Response to Request for Additional Information Regarding Decommissioning Funding Plans for Independent Spent Fuel Storage Installations (Isfsis)ML18124A197 |
Person / Time |
---|
Site: |
Calvert Cliffs, Dresden, Peach Bottom, Salem, Nine Mile Point, Oyster Creek, Byron, Braidwood, Limerick, Clinton, Quad Cities, Zion, LaSalle, 07201036, 07200001 ![Constellation icon.png](/w/images/b/be/Constellation_icon.png) |
---|
Issue date: |
05/02/2018 |
---|
From: |
Simpson P Exelon Generation Co |
---|
To: |
Document Control Desk, Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation |
---|
References |
---|
RS-18-061 |
Download: ML18124A197 (12) |
|
Similar Documents at Calvert Cliffs, Dresden, Peach Bottom, Salem, Nine Mile Point, Oyster Creek, Byron, Braidwood, Limerick, Clinton, Quad Cities, Zion, LaSalle, 07201036, 07200001 |
---|
Category:Letter type:RS
MONTHYEARRS-24-004, Proposed Alternative to the Distribution Requirements of ASME Code Table IWC-2411-1 for the Steam Generators2024-01-11011 January 2024 Proposed Alternative to the Distribution Requirements of ASME Code Table IWC-2411-1 for the Steam Generators RS-24-001, Response to Request for Additional Information Regarding Relief Request I5R-26, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval2024-01-0303 January 2024 Response to Request for Additional Information Regarding Relief Request I5R-26, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval RS-23-128, Response to Request for Additional Information for the Emergency License Amendment Request Increase Technical Specifications Completion Time in TS 3.8.1.B.4 from 7 Days to 30 Days2023-12-15015 December 2023 Response to Request for Additional Information for the Emergency License Amendment Request Increase Technical Specifications Completion Time in TS 3.8.1.B.4 from 7 Days to 30 Days RS-23-123, Emergency License Amendment Request - Increase Technical Specifications Completion Time in TS 3.8.1.B.4 from 7 Days to 30 Days2023-12-13013 December 2023 Emergency License Amendment Request - Increase Technical Specifications Completion Time in TS 3.8.1.B.4 from 7 Days to 30 Days RS-23-125, Request for Exemption from 10 CFR 2.109(b)2023-12-0707 December 2023 Request for Exemption from 10 CFR 2.109(b) RS-23-126, Request for Exemption from 10 CFR 2.109(b)2023-12-0707 December 2023 Request for Exemption from 10 CFR 2.109(b) RS-23-121, Sixth Ten-Year Interval Inservice Testing Program2023-11-30030 November 2023 Sixth Ten-Year Interval Inservice Testing Program RS-23-122, Amendment No. 15 to Indemnity Agreement No. B-592023-11-29029 November 2023 Amendment No. 15 to Indemnity Agreement No. B-59 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-23-117, Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information2023-11-10010 November 2023 Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information RS-23-118, Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information2023-11-10010 November 2023 Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information RS-23-120, Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information2023-11-10010 November 2023 Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information RS-23-119, Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information2023-11-10010 November 2023 Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information RS-23-116, Supplemental Information in Response to Order Consenting to License Transfers and Approval of Conforming License Amendments2023-11-0808 November 2023 Supplemental Information in Response to Order Consenting to License Transfers and Approval of Conforming License Amendments RS-23-107, Relief Request I5R-22, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval2023-11-0808 November 2023 Relief Request I5R-22, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval RS-23-114, Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds2023-11-0101 November 2023 Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds RS-23-113, Submittal of Updated Final Safety Analysis Report (Ufsar), Revision 17 and Fire Protection Report (Fpr), Revision 262023-10-20020 October 2023 Submittal of Updated Final Safety Analysis Report (Ufsar), Revision 17 and Fire Protection Report (Fpr), Revision 26 RS-23-102, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-10-16016 October 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation RS-23-103, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-10-13013 October 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation RS-23-100, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-10-13013 October 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023 Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans RS-23-108, Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles2023-10-11011 October 2023 Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles RS-23-105, Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections2023-10-10010 October 2023 Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections RS-23-093, License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel.2023-09-29029 September 2023 License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel. RS-23-094, Relief Request I4R-24, Alternative for Post-Peening Reexamination Frequency for Reactor Pressure Vessel Head Penetration Nozzle Number 752023-09-29029 September 2023 Relief Request I4R-24, Alternative for Post-Peening Reexamination Frequency for Reactor Pressure Vessel Head Penetration Nozzle Number 75 RS-23-091, Relief Request I4R-25, Alternative Requirements for Reactor Pressure Vessel Inservice Inspection Intervals2023-09-26026 September 2023 Relief Request I4R-25, Alternative Requirements for Reactor Pressure Vessel Inservice Inspection Intervals RS-23-090, Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors for Clinton Power Station2023-09-0707 September 2023 Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors for Clinton Power Station 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-23-081, Request for License Amendment to Revise Technical Specifications Related to Reactor Water Cleanup Isolation Instrumentation2023-08-21021 August 2023 Request for License Amendment to Revise Technical Specifications Related to Reactor Water Cleanup Isolation Instrumentation RS-23-087, Revision to Approved Alternatives Associated with the Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements on Reactor2023-08-0404 August 2023 Revision to Approved Alternatives Associated with the Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements on Reactor RS-23-085, Supplemental Information Related to Request for Partial Site Release2023-08-0303 August 2023 Supplemental Information Related to Request for Partial Site Release RS-23-084, Response to Request for Additional Information Regarding the Application to Revise Design Basis to Allow Use of Plastic Section Properties in Lower Downcomer Braces Analysis2023-07-24024 July 2023 Response to Request for Additional Information Regarding the Application to Revise Design Basis to Allow Use of Plastic Section Properties in Lower Downcomer Braces Analysis RS-23-083, Withdrawal - Proposed Alternatives Related to the Steam Generators2023-06-27027 June 2023 Withdrawal - Proposed Alternatives Related to the Steam Generators RS-23-077, 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-23-074, Supplement to Application for License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink2023-06-0909 June 2023 Supplement to Application for License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink RS-23-059, 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-23-073, Request for Partial Site Release2023-06-0707 June 2023 Request for Partial Site Release RS-23-075, Application for Technical Specification Improvement to Extend the Completion Time for Condition B of Technical Specification 3.5.1, Accumulators, Using the Consolidated Line Item Improvement Process2023-06-0707 June 2023 Application for Technical Specification Improvement to Extend the Completion Time for Condition B of Technical Specification 3.5.1, Accumulators, Using the Consolidated Line Item Improvement Process RS-23-042, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2023-05-25025 May 2023 Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling RS-23-050, Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube.2023-05-22022 May 2023 Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube. RS-23-070, Supplement to License Amendment Request Regarding Transition to GNF3 Fuel2023-05-16016 May 2023 Supplement to License Amendment Request Regarding Transition to GNF3 Fuel RS-22-067, 10 CFR 50.46 Annual Report2023-05-0404 May 2023 10 CFR 50.46 Annual Report RS-23-068, Response to Request for Additional Information for Quad Cities Relief Request I6R-11, Proposed Alternatives for a Temper Bead Weld Repair of the Mating Surfaces of the Reactor Pressure Vessel Head and Shell2023-04-28028 April 2023 Response to Request for Additional Information for Quad Cities Relief Request I6R-11, Proposed Alternatives for a Temper Bead Weld Repair of the Mating Surfaces of the Reactor Pressure Vessel Head and Shell RS-23-058, Submittal of Sixth Inservice Inspection Interval Relief Request I6R-11 Proposed Alternatives for a Temper Bead Weld Repair of the Mating Surfaces of the Reactor Pressure Vessel Head and Shell Flanges2023-04-24024 April 2023 Submittal of Sixth Inservice Inspection Interval Relief Request I6R-11 Proposed Alternatives for a Temper Bead Weld Repair of the Mating Surfaces of the Reactor Pressure Vessel Head and Shell Flanges RS-23-056, Response to Request for Additional Information to Braidwood Station, Unit 1, and Byron Station, Unit 1, for Steam Generator License Renewal Response to Commitment 102023-04-20020 April 2023 Response to Request for Additional Information to Braidwood Station, Unit 1, and Byron Station, Unit 1, for Steam Generator License Renewal Response to Commitment 10 2024-01-03 The following query condition could not be considered due to this wiki's restrictions on query size or depth: <code> [[:Calvert Cliffs]] OR [[:Dresden]] OR [[:Peach Bottom]] OR [[:Salem]] OR [[:Nine Mile Point]] OR [[:Oyster Creek]] OR [[:Byron]] OR [[:Braidwood]] OR [[:Limerick]] OR [[:Clinton]] OR [[:Quad Cities]] OR [[:Zion]] OR [[:LaSalle]] OR [[:07201036]] OR [[:07200001]] </code>.
[Table view]The following query condition could not be considered due to this wiki's restrictions on query size or depth: <code> [[:Calvert Cliffs]] OR [[:Dresden]] OR [[:Peach Bottom]] OR [[:Salem]] OR [[:Nine Mile Point]] OR [[:Oyster Creek]] OR [[:Byron]] OR [[:Braidwood]] OR [[:Limerick]] OR [[:Clinton]] OR [[:Quad Cities]] OR [[:Zion]] OR [[:LaSalle]] OR [[:07201036]] OR [[:07200001]] </code>. Category:Response to Request for Additional Information (RAI)
MONTHYEARML24031A6612024-01-31031 January 2024 International, Rsi Responses on HI-STORM Umax Revisions to Amendments 0, 1, and 2 NL-24-0014, Revised Response to Request for Additional Information Regarding License Amendment Request to Relax the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Studs in Technical.2024-01-30030 January 2024 Revised Response to Request for Additional Information Regarding License Amendment Request to Relax the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Studs in Technical. ML24026A1962024-01-26026 January 2024 GEH - Response to NRC Request for Additional Information ML24025A1362024-01-25025 January 2024 Louisiana Energy Services, LLC - Response to Request for Supplemental Information Regarding LAR 23-07 NLS2024006, Response to Nuclear Regulatory Commission'S Request for Additional Information for Relief Request RC3-022024-01-25025 January 2024 Response to Nuclear Regulatory Commission'S Request for Additional Information for Relief Request RC3-02 ML24025A0952024-01-24024 January 2024 Clarifications Related to the NRC Staff'S EA for Crystal River NL-24-0020, Plan, Unit 1 Responses to NRC Request for Additional Information for Refueling Outage 1R24 Steam Generator Tube Inspection Report2024-01-22022 January 2024 Plan, Unit 1 Responses to NRC Request for Additional Information for Refueling Outage 1R24 Steam Generator Tube Inspection Report ML24012A1962024-01-12012 January 2024 Response to 2nd Round Request for Additional Information Concerning Relief Request Number EN-RR-22-001 Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and ML24012A2452024-01-12012 January 2024 Response to Request for Additional Information to Proposed Method to Manage Environmentally Assisted Fatigue for the Pressurizer Surge Line NRC-24-0002, Clarification for Request for Additional Information Responses for License Amendment Request to Revise Technical Specification 3.8.1, AC Sources - Operating, Surveillance Requirement SR 3.8.1.122024-01-12012 January 2024 Clarification for Request for Additional Information Responses for License Amendment Request to Revise Technical Specification 3.8.1, AC Sources - Operating, Surveillance Requirement SR 3.8.1.12 2CAN012403, Supplemental Information - Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 42024-01-11011 January 2024 Supplemental Information - Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4 ML24011A1702024-01-11011 January 2024 Washington State University, Revised Responses to Request for Additional Information in Reference to LAR 2023-1: License Amendment Request - Section 5 of the Technical Specifications and Bases ML24011A1712024-01-11011 January 2024 Washington State University, Technical Specifications and Bases, Amendment 22 CNL-23-071, Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, Inservice Inspection and Augmented Program Interval Revised Request for Alternative 0-ISI-472024-01-11011 January 2024 Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, Inservice Inspection and Augmented Program Interval Revised Request for Alternative 0-ISI-47 PLA-8096, Response to Request for Additional Information Regarding Proposed Relief Request for the Fifth 10-Year Inservice Test Program Interval2024-01-0404 January 2024 Response to Request for Additional Information Regarding Proposed Relief Request for the Fifth 10-Year Inservice Test Program Interval 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 ML24004A0402024-01-0303 January 2024 Response to NRCs November 8, 2023, Request for Additional Information - Related to Independent Spent Fuel Storage Installation L-PI-23-034, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.7.8, Cooling Water (Cl) System,2024-01-0202 January 2024 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.7.8, Cooling Water (Cl) System, ML23361A0992023-12-27027 December 2023 LLC, Response to NRC Request for Additional Information (RAI 10083) on the NuScale Standard Design Approval Application ML23361A0942023-12-21021 December 2023 Response to Request for Additional Information Regarding Proposed License Amendment Request to Revise Technical Specifications for Reactor Core Safety Limits, Fuel Assemblies and Core Operating Limits Report . L-PI-23-035, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report2023-12-20020 December 2023 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report ML23354A2882023-12-20020 December 2023 TRISO-X, LLC, Response to Request for Additional Information Part 2-1 for the TRISO-X Environmental Report and License Application ML23354A2112023-12-20020 December 2023 Response to Request for Additional Information for the TMI-2 Post-Shutdown Decommissioning Activities Report, Rev. 5 L-MT-23-056, Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information - Set 1 Part 22023-12-18018 December 2023 Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information - Set 1 Part 2 ML23349A0472023-12-15015 December 2023 GEH Response to NRC Request for Additional Information 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 ML23349A2082023-12-15015 December 2023 TRISO-X, LLC, Response to Request for Additional Information Set 6 (Structural, Material Control and Accounting, and Fire Safety) for the TRISO-X License Application ML23348A3732023-12-14014 December 2023 Acu Msrr - Environmental Review Requests for Confirmatory Information - Closure Confirmation for CA- 2, 5 and 6 1CAN122301, Responses to Request for Additional Information for Request for Alternative for Implementation of Extended Reactor Vessel Inservice Inspection Interval (ANO1-ISl-037)2023-12-14014 December 2023 Responses to Request for Additional Information for Request for Alternative for Implementation of Extended Reactor Vessel Inservice Inspection Interval (ANO1-ISl-037) ML23345A2112023-12-11011 December 2023 NAC International, Inc., Submittal of Replacement Pages for Supplemental Responses to the Nrc'S Request for Additional Information to Nac'S for the NAC OPTIMUS-L Transportation Package and Safety Analysis Report, Revision 1 ML23346A0972023-12-11011 December 2023 License Amendment Request to Revise the Emergency Plan Relocation of the Technical Support Center - Response to NRC Request for Additional Information ML23343A0022023-12-0909 December 2023 Response to Request for Additional Information Set 5 (Chemical Safety and Radiation Protection) for the TRISO-X License Application ML23346A2622023-12-0808 December 2023 Cimarron Environmental Response Trust, Response to October 2, 2023, Request for Additional Information L-PI-23-033, Supplement to License Amendment Request to Revise Technical Specification 3.8.1, Surveillance Requirement 3.8.1.2, Note 32023-12-0505 December 2023 Supplement to License Amendment Request to Revise Technical Specification 3.8.1, Surveillance Requirement 3.8.1.2, Note 3 ML23338A3062023-12-0404 December 2023 Attachment 1: HI-STORM 100 Amendment 18 RAI Responses (non-proprietary) ML23334A1952023-11-30030 November 2023 Response to Request for Additional Information in Reference to LAR 2023-1: License Amendment Request Section 5 of the Technical Specifications and Bases for the Washington State University Modified Triga Reactor and Facility License R-76, P L-23-229, Request for Additional Information Regarding the Spring 2023 Generic Letter 95-05 Voltage-Based Alternate Repair Criteria and Steam Generator F-Star Reports2023-11-29029 November 2023 Request for Additional Information Regarding the Spring 2023 Generic Letter 95-05 Voltage-Based Alternate Repair Criteria and Steam Generator F-Star Reports L-2023-155, Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-06542023-11-28028 November 2023 Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, L-MT-23-049, Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information - Set 12023-11-21021 November 2023 Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information - Set 1 L-2023-162, Response to 50.69 2nd Round of Rals2023-11-21021 November 2023 Response to 50.69 2nd Round of Rals ML23321A2472023-11-17017 November 2023 Attachment 1: Holtec International - Summary of Additional Clarifications/Changes Submitted for Review ML23321A2192023-11-17017 November 2023 International, NRC Clarification Questions from EA-23-044 Holtec Pec Presentation ML23297A261 (Edited Excerpt from the Pec Transcript ML23307A107) NL-23-0827, Response to Requests for Additional Information for a License Amendment Request and a Proposed Alternative Related to TS 3.4.142023-11-17017 November 2023 Response to Requests for Additional Information for a License Amendment Request and a Proposed Alternative Related to TS 3.4.14 ML23319A2032023-11-15015 November 2023 Cimarron Environmental Response Trust - Response to November 1, 2023, Request for Additional Information Related to Nuclear Criticality Safety CCN:23-09, 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 ML23317A1032023-11-10010 November 2023 Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information 2024-01-04 The following query condition could not be considered due to this wiki's restrictions on query size or depth: <code> [[:Calvert Cliffs]] OR [[:Dresden]] OR [[:Peach Bottom]] OR [[:Salem]] OR [[:Nine Mile Point]] OR [[:Oyster Creek]] OR [[:Byron]] OR [[:Braidwood]] OR [[:Limerick]] OR [[:Clinton]] OR [[:Quad Cities]] OR [[:Zion]] OR [[:LaSalle]] OR [[:07201036]] OR [[:07200001]] </code>.
[Table view]The following query condition could not be considered due to this wiki's restrictions on query size or depth: <code> [[:Calvert Cliffs]] OR [[:Dresden]] OR [[:Peach Bottom]] OR [[:Salem]] OR [[:Nine Mile Point]] OR [[:Oyster Creek]] OR [[:Byron]] OR [[:Braidwood]] OR [[:Limerick]] OR [[:Clinton]] OR [[:Quad Cities]] OR [[:Zion]] OR [[:LaSalle]] OR [[:07201036]] OR [[:07200001]] </code>. |
Text
4300 Winfield Road Warrenville, IL 60555 Exelon Generation 630 65 7 2000 Office RS-18-061 10 CFR 72.30 May 2, 2018 ATTN: Document Control Desk Director - Division of Spent Fuel Storage and Transportation Office of Nuclear Material Safety and Safeguards U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Braidwood Station, Units 1 and 2 Renewed Facility Operating License Nos. NPF-72 and NPF-77 NRC Docket Nos. STN 50-456. STN 50-457. and 72-73 Byron Station, Units 1 and 2 Renewed Facility Operating License Nos. NPF-37 and NPF-66 NRC Docket Nos. STN 50-454. STN 50-455. and 72-68 Calvert Cliffs Nuclear Power Plant, Units 1 and 2 Renewed Facility Operating License Nos. DPR-53 and DPR-69 NRC Docket Nos. STN 50-317 and STN 50-318 Clinton Power Station, Unit 1 Facility Operating License No. N PF-62 NRC Docket No. 50-461 and 72-1046 Dresden Nuclear Power Station, Units 1, 2 and 3 Facility Operating License No. DPR-2 Renewed Facility Operating License Nos. DPR-19 and DPR-25 NRC Docket Nos. 50-1 O. 50-237. 50-249. and 72-37 LaSalle County Station, Units 1 and 2 Renewed Facility Operating License Nos. NPF-11 and NPF-18 NRC Docket Nos. 50-373. 50-374. and 72-70 Limerick Generating Station, Units 1 and 2 Renewed Facility Operating License Nos. NPF-39 and NPF-85 NRC Docket Nos. 50-352. 50-353. and 72-65 Nine Mile Point Nuclear Station, Units 1 and 2 Renewed Facility Operating License Nos. DPR-63 and DPR-69 NRC Docket Nos. 50-220. 50-410. and 72-1036
May 8, 2018 U.S. Nuclear Regulatory Commission Page2 Oyster Creek Nuclear Generating Station Renewed Facility Operating License No. DPR-16 NRC Docket No. 50-219 and 72-15 Peach Bottom Atomic Power Station, Units 1, 2, and 3 Facility Operating License No. DPR-12 Renewed Facility Operating License Nos. DPR-44 and DPR-56 NRC Docket Nos. 50-171. 50-277. 50-278. and 72-29 Quad Cities Nuclear Power Station, Units 1 and 2 Renewed Facility Operating License Nos. DPR-29 and DPR-30 NRC Docket Nos. 50-254. 50-265. and 72-53 R.E. Ginna Nuclear Power Plant Renewed Facility Operating License No. DPR-18 NRC Docket Nos. 50-244 and 72-67 Salem Generating Station, Units 1 and 2 Renewed Facility Operating License Nos. DPR-70 and DPR-75 NRC Docket Nos. 50-272. 50-311. and 72-48 Zion Nuclear Power Station, Units 1 and 2 Facility Operating License Nos. DPR-39 and DPR-48 NRC Docket Nos. STN 50-295. STN 50-304. and 72-1037 Calvert Cliffs Nuclear Power Plant, Units 1 and 2 Independent Spent Fuel Storage Installation Materials License No. SNM-2505 NRC Docket No. 72-08
Subject:
Response to Request for Additional Information Regarding Decommissioning Funding Plans for Independent Spent Fuel Storage Installations (ISFSls)
References:
- 1. Letter from U.S. Nuclear Regulatory Commission to Patrick R. Simpson, 11 Request for Additional Information Regarding Exelon Generating Company, LLC's Decommissioning Funding Plan Update for Calvert Cliffs Nuclear Power Plant, Nine Mile Point Nuclear Station, R.E. Ginna Nuclear Power Plant, Braidwood Station, Byron Station, Dresden Nuclear Power Station, LaSalle County Station, Limerick Generating Station, Oyster Creek Nuclear Generating Station, Peach Bottom Atomic Power Station, Quad Cities Nuclear Power Station, and Salem Generating Station Independent Spent Fuel Storage lnstallations, 11 dated March 8, 2018
- 2. Letter from U.S. Nuclear Regulatory Commission to Patrick R. Simpson, 11 Request for Additional Information Regarding ZionSolutions LLC's Decommissioning Funding Plan Update for Zion Independent Spent Fuel Storage Installation," dated March 9, 2018
May 8, 20'18 U.S. Nuclear Regulatory Commission Page 3 In accordance with '1 O CFR 72.30, "Financial assurance and recordkeeping for decommissioning," Exelon Generation Company, LLC (EGC), or a prior licensee, previously submitted proposed ISFSI decommissioning funding plans for Braidwood Station, Byron Station, Calvert Cliffs Nuclear Power Plant, Clinton Power Station, Dresden Nuclear Power Station, LaSalle County Station, Limerick Generating Station, Nine Mile Point Nuclear Station, Oyster Creek Nuclear Generating Station, Peach Bottom Atomic Power Station, R.E. Ginna Nuclear Power Plant, Quad Cities Nuclear Power Station, Salem Generating Station, and Zion Nuclear Power Station.
The Nuclear Regulatory Commission (NRC) reviewed the EGC provided decommissioning funding plans for each ISFSI and concluded that additional information is necessary.
References 1 and 2 requested the additional information needed to complete the NRC's review.
The EGC response to the NRC's request for additional information is provided in the attachments to this letter and is subdivided as follows.
- Attachment 1 provides a response to Reference 1.
- Attachment 2 provides a response to Reference 2.
There are no regulatory commitments contained within this letter.
If you have any questions concerning this letter, please contact me at (630) 657-2823.
Patrick R. Simpson Manager - Licensing Exelon Generation Company, LLC cc: Regional Administrator - NRC Region I Regional Administrator- NRC Region Ill NRC Senior Resident Inspector- Braidwood Station NRC Senior Resident Inspector- Byron Station NRC Senior Resident Inspector - Calvert Cliffs Nuclear Power Plant NRC Senior Resident Inspector - Clinton Power Station NRC Senior Resident Inspector - Dresden Nuclear Power Station NRC Senior Resident Inspector- LaSalle County Station NRC Senior Resident Inspector - Limerick Generating Station NRC Senior Resident Inspector- Nine Mile Point Nuclear Station NRC Senior Resident Inspector- Oyster Creek Nuclear Generating Station NRC Senior Resident Inspector - Peach Bottom Atomic Power Station NRC Senior Resident Inspector - Quad Cities Nuclear Power Station NRC Senior Resident Inspector- R.E. Ginna Nuclear Power Plant NRC Senior Resident Inspector - Salem Generating Station
May 8, 2018 U.S. Nuclear Regulatory Commission Page4 Attachments:
- 1. Response to Request for Additional Information Regarding Independent Spent Fuel Storage Installation Decommissioning Funding Plans
- 2. Response to Request for Additional Information Regarding Decommissioning Funding Plan Update for Zion Independent Spent Fuel Storage Installation
ATTACHMENT 1 Response to Begyest for Addjtjonal lnformatjon Begardjnq Independent Spent Fuel Storage Installation Decommissionin g Fynding Plans By letters dated December 17, 2012(References 1 and 2), Exelon Generation Company, LLC (EGC) and Constellation Energy Nuclear Group, LLC submitted decommissioning funding plans (DFPs) for the independent spent fuel storage installations (ISFSls) pursuant to 10 CFR 72.30(b) for Braidwood Station, Byron Station, Dresden Nuclear Power Station, LaSalle County Station, Limerick Generating Station, Oyster Creek Nuclear Generating Station, Peach Bottom Atomic Power Station, Quad Cities Nuclear Power Station, Salem Generating Station, Calvert Cliffs Nuclear Power Plant, Nine Mile Point Nuclear Station, and R.E. Ginna Nuclear Power Plant.
In accordance with 10 CFR 72.30(c), 11 *** at the time of license renewal and at intervals not to exceed 3 years, the decommissioning funding plan required to be submitted by 10 CFR 72.30(b) must be resubmitted with adjustments as necessary to account for changes in costs and the extent of contamination," the December 17, 2012 submittals were updated by EGC in a letter dated March 31, 2015 (Reference 3). The Braidwood Station Units 1 and 2 and Byron Station Unit 2 DFPs were updated in a letter dated February 4, 2016 (Reference 6). An update of the DFPs for all ISFSI facilities was submitted by EGC in a letter dated March 30, 2017 (Reference 4).
A detailed ISFSI decommissioning cost estimate was included for each ISFSI facility in the original DFP submittal (References 1 and 2). The detailed cost estimate is periodically revised based on the schedule for refreshing the full decommissioning cost estimate for the site. The revised detailed ISFSI cost estimate is included in the subsequent DFP update.
ISFSI Facility Current Current Detailed Original DFP Updated DFP Cost Estimate Braidwood Station Reference 1 Reference 4 Reference 7 Byron Station Reference 1 Reference 4 Reference 7 Dresden Nuclear Power Station Reference 1 Reference 4 Reference 1 LaSalle County Station Reference 1 Reference 4 Reference 7 Limerick Generating Station Reference 1 Reference 4 Reference 3 Oyster Creek Nuclear Reference 1 Reference 4 Reference 8 Generating Station Peach Bottom Atomic Power Reference 1 Reference 4 Reference 4 Station Quad Cities Nuclear Power Reference 1 Reference 4 Reference 4 Station Salem Generating Station Reference 1 Reference 4 Reference 4 1
Calvert Cliffs Nuclear Power Reference 2 Reference 4 Reference 4 Plant Nine Mile Point Nuclear Station Reference 2 Reference 4 Reference 4 R.E. Ginna Nuclear Power Reference 2 Reference 4 Reference 4 Plant In a Nuclear Regulatory Commission (NRC) letter dated March 8, 2018 (Reference 5), the NRC indicated that it had reviewed the information submitted in the March 31, 2015 letter and requested additional clarifying information to support its continued review. The NRC is requesting that EGC respond to the request for addttional information (RAI) within 45 working days of the date of the letter.
EGC has reviewed the RAI and determined that the RAI applies to the February 4, 2016 (Reference 6) and March 30, 2017 (Reference 4) DFP updates submitted by EGC in addition to the March 31, 2015 update. The NRC question in the March 8, 2018 letter is identified below followed by EGC's response relative to EGC's March 31, 2015, February 4, 2016, and March 30, 2017 DFP updates.
Review of the Clinton Power Station updated ISFSI DFP in the Reference 4 letter indicates that the RAI applies to the Clinton Power Station ISFSI in addition to the previously identified ISFSI facilities. EGC's response relative to the March 30, 2017, Clinton Power Station ISFSI DFP update is included below. Reference 9 contains the original DFP and the detailed decommissioning cost estimate for the Clinton Power Station ISFSI.
Request for Additional Information For each ISFSI, provide a revised DFP that includes information on the occurrence, and the effect on decommissioning costs, of each of the events listed in 10 CFR 72.30(c)(1)-(4): (1) spills of radioactive material producing additional residual radioactivity in onsite subsurface material, (2) facility modifications, (3) changes in authorized possession limits, and (4) actual remediation costs that exceed the previous cost estimate.
Response
The effect of each of the events listed in 10 CFR 72.30(c)(1) through (4) on the cost estimates provided in the ISFSI decommissioning funding plans in References 1, 3, 4, and 6 for Braidwood Station, Byron Station, Dresden Nuclear Power Station, LaSalle County Station, Limerick Generating Station, Oyster Creek Nuclear Generating Station, Peach Bottom Atomic Power Station, Quad Cities Nuclear Power Station, and Salem Generating Station is listed below:
( 1) spills of radioactive material producing additional residual radioactivity in onsite subsurface material No impact. There have not been any spills of radioactive material producing additional residual radioactivity in onsite subsurface material from 2012 to 2017 at any of the ISFSls at the facilities listed above.
2
(2) facility modifications No impact. There have not been any modifications to the ISFSls at the facilities listed above from 2012 to 2017 that would materially change the latest decommissioning cost estimate.
The ISFSI facility design at the time the cost estimate was prepared was incorporated in the estimate for the facilities listed above. Also, any ISFSI modifications (i.e., ISFSI pad expansions) required to accommodate spent fuel storage after permanent shutdown were incorporated in the cost estimate.
(3) changes in authorized possession limits No impact. There have not been any changes in authorized possession limits at the ISFSls at the facilities listed above from 2012 to 2017 that would materially change the decommissioning cost estimate.
The capacity of the cask used at the ISFSI at the time the cost estimate was performed was incorporated in the estimate for the facilities listed above. In anticipation of a change in cask size at Peach Bottom, a larger cask size was incorporated in the latest Peach Bottom ISFSI cost estimate (Reference 4).
(4) actual remediation costs that exceed the previous cost estimate.
No impact. As of 2017, decommissioning had not begun at any of the ISFSls at the facilities listed above. Consequently, there have been no actual remediation costs that exceed the latest cost estimate.
In References 2, 3, and 4 decommissioning cost estimates were provided for the ISFSls at Calvert Cliffs Nuclear Power Plant, Nine Mile Point Nuclear Station, and R.E. Ginna Nuclear Power Plant. Each of the items listed in 10 CFR 72.30(c)(1) through (4) was considered in preparation of the cost estimates. A discussion of each item is included below.
(1) spills of radioactive material producing additional residual radioactivity in onsite subsurface material No impact. There were no spills of radioactive material producing additional residual radioactivity in onsite subsurface material from 2012 to 2017 at any of the ISFSls at the facilities listed above.
3
(2) facility modifications No impact. There have not been any modifications to the ISFSls at the facilities listed above from 2012 to 2017 that would materially change the latest decommissioning cost estimate.
The ISFSI facility design at the time the updated cost estimate was prepared was incorporated in the estimate for the facilities listed above.
Also, any ISFSI modifications (i.e., ISFSI pad expansions) required to accommodate spent fuel storage after permanent shutdown were incorporated in the updated cost estimate.
(3) changes in authorized possession limits No impact. There have not been any changes in authorized possession limits at the ISFSls at the facilities listed above from 2012 to 2017 that would materially change the latest decommissioning cost estimate.
The capacity of the cask used at the ISFSI at the time the updated cost estimate was performed was incorporated in the estimate for the facilities listed above. The cask size did not change in the updated estimate relative to the previous estimate.
(4) actual remediation costs that exceed the previous cost estimate.
No impact. As of 2017, decommissioning had not begun at any of the ISFSls at the facilities listed above. Consequently, there have been no actual remediation costs that exceed the costs included in the latest cost estimate.
In References 9 and 4 decommissioning cost estimates were provided for the Clinton Power Station ISFSI. Each of the items listed in 10 CFR 72.30(c)(1) through (4) was considered in preparation of the cost estimates. A discussion of each item is included below.
(1) spills of radioactive material producing additional residual radioactivity in onsite subsurface material No impact. There were no spills of radioactive material producing additional residual radioactivity in onsite subsurface material from 2016 to 2017 at the Clinton Power Station ISFSI.
(2) facility modifications No impact. There have not been any modifications to the Clinton Power Station ISFSI from 2016 to 2017 that would materially change the latest decommissioning cost estimate.
4
The ISFSI facility design at the time the cost estimate was prepared was incorporated in the estimate. Also, any ISFSI modifications (i.e.,
ISFSI pad expansions) required to accommodate spent fuel storage after permanent shutdown were incorporated in the cost estimate.
(3) changes in authorized possession limits No impact. There have not been any changes in authorized possession limits at the Clinton Power Station ISFSI from 2016 to 2017 that would materially change the latest decommissio ning cost estimate.
The capacity of the cask planned for use at the ISFSI at the time the cost estimate was performed was incorporated in the estimate for the Clinton Power Station ISFSI. The cask size in use has not changed from that assumed in the cost estimate.
(4) actual remediation costs that exceed the previous cost estimate.
No impact. As of 2017, decommissio ning had not begun at the Clinton Power Station ISFSI. Consequently , there have been no actual remediation costs that exceed the costs included in the cost estimate.
Therefore, based on the above information, EGC has concluded that the ISFSI decommission ing funding plan updates (References 3, 4, and 6) for each facility remain valid.
References
- 1. Letter from Patrick R. Simpson (EGC) to U.S. Nuclear Regulatory Commission, 11 Proposed Independent Spent Fuel Storage Installation (ISFSI) Decommissio ning Funding Plans for Braidwood, Byron, Dresden, LaSalle, Limerick, Oyster Creek, Peach Bottom, Quad Cities, and Salem," dated December 17, 2012
- 2. Letter from Stephen A. Mormann (Constellation Energy Nuclear Group, LLC) to U.S. Nuclear Regulatory Commission, "ISFSI Decommissio ning Funding Plans,"
dated December 17, 2012
- 3. Letter from Patrick R. Simpson (EGC) to U.S. Nuclear Regulatory Commission, 11 Report on the Status of Decommissio ning Funding for Reactors and Independent Spent Fuel Storage Installations," dated March 31, 2015
- 4. Letter from Patrick R. Simpson (EGC) to U.S. Nuclear Regulatory Commission, 11 Report on Status of Decommissio ning Funding for Reactors and Independent Spent Fuel Storage Installations," dated March 30, 2017
- 5. Letter from U.S. Nuclear Regulatory Commission to Patrick R. Simpson, 11 Request for Additional Information Regarding Exelon Generating Company, LLC's 5
Decommissioning Funding Plan Update for Calvert Cliffs Nuclear Power Plant, Nine Mile Point Nuclear Station, R.E. Ginna Nuclear Power Plant, Braidwood Station, Byron Station, Dresden Nuclear Power Station, LaSalle County Station, Limerick Generating Station, Oyster Creek Nuclear Generating Station, Peach Bottom Atomic Power Station, Quad Cities Nuclear Power Station, and Salem Generating Station Independent Spent Fuel Storage Installations," dated March 8, 2018
- 6. Letter from Patrick R. Simpson (EGC) to U.S. Nuclear Regulatory Commission, "Report on Status of Decommissioning Funding for Braidwood Station, Units 1 and 2 and Byron Station, Unit 2," dated February 4, 2016
- 7. Letter from Patrick R. Simpson (EGC) to U.S. Nuclear Regulatory Commission, "Submittal of Updated Site-Specific SAFSTOR Decommissioning Cost Estimates for Braidwood Station, Byron Station, and LaSalle County Station," dated February 19, 2015
- 8. Letter from James Barstow (EGC) to U.S. Nuclear Regulatory Commission, "Submittal of Updated Decommissioning Cost Analysis for Oyster Creek Generating Station," dated March 30, 2016
- 9. Letter from David M. Gullett (EGC) to U.S. Nuclear Regulatory Commission, "Proposed Independent Spent Fuel Storage Installation (ISFSI) Decommissioning Funding Plans for Clinton Power Station," dated September 6, 2016 6
ATTACHMENT 2 Response to Regyest for Addjtjonal Information Regardjnq Decommissioning Fynding Plan Update for Zion lndepentjent Spent Fuel Storage Installation By letter dated October 17, 2013 (Reference 1), Exelon Generation Company, LLC (EGC) submitted a decommissioning funding plan (DFP) for the Zion independent spent fuel storage installation (ISFSI) pursuant to 10 CFR 72.30(b).
In accordance with 10 CFR 72.30(c), 11 *** at the time of license renewal and at intervals not to exceed 3 years, the decommissioning funding plan required to be submitted by 10 CFR 72.30(b) must be resubmitted with adjustments as necessary to account for changes in costs and the extent of contamination," the October 17, 2013 submittal was updated by EGC in a letter dated October 17, 2016 (Reference 2).
In a Nuclear Regulatory Commission (NRC) letter dated March 9, 2018 (Reference 3), the NRC indicated that it had reviewed information on the Zion ISFSI decommissioning funding plan submitted by ZionSolutions and requested additional clarifying information. The NRC is requesting that EGC respond to the request for addnional information (RAI) within 45 working days of the date of the letter.
EGC has reviewed the RAI and determined that the request applies to the October 17, 2016 letter EGC submitted for the Zion ISFSI (Reference 2). The NRC question in the March 9, 2018 letter is identified below followed by EGC's response relative to EGC's October 17, 2016 Zion ISFSI decommissioning funding plan.
Regyest for Addjtjonal lnformatjon For the ISFSI at Zion, provide a revised DFP that includes the effect on decommissioning costs of each of the events listed in 10 CFR 72.30(c)(1)-(4): (1) spills of radioactive material producing additional residual radioactivity in onsite subsurface material, (2) facility modifications, (3) changes in authorized possession limits, and (4) actual remediation costs that exceed the previous cost estimate.
Response
In the Reference 2 update of the Zion ISFSI decommissioning funding plan, an updated decommissioning cost estimate was provided. Each of the items listed in 10 CFR 72.30(c)(1) through (4) was considered in preparation of the updated cost estimate. A discussion of each item is included below.
(1) spills of radioactive material producing additional residual radioactivity in onsite subsurface material No change in the updated cost estimate due to radioactive material spills. There have not been any spills of radioactive material producing additional residual radioactivity in onsite subsurface material at the Zion ISFSI.
1
(2) facility modifications The actual ISFSI facility design was accounted for in the updated cost estimate, whereas the planned design was used in the previous cost estimate. There are no planned changes to the Zion ISFSI facility that would materially change the decommissioning cost.
(3) changes in authorized possession limits The actual number and content of casks on the Zion ISFSI facility were included in the updated cost estimate, whereas the planned number and content was used in the previous cost estimate. No additional casks will be placed on the Zion ISFSI.
(4) actual remediation costs that exceed the previous cost estimate.
Decommissioning of the Zion ISFSI has not begun. Consequently, there have been no actual remediation costs that exceed the updated (or previous) cost estimate.
Therefore, based on the above information, EGC has concluded that the decommissioning funding plan update in Reference 2 for Zion's ISFSI remains valid.
References
- 1. Letter from Patrick R. Simpson (Exelon Generation Company, LLC) to U.S. NRC, 11 Proposed Independent Spent Fuel Storage Installation (ISFSI) Decommissioning Funding Plan for Zion," dated October 17, 2013
- 2. Letter from Patrick R. Simpson (Exelon Generation Company, LLC) to U.S. NRC, "Independent Spent Fuel Storage Installation (ISFSI) Decommissioning Funding Plan for Zion," dated October 17, 2016
- 3. Letter from U.S. Nuclear Regulatory Commission to Patrick R. Simpson, "Request for Additional Information Regarding ZionSolutions LLC's Decommissioning Funding Plan Update for Zion Independent Spent Fuel Storage lnstallation, 11 dated March 9, 2018 2