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Category:Letter
MONTHYEARIR 05000456/20230042024-02-0202 February 2024
Integrated Inspection Report 05000456/2023004 and 05000457/2023004
IR 05000454/20230042024-02-0202 February 2024
Integrated Inspection Report 05000454/2023004 and 05000455/2023004
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
ML24022A2722024-01-23023 January 2024
Request for Information for an NRC Post-Approval Site Inspection for License Renewal Inspection Report 05000454/2024011
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
ML23320A1762023-12-13013 December 2023
Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0027 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting))
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
ML23318A5102023-12-0101 December 2023
Relief from the Requirements of the ASME Code
IR 05000454/20233012023-11-27027 November 2023
NRC Initial License Examination Report 05000454/2023301 and 05000455/2023301
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
BYRON 2023-0065, Unit 2 - 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 Guideline2023-11-17017 November 2023
Unit 2 - 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
BYRON 2023-0063, Day Inservice Inspection Report for Interval 4, Period 3, (B2R24)2023-11-16016 November 2023
Day Inservice Inspection Report for Interval 4, Period 3, (B2R24)
IR 05000454/20230032023-11-13013 November 2023
Integrated Inspection Report 05000454/2023003 and 05000455/2023003 and Exercise of Enforcement Discretion
RS-23-117, 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-23-118, 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
ML23313A0852023-11-0909 November 2023
Submittal of 2023-301 Byron Initial License Examination Post-Examination Comments
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
ML23297A2352023-10-26026 October 2023
Information Request for the Cyber Security Baseline Inspection, Notification to Perform Inspection
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-23-100, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-10-13013 October 2023
Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation
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
ML23278A0272023-10-0505 October 2023
Operator Licensing Examination Approval - Byron Station, October 2023
RS-23-094, Relief Request I4R-24, Alternative for Post-Peening Reexamination Frequency for Reactor Pressure Vessel Head Penetration Nozzle Number 752023-09-29029 September 2023
Relief Request I4R-24, Alternative for Post-Peening Reexamination Frequency for Reactor Pressure Vessel Head Penetration Nozzle Number 75
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.
ML23251A1622023-09-29029 September 2023
Steam Generator Tube Inspection Reports to Reflect TSTF-577 Reporting Requirements
RS-23-091, Relief Request I4R-25, Alternative Requirements for Reactor Pressure Vessel Inservice Inspection Intervals2023-09-26026 September 2023
Relief Request I4R-25, Alternative Requirements for Reactor Pressure Vessel Inservice Inspection Intervals
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)
ML23242A3282023-09-0101 September 2023
Amendment No. 233 Correction
IR 05000454/20235012023-08-31031 August 2023
Emergency Preparedness Biennial Exercise Inspection Report 05000454/2023501 and 05000455/2023501
IR 05000454/20230052023-08-30030 August 2023
Updated Inspection Plan for Byron Station (Report 05000454/2023005 and 05000455/2023005)
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
IR 05000454/20230022023-08-0303 August 2023
Integrated Inspection Report 05000454/2023002 and 05000455/2023002
2024-02-02
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Text
4300 Winfield Road Warrenville, IL 60555 630 657 2000 Office Proprietary Information - Withhold from Public Disclosure Under 10 CFR 2.390 RS-22-071 June 7, 2022 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Braidwood Station, Unit 1 Renewed Facility Operating License Nos. NPF-72 NRC Docket No. 50-456 Byron Station, Unit 1 Renewed Facility Operating License Nos. NPF-37 NRC Docket No. 50-454
Subject:
Braidwood and Byron Stations, Unit 1 Steam Generator 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
References:
- 1. Letter from Michael P. Gallagher (Exelon Generation Company, LLC) to U.S. NRC, " Response to NRC Requests for Additional Information, Set 13, dated February 7, 2014 related to the Braidwood Station, Units 1 and 2 and Byron Station, Units 1 and 2 License Renewal Application," dated March 4, 2014 (ML14063A495)
- 2. NUREG-2190, Volume 2, "Safety Evaluation Report Related to the License Renewal of Byron Station, Units 1 and 2, and Braidwood Station, Units 1 and 2," dated December 2015 (ML15350A041)
In accordance with Braidwood Station (Braidwood) and Byron Station (Byron) License Renewal Commitment Number 10, "Steam Generators," Constellation Energy Generation, LLC (CEG) is submitting the following program enhancements to 1) validate that primary water stress corrosion cracking of the divider plate welds to the primary head and tubesheet cladding is not occurring at Braidwood and Byron Unit 1, and 2) validate that primary water stress corrosion cracking of the tube-to-tubesheet welds is not occurring at Braidwood Unit 1 and Byron Unit 1.
Attachments 6 and 7, contain Proprietary Information, hold from Public Disclosure Under 10 CFR 2.390. When separated from this document is decontrolled.
June 7, 2022 U.S. Nuclear Regulatory Commission Page 2 Braidwood and Byron License Renewal Commitment Number 10 part 1) gave the stations three options to fulfill this commitment. Braidwood Unit 1 and Byron Unit 1 have chosen Option 2:
Analysis. This option requires the Braidwood and Byron to:
"Perform an analytical evaluation of the steam generator divider plate welds in order to establish a technical basis which concludes that the steam generator reactor coolant pressure boundary is adequately maintained with the presence of steam generator divider plate weld cracking. This analytical evaluation will be submitted to the NRC for review and approval two (2) years prior to entering the associated period of extended operation."
Braidwood and Byron License Renewal Commitment Number 10 part 2) gave the stations three options to fulfill this commitment. Braidwood Unit 1 and Byron Unit 1 have chosen Option 2:
Analysis - Susceptibility. This option requires the Braidwood and Byron to:
"Perform an analytical evaluation of the steam generator tube-to-tubesheet welds to determine that the welds are not susceptible to primary water stress corrosion cracking. The evaluation for determining that the tube-to-tubesheet welds are not susceptible to primary water stress corrosion cracking will be submitted to the NRC for review and approval two (2) years prior to entering the associated period of extended operation."
The response to Braidwood and Byron License Renewal Commitment Number 10 is subdivided as follows:
- Attachment 1 provides a Summary of Braidwood and Byron, Unit 1 Steam Generator License Renewal for Possible Crack Initiation and Propagation in the Steam Generator Channel Head Assembly.
- Attachment 2 provides the Affidavit for withholding signed by BWXT, the owner of the proprietary information provided in Attachment 7.
- Attachment 3 provides BWXT Canada Report No. M1702-LR-01 Revision 02, EPRI Steam Generator Divider Plate Design for Possibility of Cracking (Non-Proprietary).
- Attachment 4 provides the Affidavit for withholding signed by BWXT, the owner of the proprietary information provided in Attachment 6.
- Attachment 5 provides BWXT Canada Report No. M2004-SR-01-NP Revision 1, " Byron
/ Braidwood Unit 1 Flaw Tolerance Evaluation at Primary Head / Tubesheet / Divider Plate Triple Point Analysis Report (Non-Proprietary).
- Attachment 6 provides BWXT Canada Report No. M2004-SR-01 Revision 1, " Byron /
Braidwood Unit 1 Flaw Tolerance Evaluation at Primary Head / Tubesheet / Divider Plate Triple Point Analysis Report (Proprietary).
Attachments 6 and 7, contain Proprietary Information, hold from Public Disclosure Under 10 CFR 2.390. When separated from this document is decontrolled.
June 7, 2022 U.S. Nuclear Regulatory Commission Page 3
- Attachment 7 provides BWXT Canada Report No. M1702-LR-01 Revision 02, EPRI Steam Generator Divider Plate Design for Possibility of Cracking (Proprietary).
As Attachments 6 and 7 contain information proprietary to BWXT, it is supported by Affidavits signed by BWXT, the owner of the information (Attachments 6 and 7). The Affidavits set forth the basis on which the information may be withheld from public disclosure by the Nuclear Regulatory Commission (NRC) and addresses with specificity the considerations listed in paragraph (b)(4) of 10 CFR 2.390, "Public inspections, exemptions, requests for withholding."
Accordingly, it is respectfully requested that the information that is proprietary to BWXT be withheld from public disclosure in accordance with 10 CFR 2.390.
Approval of the evaluation provided in Attachments 1, 6 and 7 is requested by October 31, 2023, which will support the License Renewal commitment.
This submittal contains no regulatory commitments. Should you have any questions concerning this submittal, please contact Ms. Lisa Zurawski at (630) 657-2816.
Respectfully, Lueshen, Digitally signed by Lueshen, Kevin Kevin Date: 2022.06.07 11:50:28 -05'00' Kevin Lueshen Sr. Manager - Licensing Constellation Energy Generation, LLC Attachments:
- 1) Summary of Braidwood and Byron, Unit 1 Steam Generator License Renewal for Possible Crack Initiation and Propagation in the Steam Generator Channel Head Assembly
- 2) Affidavit for withholding Attachment 7 signed by BWXT
- 3) BWXT Canada Report No M1702-LR-01 Revision 02, EPRI-Steam Generator Divider Plate Design for Possibility of Cracking (Non-Proprietary)
- 4) Affidavit for withholding Attachment 6 signed by BWXT
- 5) BWXT Canada Report No. M2004-SR-01-NP Revision 1, " Byron / Braidwood Unit 1 Flaw Tolerance Evaluation at Primary Head / Tubesheet / Divider Plate Triple Point Analysis Report (Non-Proprietary)
- 6) BWXT Canada Report No. M2004-SR-01 Revision 1, " Byron / Braidwood Unit 1 Flaw Tolerance Evaluation at Primary Head / Tubesheet / Divider Plate Triple Point Analysis Report (Proprietary)
- 7) BWXT Canada Report No M1702-LR-01 Revision 02, EPRI-Steam Generator Divider Plate Design for Possibility of Cracking (Proprietary)
Attachments 6 and 7, contain Proprietary Information, hold from Public Disclosure Under 10 CFR 2.390. When separated from this document is decontrolled.
June 7, 2022 U.S. Nuclear Regulatory Commission Page 4 cc: NRC Regional Administrator, Region III NRC Senior Resident Inspector - Braidwood Station NRC Senior Resident Inspector - Byron Station Illinois Emergency Management Agency - Division of Nuclear Safety Attachments 6 and 7, contain Proprietary Information, hold from Public Disclosure Under 10 CFR 2.390. When separated from this document is decontrolled.
