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Category:Letter type:RS
MONTHYEARRS-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
RS-24-001, Response to Request for Additional Information Regarding Relief Request I5R-26, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval2024-01-0303 January 2024
Response to Request for Additional Information Regarding Relief Request I5R-26, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval
RS-23-128, Response to Request for Additional Information for the Emergency License Amendment Request Increase Technical Specifications Completion Time in TS 3.8.1.B.4 from 7 Days to 30 Days2023-12-15015 December 2023
Response to Request for Additional Information for the Emergency License Amendment Request Increase Technical Specifications Completion Time in TS 3.8.1.B.4 from 7 Days to 30 Days
RS-23-123, Emergency License Amendment Request - Increase Technical Specifications Completion Time in TS 3.8.1.B.4 from 7 Days to 30 Days2023-12-13013 December 2023
Emergency License Amendment Request - Increase Technical Specifications Completion Time in TS 3.8.1.B.4 from 7 Days to 30 Days
RS-23-121, Sixth Ten-Year Interval Inservice Testing Program2023-11-30030 November 2023
Sixth Ten-Year Interval Inservice Testing Program
RS-23-104, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-11-17017 November 2023
Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation
RS-23-120, 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
RS-23-119, 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
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
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
RS-23-107, Relief Request I5R-22, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval2023-11-0808 November 2023
Relief Request I5R-22, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval
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
RS-23-113, Submittal of Updated Final Safety Analysis Report (Ufsar), Revision 17 and Fire Protection Report (Fpr), Revision 262023-10-20020 October 2023
Submittal of Updated Final Safety Analysis Report (Ufsar), Revision 17 and Fire Protection Report (Fpr), Revision 26
RS-23-102, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-10-16016 October 2023
Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation
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-23-103, 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
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.
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
RS-23-089, Sixth Ten-Year Interval Inservice Testing Program2023-09-0505 September 2023
Sixth Ten-Year Interval Inservice Testing Program
RS-23-071, Application to Adopt TSTF-564, Safety Limit MCPR2023-08-30030 August 2023
Application to Adopt TSTF-564, Safety Limit MCPR
RS-23-080, Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs2023-08-30030 August 2023
Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs
RS-23-086, Relief Request I5R-26, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval2023-08-28028 August 2023
Relief Request I5R-26, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval
RS-23-087, Revision to Approved Alternatives Associated with the Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements on Reactor2023-08-0404 August 2023
Revision to Approved Alternatives Associated with the Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements on Reactor
RS-23-084, Response to Request for Additional Information Regarding the Application to Revise Design Basis to Allow Use of Plastic Section Properties in Lower Downcomer Braces Analysis2023-07-24024 July 2023
Response to Request for Additional Information Regarding the Application to Revise Design Basis to Allow Use of Plastic Section Properties in Lower Downcomer Braces Analysis
RS-23-083, Withdrawal - Proposed Alternatives Related to the Steam Generators2023-06-27027 June 2023
Withdrawal - Proposed Alternatives Related to the Steam Generators
RS-23-078, Supplement to License Amendment Request to Revise Technical Specification 3.1.4, Control Rod Scram Times2023-06-16016 June 2023
Supplement to License Amendment Request to Revise Technical Specification 3.1.4, Control Rod Scram Times
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
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-23-060, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors2023-06-0808 June 2023
Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors
RS-23-059, License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2023-06-0808 June 2023
License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b
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-23-042, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2023-05-25025 May 2023
Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling
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.
RS-23-070, Supplement to License Amendment Request Regarding Transition to GNF3 Fuel2023-05-16016 May 2023
Supplement to License Amendment Request Regarding Transition to GNF3 Fuel
RS-22-067, 10 CFR 50.46 Annual Report2023-05-0404 May 2023
10 CFR 50.46 Annual Report
RS-23-068, Response to Request for Additional Information for Quad Cities Relief Request I6R-11, Proposed Alternatives for a Temper Bead Weld Repair of the Mating Surfaces of the Reactor Pressure Vessel Head and Shell2023-04-28028 April 2023
Response to Request for Additional Information for Quad Cities Relief Request I6R-11, Proposed Alternatives for a Temper Bead Weld Repair of the Mating Surfaces of the Reactor Pressure Vessel Head and Shell
RS-23-058, Submittal of Sixth Inservice Inspection Interval Relief Request I6R-11 Proposed Alternatives for a Temper Bead Weld Repair of the Mating Surfaces of the Reactor Pressure Vessel Head and Shell Flanges2023-04-24024 April 2023
Submittal of Sixth Inservice Inspection Interval Relief Request I6R-11 Proposed Alternatives for a Temper Bead Weld Repair of the Mating Surfaces of the Reactor Pressure Vessel Head and Shell Flanges
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-23-057, Supplement to License Amendment Request Regarding Transition to GNF3 Fuel2023-04-17017 April 2023
Supplement to License Amendment Request Regarding Transition to GNF3 Fuel
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
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
RS-23-041, Response to Request for Additional Information for Alternative Request RV-23H2023-03-14014 March 2023
Response to Request for Additional Information for Alternative Request RV-23H
RS-23-048, Exigent Amendment Request to Revise Design Basis Related to Seismic Requirements2023-03-0707 March 2023
Exigent Amendment Request to Revise Design Basis Related to Seismic Requirements
RS-23-007, Application to Adopt TSTF-564, Safety Limit MCPR2023-03-0303 March 2023
Application to Adopt TSTF-564, Safety Limit MCPR
RS-23-045, Constellation Energy Generation, LLC Submittal of Fitness for Duty Performance Data Reports for 2022 Per 10 CFR 26.717(c) & 10 CFR 26.2032023-02-28028 February 2023
Constellation Energy Generation, LLC Submittal of Fitness for Duty Performance Data Reports for 2022 Per 10 CFR 26.717(c) & 10 CFR 26.203
2024-01-03
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Text
SAFEGUARDS INFORMATION Exelnt.
Exelon Generation 4300 Winfield Road www exeloncorp corn Nuclear Warrenville, IL 60555 RS-03-016 January 27, 2003 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Braidwood Station, Units I and 2 Facility Operating License Nos. NPF-72 and NPF-77 NRC Docket Nos. 50-456 and 50-457 Byron Station, Units 1 and 2 Facility Operating License Nos. NPF-37 and NPF-66 NRC Docket Nos. 50-454 and 50-455 Dresden Nuclear Power Station, Units 2 and 3 Facility Operating License Nos. DPR-19 and DPR-25 NRC Docket Nos. 50-237 and 50-249 LaSalle County Station, Units 1 and 2 Facility Operating License Nos. NPF-1 1 and NPF-18 NRC Docket Nos. 50-373 and 50-374 Limerick Generating Station, Units I and 2 Facility Operating License Nos. NPF-39 and NPF-85 NRC Docket Nos. 50-352 and 50-353 Peach Bottom Atomic Power Station, Units 2 and 3 Facility Operating License Nos. DPR-44 and DPR-56 NRC Docket Nos. 50-277 and 50-278 Quad Cities Nuclear Power Station, Units 1 and 2 Facility Operating License Nos. DPR-29 and DPR-30 NRC Docket Nos. 50-254 and 50-265
Subject:
Response to Commission Order to Modify License for Compensatory Measures Related to Access Authorization
Reference:
Letter from U. S. NRC, "Issuance of Order for Compensatory Measures Related to Access Authorization," dated January 7, 2003 SAFEGUARDS INFORMATION The Attachment Contains Safeguards Information 7/
Upon Separation This Page Is Decontrolled
SAFEGUARDS INFORMATION January 27, 2003 U. S. Nuclear Regulatory Commission Page 2 In accordance with 10 CFR 50.4, Exelon Generation Company, LLC (Exelon),
hereby submits its response to the Order for Compensatory Measures Related to Access Authorization (Order) issued by the NRC in the referenced letter.
Attachment A to this response contains Safeguards Information that must be protected from public disclosure pursuant to 10 CFR 73.21, "Requirements for the Protection of Safeguards Information." Exelon therefore requests that the Enclosure be withheld from public disclosure.
Pursuant to the requirements of 10 CFR 2.202(a)(2), the Answer to the Order is being transmitted to the NRC under separate cover.
Should you have any questions concerning this letter, please contact Patrick Simpson at (630) 657-2823.
Respectfully, Vice President - Licensing and Regulatory Affairs
Enclosure:
Attachment A - Response to Order SAFEGUARDS INFORMATION The Attachment Contains Safeguards Information Upon Separation This Page Is Decontrolled
SAFEGUARDS INFORMATION STATE OF ILLINOIS The above-subscribed individual appeared before me and made oath that he is duly authorized to execute this response on behalf of Exelon Generation Company, LLC, the statements contained within this response are true to the best of his knowledge and belief, and that copies of the response were sent to the addressee and listed individuals.
Before me, OFFICIAL SEAL Motary Publics E r ANESE L. GRIGSBY NOTARY PUBLIC, STATE OF ILLINOIS My Commission Expires: ,Y//,3 lnop My COMMISSION EXPIRES 3-13-2005 CC:
Secretary (without attachment) U.S. Nuclear Regulatory Commission Office of the Secretary ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 ATTN: Rulemakings and Adjudications Staff (signed original and three copies)
Washington, DC 20555-0001 U. S. Nuclear Regulatory Commission Regional Administrator - Region III Samuel J. Collins, Director U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation 801 Warrenville Road Mail Stop O-5E7 Lisle, IL 60532-4351 Rockville, MD 20852-2738 (two copies)
(via overnight delivery)
U. S. Nuclear Regulatory Commission Regional Administrator - Region I ATTN: Mr. Glenn Tracy U.S. Nuclear Regulatory Commission Mail Stop 04A1 5 475 Allendale Road One White Flint North King of Prussia, PA 19406 11555 Rockville Pike (two copies) Rockville, MD 20852-2738 (via overnight delivery)
Assistant General Counsel for Materials Litigation and Enforcement (without attachment)
U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 SAFEGUARDS INFORMATION The Attachment Contains Safeguards Information Upon Separation This Paqe Is Decontrolled
UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION In the Matter of )
)
Exelon Generation Company, LLC )
) Docket Nos. 50-456 Braidwood Station, Units 1 and 2; ) 50-457 NPF-72 and NPF-77 ) 50-454
) 50-455 Byron Station, Units 1 and 2; ) 50-237 NPF-37 and NPF-66 ) 50-249
) 50-373 Dresden Nuclear Power Station, ) 50-374 Units 2 and 3; ) 50-352 DPR-19 and DPR-25 ) 50-353
) 50-277 LaSalle County Station, Units 1 and 2; ) 50-278 NPF-11 and NPF-18 ) 50-254
) 50-265 Limerick Generating Station, Units 1 and 2; )
NPF-39 and NPF-85 )
)
Peach Bottom Atomic Power Station, )
Units 2 and 3; )
DPR-44 and DPR-56 )
)
Quad Cities Nuclear Power Station, )
Units 1 and 2; DPR-29 and DPR-30 )
)
LICENSEE'S ANSWER TO JANUARY 7,2003 COMMISSION ORDER TO MODIFY LICENSE FOR COMPENSATORY MEASURES RELATED TO ACCESS AUTHORIZATION On January 7, 2003, the Nuclear Regulatory Commission ("NRC" or "Commission")
issued an immediately effective order in the captioned matter entitled Order Modifying Licenses (Effective Immediately) ("Order") to, inter alia, Exelon Generation Company, LLC ("Exelon").
The Order stated that following September 11, 2001, the Commission took a number of actions, including the commencement of a comprehensive review of its safeguards and security programs and requirements. The Commission stated its determination that operating power reactor licensees be required to implement certain compensatory measures as prudent measures to improve access authorization. Therefore, the NRC stated it was imposing requirements as set forth in Attachment 2 of the Order.' Exelon, has responded to the substantive requirements of the Order by letter dated January 27, 2003, in accordance with the provisions of 10 CFR 50.4, as 2
directed by the Order.
1 Attachment 2 contained Safeguards Information and was not publicly released.
2 The enclosure to that letter was transmitted as Safeguards Information.
In accordance with Section IV of the Order and pursuant to 10 CFR 2.202, Exelon consents to the Order.
Respectfully, Vice President - Licensing and Regulatory Affairs STATE OF ILLINOIS The above-subscribed individual appeared before me on this 27th day of January, 2003 and made oath that he is duly authorized to execute this Answer on behalf of Exelon Generation Company, LLC and the statements contained within this Answer are true to the best of his knowledge, information and belief.
Before me, Notary Public d G My Commission Expires: 3//'3/0,y OFFICIAL SEAL ANESE L.GRIGSBY NOTARY PUBLIC, STATE OF ILLINOIS MY COMMISSION EXPIRES 3.13-2005
UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION In the Matter of )
)
Exelon Generation Company, LLC )
) Docket Nos. 50456 Braidwood Station, Units 1 and 2; ) 50-457 NPF-72 and NPF-77 ) 50-454
) 50-455 Byron Station, Units 1 and 2; ) 50-237 NPF-37 and NPF-66 ) 50-249
) 50-373 Dresden Nuclear Power Station, ) 50-374 Units 2 and 3; ) 50-352 DPR-19 and DPR-25 ) 50-353
) 50-277 LaSalle County Station, Units 1 and 2; ) 50-278 NPF-11 and NPF-18 ) 50-254
) 50-265 Limerick Generating Station, Units 1 and 2; )
NPF-39 and NPF-85 )
)
Peach Bottom Atomic Power Station, )
Units 2 and 3; )
DPR-44 and DPR-56 )
)
Quad Cities Nuclear Power Station, )
Units 1 and 2; DPR-29 and DPR-30 )
)
CERTIFICATE OF SERVICE I hereby certify that copies of the ANSWER TO JANUARY 7, 2003, COMMISSION ORDER TO MODIFY LICENSE FOR COMPENSATORY MEASURES RELATED TO ACCESS AUTHORIZATION in the captioned action have been served on the following by deposit in the United States mail, first class, or by overnight delivery, as indicated by an asterisk (*), this 27th day of January 2003.
Secretary U. S. Nuclear Regulatory Commission*
Office of the Secretary Samuel J. Collins, Director U. S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation ATTN: Rulemakings and Adjudications Staff Mail Stop O-5E7 Washington, DC 20555-0001 One White Flint North 11555 Rockville Pike Rockville, MD 20852-2738 U. S. Nuclear Regulatory Commission ATTN: U. S. Nuclear Regulatory Commission Document Control Desk ATTN: Mr. Glenn Tracy Washington, DC 20555-0001 Mail Stop 04A15 (signed original and three copies) One White Flint North 11555 Rockville Pike Rockville, MD 20852-2738 Regional Administrator - Region I Regional Administrator - Region III U. S. Nuclear Regulatory Commission U. S. Nuclear Regulatory Commission 475 Allendale Road 801 Warrenville Road King of Prussia, PA 19406 Lisle, IL 60532-4351 (two copies) (two copies)
Assistant General Counsel for Materials Litigation and Enforcement U. S. Nuclear Regulatory Commission Washington, DC 20555-0001 Jef y B nja*n i eP ent, Licensing and Rfi latory Affairs STATE OF ILLINOIS The above-subscribed individual appeared before me this 27th day of January, 2003 and made oath that he is duly authorized to serve this Answer on behalf of Exelon Generation Company, LLC, and has done so the best of his knowledge, information and belief.
Before me, Notary Public- d My Commission Expires: 1Z,3J106 ANESE L.GRIGSBYSEAL I NO TARY PUBLIC. STATE OF ILLINOIS OFFICIAL WCOMMISSION EXPIRES 3-13-2005 m~-
2-
