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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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UNITED STATES WASHINGTON, D.C. 20555-0001 September 25, 2019 Mr. Bryan C. Hanson Senior Vice President Exelon Generation Company, LLC President and Chief Nuclear Officer (CNO)
Exelon Nuclear Braidwood 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
BRAIDWOOD STATION, UNITS 1 AND 2-WITHDRAWAL OF AN AMENDMENT REQUEST {EPID L-2018-LLA-0208)
Dear Mr. Hanson:
By letter dated July 19, 2018 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML18204A169), as supplemented by letters dated October 19, 2018 (ADAMS Accession No. ML18296A288) and May 30, 2019 (ADAMS Accession No.
Ml19150A428), you applied for amendments to the Braidwood Station, Units 1 and 2, Renewed Facility Operating License Nos. NPF-72 and NPF-77. The proposed change would have modified the facility operating licenses to utilize TVEL TVS-K lead test assemblies.
Subsequently, by letter dated August 12, 2019 (ADAMS Accession No. ML19225C054), you withdrew the amendment request.
The U.S. Nuclear Regulatory Commission has filed the enclosed Notice of Withdrawal of Application for Amendment to Facility Operating License with the Office of the Federal Register for publication.
Sincerely, 1
oel S. Wiebe, Sr. Project Manager Plant Licensing Branch Ill Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-456 and 50-457
Enclosure:
Notice of Withdrawal cc: Listserv
ENCLOSURE FEDERAL REGISTER NOTICE
[7590-01-P]
NUCLEAR REGULATORY COMMISSION
[Docket No. 50-456 and 50-457; NRC-2018-0277]
Exelon Generation Company, LLC; Braidwood Station Units 1 and 2 AGENCY: Nuclear Regulatory Commission.
ACTION: License amendment application; withdrawal by applicant.
SUMMARY
- The U.S. Nuclear Regulatory Commission (NRC) has granted the request of Exelon Generation Company, LLC to withdraw its application dated July 19, 2018, as supplemented by letters dated October 19, 2018 and May 30, 2019, for proposed amendments to Renewed Facility Operating License Nos. NPF-72 and NPF-77. The proposed amendment would have modified the renewed facility operating licenses to utilize TVEL TVS-K lead test assemblies.
DATES: [INSERT DATE OF PUBLICATION IN THE FEDERAL REGISTER].
ADDRESSES: Please refer to Docket ID NRC-2018-0277 when contacting the NRC about the availability of information regarding this document. You may obtain publicly-available information related to this document using any of the following methods:
- Federal Rulemaking Web Site: Go to and search for Docket ID NRC-2018-0277. Address questions about NRC dockets IDs in
- ..;.,;
- ;;;.====::...::. to Jennifer Borges; telephone: 301-287-9127; e-mail:
For technical questions, contact the individual listed in the FOR FURTHER INFORMATION CONTACT section of this document.
- NRC's Agencywide Documents Access and Management System (ADAMS): You may obtain publicly-available documents online in the ADAMS Public
search, select " For problems with ADAMS, please contact the NRC's Public Document Room (PDR) reference staff at 1-800-397-4209, The ADAMS accession number for each document referenced (if it is available in ADAMS) is provided the first time that it is mentioned in this document.
- NRC's PDR: You may examine and purchase copies of public documents at the NRC's PDR, Room 01-F21, One White Flint North, 11555 Rockville Pike, Rockville, Maryland 20852.
FOR FURTHER INFORMATION CONTACT: Joel S. Wiebe, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington DC 20555-0001; telephone: 301-415-6606, e-mail: ~il:Y.1l!fil~!illr:~2Y SUPPLEMENTARY INFORMATION:
The NRC has granted the request of Exelon Generation Company, LLC (the licensee) to withdraw its July 19, 2018, application (ADAMS Accession No. ML18204A169), as supplemented by letters dated October 19, 2018 (ADAMS Accession No. ML18296A288), and May 30, 2019 (ADAMS Accession No. Ml19150A428), for proposed amendments to Renewed Facility Operating License Nos. NPF-72 and NPF-77 for the Braidwood Station, Units 1 and 2, located in Dewitt County, Illinois.
The proposed amendments would have added new License Conditions to Appendix C, "Additional Conditions," of the Braidwood Station Renewed Operating Licenses for Units 1 and 2, that authorize the use of up to eight Joint Stock Company TVEL (Fuel Company of Rosatom) TVS-K lead test assemblies in non-limiting reactor core locations for operation and evaluation.
2
The NRC's initial proposed finding of no significant hazards consideration was published in the Federal Register dated January 8, 2019 (84 FR 91).
Dated at Rockville, Maryland, this 25th day of September, 2019.
For the Nuclear Regulatory Commission.
IRA/
Jo.el S. Wiebe, Senior Project Manager, Plant Licensing Branch Ill, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation.
3
SUBJECT:
BRAIDWOOD STATION, UNITS 1 AND 2 - WITHDRAWAL OF AN AMENDMENT REQUEST (EPID L-2018-LLA-0208)
DATED SEPTEMBER 25, 2019 DISTRIBUTION:
PUBLIC PM File Copy RidsACRS_MailCTR Resource RidsNrrDorlDpr Resource RidsNrrDorlLpl3 Resource RidsNrrLASRohrer Resource RidsNrrPMBraidwood Resource RidsRgn3MailCenter Resource ADAMS Accession Nos.:
LTR: ML19260F412 FRN: ML19260F307 OFFICE NRR/D0RL/LPL3/PM NRR/D0RL/LPL3/LA NRR/D0RL/LPL3/BC NRR/D0RL/LPL3/PM NAME JWiebe SRohrer LRegner JWiebe DATE 09/18-19 09/18/19 09/20/19 09/25/19 OFFICIAL AGENCY RECORD