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| * Review and Status Update | | * Review and Status Update |
| *Schedule | | *Schedule |
| *Questions | | *Questions 1 ~ Exelon Generation |
| .,,,__
| |
| 1 ~ Exelon Generation | |
|
| |
|
| === | | === |
Line 125: |
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| . [ | | . [ |
| ] | | ] |
| ,,,,_,
| |
| 5 ~ ExelonGeneration. | | 5 ~ ExelonGeneration. |
|
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Line 137: |
Line 134: |
| [ | | [ |
| ] | | ] |
| ,,,,,.,.,
| |
| 6 ~ Exelon Generation | | 6 ~ Exelon Generation |
|
| |
|
Line 152: |
Line 148: |
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| -....(1S 4> | | -....(1S 4> |
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Line 398: |
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| CJ | | CJ |
| * IO | | * IO |
| .-!
| |
|
| |
|
| Critical Power Correlation for OPTIMA2 | | Critical Power Correlation for OPTIMA2 |
| * Overall additive constant uncertainty is determined using the indirect method defined in EMF-2245PA I | | * Overall additive constant uncertainty is determined using the indirect method defined in EMF-2245PA I |
| ,__,.,
| |
| J 16 ~ Exelon Generation | | J 16 ~ Exelon Generation |
|
| |
|
Line 438: |
Line 376: |
| ] | | ] |
| * Bounds of the [ ] correlation for application to OPTIMA2 conservatively set to the more limiting of the range of the approved [ | | * Bounds of the [ ] correlation for application to OPTIMA2 conservatively set to the more limiting of the range of the approved [ |
| ] correlation and the range of data in the OPTIMA2 critical power database | | ] correlation and the range of data in the OPTIMA2 critical power database 20 ~ Exelon Generation |
| ,,,,_,
| |
| 20 ~ Exelon Generation | |
|
| |
|
| Critical Power Correlation for OPTIMA2 | | Critical Power Correlation for OPTIMA2 |
Line 459: |
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| .[ | | .[ |
| ] | | ] |
| ,.._,
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| 23 ~ Exelon Generation. | | 23 ~ Exelon Generation. |
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Line 471: |
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| . [ | | . [ |
| ] | | ] |
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| 24 ~ Exelon Generation | | 24 ~ Exelon Generation |
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Line 488: |
Line 422: |
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Line 470: |
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| |
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Line 624: |
Line 522: |
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| | c |
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| |
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| |
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| |
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| |
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| * 0 C') | | * 0 C') |
Line 658: |
Line 550: |
| w t1, N | | w t1, N |
| cc | | cc |
| :E | | :E I-Q. |
| -
| |
| I- | |
| ......
| |
| Q. | |
| 0 0 | | 0 0 |
| c | | c |
| *-
| |
| ..., 0 | | ..., 0 |
| -.. ca Q) | | -.. ca Q) |
Line 674: |
Line 561: |
| -ca co E | | -ca co E |
| E ........ | | E ........ |
| *-*-...,..
| |
| (.) | | (.) |
| :J Cf) * | | :J Cf) * |
Line 698: |
Line 584: |
| - Status and schedule for release of the draft and final SRP revision for reactivity insertion accidents | | - Status and schedule for release of the draft and final SRP revision for reactivity insertion accidents |
| * Use of 230 cal/gram as the appropriate upper limit for coolability | | * Use of 230 cal/gram as the appropriate upper limit for coolability |
| * LAR approach to be used depends on schedule for issuance of the revised SRP | | * LAR approach to be used depends on schedule for issuance of the revised SRP 33 ~ Exelon Generation |
| ,,,,_,
| |
| 33 ~ Exelon Generation | |
|
| |
|
| May 19, 2014 Pre-Submittal Meeting Summary | | May 19, 2014 Pre-Submittal Meeting Summary |
Line 716: |
Line 600: |
| * Westinghouse provided response to NRC request regarding eva luation of TCD using Westinghouse methods in letter LTR-NRC-12-18, dated February 17, 2012. | | * Westinghouse provided response to NRC request regarding eva luation of TCD using Westinghouse methods in letter LTR-NRC-12-18, dated February 17, 2012. |
| * Westinghouse LOCA analyses for Dresden and Quad Cities use methods as discussed in letter LTR-NRC-12-18. TCD is accounted for in these analyses. | | * Westinghouse LOCA analyses for Dresden and Quad Cities use methods as discussed in letter LTR-NRC-12-18. TCD is accounted for in these analyses. |
| ..._,
| |
| 35 ~ Exelon Generation | | 35 ~ Exelon Generation |
|
| |
|
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| c: | | c: |
| 0 Cf) z 0 | | 0 Cf) z 0 |
| -
| |
| lnLJ.J | | lnLJ.J |
| => | | => |
| O'}} | | O'}} |
Letter Sequence Request |
---|
|
|
MONTHYEARML13225A7492013-08-12012 August 2013 NRR E-mail Capture - Slide Deck for Exelon Pre-Submittal Meeting Project stage: Request ML13193A0482013-08-14014 August 2013 Notice of Forthcoming Meeting with Exelon Generation Company, LLC (EGC) Regarding Areva Xm Fuel Transition Request for Dresden and Quad Cities Nuclear Stations Project stage: Meeting ML13238A1882013-08-26026 August 2013 8/27/2013 - Notice of Forthcoming Meeting with Exelon Generation Company, LLC (Egc)Regarding Areva Xm Fuel Transition Request for Dresden and Quad Cities Nuclear Stations Project stage: Meeting ML14232A7852014-05-19019 May 2014 Fuel Transition License Amendment Request Pre-Submittal Update Meeting Project stage: Meeting ML14219A2822014-08-0707 August 2014 Notice of Forthcoming Meeting with Exelon Generation Company, LLC (EGC) Regarding Areva Xm Fuel Transition Request for Dresden and Quad Cities Nuclear Stations Project stage: Meeting RS-14-238, Transmittal of Proprietary Meeting Slides2014-08-25025 August 2014 Transmittal of Proprietary Meeting Slides Project stage: Request ML14241A6332014-09-11011 September 2014 Summary of August 23, 2014, Meeting with Exelon Generation Company, LLC Regarding Areva Xm Fuel Transition Request for Dresden and Quad Cities Nuclear Station Project stage: Meeting ML14226B0122014-09-11011 September 2014 May 19, 2014 Summary of Meeting with Exelon Generation Company, LLC Regarding Areva Xm Fuel Transition for Dresden and Quad Cities Nuclear Stations Project stage: Meeting ML14246A5762014-09-17017 September 2014 Request for Withholding Proprietary Information from Public Disclosure (TAC Nos. MF2422, MF2423, MF2424, and MF2425) Project stage: Other ML14254A1532014-09-22022 September 2014 8/19/2014, Summary of Closed Meeting with Exelon Generation Company, LLC, Regarding Areva Am Fuel Transition for Dresden and Quad Cities Nuclear Stations Project stage: Meeting 2014-08-25
[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 ML16088A3992016-03-28028 March 2016 Transmittal of Exelon Nuclear Radiological Emergency Plan Addendum Revision 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 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 RS-14-310, License Amendment Request Regarding Spent Fuel Storage Pool Criticality Methodology and Proposed Change to Technical Specification 4.3.1, Criticality2014-12-30030 December 2014 License Amendment Request Regarding Spent Fuel Storage Pool Criticality Methodology and Proposed Change to Technical Specification 4.3.1, Criticality 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-05-059, 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-05-055, 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-05-053, 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 SVPLTR 04-0020, Core Operating Limits Report for Unit 3 Cycle 18A, Revision 1, and General Electric Affidavit2004-04-30030 April 2004 Core Operating Limits Report for Unit 3 Cycle 18A, Revision 1, and General Electric Affidavit 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-24-073, Alternative Schedule to Complete Decommissioning Beyond 60 Years of Permanent Cessation of Operations – Additional Information Supporting Request to Withhold Security-Related Information2024-07-31031 July 2024 Alternative Schedule to Complete Decommissioning Beyond 60 Years of Permanent Cessation of Operations – Additional Information Supporting Request to Withhold Security-Related Information RS-24-070, Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 and 2, Quad Cities, Units 1 and 2, R. E. Ginna - Nuclear Radiological Emergency Plan Document Revisions2024-07-12012 July 2024 Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 and 2, Quad Cities, Units 1 and 2, R. E. Ginna - Nuclear Radiological Emergency Plan Document Revisions RS-24-061, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-06-14014 June 2024 Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations RS-24-063, Response to Request for Additional Information for 10 CFR 50.55a Request No. I5R-222024-06-14014 June 2024 Response to Request for Additional Information for 10 CFR 50.55a Request No. I5R-22 RS-24-053, Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed2024-06-0606 June 2024 Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed RS-24-056, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors2024-05-28028 May 2024 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors RS-24-055, 2023 Corporate Regulatory Commitment Change Summary Report2024-05-17017 May 2024 2023 Corporate Regulatory Commitment Change Summary Report RS-24-042, Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion2024-05-10010 May 2024 Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion RS-24-046, 10 CFR 50.46 Annual Report2024-05-0606 May 2024 10 CFR 50.46 Annual Report RS-24-041, Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-04-30030 April 2024 Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests 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-23-119, 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-23-107, 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-23-113, 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-23-097, 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-23-071, Application to Adopt TSTF-564, Safety Limit MCPR2023-08-30030 August 2023 Application to Adopt TSTF-564, Safety Limit MCPR 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-23-078, 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-23-059, 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-23-060, 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-23-042, 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-23-070, 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-23-057, 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-23-049, 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-23-007, 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-23-004, 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 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-22-121, Notice of Intent to Pursue Subsequent License Renewal Applications2022-11-0909 November 2022 Notice of Intent to Pursue Subsequent License Renewal Applications RS-22-117, Response to Request for Additional Information License Amendment Request Regarding New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies2022-11-0303 November 2022 Response to Request for Additional Information License Amendment Request Regarding New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies RS-22-116, Submittal of Relief Requests Associated with the Sixth Inservice Testing Interval2022-11-0101 November 2022 Submittal of Relief Requests Associated with the Sixth Inservice Testing Interval 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 2024-07-31
[Table view] Category:Meeting Briefing Package/Handouts
MONTHYEARML24232A2052024-08-12012 August 2024 Presentation Slides for Dresden End-of-Cycle Meeting ML24172A1092024-08-0707 August 2024 Scoping Power Point Presentation ML24029A1742024-01-30030 January 2024 Constellation Pre-Application January 30, 2024, Meeting Slides - Proposed Alternative to Utilize Code Case N-932, Alternative Requirements for Acceptance of Containment Base Metal Corrosion or Erosion ML23317A0712023-11-14014 November 2023 NRC Pre-Submittal Meeting on November 14th, 2023 - TSTF-591 and Selected 50.69 License Condition Updates (EPID L-2023-LLM-0098) (Slides) ML23255A1042023-08-11011 August 2023 Slides - Constellation - Pre-Application EP 9/18/2023 Draft CEG Presubmittal SG Performance Monitoring Plan Meeting Handout ML23173A0472023-06-28028 June 2023 SLRA - NRC Presubmittal Meeting Slides - 6-28-23 ML23173A0462023-06-28028 June 2023 DNPS SLR Pre-submittal Meeting Presentation Rev. 1 ML23145A1322023-06-27027 June 2023 June 27, 2023, Dresden Nuclear Power Station Subsequent License Renewal Environmental Pre-application Public Meeting - Constellation Slides ML23165A0242023-06-27027 June 2023 June 27, 2023, Dresden Nuclear Power Station Subsequent License Renewal Environmental Pre-application Public Meeting - NRC Slides ML23055A2712023-03-0202 March 2023 March 2, 2023, Preapplication Meeting to Discuss Planned Amendments to Adopt TSTF-505 and 10 CFR 50.69 (EPID L-2023-LRM-0007) - Slides ML21314A4472021-11-10010 November 2021 Slides for Presubmittial Meeting for Proposed Alternative to Adopt ASME Code Case N-921 to Extend the Inservice Inspection Interval ML21194A1822021-07-13013 July 2021 and Quad Cities Nuclear Generating Stations 2020 Annual Assessment Meeting Slides ML20258A0302020-09-22022 September 2020 Decommissioning Licensing Action Submittal Plan for Byron and Dresden Stations Early Shutdowns ML20261G7322020-09-16016 September 2020 Pre-Submittal Slides Extend 120-month Isi/Ist Interval Under 50.55a ML20238B8572020-08-25025 August 2020 Quad 2019 Hq Online EOC Slides ML20178A4202020-06-30030 June 2020 NEI Slides for June 30, 2020, Public Meeting on COVID-19 Response ML20170B0212020-06-23023 June 2020 NRC Pre-Submittal Meeting Byron Unit 2 One-Time Deferral of Reactor Pressure Vessel Head Penetration Nozzle (Rpvhpn) Inspections ML20163A6552020-06-16016 June 2020 6-16-20 Byron Unit 2 Steam Generator License Amendment Request Pre-Submittal Meeting (NRC) - Byron Unit 2 LAR for One-Time Deferral of Steam Generator Inspections ML20169A5592020-06-16016 June 2020 Steam Generator License Amendment Request Pre-Submittal Meeting (NRC) - Byron Unit 2 LAR for One-Time Deferral of Steam Generator Inspections (Rev 1) ML19318F9512019-11-20020 November 2019 Presentation Slides for November 20, 2019, Pre-Application Meeting - Request for Revision to Quality Assurance Program Internal Audit Frequency ML19161A2572019-06-0404 June 2019 BWR Fleet Msv/Srv - Testing Frequency Relief Request NRC Pre-Application Meeting June 4, 2019 ML19151A6602019-05-31031 May 2019 BWR Fleet Mssv/Srv Testing Frequency Relief Request NRC Pre-Application Meeting June 4, 2019 ML19022A2002019-01-23023 January 2019 Request for Use of ASME Code Case N-879 for Exelon Nuclear Power Plants ML18347B3142018-12-19019 December 2018 Bwrvip/Asme Relief Request Discussion December 19, 2018 ML18334A2162018-11-30030 November 2018 Presentation Slides: Exelon BWR MSIV (Boiling-Water Reactor - Main Steam Isolation Valve) Leakage Optimization for NRC Pre-Submittal Meeting of December 6, 2018 ML18319A1272018-11-19019 November 2018 Slides for 11/19/18 Public Meeting - Exelon Fleet LAR for Common Language for TS 5.7 High Radiation Areas ML18054B3592018-02-27027 February 2018 Slide: NRC Pre-Submittal Meeting for Exelon Fleet LAR to Relocate TS Unit Staff Qualification ANSI Requirements to the QATR, February 27, 2018, Profile Info: Submitted by Frank Mascitelli ML17156A7972017-06-0505 June 2017 Presentation for 2016 Dresden Nuclear Power Station EOC Open House ML17142A2382017-05-25025 May 2017 OEDO-17-00280 - Briefing Package for Drop-In Visit on June 9, 2017, by Senior Management of Exelon Generation Company, LLC with Chairman Svinicki, Commissioner Baran, and Commissioner Burns ML16314E4812016-11-14014 November 2016 Part 37 Applicability to Reactor Vessels and Associated Structures, Systems, and Components While in Safstor Awaiting Active Decommissioning Activities - November 14, 2016 ML16189A4332016-07-12012 July 2016 July 12, 2016, Public Meeting with NRC - Exelon Decommissioning Licensing Action Submittal Plan ML16189A2552016-07-0707 July 2016 Annual Assessment Meeting/Open House (Hand Out) ML16077A1562016-03-22022 March 2016 Fleet: Pre-application Teleconference with Exelon to Discuss a Potential License Amendment Request Regarding Operating Training Standards ML16075A3292016-03-16016 March 2016 OEDO-16-00165 - Briefing Package for Drop-In Visit on March 23, 2016, by Senior Management of Exelon Generation Company, LLC with the NRC Executive Director for Operations ML15013A1562015-01-14014 January 2015 Meeting Slide Regarding Dresden Nuclear Power Station Pre-Application Meeting for Providing Natural Gas as a Primary Fuel to Station Auxiliary Heating Boilers RS-14-238, Transmittal of Proprietary Meeting Slides2014-08-25025 August 2014 Transmittal of Proprietary Meeting Slides ML14167A4122014-06-17017 June 2014 NRC Slides for Quad Cities 2013 EOC Public Meeting ML14232A7852014-05-19019 May 2014 Fuel Transition License Amendment Request Pre-Submittal Update Meeting ML13149A2062013-05-22022 May 2013 NRC Slides from Public Meeting ML12164A5962012-06-12012 June 2012 Annual Assessment Meeting Slides ML1208701402012-03-27027 March 2012 Licensee Slides for Exelon Fleet Pre-Submittal Public Meeting 4-10-12 Licensed Operator Eligibility Requirements LAR ML1203301242012-02-0909 February 2012 Handout for Public Meeting on February 9, 2012 (Slides) ML1109602872011-04-0505 April 2011 Quad Cities Nuclear Power Station 2010 End-of-Cycle Assessment Presentation (Short) ML1016800822010-06-15015 June 2010 Annual Assessment Meeting, Reactor Oversight Program - 2009, Slides ML0919803632009-08-20020 August 2009 Summary of Licensing Counterparts Meeting with Exelon Generation Company, to Discuss Licensing Practices and Processes ML0914003382009-05-14014 May 2009 Slides Presented at the Dresden Station 2008 EOC Public Meeting ML0911802252009-04-0707 April 2009 NRC - Quad Cities Annual Assessment Meeting Slides ML0911802142009-04-0707 April 2009 NRC End-of-Cycle Meeting Slides ML0812007842008-06-0202 June 2008 Meeting Slides, Nrc/Exelon Licensing Counterparts Meeting. ML0814405062008-05-22022 May 2008 EOC Summary Meeting Slides 2024-08-07
[Table view] Category:Slides and Viewgraphs
MONTHYEARML24232A2052024-08-12012 August 2024 Presentation Slides for Dresden End-of-Cycle Meeting ML24172A1092024-08-0707 August 2024 Scoping Power Point Presentation ML24029A1742024-01-30030 January 2024 Constellation Pre-Application January 30, 2024, Meeting Slides - Proposed Alternative to Utilize Code Case N-932, Alternative Requirements for Acceptance of Containment Base Metal Corrosion or Erosion ML23317A0712023-11-14014 November 2023 NRC Pre-Submittal Meeting on November 14th, 2023 - TSTF-591 and Selected 50.69 License Condition Updates (EPID L-2023-LLM-0098) (Slides) ML23251A0782023-09-0606 September 2023 DRE1 Decom Pre-Submittal Slides ML23255A1042023-08-11011 August 2023 Slides - Constellation - Pre-Application EP 9/18/2023 Draft CEG Presubmittal SG Performance Monitoring Plan Meeting Handout ML23173A0472023-06-28028 June 2023 SLRA - NRC Presubmittal Meeting Slides - 6-28-23 ML23173A0462023-06-28028 June 2023 DNPS SLR Pre-submittal Meeting Presentation Rev. 1 ML23145A1322023-06-27027 June 2023 June 27, 2023, Dresden Nuclear Power Station Subsequent License Renewal Environmental Pre-application Public Meeting - Constellation Slides ML23165A0242023-06-27027 June 2023 June 27, 2023, Dresden Nuclear Power Station Subsequent License Renewal Environmental Pre-application Public Meeting - NRC Slides ML23055A2712023-03-0202 March 2023 March 2, 2023, Preapplication Meeting to Discuss Planned Amendments to Adopt TSTF-505 and 10 CFR 50.69 (EPID L-2023-LRM-0007) - Slides NEI 99-01, Slides - Constellation - Pre-Application EP 2/23/2023 Meeting Slides2023-02-21021 February 2023 Slides - Constellation - Pre-Application EP 2/23/2023 Meeting Slides ML22053A2912022-02-22022 February 2022 NRC Slides for February 25, 2022 Meeting - Acceptance Review of Proposed Alternative to Adopt ASME Code Case N-921 at Dresden and Quad Cities ML21314A4472021-11-10010 November 2021 Slides for Presubmittial Meeting for Proposed Alternative to Adopt ASME Code Case N-921 to Extend the Inservice Inspection Interval ML21194A1822021-07-13013 July 2021 and Quad Cities Nuclear Generating Stations 2020 Annual Assessment Meeting Slides ML21162A3322021-06-11011 June 2021 BWR Fleet Relief Request Associated with RPV Instrument Nozzle Repairs ML20258A0302020-09-22022 September 2020 Decommissioning Licensing Action Submittal Plan for Byron and Dresden Stations Early Shutdowns ML20261G7322020-09-16016 September 2020 Pre-Submittal Slides Extend 120-month Isi/Ist Interval Under 50.55a ML20238B8572020-08-25025 August 2020 Quad 2019 Hq Online EOC Slides ML20178A4202020-06-30030 June 2020 NEI Slides for June 30, 2020, Public Meeting on COVID-19 Response ML20170B0212020-06-23023 June 2020 NRC Pre-Submittal Meeting Byron Unit 2 One-Time Deferral of Reactor Pressure Vessel Head Penetration Nozzle (Rpvhpn) Inspections ML20169A5592020-06-16016 June 2020 Steam Generator License Amendment Request Pre-Submittal Meeting (NRC) - Byron Unit 2 LAR for One-Time Deferral of Steam Generator Inspections (Rev 1) ML20163A6552020-06-16016 June 2020 6-16-20 Byron Unit 2 Steam Generator License Amendment Request Pre-Submittal Meeting (NRC) - Byron Unit 2 LAR for One-Time Deferral of Steam Generator Inspections ML18347B3142018-12-19019 December 2018 Bwrvip/Asme Relief Request Discussion December 19, 2018 ML18334A2162018-11-30030 November 2018 Presentation Slides: Exelon BWR MSIV (Boiling-Water Reactor - Main Steam Isolation Valve) Leakage Optimization for NRC Pre-Submittal Meeting of December 6, 2018 ML18319A1272018-11-19019 November 2018 Slides for 11/19/18 Public Meeting - Exelon Fleet LAR for Common Language for TS 5.7 High Radiation Areas ML18207A1882018-07-26026 July 2018 Slides for Dresden 2017 EOC Open House ML18086A8432018-03-27027 March 2018 NUREG-1021, Revision 11 Implementation ML18054B3592018-02-27027 February 2018 Slide: NRC Pre-Submittal Meeting for Exelon Fleet LAR to Relocate TS Unit Staff Qualification ANSI Requirements to the QATR, February 27, 2018, Profile Info: Submitted by Frank Mascitelli ML17156A7972017-06-0505 June 2017 Presentation for 2016 Dresden Nuclear Power Station EOC Open House ML16314E4812016-11-14014 November 2016 Part 37 Applicability to Reactor Vessels and Associated Structures, Systems, and Components While in Safstor Awaiting Active Decommissioning Activities - November 14, 2016 ML16189A4332016-07-12012 July 2016 July 12, 2016, Public Meeting with NRC - Exelon Decommissioning Licensing Action Submittal Plan ML16189A2552016-07-0707 July 2016 Annual Assessment Meeting/Open House (Hand Out) ML16077A1562016-03-22022 March 2016 Fleet: Pre-application Teleconference with Exelon to Discuss a Potential License Amendment Request Regarding Operating Training Standards ML15135A4252015-05-19019 May 2015 EOC Mtg Slides ML15013A1562015-01-14014 January 2015 Meeting Slide Regarding Dresden Nuclear Power Station Pre-Application Meeting for Providing Natural Gas as a Primary Fuel to Station Auxiliary Heating Boilers RS-14-238, Transmittal of Proprietary Meeting Slides2014-08-25025 August 2014 Transmittal of Proprietary Meeting Slides ML14167A4122014-06-17017 June 2014 NRC Slides for Quad Cities 2013 EOC Public Meeting ML14232A7852014-05-19019 May 2014 Fuel Transition License Amendment Request Pre-Submittal Update Meeting ML13149A2062013-05-22022 May 2013 NRC Slides from Public Meeting ML12164A5962012-06-12012 June 2012 Annual Assessment Meeting Slides ML1208701402012-03-27027 March 2012 Licensee Slides for Exelon Fleet Pre-Submittal Public Meeting 4-10-12 Licensed Operator Eligibility Requirements LAR ML1205906462012-03-0505 March 2012 February 9, 2012 - Summary of Meeting with Exelon Nuclear Regarding Future Submittal of Amendment to Use Netco Spent Fuel Pool Inserts ML1203301242012-02-0909 February 2012 Handout for Public Meeting on February 9, 2012 (Slides) ML11201A2132011-07-20020 July 2011 Summary of Public Meeting to Discuss Exelon'S Plans for Implementing an Electronic Document Control System (Edocs) for Use by NRC Inspectors with U.S. Nuclear Regulatory Commission (NRC) Region III Staff ML1113202162011-05-11011 May 2011 Slides for Dresden Nuclear Power Station End-Of-Cycle Public Open House ML1109602782011-04-0505 April 2011 Quad Cities Nuclear Power Station 2010 End-of-Cycle Annual Assessment Meeting Presentation (Long) ML1109602872011-04-0505 April 2011 Quad Cities Nuclear Power Station 2010 End-of-Cycle Assessment Presentation (Short) ML1016800822010-06-15015 June 2010 Annual Assessment Meeting, Reactor Oversight Program - 2009, Slides ML1012000332010-04-28028 April 2010 Annual Assessment Meeting Slides 2024-08-07
[Table view] |
Text
4300 Winfield Road Warrenville, IL 60555 Exelon Generation ,. 630 657 2000 Office Attachment 1 contains proprietary information. Withhold from public disclosure under 10 CFR 2.390. When Attachment 1 is separated, the remainder of the Attachments and this cover letter are decontrolled.
RS-14-238 August 25, 2014 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Dresden Nuclear Power Station, Units 2 and 3 Renewed Facility Operating License Nos. DPR-19 and DPR-25 NRC Docket Nos. 50-237 and 50-249 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:
Transmittal of Proprietary Meeting Slides The purpose of this letter is to transmit the proprietary slides generated by AREVA, Inc. for Dresden Nuclear Power Station (DNPS) and Quad Cities Nuclear Power Station (QCNPS) in support of the pre-submittal meeting conducted on August 19, 2014. The pre-submittal meeting was conducted to discuss the planned Exelon Generation Company, LLC (EGC) amendment request to transition to ATRIUM 10XM fuel at DNPS and QCNPS.
This letter provides a copy of the August 19, 2014, presentation material, wh ich AREVA, Inc.
considers to contain proprietary information. The proprietary information is identified by bracketed text. AREVA requests that the proprietary information in Attachment 1 to this letter be withheld from public disclosure, in accordance with the requirements of 10 CFR 2.390, "Public inspections, exemptions, requests for withholding," paragraph (a)(4). A signed affidavit supporting this request is provided in Attachment 2 to this letter. Attachment 3 to this letter provides a non-proprietary version of the presentation .
Attachment 1 contains proprietary information. Withhold from public disclosure under 10CFR 2.390. When Attachment 1 is separated, the remainder of the Attachments and this cover letter are decontrolled.
August 25, 2014 U.S. Nuclear Regulatory Commission Page2 There are no regulatory commitments contained in this letter. Should you have any questions concerning this letter, please contact Mr. Timothy A. Byam at (630) 657-2818.
Respectfully,
~Q Patrick R. Simpson Manager - Licensing Attachments:
- 1. Fuel Transition License Amendment Request Pre-Submittal Meeting Presentation (Proprietary), dated August 19, 2014
- 2. AREVA, Inc. Affidavit
- 3. Fuel Transition License Amendment Request Pre-Submittal Meeting Presentation (Non-Proprietary), dated August 19, 2014 Attachment 1 contains proprietary information. Withhold from public disclosure under 10 CFR 2.390. When Attachment 1 is separated, the remainder of the Attachments and this cover letter are decontrolled.
contains proprietary information. Withhold from public disclosure under 10 CFR 2.390. When Attachment 1 is separated, the remainder of the Attachments and this cover letter are decontrolled.
ATTACHMENT 2 AREVA, Inc.
Affidavit contains proprietary information. Withhold from public disclosure under 10 CFR 2.390. When Attachment 1 is separated, the remainder of the Attachments and this cover letter are decontrolled.
AFFIDAVIT STATE OF WASHINGTON )
) SS.
COUNTY OF BENTON )
- 1. My name is Alan B. Meginnis. I am Manager, Product Licensing, for AREVA Inc. and as such I am authorized to execute this Affidavit.
- 2. I am familiar with the criteria applied by AREVA to determine whether certain AREVA information is proprietary. I am familiar with the policies established by AREVA to ensure the proper application of these criteria.
- 3. I am familiar with the AREVA information contained in the Exelon Generation Company, LLC Dresden and Quad Cities Stations Presentation "Fuel Transition License Amendment Request Pre-Submittal Update Meeting," dated August 19, 2014 and referred to herein as "Document." Information contained in this Document has been classified by AREVA as proprietary in accordance with the policies established by AREVA 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 AREVA 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 AREVA to determine whether information should be classified as proprietary:
(a) The information reveals details of AREVA's 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 AREVA.
(d) The information reveals certain distinguishing aspects of a process, methodology, or component, the exclusive use of which provides a competitive advantage for AREVA in product optimization or marketability.
(e) The information is vital to a competitive advantage held by AREVA, would be helpful to competitors to AREVA, and would likely cause substantial harm to the competitive position of AREVA.
The information in the Document is considered proprietary for the reasons set forth in paragraphs 6(b), 6(d) and 6(e) above.
- 7. In accordance with AREVA's policies governing the protection and control of information, proprietary information contained in this Document have been made available, on a limited basis, to others outside AREVA only as required and under suitable agreement providing for nondisclosure and limited use of the information.
- 8. AREVA 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.
SUBSCRIBED before me this ;l. I J-day of A~ 2014.
Susan K. McCoy NOTARY PUBLIC, STATE OFWA HINGTON MY COMMISSION EXPIRES: 1/14/2016 contains proprietary information. Withhold from public disclosure under 10 CFR 2.390. When Attachment 1 is separated, the remainder of the Attachments and this cover letter are decontrolled.
ATIACHMENT3 Fuel Transition License Amendment Request Pre-Submittal Meeting Presentation (Non-Proprietary),
dated August 19, 2014 contains proprietary information. Withhold from public disclosure under 10 CFR 2.390. When Attachment 1 is separated, the remainder of the Attachments and this cover letter are decontrolled.
Fuel Transition License Amendment Request Pre-Submittal Update Meeting Exelon Generation Company, LLC Dresden and Quad Cities Stations August 19, 2014
,.---- Exelon Generation.
Meeting Agenda
- Critical Power Correlation For OPTIMA2
- Questions 1 ~ Exelon Generation
=
Background===
- Dresden Nuclear Power Station (DNPS) and Quad Cities Nuclear Power Station (QCNPS) are both General Electric BWR/3 reactors with Mark I containments
- DNPS Units 2 and 3 - 2957 MWt
- QCNPS Units 1 and 2 - 2957 MWt
- Renewed Operating License expires
- DNPS Unit 2 - 12/22/2029
- DNPS Unit 3 - 01/12/2031
- QCNPS Units 1 and 2 - 12/14/2032
- DNPS and QCNPS fuel transition project began in December 2012 when AREVA was awarded a contract fo r fuel beginning in 2016
- April 2013 through present AREVA has been collecting and evaluating plant data needed for fuel transition
- In June 2013 fuel transition LAR planning activities began
~
2 ~ Exelon Generation
Critical Power Correlation for OPTIMA2
- Application of EMF-2245(P)(A) - Application of Siemens Power Corporation's Critical Power Correlations to Co-Resident Fuel
- Method describes a process for generating additive constants for co-resident fuel using an NRC AREVA critical power correlation
- Direct and Indirect method
- Direct method is used when experimental test data is available for co-resident fuel
- Indirect method is used when experimental test data is not available and involves using a calculated critical power database
- Critical power is calculated using co-resident fuel vendor's NRC approved critical power correlation
- Using co-variance, a combined standard deviation is calculated using both the standard deviation of the AREVA correlation applied to the database, and the standard deviation of the co-resident fuel vendor's a pp roved correlation
~
3 ,=:' Exelon Generation
Critical Power Correlation for OPTIMA2
- Indirect method used in the QCNPS and DNPS application
- Calculated critical power database was constructed using the Westinghouse approved OPTIMA2 correlation
.[
]
- The first step in the process is to select the AREVA critical power correlation to be used
.[
]
4 -
~ Exelon Generation
Critical Power Correlation for OPTIMA2
- Next step is a partition of the data
- Consistent with the process used in developing additive constants for AREVA fuel, the data is randomly divided into two sets
- The first set of defining data contains [
]
.[
]
- Second set contains the remain ing [
]
- All data points are used to evaluate the mean and uncertainty of the correlation
. [
]
5 ~ ExelonGeneration.
Critical Power Correlation for OPTIMA2
- F-effective captures the local rod peaking effects an d consists of two parts
- Depends solely on the rod local peaking of interest, an d its surrounding neighbors
- Calculated using the methods described in Section 2.3 from EMF-2209PA, "SPCB Critical Power Correlation"
- Accounts for other local effects of spacing and geometry
[
]
6 ~ Exelon Generation
Critical Power Correlation for OPTIMA2
.[
1
- [ ] calculations are performed using the defining and validating data set
- ECPR is the figure of merit and is defined as the AREVA calculated critica I power divided by the data base critica I power
- ECPR and standard deviation are calculated for each set of data, and the combined data set
.[ ]
- Combined data set ECPR and standard deviation are used to define the overall statistics of the method 7 -
~ Exelon Generation
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Critical Power Correlation for OPTIMA2
- Overall additive constant uncertainty is determined using the indirect method defined in EMF-2245PA I
J 16 ~ Exelon Generation
Critical Power Correlation for OPTIMA2
- OPTIMA2 with [ ] statistics Parameter Value
[
]
~
17 .=' Exelon Generation
Critical Power Correlation for OPTIMA2
- OPTIMA2 with [ ] bounds Parameter Range Pressure (psia) [
Inlet subcoolinfl (Btu/lbm)
Inlet assembly mass flux (Mlbm/hr-ft2)
]
[
r -
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18 ~ Exelon Generation
Critical Power Correlation for OPTIMA2
- OPTIMA2 with [ ] bounds Pa rameter Range
[
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~
19 ~ Exelon Generation
Critical Power Correlation for OPTIMA2
- Statistics show acceptable fit can be achieved for OPTIMA2 with [
]
- Best-estimate additive constants have been determined [
]
.[
]
- Bounds of the [ ] correlation for application to OPTIMA2 conservatively set to the more limiting of the range of the approved [
] correlation and the range of data in the OPTIMA2 critical power database 20 ~ Exelon Generation
Critical Power Correlation for OPTIMA2
- ANP-10307PA, "AREVA MCPR Safety Limit Methodology for Boiling Water Reactors"
.[
]
21 -
~ ExelonGeneration.
Critical Power Correlation for OPTIMA2 Sub-assembly Outlet Tie Plate Sub-assembly Inlet Tie Plate 22 -
~ Exelon Generation
Critical Power Correlation for OPTIMA2
- MICROBURN-82 is used to [ ]
- Given core overa 11 boundary conditions [
]
.[
]
23 ~ Exelon Generation.
Critical Power Correlation for OPTIMA2
- For each Monte Carlo trial [ ] perform MICROBURN-82 [ ]
- Perturb system and core conditions and assembly radial and axial power profiles including uncertainties from channel bow
- Randomly perturbed system uncertainties that are applicable to QCNPS and DNPS
- Core uncertainties determined from uncertainty in POWERPLEX predicted power and flows
- e.g. radial bundle power, axial power, assembly flow
. [
]
24 ~ Exelon Generation
Critical Power Correlation for OPTIMA2
- For each Monte Carlo tria I [ ] perform MICROBURN-82 [ ] (continued)
.[
]
25 -
~ Exelon Generation
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May 19, 2014 Pre-Submittal Meeting Summary
- Exelon will utilize an established transition process followed by industry
- One License Amendment Request will be submitted for both DNPS and QCNPS
- Finalize approach on channel bow and verify it will be submitted as part of the LAR as a plant specific method
- Channel Bow evaluation will be performed using approved methodologies
- The approach and results of the evaluation will be discussed in the LAR for plant specific application
- This discussion is intended to support NRC review and resolution in the subsequent safety evaluation 32 ----
~ Exelon Generation
May 19, 2014 Pre-Submittal Meeting Summary
- Follow-up Issues (continued)
- Finalize approach to completing the Spent Fuel Pool (SFP) Criticality Safety Analysis (CSA) for DNPS and QCNPS (i.e., analysis for only one station and implementation under 50.59 at the other)
- A separate LAR will be submitted to address SFP CSA for DNPS Units 2 and 3 only (submittal scheduled for October 2014)
- QCNPS Units 1 and 2 criticality changes will be completed under 10 CFR 50.59 using the QCNPS rack insert application currently under review as a basis
- DNPS SFP CSA analysis will follow the same methodology used in the QCNPS rack insert application currently under review
- Status and schedule for release of the draft and final SRP revision for reactivity insertion accidents
- Use of 230 cal/gram as the appropriate upper limit for coolability
- LAR approach to be used depends on schedule for issuance of the revised SRP 33 ~ Exelon Generation
May 19, 2014 Pre-Submittal Meeting Summary
- Follow-up Issues (continued)
- Address any maneuvering restrict ions associated with the new fuel and how those restrictions accou nt for current Westinghouse fuel
- Both Westinghouse fuel and ATRIUM 10XM fuel utilize barrier cladding
- There will be no changes to Westinghouse maneuvering restrictions
- Exelon intends to apply Westinghouse and AREVA specific fuel conditioning rules to Westinghouse and AREVA fuel respectively 34 ---
~ Exelon Generation
Westinghouse Non-Proprietary - Class 3 Critical Power Correlation for OPTIMA2
- Follow-up Issues (continued)
- Evaluate Westinghouse Methods for Thermal Con ductivity Degradation (TCD) Issue
- With transition to AREVA fuel, Westinghouse will continue to hold LOCA analysis of record for Westinghouse fuel loaded in the core with inputs from steady-state fuel rod performance analyses.
- Westinghouse provided response to NRC request regarding eva luation of TCD using Westinghouse methods in letter LTR-NRC-12-18, dated February 17, 2012.
- Westinghouse LOCA analyses for Dresden and Quad Cities use methods as discussed in letter LTR-NRC-12-18. TCD is accounted for in these analyses.
35 ~ Exelon Generation
Fuel Transition LAR Schedule
- Fuel Transition Schedule (Consistent with 08/ 27/ 13 and 05/19/14 Meetings)
- LAR Submittal: February 2015
- Amendment Need Date: March 2016
- QCNPS Unit 2 implementation: March 2016
- DNPS Unit 3 implementation: November 2016
- QCNPS Unit 1 implementation: March 2017
- DNPS Unit 2 implementation: November 2017 36 -
~ Exelon Generation
Fuel Transition LAR Schedule Concurrent Reviews
- Spent Fuel Pool (SFP) Criticality Safety Analysis (CSA) LAR
- SFP CSA for ATRIUM 10XM will follow the same methodology used in the QCNPS rack insert application currently under review
- QCNPS SFP CSA for ATRIUM 10XM will be completed under 10 CFR 50.59
- DNPS SFP CSA for ATRIUM 10XM will be submitted as a LAR (SFP CSA LAR)
- Submittal scheduled for October 2014
- Fuel Transition LAR does not depend on NRC approval of SFP CSA LAR
- SFP CSA LAR does not depend on NRC approval of Fuel Transition LAR
- If accident dose increases by more than 10% as a result of fuel transition, AST analysis will require revision and results will be included in the fuel transition LAR
- Preliminary evaluation has determined there will be no impact to source term design basis 37 -
.=:' Exelon Generation
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