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| | number = ML063550199 | | | number = ML063550199 |
| | issue date = 12/21/2006 | | | issue date = 12/21/2006 |
| | title = Braidwood Station, Unit 2, 60-Day Response to NRC Bulletin 2004-01, Inspection of Alloy 82/182/600 Materials Used in the Fabrication of Pressurizer Penetrations and Steam Space Piping Connections at Pressurized-Water Reactors. | | | title = 60-Day Response to NRC Bulletin 2004-01, Inspection of Alloy 82/182/600 Materials Used in the Fabrication of Pressurizer Penetrations and Steam Space Piping Connections at Pressurized-Water Reactors. |
| | author name = Coutu T | | | author name = Coutu T |
| | author affiliation = Exelon Nuclear | | | author affiliation = Exelon Nuclear |
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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
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______________Exel_nQ Exelon Generation Company LLC ww~v.exe1oncorp~com N uc]ear Braidwood Station~~O S~~t Erc~o~E~'8'~~17 O~O December 21, 2006 10 CFR 50.54 (f)BW060117 U.S.NuclearRegulatory Commission ATTN: DocumentControlDesk11555Rockvilie Pike Rockville, Maryland 20852 BraidwoodStation,Unit 2 Facility Operating License No.NPF-77NRCDocket No.STN 50-457
Subject:
Braidwood Station, Unit 2 60-Day Response to NRC Bulletin 2004-01,"Inspection of Alloy 82/182/600 Materials Used in the Fabrication of Pressurizer Penetrations and SteamSpacePiping Connections at Pressurized-Water Reactors"On May 28, 2004, the NRC issued NRC Bulletin 2004-01,"Inspection of Alloy 82/182/600 Materials Used in theFabricationof Pressurizer Penetrations andSteamSpacePiping Connections at Pressurized-Water Reactors."RequestedInformation Section 2(a)of this bulletin requires the following information be submiffed to the NRC within 60 days after plantrestartfollowing the next inspection oftheAlloy 82/182/600 pressurizer penetrations and steamspacepiping connections:
"...astatementindicating that the inspections described in thelicensee'sresponseto item (1)(c)of this bulletin were completed and a description of the as-found condition of the pressurizer shell, any findings of relevant indications of through-wall leakage, tollowup NDE performed to characterize flaws in leaking penetrations or steamspacepiping connections, a summary of all relevant indications found by NDE, a summary of the disposition of any findings ofboricacid, and any corrective actions taken and/or repairs madeasa result of the indications found."Pursuantto 10 CFR 50.54,"Conditionsoflicenses,"
paragraph (f), Attachment 1 to this letter provides the Braidwood Station Unit 2 60-Day response.This response is due to theNRCby January 2, 2007.
December 21, 2006 U.S.NuclearRegulatory Commission Page 2 Please direct any questions you may have regarding this submittal to Mr.Dale Ambler, Regulatory AssuranceManager,at (815)417-2800.Ideclareunder penalty of perjury that the foregoing istrueand correct.Respectfully, Executed on 12/21/06________________________
Thomas Coutu Site Vice PresidentBraidwoodStation
Attachment:
BraidwoodStation Unit 2 60-Day Response to NRC Bulletin 2004-01 ATTACHMENT Braidwood Station Unit 2 60-Day Response to NRC Bulletin 2004-01"Inspection of Alloy 82/182/600 Materials Used in theFabricationof Pressurizer Penetrations and Steam SpacePipingConnections at Pressurized-Water Reactors" ATTACHMENTBraidwoodStation Unit 2 60-Day Response to NRC Bulletin 2004-01 On May 28, 2004, the NRC issued NRC Bulletin 2004-01,"Inspection of Alloy 82/182/600 Materials Used in theFabricationofPressurizerPenetrations andSteamSpacePiping Connections at Pressurized-Water Reactors."
This bulletin requires the following information be submitted to the NRC within 60 days afterplantrestart following the next inspection of the Alloy 82/182/600 pressurizer penetrations and steamspacepiping connections:
"...a statement indicating that the inspections described in the licensee's response to item (1)(c)of this bulletin were completed and a description of the as-found condition of the pressurizer shell, any findings of relevant indications ofthrough-wa//leakage,followupNDE performed to characterize flaws inleakingpenetrations or steam space piping connections, a summary of a/I relevantindicationsfound by NDE, a summary of the disposition of any findings of boric acid,andany corrective actions taken and/or repairs made as a result of the indications found."ResDonse Summary of the InspectionsPerformed,Extent of theInspections,andMethods Used During the Fall 2006 refueling outage (A2R12), a baremetalvisual(BMV)examination was performed on all five of the pressurizer steam space penetrations and adjacent pressurizer shellsurfaces.The examination was conducted in accordance with Exelon Corporate procedures ER-AA-335-01 5,"VT-2 Examination", ER-AP-331-1001,"Boric Acid Corrosion Control (BACC)InspectionLocations,Implementation, and Inspection Guidelines,"
andER-AP-331-1002,"Boric Acid Corrosion Control Program Identification, Screening, and Evaluation."
The examination was performed after insulation was removedfromthetop of the pressurizer and the five associatedpenetrations.The examination was adirectvisual examination within two feet of the area of interest,ensuringany boric acid leakage would beeasilyidentified.
The full circumference of each of thefivepenetrations was examined.The examination was performed real time bycertifiedVT-2 examiners.
Description of the As-FoundCondition,Findings of Relevant Indications, and Summary of theDispositionofAny Findings The examination of thefivepenetrations and adjacent pressurizer vessel surfaces identified no evidence of any boric acid deposits associated with reactor coolant leakage.Corrective Actions Taken Based on the acceptable as found condition of thefivepenetrations and adjacent pressurizer vessel surfaces, there was no follow up NDE, disposition of findings, or corrective actions required.Page 1 of 1