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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] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 March 23, 2015 Mr. Reid Nelson, Director Office of Federal Agency Programs Advisory Council on Historic Preservation 401 F Street NW, Suite 308 Washington, DC 20001-2637
SUBJECT:
NOTICE OF AVAILABILITY OF THE DRAFT SUPPLEMENTAL ENVIRONMENTAL IMPACT STATEMENT FOR LICENSE RENEWAL OF BRAIDWOOD STATION, UNITS 1 AND 2, FOR PUBLIC COMMENT
Dear Mr. Nelson:
The U.S. Nuclear Regulatory Commission (NRC) is reviewing an application submitted by Exelon Generation Company, LLC, for license renewal of Braidwood Station, Units 1 and 2 (Braidwood). Braidwood is located in Will County, Illinois, approximately 60 miles southwest of Chicago, and 20 miles south-southwest of Joliet, Illinois. As part of its review of the proposed action, the NRC has prepared a draft site-specific Supplemental Environmental Impact Statement (SEIS) to its Generic Environmental Impact Statement for License Renewal of Nuclear Plants, NUREG-1437. The draft SEIS includes analyses of relevant environmental issues, including potential impacts to historic, archeological and cultural properties from extended operation activities associated with license renewal.
As stated in our letter dated August 8, 2013, the NRC has determined that the area of potential effect (APE) for a license renewal action is the area at the power plant site and its immediate environs that may be impacted by post-license renewal land disturbing operation or projected refurbishment activities associated with the proposed action. The NRC views the APE for the Braidwood license renewal as including the Braidwood site and the immediate environs.
In the context of the National Environmental Policy Act of 1969, under which the draft environmental impact statement was prepared, the NRC staffs preliminary determination is that the impact of license renewal on historical and archaeological resources is small, and additional mitigation is not warranted. Under the provisions of the National Historic Preservation Act of 1966, the NRC staffs preliminary determination is that no historic properties will be affected by the proposed action.
In support of this conclusion, the NRC has conducted an environmental audit at the site and performed an independent analysis and review of historic and archaeological records. The NRC also initiated consultation with 14 Federally recognized Native American tribes, notifying them of the proposed action and requesting comments and concerns. Documentation for tribal consultation is presented in Appendix D of the SEIS.
R. Nelson A copy of the draft SEIS with this conclusion is enclosed. Pursuant to 36 CFR 800.8(c), we are requesting your comments on the draft supplement and on our preliminary conclusions.
Electronic comments on the draft SEIS may be submitted to the NRC by accessing www.regulations.gov and searching for Docket ID NRC-2013-0169. Written comments may be mailed to the NRC at:
Cindy Bladey, Chief Rules, Announcements, and Directives Branch (RADB)
Office of Administration, Mail Stop: 3WFN-06-44M U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Please note that the public comment period for the draft SEIS ends on May 12, 2015.
Public meetings to discuss the findings of the draft SEIS will be held on Tuesday, April 21, 2015, at the Godley Park District, 500 Kankakee Street, Braceville, Illinois 60407. The first session will convene at 2:00 p.m. and will continue until 4:00 p.m., as necessary. The second session will convene at 7:00 p.m. and will continue until 9:00 p.m., as necessary. A meeting notice will be published shortly providing more details about those public meetings. A separate Notice of Availability of the draft SEIS will be placed in the Federal Register through the U.S.
Environmental Protection Agency. If you have any questions regarding this matter, please contact Russell Chazell, Environmental Scientist, at 301-415-5003 or by e-mail at Russell.Chazell@nrc.gov.
Sincerely,
/RA/
David J. Wrona, Chief Environmental Review and Guidance Update Branch Division of License Renewal Office of Nuclear Reactor Regulation Docket Nos. 50-456 and 50-457
Enclosures:
- 1. Federal Register Notice
- 2. NUREG-1437, Generic Environmental Impact Statement for License Renewal of Nuclear Plants, Supplement 55 cc w/encls: Listserv
R. Nelson A copy of the draft SEIS with this conclusion is enclosed. Pursuant to 36 CFR 800.8(c), we are requesting your comments on the draft supplement and on our preliminary conclusions.
Electronic comments on the draft SEIS may be submitted to the NRC by accessing www.regulations.gov and searching for Docket ID NRC-2013-0169. Written comments may be mailed to the NRC at:
Cindy Bladey, Chief Rules, Announcements, and Directives Branch (RADB)
Office of Administration, Mail Stop: 3WFN-06-44M U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Please note that the public comment period for the draft SEIS ends on May 12, 2015.
Public meetings to discuss the findings of the draft SEIS will be held on Tuesday, April 21, 2015, at the Godley Park District, 500 Kankakee Street, Braceville, Illinois 60407. The first session will convene at 2:00 p.m. and will continue until 4:00 p.m., as necessary. The second session will convene at 7:00 p.m. and will continue until 9:00 p.m., as necessary. A meeting notice will be published shortly providing more details about those public meetings. A separate Notice of Availability of the draft SEIS will be placed in the Federal Register through the U.S.
Environmental Protection Agency. If you have any questions regarding this matter, please contact Russell Chazell, Environmental Scientist, at 301-415-5003 or by e-mail at Russell.Chazell@nrc.gov.
Sincerely,
/RA/
David J. Wrona, Chief Environmental Review and Guidance Update Branch Division of License Renewal Office of Nuclear Reactor Regulation Docket Nos. 50-456 and 50-457
Enclosures:
- 1. Federal Register Notice
- 2. NUREG-1437, Generic Environmental Impact Statement for License Renewal of Nuclear Plants, Supplement 55 cc w/encls: Listserv DISTRIBUTION:
See next page Adams Accession Number: ML15008A145 *concurred via email OFFICE LA:DLR PM:DLR/RPB2 RERB Technical BC:DLR/RERB Staff Member NAME IBetts TTran RChazell DWrona DATE 1/14/15 3/18/15 3/18/15 3/21/15 OFFICIAL RECORD COPY
SUBJECT:
NOTICE OF AVAILABILITY OF THE DRAFT SUPPLEMENTAL ENVIRONMENTAL IMPACT STATEMENT FOR LICENSE RENEWAL OF BRAIDWOOD STATION, UNITS 1 AND 2, FOR PUBLIC COMMENT DISTRIBUTION:
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