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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:Confirmatory Action Letter (CAL)
MONTHYEARML0825200392008-09-16016 September 2008 Closure of Confirmatory Action Letter NRR-07-008 ML0819202872008-07-10010 July 2008 Closeout of Confirmatory Action Letter Requirements - Unit 2 ML0807403252008-03-14014 March 2008 Evaluation of New Information Related to Alloy 82/182 Pressurizer Butt Weld Inspections Confirmatory Action Letter NRR-07-008 ML0733901792007-12-17017 December 2007 Completion of Actions for Confirmatory Action Letter NRR-07-008 ML0731803832007-11-14014 November 2007 Closeout of Confirmatory Action Letter Requirements ML0724302922007-09-0707 September 2007 Evaluation of Finite Element Analysis in Support of Alloy 82/182 Pressurizer Butt Weld Inspections in 2008 as Provided by Completion of Analysis Required by CAL NRR-07-008 ML0707402942007-03-22022 March 2007 Confirmatory Action Letter - Braidwood, Units 1 and 2 2008-09-16
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Text
November 14, 2007 CAL No. NRR-07-008 BW070096 Mr. J. E. Dyer, Director Office of Nuclear Reactor Regulation ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555-0001 Braidwood Station, Unit 1 Facility Operating License No. NPF-72 NRC Docket No, STN 50-456
Subject:
Closeout of Confirmatory Action Letter Requirements Braidwood Station Unit 1 (TAC NO. MD4134)
References:
(1) Letter from T. S. ONeill (Exelon Generation Company, LLC) to U. S. NRC, Supplemental Response Regarding Inspection and Mitigation of Alloy 600/82/1 82 Pressurizer Butt Welds, dated February 21, 2007 (2) Letter from J. E. Dyer (U. S. NRC) to C. M. Crane (Exelon Generation Company, LLC), Confirmatory Action Letter Braidwood Station, Units 1 and 2 (TAC Nos.
MD4134 and MD4135), dated March 22, 2007
Dear Mr. Dyer:
The purpose of this letter is to notify you that the actions and commitments identified in the Reference 1 submittal and confirmed in the Reference 2 Confirmatory Action Letter (CAL No. NRR-07-008) have been completed for Braidwood Station Unit 1. The commitments involved: schedule for mitigation actions, enhanced Reactor Coolant System leakage monitoring, and inspection reporting requirements. All commitments were related to Alloy 82/1 82 pressurizer connection activities.
The details of the commitments and a summation of the closeout activities for Braidwood Station Unit 1 are provided in the attachment to this letter.
U. S. Nuclear Regulatory Commission Page 2 November 14, 2007 This submittal does not contain any additional Regulatory Commitments.
Should you have any questions concerning this letter, please contact Mr. David Gullott, Regulatory Assurance Manager, at (815) 417-2800.
Respec~tfully /~
1~ /
/ /~~L~-/ S~J~
Thomas Coutu Braidwood Station Site Vice President
Attachment:
Braidwood Station Unit 1 Confirmatory Action Letter Closeout CAL No.
NRR 07-008
Braidwood Station Unit 1 Confirmatory Action Letter Closeout CAL No. NRA 07-008 COMMITMENT COMPLETION DETAILS Exelon Generation Company, LLC (EGC) will Full structural weld overlays, with primary complete mitigation activities on the water stress corrosion cracking resistant pressurizer surge, spray, safety, and relief material, were installed on Braidwood Station nozzle butt welds and safe end butt welds Unit 1 pressurizer surge, spray, safety, and containing Alloy 82/i 82 material prior to relief nozzle-to-safe end butt welds containing December 31, 2007 for Braidwood Station Alloy 82/i 82 material. The overlays were Unit 1. completed in the Fall 2007 refueling outage (A1Ri3).
The pressurizer surge, spray, safety, and relief Mitigation activities were completed for nozzle butt welds and safe end butt welds Braidwood Station Unit 1 during the Ai Ri 3 containing Alloy 82/182 material will be refueling outage.
inspected within every 4 years, until mitigated.
Braidwood Station Unit 1 will adopt enhanced Braidwood Station Unit 1 adopted the unidentified leakage monitoring requirements. enhanced unidentified leakage monitoring These unidentified reactor coolant system requirements starting on February 28, 2007.
(RCS) leakage monitoring enhancements From that time until Unit 1 shutdown for the include: Al Ri 3 refueling outage on October 1, 2007, Daily measurement of unidentified RCS there were no instances of sustained elevated leakage leakage that required a Unit 1 shutdown.
Incorporation of two new action levels for the following unidentified RCS leakage scenarios:
- a 0.l0gpm change from one day to the next, sustained for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> with at least 0.10 gpm not confirmed from sources other than pressurizer nozzle welds.
- a 0.25gpm above a baseline sustained After restart from refueling outage Al Ri 3,1 for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> with at least 0.25 gpm not and the mitigation, as described above, confirmed from sources other than the completed, Braidwood Station Unit 1 reverted pressurizer nozzle welds back to the standard Technical Specification required RCS leakage monitoring
- Once the 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> evaluation period, i.e. requirements.
the 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> period of sustained increased leakage, is complete, and the leakrate is still elevated, Braidwood Station Unit 1 or Unit 2, as applicable, will be placed in MODE 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in MODE 5 within 36 additional hours and a bare metal visual inspection of unmitigated Alloy 82/182 pressurizer nozzles will be performed.
1 The return to service date from Al R13 was October 26, 2007.
Page 1 of 3
Braidwood Station Unit 1 Confirmatory Action Letter Closeout CAL No. NRA 07-008 COMMITMENT COMPLETION DETAILS Reports of any Alloy 82/i 82 pressurizer nozzle Since the initiation of this commitment on connections inspection results for Braidwood February 28, 2007 until the shutdown of Station Unit 1 will be submitted to the NRC Braidwood Station Unit 1 on October 1, 2007, within 60 days of the completion date of the there were no bare metal visual examinations inspection. This includes reports of any bare performed as a result of RCS leakage.
metal visual inspections as a result of increased RCS leak rate, and reports of any In accordance with the requirements of corrective or mitigative actions taken on the Bulletin 2004-01, Inspection of Alloy pressurizer surge, spray, safety, or relief 82/182/600 Materials Used in the Fabrication nozzle butt welds and safe end butt welds of Pressurizer Penetrations and Steam Space containing Alloy 82/1 82 material. Piping Connections at Pressurized-Water Reactors, Braidwood Station Unit i performed bare metal visual examinations of the pressurizer steam space connections. There were no indications of pressurizer pressure boundary leakage at any of the connections.
In addition, as part of the installation of full structural overlays on the pressurizer connections during the Fall 2007 refueling outage at Braidwood Station Unit 1, dye penetrant examinations of all Alloy 82/i 82 pressurizer connections were performed.
There were no indications associated with primary water stress corrosion cracking (PWSCC).
Finally, all six Braidwood Station Unit 1 pressurizer connections weld overlays were volumetrically examined in accordance with the requirements of the Reference 3 relief request. The results of these examinations were provided to the NRC in the Reference 4 submittal.
Page 2 of 3
Braidwood Station Unit 1 Confirmatory Action Letter Closeout CAL No. NRR 07-008
References:
(1) Letter from T. S. ONeill (Exelon Generation Company, LLC) to U. S. NRC, Supplemental Response Regarding Inspection and Mitigation of Alloy 600/82/182 Pressurizer Butt Welds, dated February 2i, 2007 (2) Letter from J. E. Dyer (U. S. NRC) to C. M. Crane (Exelon Generation Company, LLC),
Confirmatory Action Letter Braidwood Station, Units 1 and 2 (TAC Nos. MD41 34 and MD41 35), dated March 22, 2007 (3) Letter from T. Coutu (Exelon Generation Company, LLC) to U. S. NRC, Second 10-Year Inservice Inspection Interval, Relief Request l2R-48, Structural Weld Overlays on Pressurizer Spray, Relief, Safety and Surge Nozzles and Associated Alternative Repair Techniques, dated February 23, 2007 (4) Letter from T. Coutu (Exelon Generation Company, LLC) to U. S. NRC, Pressurizer Weld Overlay Examination Results Related to Braidwood Station Relief Request 12R-48, dated November i, 2007 Page 3 of 3