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MONTHYEARRS-10-114, License Amendment Request Regarding Low Temperature Overpressure Protection and Loss of Decay Heat Removal2010-06-29029 June 2010 License Amendment Request Regarding Low Temperature Overpressure Protection and Loss of Decay Heat Removal Project stage: Request ML1021401282010-08-0505 August 2010 Unit Nos.1 and 2 - Supplemental Information Needed for Acceptance of Requested Licensing Action Low Temperature Overpessure Protection Project stage: Acceptance Review RS-10-137, Supplemental Information Supporting License Amendment Request Regarding Low Temperature Overpressure Protection and Loss of Decay Heat Removal2010-08-24024 August 2010 Supplemental Information Supporting License Amendment Request Regarding Low Temperature Overpressure Protection and Loss of Decay Heat Removal Project stage: Supplement ML1024204702010-09-0303 September 2010 Acceptance Review of License Amendment Request Low Temperature Overpressure Protection Project stage: Acceptance Review RS-11-006, Additional Information Supporting Request for License Amendment Regarding Low Temperature Overpressure Protection and Loss of Decay Heat Removal2011-01-13013 January 2011 Additional Information Supporting Request for License Amendment Regarding Low Temperature Overpressure Protection and Loss of Decay Heat Removal Project stage: Request ML11132A1292011-03-17017 March 2011 Transmittal of Ihpb Safety Evaluation, Byron, Units 1 and 2, Braidwood, Units 1 and 2, License Amendment Request Regarding Low Temperature Overpressure Protection and Loss of Decay Heat Removal Project stage: Approval ML1108406572011-06-29029 June 2011 Issuance of Amendments 167, 167, 174 & 174 Low Temperature Overpressure Protection and Loss of Decay Heat Removal Project stage: Approval 2010-09-03
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Category:Acceptance Review Letter
MONTHYEARIR 05000456/20210102021-07-19019 July 2021 Triennial Fire Protection Inspection Report 05000456/2021010 and 05000457/2021010 ML21077A1772021-04-0808 April 2021 Withdrawal of Requested Exemption from Certain Requirement in 10 CFR 50.55a (Epids L-2021-LLE-0014, 0015, & 0016) ML21081A0972021-03-19019 March 2021 Acceptance Review for Byron Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis-External Events (EPID L-2021-JLD-0004) (E-mail) ML21081A0792021-03-19019 March 2021 Acceptance Review for Byron Order EA-12-051, Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation ML20317A3112020-10-30030 October 2020 Acceptance of Requested Licensing Action: Certified Fuel Handler Training and Retraining Program ML17300A2972017-11-0101 November 2017 Non-Acceptance of Relief Request RV-2 Related to Extension of Pressure Relief Valve Testing Intervals (Cac/Epid Nos. 000976/05000454/L-2017-LLR-0091 and 000976/05000455/L-2017-LLR-0091) ML1116804112011-06-17017 June 2011 Acceptance Review for Exelon Threshold Determination Request (TAC ME6269 - ME6287) ML1024204702010-09-0303 September 2010 Acceptance Review of License Amendment Request Low Temperature Overpressure Protection ML1008800852010-07-21021 July 2010 Fleet - Acceptance Review Implementation of Emergency Action Level Schemes Developed from NEI 99-01m Rev. 5 ML1002101352010-01-20020 January 2010 Application Accepted - Braidwood/Byron LAR Re. Astrum Best Estimate LOCA Methodology (ME2941-44) ML0926808512009-09-25025 September 2009 Application Accepted - Braidwood Relief Request I3R-06 Re. Visual Examinations During Appendix J Testing (ME2194-95) ML0926808252009-09-25025 September 2009 Application Accepted - Braidwood Relief Request I3R-05 Re. Testing of H2 Sampling Piping (ME2200-01) ML0926807942009-09-25025 September 2009 Application Accepted - Braidwood Relief Request I3R-03 Re. Qualification Requirements for Examination of Swols (ME2198-99) ML0924700432009-09-0303 September 2009 3 Acceptance Review Results Request to Use Specific Provisions from a Later Edition of the ASME Boiler and Pressure Vessel Code ML0906408762009-03-0606 March 2009 Acceptance of Requested Licensing Action Relief Request 13R-04 ML0900606062009-01-0505 January 2009 Application Accepted - Braidwood Risk-Informed ISI Relief Request I3R-01 (ME0225-26) 2021-07-19
[Table view] 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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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 September 3, 2010 Mr. Michael J. Pacilio President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555 BRAIDWOOD STATION, UNITS 1 AND 2, AND BYRON STATION, UNIT NOS. 1 AND 2 -ACCEPTANCE REVIEW OF LICENSE AMENDMENT REQUEST RE: LOW TEMPERATURE OVERPRESSURE PROTECTION (TAC NOS. ME4194, ME4195, ME4196, AND ME4197)
Dear Mr. Pacilio:
By letter dated June 29, 2010 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 101810069), Exelon Generation Company, LLC (EGC, the licensee) submitted a license amendment request for technical specification changes related to low temperature overpressure protection and loss of decay heat removal. The purpose of this letter is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staff's acceptance review of this amendment request. The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the NRC staff to complete its detailed technical review. The acceptance review is also intended to identify whether the application has any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plant. Consistent with Section 50.90 of Title 10 of the Code of Federal Regulations (10 CFR), an amendment to the license (including the technical specifications) must fully describe the changes requested, and following as far as applicable, the form prescribed for original applications.
Section 50.34 of 10 CFR addresses the content of technical information required.
This section stipulates that the submittal address the design and operating characteristics, unusual or novel design features, and principal safety considerations.
By letter dated August 5,2010 (ADAMS Accession No. ML 102140128), the NRC staff notified EGC of specific supplemental information that needed to be submitted to enable the staff to begin its detailed technical review. By letter dated 24,2010 (ADAMS Accession No. ML 102360663), EGC provided the supplemental information.
The NRC staff has reviewed the supplemental information and concluded that it does provide technical information in sufficient detail to enable the staff to proceed with its detailed technical review and make an independent assessment regarding the acceptability of the proposed amendment in terms of regulatory requirements and the protection of public health and safety and the environment.
On August 27, 2010, your staff was notified of the NRC staff's acceptance of the proposed amendment for detailed technical review. Given the lesser scope and depth of the acceptance review as compared to the detailed technical review, there may be instances in which issues that impact the NRC staff's ability to complete the detailed technical review are identified despite completion of an adequate acceptance review. You will be advised M. Pacilio -2 of any further information needed to support the NRC staff's detailed technical review separate If you have any questions, please contact me at (301)
Sincerely, :ihall J. David, raject Manager Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. STN-456, STN-457, STN 50-454, and STN 50-455 cc: Distribution via Listserv M. Pacilio of any further information needed to support the NRC staffs detailed technical review by separate correspondence.
If you have any questions, please contact me at (301) 415-1547.
Sincerely, IRA! Marshall J. David, Senior Project Manager Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. STN-456, STN-457, STN 50-454, and STN 50-455 cc: Distribution via Listserv DISTRIBUTION PUBLIC RidsOgcRp Resource LPL3-2 RlF RidsAcrsAcnw
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