Letter Sequence Response to RAI |
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EPID:L-2022-LLA-0121, Updated Final Safety Analysis Report (Ufsar), Revision 16 and Fire Protection Report (Fpr), Revision 25 (Open) |
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MONTHYEARML21298A2082021-10-21021 October 2021 Updated Final Safety Analysis Report (Ufsar), Revision 16 and Fire Protection Report (Fpr), Revision 25 Project stage: Request RS-22-005, Response to Request for Additional Information for the GNF3 Fuel Transition License Amendment Request2022-01-11011 January 2022 Response to Request for Additional Information for the GNF3 Fuel Transition License Amendment Request Project stage: Response to RAI RS-22-006, Request to Expand Applicability of Prime Methods to Evaluate Fuel Centerline Melt and Cladding Strain Compliance for Framatome Fuel2022-01-20020 January 2022 Request to Expand Applicability of Prime Methods to Evaluate Fuel Centerline Melt and Cladding Strain Compliance for Framatome Fuel Project stage: Request RS-22-028, Supplement to Request to Expand Applicability of Prime Methods to Evaluate Fuel Centerline Melt and Cladding Strain Compliance for Framatome Fuel at Quad Cities2022-03-16016 March 2022 Supplement to Request to Expand Applicability of Prime Methods to Evaluate Fuel Centerline Melt and Cladding Strain Compliance for Framatome Fuel at Quad Cities Project stage: Request RS-22-040, Response to Request for Additional Information Related to the License Amendment Request to Transition to GNF3 Fuel2022-04-11011 April 2022 Response to Request for Additional Information Related to the License Amendment Request to Transition to GNF3 Fuel Project stage: Response to RAI RS-22-065, License Amendment Request Regarding Transition to GNF3 Fuel2022-08-18018 August 2022 License Amendment Request Regarding Transition to GNF3 Fuel Project stage: Request ML22258A1872022-09-13013 September 2022 NRR E-mail Capture - NRC Acceptance Review Dresden, Units 2 and 3, Amendment Request - Transition to GNF3 Fuel Project stage: Acceptance Review ML22335A5652022-12-14014 December 2022 Audit Plan to Support the Review of Licensee'S Information Related to Equipment Qualification License Amendment Request for Transition to GNF3 Fuel Project stage: Other ML23019A0132023-01-12012 January 2023 NRR E-mail Capture - Final RAI Dresden 2 and 3 - License Amendment Pertaining to GNF3 Fuel Transition Project stage: RAI RS-23-004, Response to Request for Additional Information Regarding Transition to GNF3 Fuel License Amendment Request2023-01-23023 January 2023 Response to Request for Additional Information Regarding Transition to GNF3 Fuel License Amendment Request Project stage: Response to RAI ML23088A2242023-04-0505 April 2023 Regulatory Audit Report Regarding License Amendment Request to Transition to GNF3 Fuel Project stage: Other 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 Project stage: Supplement 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 Project stage: Supplement ML23144A3142023-07-0606 July 2023 Issuance of Amendment Nos. 281 and 274 Transition to GNF3 Fuel (EPID L-2022-LLA-0121) - Nonproprietary Project stage: Approval ML23192A6292023-07-11011 July 2023 Correction Letter - Issuance of Amendment Nos. 281 and 274 Regarding Transition to GNF3 Fuel (EPID L-2022-LLA-0121) (Non-Proprietary) Project stage: Approval 2022-09-13
[Table View] |
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Category:Legal-Affidavit
MONTHYEARML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums ML22320A5592022-11-16016 November 2022 2022 Annual Report - Guarantees of Payment of Deferred Premiums RS-22-108, Response to Request for Additional Information LaSalle County Station, Units 1 and 2 and Quad Cities Nuclear Power Station, Units 1 and 2 License Amendments Related to Fuel Storage2022-10-0505 October 2022 Response to Request for Additional Information LaSalle County Station, Units 1 and 2 and Quad Cities Nuclear Power Station, Units 1 and 2 License Amendments Related to Fuel Storage RS-22-090, Response to Request for Additional Information Regarding Quad Cities New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies2022-07-13013 July 2022 Response to Request for Additional Information Regarding Quad Cities New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies RS-22-006, Request to Expand Applicability of Prime Methods to Evaluate Fuel Centerline Melt and Cladding Strain Compliance for Framatome Fuel2022-01-20020 January 2022 Request to Expand Applicability of Prime Methods to Evaluate Fuel Centerline Melt and Cladding Strain Compliance for Framatome Fuel RS-22-005, Response to Request for Additional Information for the GNF3 Fuel Transition License Amendment Request2022-01-11011 January 2022 Response to Request for Additional Information for the GNF3 Fuel Transition License Amendment Request ML21307A0542021-11-0202 November 2021 Annual Report - Guarantees of Payment of Deferred Premiums RS-21-065, License Amendment Request Regarding New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies with Proposed Change to Technical Specifications Section 4.3.12021-10-25025 October 2021 License Amendment Request Regarding New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies with Proposed Change to Technical Specifications Section 4.3.1 ML21272A2772021-09-29029 September 2021 Update to Application for Order Approving License Transfers and Proposed Conforming License Amendments ML21057A2732021-02-25025 February 2021 Application for Order Approving License Transfers and Proposed Conforming License Amendments RS-21-072, Framatome Affidavit for GEXL98 Correlation for Atrium 10 Xm Fuel2021-02-22022 February 2021 Framatome Affidavit for GEXL98 Correlation for Atrium 10 Xm Fuel NMP1L3371, Summary of Changes, Quality Assurance Topical Report, NO-AA-10 & Decommissioning Quality Assurance Program, NO-DC-102021-02-10010 February 2021 Summary of Changes, Quality Assurance Topical Report, NO-AA-10 & Decommissioning Quality Assurance Program, NO-DC-10 ML20310A1152020-11-0404 November 2020 Annual Report - Guarantees of Payment of Deferred Premiums ML19318G1702019-11-14014 November 2019 2019 Annual Report - Guarantees of Payment of Deferred Premiums ML18316A0032018-11-0707 November 2018 Submittal of 2018 Annual Report - Guarantees of Payment of Deferred Premiums RS-16-059, Quad Cities, Units 1 and 2 - Transmittal of Exelon Nuclear Radiological Emergency Plan Addendum Revision2016-03-28028 March 2016 Quad Cities, Units 1 and 2 - Transmittal of Exelon Nuclear Radiological Emergency Plan Addendum Revision ML16088A3992016-03-28028 March 2016 Transmittal of Exelon Nuclear Radiological Emergency Plan Addendum Revision RS-16-062, Additional Information Regarding License Amendment Request for Spent Fuel Storage Pool Criticality Methodology for Fuel Channel Bow/Bulge2016-03-0909 March 2016 Additional Information Regarding License Amendment Request for Spent Fuel Storage Pool Criticality Methodology for Fuel Channel Bow/Bulge RS-16-018, Response to Request for Additional Information Regarding Request for License Amendment Regarding Transition to Areva Fuel2016-01-28028 January 2016 Response to Request for Additional Information Regarding Request for License Amendment Regarding Transition to Areva Fuel ML14321A7052014-11-14014 November 2014 2014 Annual Report - Guarantees of Payment of Deferred Premiums RS-14-238, Transmittal of Proprietary Meeting Slides2014-08-25025 August 2014 Transmittal of Proprietary Meeting Slides ML14204A7092014-07-23023 July 2014 Enclosure 3, Affidavit of Peter M. Yandow RS-14-160, Co. - Submission of Standard Practice Procedure Plans and Foreign Ownership Control or Influence Package2014-07-0202 July 2014 Co. - Submission of Standard Practice Procedure Plans and Foreign Ownership Control or Influence Package ML13044A6642013-01-14014 January 2013 Attachment 3, Areva Np Inc., Affidavit of Gayle F. Elliott RS-12-227, Exelongeneration, Submission of Standard Practice Procedure Plans and Updated Foreign Ownership Control or Influence Package2012-12-19019 December 2012 Exelongeneration, Submission of Standard Practice Procedure Plans and Updated Foreign Ownership Control or Influence Package ML11287A1892011-10-14014 October 2011 Affidavit - Mr. T. Foster ML1127000682011-09-26026 September 2011 Enclosure 3, Mfn 10-245 R4, Affidavit ML1031904262010-11-0808 November 2010 Corp. - 2010 Annual Report - Guarantees of Payment of Deferred Premiums ML0711004532007-04-0404 April 2007 Westinghouse Application for Withholding, Affidavit, and Non-Proprietary Version of Attachment 2 (Attachment 3) ML0606605542006-03-0101 March 2006 Attachment 2 to March 3, 2006, Letter (Affidavit and Non-proprietary Version of Attachment 1) ML0606203832006-02-22022 February 2006 Affidavit and Non-Proprietary Version of Attachment 1 to February 22, 2006, Exelon Letter ML0604603842006-02-0707 February 2006 Affidavit, Quad Cities Replacement Steam Dryer Meeting on November 8 - 9, 2005 ML0606203682006-01-26026 January 2006 Attachment 3 (Technical Specifications) and 4 (Affidavit and Non-Proprietary Version of Attachment 2 to Exelon Letter Dated January 26, 2006) RS-05-176, Affidavit and Attachment 6 to Exelon Letter Dated December 15, 20052005-12-13013 December 2005 Affidavit and Attachment 6 to Exelon Letter Dated December 15, 2005 RS-05-145, Technical Documentation Related to Analysis and Design of New Quad-Cities Steam Dryers, and Responses to Requests for Additional Information Related to EPU Operation at Dresden and Quad-Cities Nuclear Power Stations2005-10-17017 October 2005 Technical Documentation Related to Analysis and Design of New Quad-Cities Steam Dryers, and Responses to Requests for Additional Information Related to EPU Operation at Dresden and Quad-Cities Nuclear Power Stations ML0520003282005-07-14014 July 2005 Surveillance Program for Channel-Control Blade Interference RS-05-061, Response to Request for Additional Information for Review of Quad Cities Replacement Steam Dryer2005-05-12012 May 2005 Response to Request for Additional Information for Review of Quad Cities Replacement Steam Dryer RS-05-055, Technical Documentation Related to Analysis and Design of New Quad Cities Steam Dryers, and Responses to Requests for Additional Information Related to EPU Operation at Dresden and Quad Cities Nuclear Power Stations2005-05-0606 May 2005 Technical Documentation Related to Analysis and Design of New Quad Cities Steam Dryers, and Responses to Requests for Additional Information Related to EPU Operation at Dresden and Quad Cities Nuclear Power Stations RS-05-059, General Electric Technical Documents Related to Analysis and Design of New Quad Cities Steam Dryers, and Responses to Requests for Additional Information Related to EPU Operation at Dresden and Quad Cities Nuclear Power Stations2005-05-0606 May 2005 General Electric Technical Documents Related to Analysis and Design of New Quad Cities Steam Dryers, and Responses to Requests for Additional Information Related to EPU Operation at Dresden and Quad Cities Nuclear Power Stations RS-05-053, Technical Documentation Related to Analysis and Design of New Quad Cities Steam Dryers, and Responses to Requests for Additional Information Related to EPU Operation at Dresden and Quad Cities Nuclear Power Stations2005-04-28028 April 2005 Technical Documentation Related to Analysis and Design of New Quad Cities Steam Dryers, and Responses to Requests for Additional Information Related to EPU Operation at Dresden and Quad Cities Nuclear Power Stations RS-05-040, Technical Documentation Related to Analysis and Design of New Quad Cities Steam Dryers, and Responses to Requests for Additional Information Related to EPU Operation at Dresden and Quad Cities Nuclear Power Stations2005-04-0101 April 2005 Technical Documentation Related to Analysis and Design of New Quad Cities Steam Dryers, and Responses to Requests for Additional Information Related to EPU Operation at Dresden and Quad Cities Nuclear Power Stations ML0504505642005-01-26026 January 2005 Affidavit of David J. Robare Dated January 26, 2005 ML0408900452004-03-16016 March 2004 Core Operating Limits Report for Quad Cities Unit 2, Cycle 18, Revision 0 2023-11-10
[Table view] Category:Letter type:RS
MONTHYEARRS-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-23-104, 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-23-113, 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-23-097, 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-23-089, Sixth Ten-Year Interval Inservice Testing Program2023-09-0505 September 2023 Sixth Ten-Year Interval Inservice Testing Program 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-23-077, 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-23-060, 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-23-042, 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-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-23-049, 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-23-007, 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 RS-23-032, Application to Move SR 3.5.1.2 Note to LCO 3.5.1 in Accordance with TSTF-416, LPCI Valve Alignment Verification Note Location2023-02-0303 February 2023 Application to Move SR 3.5.1.2 Note to LCO 3.5.1 in Accordance with TSTF-416, LPCI Valve Alignment Verification Note Location RS-23-034, Notification of Extension to the Fifth Ten-Year Interval of the Inservice Testing Program2023-02-0202 February 2023 Notification of Extension to the Fifth Ten-Year Interval of the Inservice Testing Program RS-23-003, Constellation Energy Generation, LLC, Summary of Changes to Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-102023-01-31031 January 2023 Constellation Energy Generation, LLC, Summary of Changes to Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-10 RS-23-033, Request for Exemption from 10 CFR 2.109(b)2023-01-27027 January 2023 Request for Exemption from 10 CFR 2.109(b) RS-23-005, Response to Request for Additional Information for Quad Cities Relief Request RV-04, Inservice Testing of High Pressure Coolant Injection Drain Pot Solenoid Valves2023-01-17017 January 2023 Response to Request for Additional Information for Quad Cities Relief Request RV-04, Inservice Testing of High Pressure Coolant Injection Drain Pot Solenoid Valves RS-22-127, Submittal of Sixth Inservice Inspection Interval Relief Request I6R-10 Reactor Pressure Vessel Penetration N-11B Repair2022-12-14014 December 2022 Submittal of Sixth Inservice Inspection Interval Relief Request I6R-10 Reactor Pressure Vessel Penetration N-11B Repair RS-22-126, Constellation Energy Generation, LLC - Request to Use Provisions of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI2022-11-30030 November 2022 Constellation Energy Generation, LLC - Request to Use Provisions of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI RS-22-119, Withdrawal of Relief Request RV-11 Associated with the Sixth Inservice Testing Interval2022-10-31031 October 2022 Withdrawal of Relief Request RV-11 Associated with the Sixth Inservice Testing Interval RS-22-109, Response to Request for Additional Information License Amendments Related to Fuel Storage2022-10-12012 October 2022 Response to Request for Additional Information License Amendments Related to Fuel Storage RS-22-112, Submittal of RV-04 Relief Request Associated with the Sixth Inservice Testing Interval2022-10-0707 October 2022 Submittal of RV-04 Relief Request Associated with the Sixth Inservice Testing Interval RS-22-108, Response to Request for Additional Information LaSalle County Station, Units 1 and 2 and Quad Cities Nuclear Power Station, Units 1 and 2 License Amendments Related to Fuel Storage2022-10-0505 October 2022 Response to Request for Additional Information LaSalle County Station, Units 1 and 2 and Quad Cities Nuclear Power Station, Units 1 and 2 License Amendments Related to Fuel Storage RS-22-092, Nine and Quad Cities - Application to Revise Primary Containment Isolation Instrumentation Technical Specifications in Accordance with TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration2022-10-0303 October 2022 Nine and Quad Cities - Application to Revise Primary Containment Isolation Instrumentation Technical Specifications in Accordance with TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration RS-22-102, Supplement to Request to Revise Technical Specification 3.1.4, Control Rod Scam Times2022-08-18018 August 2022 Supplement to Request to Revise Technical Specification 3.1.4, Control Rod Scam Times RS-22-093, Advisement of Leadership Changes for Constellation Energy Generation, LLC and Submittal of Updated Standard Practice Procedures Plans2022-08-18018 August 2022 Advisement of Leadership Changes for Constellation Energy Generation, LLC and Submittal of Updated Standard Practice Procedures Plans RS-22-095, Response to Request for Additional Information Regarding Request to Expand Applicability of GNF Thermal Mechanical Analysis Methods to Framatome Fuel2022-08-10010 August 2022 Response to Request for Additional Information Regarding Request to Expand Applicability of GNF Thermal Mechanical Analysis Methods to Framatome Fuel RS-22-096, Response to Request for Additional Information Related to Relief Request I6R-01 Associated with the Sixth Inservice Inspection Interval2022-08-10010 August 2022 Response to Request for Additional Information Related to Relief Request I6R-01 Associated with the Sixth Inservice Inspection Interval RS-22-098, Response to Request for Additional Information for Quad Cities Relief Request RV-11, Code Case OMN-282022-08-0101 August 2022 Response to Request for Additional Information for Quad Cities Relief Request RV-11, Code Case OMN-28 RS-22-094, Submittal of Sixth Inservice Inspection Interval Relief Request I6R-09 to Permit Continued Application of Certain ASME Section XI 2013 Edition Non-Destructive Examination Requirements2022-07-25025 July 2022 Submittal of Sixth Inservice Inspection Interval Relief Request I6R-09 to Permit Continued Application of Certain ASME Section XI 2013 Edition Non-Destructive Examination Requirements RS-22-090, Response to Request for Additional Information Regarding Quad Cities New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies2022-07-13013 July 2022 Response to Request for Additional Information Regarding Quad Cities New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies RS-22-077, Response to Request for Additional Information for Quad Cities Relief Requests RV-08, Safety Relief Valves2022-06-30030 June 2022 Response to Request for Additional Information for Quad Cities Relief Requests RV-08, Safety Relief Valves RS-22-078, Response to Request for Additional Information for Quad Cities Relief Request RV-09, MSSVs2022-06-30030 June 2022 Response to Request for Additional Information for Quad Cities Relief Request RV-09, MSSVs RS-22-080, Withdrawal and Proposed Alternative I6R-08 Associated with Code Case N-921 for Sixth Inservice Inspection Intervals2022-06-0909 June 2022 Withdrawal and Proposed Alternative I6R-08 Associated with Code Case N-921 for Sixth Inservice Inspection Intervals RS-22-069, Constellation Nuclear Radiological Emergency Plan Addendum Revision. Includes EP-AA-1006, Addendum 3, Revision 10, Emergency Action Levels for Quad Cities Station2022-05-25025 May 2022 Constellation Nuclear Radiological Emergency Plan Addendum Revision. Includes EP-AA-1006, Addendum 3, Revision 10, Emergency Action Levels for Quad Cities Station RS-22-059, CFR50.46 Annual Report2022-05-0404 May 2022 CFR50.46 Annual Report RS-22-056, Constellation Radiological Emergency Plan Addendum Revision2022-04-21021 April 2022 Constellation Radiological Emergency Plan Addendum Revision RS-22-054, Withdrawal of Relief Request RV-10 Associated with the Sixth Inservice Testing Interval2022-04-13013 April 2022 Withdrawal of Relief Request RV-10 Associated with the Sixth Inservice Testing Interval RS-22-051, Constellation Energy Generation, LLC - Update to Correspondence Addressees and Service Lists2022-04-12012 April 2022 Constellation Energy Generation, LLC - Update to Correspondence Addressees and Service Lists RS-22-040, Response to Request for Additional Information Related to the License Amendment Request to Transition to GNF3 Fuel2022-04-11011 April 2022 Response to Request for Additional Information Related to the License Amendment Request to Transition to GNF3 Fuel RS-22-049, Constellation Energy Generation, LLC, Supplemental Information to Correct Typographical Errors in Constellation'S Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for2022-04-0404 April 2022 Constellation Energy Generation, LLC, Supplemental Information to Correct Typographical Errors in Constellation'S Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for V RS-22-030, Submittal of Relief Request Associated with the Sixth Inservice Inspection Interval2022-03-25025 March 2022 Submittal of Relief Request Associated with the Sixth Inservice Inspection Interval RS-22-045, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2022-01, Preparation and Scheduling of Operator Licensing Examinations2022-03-25025 March 2022 Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2022-01, Preparation and Scheduling of Operator Licensing Examinations 2024-01-03
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARRS-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-23-068, 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-23-005, Response to Request for Additional Information for Quad Cities Relief Request RV-04, Inservice Testing of High Pressure Coolant Injection Drain Pot Solenoid Valves2023-01-17017 January 2023 Response to Request for Additional Information for Quad Cities Relief Request RV-04, Inservice Testing of High Pressure Coolant Injection Drain Pot Solenoid Valves ML23012A0832023-01-12012 January 2023 Response to Request for Additional Information for Alternative I6R-09 to Permit Continued Application of Certain ASME Section XI 2013 Edition Non-Destructive Examination Requirements RS-22-109, Response to Request for Additional Information License Amendments Related to Fuel Storage2022-10-12012 October 2022 Response to Request for Additional Information License Amendments Related to Fuel Storage RS-22-108, Response to Request for Additional Information LaSalle County Station, Units 1 and 2 and Quad Cities Nuclear Power Station, Units 1 and 2 License Amendments Related to Fuel Storage2022-10-0505 October 2022 Response to Request for Additional Information LaSalle County Station, Units 1 and 2 and Quad Cities Nuclear Power Station, Units 1 and 2 License Amendments Related to Fuel Storage RS-22-095, Response to Request for Additional Information Regarding Request to Expand Applicability of GNF Thermal Mechanical Analysis Methods to Framatome Fuel2022-08-10010 August 2022 Response to Request for Additional Information Regarding Request to Expand Applicability of GNF Thermal Mechanical Analysis Methods to Framatome Fuel RS-22-096, Response to Request for Additional Information Related to Relief Request I6R-01 Associated with the Sixth Inservice Inspection Interval2022-08-10010 August 2022 Response to Request for Additional Information Related to Relief Request I6R-01 Associated with the Sixth Inservice Inspection Interval RS-22-098, Response to Request for Additional Information for Quad Cities Relief Request RV-11, Code Case OMN-282022-08-0101 August 2022 Response to Request for Additional Information for Quad Cities Relief Request RV-11, Code Case OMN-28 RS-22-090, Response to Request for Additional Information Regarding Quad Cities New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies2022-07-13013 July 2022 Response to Request for Additional Information Regarding Quad Cities New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies RS-22-078, Response to Request for Additional Information for Quad Cities Relief Request RV-09, MSSVs2022-06-30030 June 2022 Response to Request for Additional Information for Quad Cities Relief Request RV-09, MSSVs RS-22-077, Response to Request for Additional Information for Quad Cities Relief Requests RV-08, Safety Relief Valves2022-06-30030 June 2022 Response to Request for Additional Information for Quad Cities Relief Requests RV-08, Safety Relief Valves RS-22-040, Response to Request for Additional Information Related to the License Amendment Request to Transition to GNF3 Fuel2022-04-11011 April 2022 Response to Request for Additional Information Related to the License Amendment Request to Transition to GNF3 Fuel RS-22-027, Constellation, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated2022-02-23023 February 2022 Constellation, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated P NMP1L3447, Constellation Energy Generation, LLC - Response to Request for Additional Information - Proposed Relief Request Associated with Reactor Pressure Vessel Water Level Instrumentation Partial Penetration Nozzle Repairs2022-02-0202 February 2022 Constellation Energy Generation, LLC - Response to Request for Additional Information - Proposed Relief Request Associated with Reactor Pressure Vessel Water Level Instrumentation Partial Penetration Nozzle Repairs RS-22-005, Response to Request for Additional Information for the GNF3 Fuel Transition License Amendment Request2022-01-11011 January 2022 Response to Request for Additional Information for the GNF3 Fuel Transition License Amendment Request RS-21-113, Response to Supplemental Request for Information Related to Request for Licensing Amendment Regarding Transition to GNF3 Fuel2021-11-0303 November 2021 Response to Supplemental Request for Information Related to Request for Licensing Amendment Regarding Transition to GNF3 Fuel JAFP-21-0087, Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments2021-09-16016 September 2021 Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments RS-21-078, Response to Request for Additional Information for Application to Revise Technical Specification to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements, and TSTF-583-T, TSTF-582 Diesel2021-08-19019 August 2021 Response to Request for Additional Information for Application to Revise Technical Specification to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements, and TSTF-583-T, TSTF-582 Diesel JAFP-21-0044, Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments2021-06-11011 June 2021 Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments JAFP-21-0032, Response to Request for Additional Information - Proposed Alternative Concerning ASME Section XI Repair/Replacement Documentation for Replacement of Pressure Retaining Bolting2021-04-20020 April 2021 Response to Request for Additional Information - Proposed Alternative Concerning ASME Section XI Repair/Replacement Documentation for Replacement of Pressure Retaining Bolting RS-20-112, Response to Request for Additional Information Related to License Amendment Request to Adopt TSTF-5682020-09-0303 September 2020 Response to Request for Additional Information Related to License Amendment Request to Adopt TSTF-568 RS-20-008, Response to Request for Additional Information for the License Amendment Request to Change Technical Specifications to Increase Allowable MSIV Leakage Rates and Revise Secondary Containment.2020-02-24024 February 2020 Response to Request for Additional Information for the License Amendment Request to Change Technical Specifications to Increase Allowable MSIV Leakage Rates and Revise Secondary Containment. JAFP-19-0057, Response to Request for Additional Information - Proposed Alternative to Utilize Code Cases N-878 and N-8802019-06-0404 June 2019 Response to Request for Additional Information - Proposed Alternative to Utilize Code Cases N-878 and N-880 NMP1L3279, Response to Request for Additional Information - Proposed Alternatives to Utilize Code Cases N-878 and N-880 for Plants2019-05-0101 May 2019 Response to Request for Additional Information - Proposed Alternatives to Utilize Code Cases N-878 and N-880 for Plants JAFP-19-0006, Response to Request for Additional Information - Proposed Alternative to Utilize Code Cases N-878 and N-8802019-01-0808 January 2019 Response to Request for Additional Information - Proposed Alternative to Utilize Code Cases N-878 and N-880 RS-18-143, Supplemental Information Supporting License Amendment Requests for Approval of Changes to Emergency Plan Staffing Requirements2018-11-29029 November 2018 Supplemental Information Supporting License Amendment Requests for Approval of Changes to Emergency Plan Staffing Requirements RS-18-097, Response to Request for Additional Information and Supplemental Information-License Amendment.2018-07-27027 July 2018 Response to Request for Additional Information and Supplemental Information-License Amendment. RS-18-061, Response to Request for Additional Information Regarding Decommissioning Funding Plans for Independent Spent Fuel Storage Installations (Isfsis)2018-05-0202 May 2018 Response to Request for Additional Information Regarding Decommissioning Funding Plans for Independent Spent Fuel Storage Installations (Isfsis) RS-18-004, Additional Information Supporting Reactor Pressure Vessel Penetration N-11B Repair Relief Request I5R-112018-01-0404 January 2018 Additional Information Supporting Reactor Pressure Vessel Penetration N-11B Repair Relief Request I5R-11 RS-17-130, Additional Information Regarding Request for License Amendment to Revise Technical Specifications Section 5.5.12 for Permanent Extension of Type a and Type C Leak Rate Test Frequencies2017-09-28028 September 2017 Additional Information Regarding Request for License Amendment to Revise Technical Specifications Section 5.5.12 for Permanent Extension of Type a and Type C Leak Rate Test Frequencies RS-17-111, Additional Information Regarding Request for License Amendment to Revise Technical Specifications Section 5.5.12 for Permanent Extension of Type a and Type C Leak Rate Test Frequencies2017-07-27027 July 2017 Additional Information Regarding Request for License Amendment to Revise Technical Specifications Section 5.5.12 for Permanent Extension of Type a and Type C Leak Rate Test Frequencies RS-17-041, Response to Request for Additional Information Regarding Request for License Amendment to Revise Loss of Voltage Relay Settings2017-04-24024 April 2017 Response to Request for Additional Information Regarding Request for License Amendment to Revise Loss of Voltage Relay Settings RS-17-044, Response to Request for Additional Information Regarding Proposed Alternative for the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography2017-03-13013 March 2017 Response to Request for Additional Information Regarding Proposed Alternative for the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography RS-16-254, Supplemental Information Regarding Request for License Amendment to Revise Technical Specifications Section 5.5.12 for Permanent Extension of Type a and Type C Leak Rate Test Frequencies2016-12-15015 December 2016 Supplemental Information Regarding Request for License Amendment to Revise Technical Specifications Section 5.5.12 for Permanent Extension of Type a and Type C Leak Rate Test Frequencies RS-16-244, Additional Information Regarding Request for License Amendment to Address Secondary Containment Access Openings2016-12-12012 December 2016 Additional Information Regarding Request for License Amendment to Address Secondary Containment Access Openings RS-16-229, Supplemental Information Regarding Request for License Amendment to Revise Loss of Voltage Relay Settings2016-11-21021 November 2016 Supplemental Information Regarding Request for License Amendment to Revise Loss of Voltage Relay Settings RS-16-159, County, and Quad Cities - Response to Request for Additional Information Regarding License Amendment to Address Secondary Containment Access Openings2016-07-28028 July 2016 County, and Quad Cities - Response to Request for Additional Information Regarding License Amendment to Address Secondary Containment Access Openings RS-16-131, Additional Information Regarding License Amendment Request for Spent Fuel Storage Pool Criticality Methodology for Fuel Channel Bow/Bulge2016-06-0101 June 2016 Additional Information Regarding License Amendment Request for Spent Fuel Storage Pool Criticality Methodology for Fuel Channel Bow/Bulge RA-16-049, Response to Request for Additional Information Regarding Requests to Withhold Emergency Preparedness Documents from Public Disclosure2016-05-26026 May 2016 Response to Request for Additional Information Regarding Requests to Withhold Emergency Preparedness Documents from Public Disclosure RS-16-105, Supplemental Information in Support of Request for License Amendment Regarding Transition to Areva Fuel2016-04-26026 April 2016 Supplemental Information in Support of Request for License Amendment Regarding Transition to Areva Fuel RS-16-077, Response to Request for Additional Information Regarding Request for License Amendment to Reduce the Reactor Steam Dome Pressure Specified in the Technical Specification 2.1.1, Reactor Core Sls.2016-04-14014 April 2016 Response to Request for Additional Information Regarding Request for License Amendment to Reduce the Reactor Steam Dome Pressure Specified in the Technical Specification 2.1.1, Reactor Core Sls. RS-16-044, High Frequency Supplement to Seismic Hazard Screening Report, Response to NRC Request for Information, Per 10CFR50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima..2016-02-19019 February 2016 High Frequency Supplement to Seismic Hazard Screening Report, Response to NRC Request for Information, Per 10CFR50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima.. RS-16-018, Response to Request for Additional Information Regarding Request for License Amendment Regarding Transition to Areva Fuel2016-01-28028 January 2016 Response to Request for Additional Information Regarding Request for License Amendment Regarding Transition to Areva Fuel RS-15-274, Supplemental Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Flooding Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2015-10-28028 October 2015 Supplemental Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Flooding Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident RS-15-258, County, and Quad Cities - Response to Request for Additional Information Regarding License Amendment Request Adding Technical Specification for Inservice Leak and Hydrostatic Testing Operation2015-09-29029 September 2015 County, and Quad Cities - Response to Request for Additional Information Regarding License Amendment Request Adding Technical Specification for Inservice Leak and Hydrostatic Testing Operation RS-12-149, Response to Request for Additional Information Regarding Relief Requests Associated with the Fifth Inservice Testing Interval2012-09-13013 September 2012 Response to Request for Additional Information Regarding Relief Requests Associated with the Fifth Inservice Testing Interval ML17238A7511973-08-31031 August 1973 Quad-Cities Stations Units 1 and 2 - 10 CFR 50, Appendix J 2024-01-03
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4300 Winfield Road Warrenville, IL 60555 630 657 2000 Office PROPRIETARY INFORMATION - WITHHOLD UNDER 10 CFR 2.390 RS-22-005 10 CFR 50.90 January 11, 2022 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Quad Cities Nuclear Power Station, Units 1 and 2 Renewed Facility Operating License Nos. DPR-29 and DPR-30 NRC Docket Nos. 50-254 and 50-265
Subject:
Response to Request for Additional Information for the GNF3 Fuel Transition License Amendment Request
References:
- 1. Letter from P.R. Simpson (Exelon Generation Company, LLC) to U.S. Nuclear Regulatory Commission, "Request for Licensing Amendment Regarding Transition to GNF3 Fuel," dated September 14, 2021 (ML21257A419)
- 2. Letter from P.R. Simpson (Exelon Generation Company, LLC) to U.S. Nuclear Regulatory Commission, "Response to Supplemental Request for Information Related to Request for Licensing Amendment Regarding Transition to GNF3 Fuel," dated November 3, 2021 (ML21307A444)
- 3. Email from B. Venkataraman (U.S. Nuclear Regulatory Commission) to R.
Steinman (Exelon Generation Company, LLC),
Subject:
Request For Additional Information: Quad Cities 1 & 2 License Amendment Request Re: Transition To GNF3 Fuel (EPID: L-2021-LLA-0159), dated December 8, 2021 (ML21342A384)
In the Reference 1 letter, Exelon Generation Company, LLC, (EGC) requested an amendment to Renewed Facility Operating License Nos. DPR-29 for Quad Cities Nuclear Power Station (QCNPS), Unit 1 and DPR-30 for QCNPS, Unit 2. The proposed changes support the transition from Framatome (formerly AREVA) ATRIUM 10XM fuel to Global Nuclear Fuel - Americas, LLC (GNF-A) GNF3 fuel at QCNPS. One aspect of the fuel transition is the use of the GEXL98 correlation for modeling ATRIUM 10XM using General Electric Company (GE) safety analysis methodologies.
Attachment 4 contains Proprietary Information. Withhold from public disclosure under 10 CFR 2.390. When separated from Attachment 4, this document is decontrolled.
January 11, 2022 U.S. Nuclear Regulatory Commission Page 2 contains the response to the GEXL98 correlation related request for additional information (RAI) in Reference 3. Attachments 4a and 4b contain information proprietary to GNF-A and Framatome, respectively. These data tables are proprietary in their entirety.
Redacted versions of these documents would not be meaningful; therefore, no redacted versions are provided. This document is supported by signed affidavits from the owners of the information, which are included in Attachments 2 and 3, respectively. Each affidavit sets forth the basis on which the corporations information may be withheld from public disclosure by the 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, which is proprietary to GNF-A and Framatome be withheld from public disclosure.
EGC has reviewed the information supporting the finding of no significant hazards consideration, and the environmental consideration that were previously provided to the NRC in References 1 and 2. The additional information provided in this submittal does not affect the bases for concluding that the proposed license amendment does not involve a significant hazards consideration. In addition, the information provided in this submittal does not affect the bases for concluding that neither an environmental impact statement nor an environmental assessment needs to be prepared in connection with the proposed amendment.
EGC is notifying the State of Illinois of this supplement to a previous application for a change to the operating license by sending a copy of this letter and its attachments to the designated State Official in accordance with 10 CFR 50.91, "Notice for public comment; State consultation,"
paragraph (b).
There are no regulatory commitments contained within this letter.
Should you have any questions concerning this letter, please contact Ms. Rebecca L. Steinman at (630) 657-2831.
I declare under penalty of perjury that the foregoing is true and correct. Executed on the 11th day of January 2022.
Respectfully, Patrick Simpson Sr Manager Licensing Exelon Generation Company, LLC Attachments:
- 1. Response to NRC Request for Additional Information
- 2. GNF-A 10 CFR 2.390 Affidavit for Withholding for Attachment 4a
- 3. Framatome 10 CFR 2.390 Affidavit for Withholding for Attachment 4b
January 11, 2022 U.S. Nuclear Regulatory Commission Page 3
- 4. Tabular Summary of GEXL98 Uncertainty Data
- a. GNF Document No. 006N9118 (142 pages) (Proprietary version)
- b. GNF Document No. 006N9119 (142 pages) (Proprietary version) cc: NRC Regional Administrator, Region III NRC Senior Resident Inspector, Quad Cities Nuclear Power Station Illinois Emergency Management Agency - Division of Nuclear Safety
ATTACHMENT 1 Response to NRC Request for Additional Information Regulatory Basis General Design Criterion (GDC) 10, Reactor design, in Title 10 of the Code of Federal Regulations (10 CFR) Part 50, Appendix A, is the principal regulation associated with this report. This criterion introduces the concept of specified acceptable fuel design limits (SAFDLs).
In essence, SAFDLs are those limits placed on certain variables to ensure that the fuel does not fail. One such SAFDL is associated with critical power performance. Because the decrease in heat transfer following critical power could result in fuel failure, a SAFDL is used to demonstrate that critical power does not occur during normal operation and anticipated operational occurrences (AOO)s. Therefore, fuel failure is precluded during normal operation and AOOs.
NRC staff Standard Review Plan (NUREG 0800, Section 4.4) includes the SAFDLs used in accounting for the uncertainties involved in developing and predicating critical power performance model and ensuring that fuel failure is precluded:
At least 99.9 percent of the fuel rods in the core will not experience a critical power during normal operation or AOOs.
In order to determine that the GEXL98 correlation for ATRIUM 10XM can satisfy the associated SAFDL, the NRC staff requests the following additional information.
SFNB-GEXL-RAI-1 Provide the data used to determine the GEXL98 uncertainty in tabular form. This data should include all relevant inputs (e.g., pressure, mass flux, inlet subcooling, R-factor, thermal diameter, boiling length, annular length) as well as all relevant outputs (e.g., GEXL calculated Critical Power, ACE-Calculated Critical Power).
Response to SFNB-GEXL-RAI-1 The requested data has been organized by the vendor into two attachments to facilitate separation of fuel vendor proprietary content. In both cases the numerical values associated with each parameter/case combination are proprietary. a contains the following information.
Case: Case identification number [#], and for each case:
Rf: GEXL R-factor ECPR: Ratio of GEXL calculated to ACE calculated critical power BL: Boiling length [inches]
ANL: Annular flow length [inches]
Xc: GEXL calculated critical quality MTML: GEXL calculated minimum thermal margin location [inches]
Page 1 of 2
ATTACHMENT 1 Response to NRC Request for Additional Information LimitingRod: Fuel rod that is predicted to experience dryout at the fuel assembly critical power by GEXL correlation [#]1 Database: Identifier for data usage 1 - GEXL98 statistical database 2 - very low mass flux database, excluded from GEXL98 statistics 3 - part length rod database, excluded from GEXL98 statistics The geometric inputs (Thermal Diameter, Hydraulic Diameter, Active Channel Flow Area, Heated Length) for all cases are those documented in NEDC-33930P Table 2-2, "ATRIUM 10 XM Modeling Dimensions." b contains the following information.
Case: Case identification number [#], and for each:
Press: Exit pressure [kPa]
MFlow: Inlet flow rate [kg/s]
SubC: Inlet subcooling [kJ/kg]
APS: Label identifying bundle axial power shape C - Cosine Peaked B - Bottom Peaked T - Top Peaked D - Double-Humped Peaked Qc: ACE calculated critical power [kW]
ReqRod: Fuel rod that the specific pin peaking map was designed to peak [#]1 LimitingRod: Fuel rod that is predicted to experience dryout at the fuel assembly critical power by ACE correlation [#]1 1 Rod identification consistent with NEDC-33930P Figure 2-1, "ATRIUM 10XM Assembly Rod Numbering System."
Page 2 of 2
ATTACHMENT 2 GNF-A 10 CFR 2.390 Affidavit for Withholding for Attachment 4a
Global Nuclear Fuel - Americas AFFIDAVIT I, Kent Halac, state as follows:
(1) I am a Senior Engineer, Regulatory Affairs, Global Nuclear Fuel - Americas, LLC (GNF-A), and have been delegated the function of reviewing the information described in paragraph (2) which is sought to be withheld, and have been authorized to apply for its withholding.
(2) The information sought to be withheld is contained in Revision 1 of Attachment 1 of Response to SFNB-GEXL-RAI-1" dated January 11, 2022. The content of Attachment 1 is proprietary in its entirety. The header of each page carries the notation GNF Proprietary Information - Non-Public. Paragraph (3) of this affidavit provides the basis for the proprietary determination.
(3) In making this application for withholding of proprietary information of which it is the owner or licensee, GNF-A relies upon the exemption from disclosure set forth in the Freedom of Information Act (FOIA), 5 USC Sec. 552(b)(4), and the Trade Secrets Act, 18 USC Sec. 1905, and NRC regulations 10 CFR 9.17(a)(4), and 2.390(a)(4) for trade secrets (Exemption 4). The material for which exemption from disclosure is here sought also qualify under the narrower definition of trade secret, within the meanings assigned to those terms for purposes of FOIA Exemption 4 in, respectively, Critical Mass Energy Project v. Nuclear Regulatory Commission, 975 F2d 871 (DC Cir. 1992), and Public Citizen Health Research Group v. FDA, 704 F2d 1280 (DC Cir. 1983).
(4) Some examples of categories of information which fit into the definition of proprietary information are:
- a. Information that discloses a process, method, or apparatus, including supporting data and analyses, where prevention of its use by GNF-A's competitors without license from GNF-A constitutes a competitive economic advantage over other companies;
- b. Information which, if used by a competitor, would reduce his expenditure of resources or improve his competitive position in the design, manufacture, shipment, installation, assurance of quality, or licensing of a similar product;
- c. Information which reveals aspects of past, present, or future GNF-A customer-funded development plans and programs, resulting in potential products to GNF-A;
- d. Information which discloses patentable subject matter for which it may be desirable to obtain patent protection.
The information sought to be withheld is considered to be proprietary for the reasons set forth in paragraphs (4)a. and (4)b. above.
Rev. 1 of Attachment 1 of Response to SFNB-GEXL-RAI-1 Page 1 of 3
(5) To address 10 CFR 2.390 (b) (4), the information sought to be withheld is being submitted to NRC in confidence. The information is of a sort customarily held in confidence by GNF-A, and is in fact so held. The information sought to be withheld has, to the best of my knowledge and belief, consistently been held in confidence by GNF-A, no public disclosure has been made, and it is not available in public sources. All disclosures to third parties including any required transmittals to NRC, have been made, or must be made, pursuant to regulatory provisions or proprietary agreements which provide for maintenance of the information in confidence. Its initial designation as proprietary information, and the subsequent steps taken to prevent its unauthorized disclosure, are as set forth in paragraphs (6) and (7) following.
(6) Initial approval of proprietary treatment of a document is made by the manager of the originating component, the person most likely to be acquainted with the value and sensitivity of the information in relation to industry knowledge, or subject to the terms under which it was licensed to GNF-A.
(7) The procedure for approval of external release of such a document typically requires review by the staff manager, project manager, principal scientist or other equivalent authority, by the manager of the cognizant marketing function (or his delegate), and by the Legal Operation, for technical content, competitive effect, and determination of the accuracy of the proprietary designation. Disclosures outside GNF-A are limited to regulatory bodies, customers, and potential customers, and their agents, suppliers, and licensees, and others with a legitimate need for the information, and then only in accordance with appropriate regulatory provisions or proprietary agreements.
(8) The information identified in paragraph (2) is classified as proprietary because it contains details of GNF-As fuel design and licensing methodology. The development of this methodology, along with the testing, development and approval was achieved at a significant cost to GNF-A.
The development of the fuel design and licensing methodology along with the interpretation and application of the analytical results is derived from an extensive experience database that constitutes a major GNF-A asset.
(9) Public disclosure of the information sought to be withheld is likely to cause substantial harm to GNF-A's competitive position and foreclose or reduce the availability of profit-making opportunities. The information is part of GNF-A's comprehensive BWR safety and technology base, and its commercial value extends beyond the original development cost. The value of the technology base goes beyond the extensive physical database and analytical methodology and includes development of the expertise to determine and apply the appropriate evaluation process. In addition, the technology base includes the value derived from providing analyses done with NRC-approved methods.
The research, development, engineering, analytical, and NRC review costs comprise a substantial investment of time and money by GNF-A.
Rev. 1 of Attachment 1 of Response to SFNB-GEXL-RAI-1 Page 2 of 3
The precise value of the expertise to devise an evaluation process and apply the correct analytical methodology is difficult to quantify, but it clearly is substantial.
GNF-A's competitive advantage will be lost if its competitors are able to use the results of the GNF-A experience to normalize or verify their own process or if they are able to claim an equivalent understanding by demonstrating that they can arrive at the same or similar conclusions.
The value of this information to GNF-A would be lost if the information were disclosed to the public. Making such information available to competitors without their having been required to undertake a similar expenditure of resources would unfairly provide competitors with a windfall, and deprive GNF-A of the opportunity to exercise its competitive advantage to seek an adequate return on its large investment in developing and obtaining these very valuable analytical tools.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on this 11th day of January 2022.
Kent Halac Senior Engineer, Regulatory Affairs Global Nuclear Fuel - Americas, LLC 3901 Castle Hayne Road Wilmington, NC 28401 Kent.Halac@ge.com Rev. 1 of Attachment 1 of Response to SFNB-GEXL-RAI-1 Page 3 of 3
ATTACHMENT 3 Framatome 10 CFR 2.390 Affidavit for Withholding for Attachment 4b
AFFI DAVIT
- 1. My name is Morris Byram. I am Product Manager, Licensing & Regulatory Affairs for Framatome Inc. (Framatome) and as such I am authorized to execute this Affidavit.
- 2. I am familiar with the criteria applied by Framatome to determine whether certain Framatome information is proprietary. I am familiar with the policies established by Framatome to ensure the proper application of these criteria.
- 3. I am familiar with the Framatome information contained in Attachment 4 to Exelon letter RS-22-005 dated January 11, 2022, with subject Response to Request for Additional Information for the GNF3 Fuel Transition License Amendment Request and referred to herein as Document. Information contained in this Document has been classified by Framatome as proprietary in accordance with the policies established by Framatome for the control and protection of proprietary and confidential information.
- 4. This Document contains information of a proprietary and confidential nature and is of the type customarily held in confidence by Framatome and not made available to the public. Based on my experience, I am aware that other companies regard information of the kind contained in this Document as proprietary and confidential.
- 5. This Document has been made available to the U.S. Nuclear Regulatory Commission in confidence with the request that the information contained in this Document be withheld from public disclosure. The request for withholding of proprietary information is made in accordance with 10 CFR 2.390. The information for which withholding from disclosure is requested qualifies under 10 CFR 2.390(a)(4) Trade secrets and commercial or financial information.
- 6. The following criteria are customarily applied by Framatome to determine whether information should be classified as proprietary:
(a) The information reveals details of Framatomes research and development plans and programs or their results.
(b) Use of the information by a competitor would permit the competitor to significantly reduce its expenditures, in time or resources, to design, produce, or market a similar product or service.
(c) The information includes test data or analytical techniques concerning a process, methodology, or component, the application of which results in a competitive advantage for Framatome.
(d) The information reveals certain distinguishing aspects of a process, methodology, or component, the exclusive use of which provides a competitive advantage for Framatome in product optimization or marketability.
(e) The information is vital to a competitive advantage held by Framatome, would be helpful to competitors to Framatome, and would likely cause substantial harm to the competitive position of Framatome.
The information in this Document is considered proprietary for the reasons set forth in paragraphs 6(c), 6(d), and 6(e) above.
- 7. In accordance with Framatomes policies governing the protection and control of information, proprietary information contained in this Document has been made available, on a limited basis, to others outside Framatome only as required and under suitable agreement providing for nondisclosure and limited use of the information.
- 8. Framatome policy requires that proprietary information be kept in a secured file or area and distributed on a need-to-know basis.
- 9. The foregoing statements are true and correct to the best of my knowledge, information, and belief.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on: (1/11/2022)
BYRAM Morris Digitally signed by BYRAM Morris Date: 2022.01.11 11:57:06 -08'00' (NAME) morris.byram@framatome.com