the documents referenced above. In addition, the licensee described corrective actions (i.e.,
tube plugging) taken in response to the inspection findings.
The licensee included information regarding the examination and evaluation procedures used during the SG eddy current inspection which included two independent analyses of the eddy current data, using automated data screening analysis systems.
As a result of the SG tube inspections, the licensee identified five tubes with indications of secondary side foreign object wear at the lattice grid elevations in SGs B, C and D. All of these tubes were plugged. In a conference call with the licensee, it was indicated that the foreign objects causing the wear could be spiral wound gasket material.
Enclosure
During this inspection, the licensee continued to monitor the potential for tubes to be in close proximity as part of the 100-percent full length bobbin coil inspection in SG B. The licensee did not identify any tube degradation associated with the tubes being in close proximity. The licensee stated that this condition will be monitored in all four SGs during the next refueling outage.
In its report dated July 29, 2003 (ADAMS Accession No. ML032190155), the licensee indicated that the tube in row 70 column 41 in SG D had a 6-percent through-wall indication which was attributed to wear at the lattice grid. In its report dated January 20, 2005 (ADAMS Accession No. ML050280208), the licensee indicated that the indication was 25-percent through-wall. In an NRC summary dated December 21, 2004, the NRC staff indicated that the indication in R70C41 (actually, the NRC staff incorrectly identified the tube as R70C2 in the summary) measured 25-percent through-wall and was attributed to wear from a foreign object and that there was no change in the signal between 2003 and 2004 SG tube inspections. In a conference call on August 4, 2005, the licensee clarified that originally (in 2003) the indications was classified as lattice grid wear, but based on the overall 2004 inspection results, they reviewed the 2003 indication at this location and concluded that this indication was a result of wear from a foreign object. The licensee also clarified that there was no growth in the indication rather the apparent change in depth (from 6 percent to 25 percent) was a result of using a different sizing method (i.e., instead of sizing the indication with a technique for lattice grid wear, the indication was sized with a foreign object wear sizing technique). The wear scar was at the bottom edge of the tube support slightly adjacent to the tube-to-lattice grid intersection.
CONCLUSIONS AND FUTURE INSPECTION PLANS Based on a review of the information provided, the NRC staff concludes that the licensee provided the information required by Braidwood TSs. In addition, the NRC staff concludes that there are no technical issues that warrant follow-up action at this time since the inspections appear to be consistent with the objective of detecting potential tube degradation and the inspection results appear to be consistent with industry operating experience at similarly designed and operated units.
Principle Contributor: Y. Diaz Date: January 26, 2006
Braidwood Station Units 1 and 2 cc:
Regional Administrator, Region III Illinois Emergency Management U.S. Nuclear Regulatory Commission Agency 801 Warrenville Road Division of Disaster Assistance &
Lisle, IL 60532-4351 Preparedness 110 East Adams Street Document Control Desk - Licensing Springfield, IL 62701-1109 Exelon Generation Company, LLC 4300 Winfield Road County Executive Warrenville, IL 60555 Will County Office Building 302 N. Chicago Street Mr. Dwain W. Alexander, Project Manager Joliet, IL 60432 Westinghouse Electric Corporation Energy Systems Business Unit Attorney General Post Office Box 355 500 S. Second Street Pittsburgh, PA 15230 Springfield, IL 62701 Joseph Gallo George L. Edgar Gallo & Ross Morgan, Lewis and Bockius 1025 Connecticut Ave., NW, Suite 1014 1111 Pennsylvania Ave, NW Washington, DC 20036 Washington, DC 20004 Ms. Bridget Little Rorem Braidwood Station Plant Manager Appleseed Coordinator Exelon Generation Company, LLC 117 N. Linden Street 35100 S. Rt. 53, Suite 84 Essex, IL 60935 Braceville, IL 60407-9619 Howard A. Learner Site Vice President - Braidwood Environmental Law and Policy Exelon Generation Company, LLC Center of the Midwest 35100 S. Rt. 53, Suite 84 35 East Wacker Dr., Suite 1300 Braceville, IL 60407-9619 Chicago, IL 60601-2110 Senior Vice President of Operations U.S. Nuclear Regulatory Commission Exelon Generation Company, LLC Braidwood Resident Inspectors Office 4300 Winfield Road 35100 S. Rt. 53, Suite 79 Warrenville, IL 60555 Braceville, IL 60407 Chairman, Ogle County Board Ms. Lorraine Creek Post Office Box 357 RR 1, Box 182 Oregon, IL 61061 Manteno, IL 60950
Braidwood Station Units 1 and 2 Regulatory Assurance Manager - Braidwood Exelon Generation Company, LLC 35100 S. Rt. 53, Suite 84 Braceville, IL 60407-9619 Director - Licensing and Regulatory Affairs Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555 Assistant General Counsel Exelon Generation Company, LLC 200 Exelon Way Kennett Square, PA 19348 Vice President - Licensing and Regulatory Affairs Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555 Manager Licensing - Braidwood, Byron and LaSalle Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555
