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Category:Letter type:RS
MONTHYEARRS-24-064, Nuclear Radiological Emergency Plan Document Revisions2024-06-28028 June 2024 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-24-055, 2023 Corporate Regulatory Commitment Change Summary Report2024-05-17017 May 2024 2023 Corporate Regulatory Commitment Change Summary Report RS-24-038, Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds2024-05-0202 May 2024 Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds 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-24-002, Constellation Energy Generation, LLC - Annual Property Insurance Status Report2024-04-0101 April 2024 Constellation Energy Generation, LLC - Annual Property Insurance Status Report 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-23-103, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-10-13013 October 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023 Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans RS-23-080, 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-23-087, Revision to Approved Alternatives Associated with the Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements on Reactor2023-08-0404 August 2023 Revision to Approved Alternatives Associated with the Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements on Reactor RS-23-084, Response to Request for Additional Information Regarding the Application to Revise Design Basis to Allow Use of Plastic Section Properties in Lower Downcomer Braces Analysis2023-07-24024 July 2023 Response to Request for Additional Information Regarding the Application to Revise Design Basis to Allow Use of Plastic Section Properties in Lower Downcomer Braces Analysis RS-23-077, 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-23-042, 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-23-049, 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-23-048, Exigent Amendment Request to Revise Design Basis Related to Seismic Requirements2023-03-0707 March 2023 Exigent Amendment Request to Revise Design Basis Related to Seismic Requirements RS-23-045, 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-23-037, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors for LaSalle County Station2023-02-22022 February 2023 Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors for LaSalle County Station 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-22-085, Application to Revise Design Basis to Allow Use of Plastic Section Properties in Lower Downcomer Braces Analysis2023-01-12012 January 2023 Application to Revise Design Basis to Allow Use of Plastic Section Properties in Lower Downcomer Braces Analysis RS-23-006, Supplemental Information Regarding License Amendment Request Relocation of Pressure and Temperature Limit Curves to the Pressure and Temperature Limits Report2023-01-10010 January 2023 Supplemental Information Regarding License Amendment Request Relocation of Pressure and Temperature Limit Curves to the Pressure and Temperature Limits Report 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-22-109, Response to Request for Additional Information License Amendments Related to Fuel Storage2022-10-12012 October 2022 Response to Request for Additional Information License Amendments Related to Fuel Storage RS-22-092, Nine and Quad Cities - Application to Revise Primary Containment Isolation Instrumentation Technical Specifications in Accordance with TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration2022-10-0303 October 2022 Nine and Quad Cities - Application to Revise Primary Containment Isolation Instrumentation Technical Specifications in Accordance with TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration RS-22-093, Advisement of Leadership Changes for Constellation Energy Generation, LLC and Submittal of Updated Standard Practice Procedures Plans2022-08-18018 August 2022 Advisement of Leadership Changes for Constellation Energy Generation, LLC and Submittal of Updated Standard Practice Procedures Plans RS-22-083, Response to Request for Additional Information Related to the License Amendment Request to Change New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies, with Proposed Changes to Technical2022-06-17017 June 2022 Response to Request for Additional Information Related to the License Amendment Request to Change New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies, with Proposed Changes to Technical RS-22-051, Constellation Energy Generation, LLC - Update to Correspondence Addressees and Service Lists2022-04-12012 April 2022 Constellation Energy Generation, LLC - Update to Correspondence Addressees and Service Lists RS-22-049, Constellation Energy Generation, LLC, Supplemental Information to Correct Typographical Errors in Constellation'S Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for2022-04-0404 April 2022 Constellation Energy Generation, LLC, Supplemental Information to Correct Typographical Errors in Constellation'S Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for V RS-22-045, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2022-01, Preparation and Scheduling of Operator Licensing Examinations2022-03-25025 March 2022 Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2022-01, Preparation and Scheduling of Operator Licensing Examinations RS-22-035, Supplemental Information Regarding Relief Request I4R-13 Relief from Code Examinations for 1B33-F060A and 1B33-F060B Repairs2022-03-0404 March 2022 Supplemental Information Regarding Relief Request I4R-13 Relief from Code Examinations for 1B33-F060A and 1B33-F060B Repairs RS-22-033, Response to Request for Additional Information Regarding Relief Request I4R-13 Relief from Code Examinations for 1B33-F060A and 1B33-F060B Repairs2022-03-0303 March 2022 Response to Request for Additional Information Regarding Relief Request I4R-13 Relief from Code Examinations for 1B33-F060A and 1B33-F060B Repairs RS-22-032, Relief Request I4R-13 Relief from Code Examinations for 1B33-F060A and 1B33-F060B Repairs2022-03-0202 March 2022 Relief Request I4R-13 Relief from Code Examinations for 1B33-F060A and 1B33-F060B Repairs RS-22-027, Constellation, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated2022-02-23023 February 2022 Constellation, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated P RS-22-023, Constellation Energy Generation, LLC, Executed Trust Fund Agreement Amendment and Subordinate Trust Agreement2022-02-23023 February 2022 Constellation Energy Generation, LLC, Executed Trust Fund Agreement Amendment and Subordinate Trust Agreement RS-22-018, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors for LaSalle County Station2022-02-22022 February 2022 Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors for LaSalle County Station RS-22-019, Constellation Energy Generation, LLC - Update to Correspondence Addressees and Service Lists2022-02-16016 February 2022 Constellation Energy Generation, LLC - Update to Correspondence Addressees and Service Lists RS-22-015, Notification of Completion of License Transfer and Request to Continue Processing Pending NRC Actions Previously Requested by Exelon Generation Company, LLC2022-02-0101 February 2022 Notification of Completion of License Transfer and Request to Continue Processing Pending NRC Actions Previously Requested by Exelon Generation Company, LLC RS-22-004, Supplement to Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements2022-01-0404 January 2022 Supplement to Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements RS-21-121, Proposed Changes to Decommissioning Trust Agreements and Master Terms2021-12-15015 December 2021 Proposed Changes to Decommissioning Trust Agreements and Master Terms RS-21-115, Supplemental Information for License Amendment Request Regarding New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies, with Proposed Changes to Technical Specifications 4.3.1 and 5.6.52021-11-0404 November 2021 Supplemental Information for License Amendment Request Regarding New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies, with Proposed Changes to Technical Specifications 4.3.1 and 5.6.5 RS-21-109, Request to Withhold Meeting Materials for the Non-Public Meeting Held on September 2, 20212021-10-14014 October 2021 Request to Withhold Meeting Materials for the Non-Public Meeting Held on September 2, 2021 RS-21-091, Implementation of Insider Threat Program Requirements Associated with the Voluntary Security Clearance Program and Advisement of Leadership Changes2021-09-13013 September 2021 Implementation of Insider Threat Program Requirements Associated with the Voluntary Security Clearance Program and Advisement of Leadership Changes RS-21-078, Response to Request for Additional Information for Application to Revise Technical Specification to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements, and TSTF-583-T, TSTF-582 Diesel2021-08-19019 August 2021 Response to Request for Additional Information for Application to Revise Technical Specification to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements, and TSTF-583-T, TSTF-582 Diesel RS-21-085, Response to Request for Additional Information Regarding License Amendment Request to Incorporate Licensing Topical Report NEDE-33885PA, Revision 1, GNF CRDA Application Methodology (EPID-L-2021-LLA-0016)2021-08-17017 August 2021 Response to Request for Additional Information Regarding License Amendment Request to Incorporate Licensing Topical Report NEDE-33885PA, Revision 1, GNF CRDA Application Methodology (EPID-L-2021-LLA-0016) RS-21-064, License Amendment Request Re New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies - Cover Letter2021-06-30030 June 2021 License Amendment Request Re New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies - Cover Letter RS-21-063, Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements2021-06-30030 June 2021 Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements RS-21-070, Proposed Alternative to Utilize Code Case N-8932021-06-30030 June 2021 Proposed Alternative to Utilize Code Case N-893 RS-21-055, Response to Third Round Request for Additional Information (Rals) for LaSalle License Amendment Request to Adopt Risk Informed Completion Times TSTF- 505, Revision 2, Provide Risk-Informed Extended.2021-05-10010 May 2021 Response to Third Round Request for Additional Information (Rals) for LaSalle License Amendment Request to Adopt Risk Informed Completion Times TSTF- 505, Revision 2, Provide Risk-Informed Extended. RS-21-054, Response to NRC Regulatory Issue Summary 2021-01, Preparation and Scheduling of Operator Licensing Examinations2021-04-29029 April 2021 Response to NRC Regulatory Issue Summary 2021-01, Preparation and Scheduling of Operator Licensing Examinations RS-21-050, Response to Request for Additional Information (RAI) Regarding Request for License Amendment Regarding Ultimate Heat Sink (EPID-L-2020-LLA-0165)2021-04-16016 April 2021 Response to Request for Additional Information (RAI) Regarding Request for License Amendment Regarding Ultimate Heat Sink (EPID-L-2020-LLA-0165) 2024-06-28
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARML24222A6772024-08-0909 August 2024 Response to Request for Additional Information for Application to Revise Technical Specifications to Adopt TSTF-591-A, “Revise Risk Informed Completion Time (RICT) Program” Revision 0 and Revise 10 CFR 50.69 License Condition 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-23-084, 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-22-109, Response to Request for Additional Information License Amendments Related to Fuel Storage2022-10-12012 October 2022 Response to Request for Additional Information License Amendments Related to Fuel Storage RS-22-083, Response to Request for Additional Information Related to the License Amendment Request to Change New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies, with Proposed Changes to Technical2022-06-17017 June 2022 Response to Request for Additional Information Related to the License Amendment Request to Change New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies, with Proposed Changes to Technical RS-22-033, Response to Request for Additional Information Regarding Relief Request I4R-13 Relief from Code Examinations for 1B33-F060A and 1B33-F060B Repairs2022-03-0303 March 2022 Response to Request for Additional Information Regarding Relief Request I4R-13 Relief from Code Examinations for 1B33-F060A and 1B33-F060B Repairs RS-22-027, Constellation, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated2022-02-23023 February 2022 Constellation, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated P NMP1L3447, Constellation Energy Generation, LLC - Response to Request for Additional Information - Proposed Relief Request Associated with Reactor Pressure Vessel Water Level Instrumentation Partial Penetration Nozzle Repairs2022-02-0202 February 2022 Constellation Energy Generation, LLC - Response to Request for Additional Information - Proposed Relief Request Associated with Reactor Pressure Vessel Water Level Instrumentation Partial Penetration Nozzle Repairs JAFP-21-0087, Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments2021-09-16016 September 2021 Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments RS-21-078, Response to Request for Additional Information for Application to Revise Technical Specification to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements, and TSTF-583-T, TSTF-582 Diesel2021-08-19019 August 2021 Response to Request for Additional Information for Application to Revise Technical Specification to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements, and TSTF-583-T, TSTF-582 Diesel RS-21-085, Response to Request for Additional Information Regarding License Amendment Request to Incorporate Licensing Topical Report NEDE-33885PA, Revision 1, GNF CRDA Application Methodology (EPID-L-2021-LLA-0016)2021-08-17017 August 2021 Response to Request for Additional Information Regarding License Amendment Request to Incorporate Licensing Topical Report NEDE-33885PA, Revision 1, GNF CRDA Application Methodology (EPID-L-2021-LLA-0016) NMP2L2773, Company - Response to Request for Additional Information2021-06-30030 June 2021 Company - Response to Request for Additional Information JAFP-21-0044, Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments2021-06-11011 June 2021 Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments RS-21-055, Response to Third Round Request for Additional Information (Rals) for LaSalle License Amendment Request to Adopt Risk Informed Completion Times TSTF- 505, Revision 2, Provide Risk-Informed Extended.2021-05-10010 May 2021 Response to Third Round Request for Additional Information (Rals) for LaSalle License Amendment Request to Adopt Risk Informed Completion Times TSTF- 505, Revision 2, Provide Risk-Informed Extended. JAFP-21-0032, Response to Request for Additional Information - Proposed Alternative Concerning ASME Section XI Repair/Replacement Documentation for Replacement of Pressure Retaining Bolting2021-04-20020 April 2021 Response to Request for Additional Information - Proposed Alternative Concerning ASME Section XI Repair/Replacement Documentation for Replacement of Pressure Retaining Bolting RS-21-050, Response to Request for Additional Information (RAI) Regarding Request for License Amendment Regarding Ultimate Heat Sink (EPID-L-2020-LLA-0165)2021-04-16016 April 2021 Response to Request for Additional Information (RAI) Regarding Request for License Amendment Regarding Ultimate Heat Sink (EPID-L-2020-LLA-0165) RS-21-045, Response to Request for Additional Information (RAI) Regarding Request for License Amendment Regarding Ultimate Heat Sink (EPID-L-2020-LLA-0165)2021-04-0707 April 2021 Response to Request for Additional Information (RAI) Regarding Request for License Amendment Regarding Ultimate Heat Sink (EPID-L-2020-LLA-0165) RS-21-040, Response to Second Round Request for Additional Information (Rais) for License Amendment Request to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2021-03-31031 March 2021 Response to Second Round Request for Additional Information (Rais) for License Amendment Request to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b RS-21-027, Response to Request for Additional Information Regarding Request for Exemption from Pre-Access Drug and Alcohol Testing Requirements in 10 CFR 26.652021-02-21021 February 2021 Response to Request for Additional Information Regarding Request for Exemption from Pre-Access Drug and Alcohol Testing Requirements in 10 CFR 26.65 ML21022A1302021-01-22022 January 2021 Response to Request for Additional Information Regarding the License Amendment Request to Adopt 10 CFR 50.69 RS-20-136, Response to Request for Additional Information Re License Amendment Requests for Amendments to Renewed Facility OL to Adopt 10CFR50.69 & to Adopt TSTF-505, Rev. 2 (EPID L-2020-LLA-0017 and EPID-L-2020-LLA-0018)2020-10-29029 October 2020 Response to Request for Additional Information Re License Amendment Requests for Amendments to Renewed Facility OL to Adopt 10CFR50.69 & to Adopt TSTF-505, Rev. 2 (EPID L-2020-LLA-0017 and EPID-L-2020-LLA-0018) RS-20-133, Response to Request for Additional Information Re License Amendment Request to Renewed Facility Operating Licenses to Adopt 10 CFR 50.692020-10-16016 October 2020 Response to Request for Additional Information Re License Amendment Request to Renewed Facility Operating Licenses to Adopt 10 CFR 50.69 RS-20-104, Supplement to the Request for a License Amendment Technical Specification 3.7.3, Ultimate Heat Sink2020-09-11011 September 2020 Supplement to the Request for a License Amendment Technical Specification 3.7.3, Ultimate Heat Sink RS-20-112, Response to Request for Additional Information Related to License Amendment Request to Adopt TSTF-5682020-09-0303 September 2020 Response to Request for Additional Information Related to License Amendment Request to Adopt TSTF-568 NMP2L2711, Byron Station; Calvert Cliffs; Clinton Power Station; LaSalle County Station; Limerick Generating Station; and Nine Mile Point Nuclear Station - Proposed Alternative to Utilize Code Case N-8792019-10-16016 October 2019 Byron Station; Calvert Cliffs; Clinton Power Station; LaSalle County Station; Limerick Generating Station; and Nine Mile Point Nuclear Station - Proposed Alternative to Utilize Code Case N-879 JAFP-19-0057, Response to Request for Additional Information - Proposed Alternative to Utilize Code Cases N-878 and N-8802019-06-0404 June 2019 Response to Request for Additional Information - Proposed Alternative to Utilize Code Cases N-878 and N-880 NMP1L3279, Response to Request for Additional Information - Proposed Alternatives to Utilize Code Cases N-878 and N-880 for Plants2019-05-0101 May 2019 Response to Request for Additional Information - Proposed Alternatives to Utilize Code Cases N-878 and N-880 for Plants RS-19-052, Supplement to the Response to Request for Additional Information Regarding License Amendment Request to Remove Operating Mode Restrictions for Performing Surveillance Testing of the Division 3 Battery and High ..2019-04-24024 April 2019 Supplement to the Response to Request for Additional Information Regarding License Amendment Request to Remove Operating Mode Restrictions for Performing Surveillance Testing of the Division 3 Battery and High .. RS-19-019, Response to Request for Additional Information Regarding Relief Request 13R-152019-04-0202 April 2019 Response to Request for Additional Information Regarding Relief Request 13R-15 JAFP-19-0006, Response to Request for Additional Information - Proposed Alternative to Utilize Code Cases N-878 and N-8802019-01-0808 January 2019 Response to Request for Additional Information - Proposed Alternative to Utilize Code Cases N-878 and N-880 RS-18-143, Supplemental Information Supporting License Amendment Requests for Approval of Changes to Emergency Plan Staffing Requirements2018-11-29029 November 2018 Supplemental Information Supporting License Amendment Requests for Approval of Changes to Emergency Plan Staffing Requirements RS-18-097, Response to Request for Additional Information and Supplemental Information-License Amendment.2018-07-27027 July 2018 Response to Request for Additional Information and Supplemental Information-License Amendment. RS-18-086, Response to Request for Additional Information Regarding License Amendment Request for Temporary Extensions to Technical Specifications Supporting Maintenance on Portions of the Core Standby Cooling System2018-07-16016 July 2018 Response to Request for Additional Information Regarding License Amendment Request for Temporary Extensions to Technical Specifications Supporting Maintenance on Portions of the Core Standby Cooling System RS-18-078, Supplemental Information Related to Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control2018-06-18018 June 2018 Supplemental Information Related to Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control RS-18-061, Response to Request for Additional Information Regarding Decommissioning Funding Plans for Independent Spent Fuel Storage Installations (Isfsis)2018-05-0202 May 2018 Response to Request for Additional Information Regarding Decommissioning Funding Plans for Independent Spent Fuel Storage Installations (Isfsis) RS-18-014, Supplement to Request to Revise Technical Specifications 2.1.1 for Minimum Critical Power Ratio Safety Limits2018-01-25025 January 2018 Supplement to Request to Revise Technical Specifications 2.1.1 for Minimum Critical Power Ratio Safety Limits RS-17-147, Response to Request for Additional Information Regarding LaSalle County Station Fourth Inservice Inspection Interval Relief Request 14R-012017-11-10010 November 2017 Response to Request for Additional Information Regarding LaSalle County Station Fourth Inservice Inspection Interval Relief Request 14R-01 RS-17-146, Additional Information Regarding License Amendment Request to Revise Suppression Pool Swell Design Analysis2017-10-19019 October 2017 Additional Information Regarding License Amendment Request to Revise Suppression Pool Swell Design Analysis RS-17-099, Response to Request for Additional Information Regarding LaSalle County Station License Amendment Request for Extension of Type a and Type C Containment Leak Rate Test Intervals (PRA Branch)2017-08-0808 August 2017 Response to Request for Additional Information Regarding LaSalle County Station License Amendment Request for Extension of Type a and Type C Containment Leak Rate Test Intervals (PRA Branch) RS-17-101, Response to Request for Additional Information Regarding License Amendment Request to Revise Suppression Pool Swell Design Analysis2017-07-28028 July 2017 Response to Request for Additional Information Regarding License Amendment Request to Revise Suppression Pool Swell Design Analysis RS-17-102, Response to Request for Supplemental Information Regarding Fourth Inservice Inspection Interval Relief Request 14R-012017-07-20020 July 2017 Response to Request for Supplemental Information Regarding Fourth Inservice Inspection Interval Relief Request 14R-01 RS-17-098, Response to Request for Additional Information Regarding License Amendment Request for Extension of Type a and Type C Containment Leak Rate Test Intervals (Sbpb Branch)2017-07-17017 July 2017 Response to Request for Additional Information Regarding License Amendment Request for Extension of Type a and Type C Containment Leak Rate Test Intervals (Sbpb Branch) RS-17-044, Response to Request for Additional Information Regarding Proposed Alternative for the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography2017-03-13013 March 2017 Response to Request for Additional Information Regarding Proposed Alternative for the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography RS-17-010, Response to Request for Additional Information Regarding LaSalle County Station Alternative Request RV-01 for the Lnservice Testing Program Fourth 10-Year Interval2017-02-0909 February 2017 Response to Request for Additional Information Regarding LaSalle County Station Alternative Request RV-01 for the Lnservice Testing Program Fourth 10-Year Interval RS-16-244, Additional Information Regarding Request for License Amendment to Address Secondary Containment Access Openings2016-12-12012 December 2016 Additional Information Regarding Request for License Amendment to Address Secondary Containment Access Openings RS-16-176, County, High Frequency Supplement to Seismic Hazard Screening Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ic2016-12-0101 December 2016 County, High Frequency Supplement to Seismic Hazard Screening Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ich RS-16-125, Spent Fuel Pool Evaluation Supplemental Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2016-08-31031 August 2016 Spent Fuel Pool Evaluation Supplemental Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident RS-16-159, County, and Quad Cities - Response to Request for Additional Information Regarding License Amendment to Address Secondary Containment Access Openings2016-07-28028 July 2016 County, and Quad Cities - Response to Request for Additional Information Regarding License Amendment to Address Secondary Containment Access Openings RS-16-144, Response to Request for Additional Information on Severe Accident Mitigation Alternatives for License Renewal Environmental Review Dated July 6, 20162016-07-11011 July 2016 Response to Request for Additional Information on Severe Accident Mitigation Alternatives for License Renewal Environmental Review Dated July 6, 2016 RA-16-049, Response to Request for Additional Information Regarding Requests to Withhold Emergency Preparedness Documents from Public Disclosure2016-05-26026 May 2016 Response to Request for Additional Information Regarding Requests to Withhold Emergency Preparedness Documents from Public Disclosure 2024-08-09
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Michael P. Gallagher Vice President. License Renewal Exelon Generation Exelon Nuclear 200 Exelon Way Kennett Square, PA 19348 610 765 5958 Office 610 765 5956 Fax www.exeloncorp.com michaelp.gallagher@exeloncorp.com 10 CFR 50 10 CFR 51 10 CFR 54 RS-15-201 July 24, 2015 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 LaSalle County Station, Units 1 and 2 Facility Operating License Nos. NPF-11 and NPF-18 NRC Docket Nos. 50-373 and 50-374
Subject:
Response to NRC Request for Additional Information, dated June 25, 2015, Regarding the LaSalle County Station, Units 1 and 2, License Renewal Application, Environmental Review
References:
- 1. Letter from Michael P. Gallagher, Exelon Generation Company, LLC (Exelon Generation), to U.S. Nuclear Regulatory Commission (NRC) Document Control Desk, "Application for Renewed Operating Licenses," dated December 9, 2014
- 2. Letter from David Drucker, NRC, to Michael P. Gallagher, Exelon Generation, "Requests for Additional Information for the Review of the LaSalle County Station, Units 1 and 2, License Renewal Application," dated June 25, 2015 In the Reference 1 letter, Exelon Generation Company, LLC (Exelon Generation) submitted the License Renewal Application (LRA) for the LaSalle County Station, Units 1 and 2. In the Reference 2 letter, the NRC requested additional information to support the Staffs review of Section 4.13 (Impacts Common to All Alternatives: Uranium Fuel Cycle) in the LaSalle County Station Applicant's Environmental Report (Appendix E to the LRA).
The enclosure to this letter contains response sheets that provide information requested by each of the Staff's questions and/or identify supporting documents and materials.
This letter and its enclosure contain no regulatory commitments.
If you have any questions, please contact Ms. Nancy Ranek, Environmental Lead, Exelon Generation License Renewal, at 610-765-5369.
July 24, 2015 U.S. Nuclear Regulatory Commission Page 2 I declare under penalty of perjury that the foregoing is true and correct.
Executed on: 7 Cf- 2<JIJ-Michael P. Gallagher Vice President - License Renewal Projects Exelon Generation Company, LLC
Enclosure:
LaSalle County Station Units 1 & 2 Response Sheets for NRC License Renewal Environmental Review Requests for Additional Information - Spent Fuel Transportation cc: Regional Administrator - NRC Region Ill NRC Project Manager (Environmental Review), NRR-DLR NRC Project Manager (Safety Review), NRR-DLR NRC Project Manager, NRR-DORL LaSalle County Station NRC Senior Resident Inspector, LaSalle County Station Illinois Emergency Management Agency - Division of Nuclear Safety
RS-15-201 Enclosure RS-15-201 ENCLOSURE LaSalle County Station, Units 1 & 2 Response Sheets for NRC License Renewal Environmental Review Requests for Additional Information - Spent Fuel Transportation
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RS-15-201 Enclosure TABLE OF CONTENTS RAI #: TR-01 .................................................................. .............................................................. 1 RAI #: TR-02 ................................................................. .............................................................. 2 RAI #: TR-03 ................................................................. .............................................................. 3 RAI #: TR-04 ................................................................. .............................................................. 6 RAI #: TR-05 ................................................................. .............................................................. 7 RAI #: TR-06 ................................................................. .............................................................. 8 RAI #: TR-07 ................................................................. .............................................................. 9 RAI #: TR-08 ................................................................. ............................................................ 10 RAI #: TR-09 ................................................................. ............................................................ 11
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RS-15-201 Enclosure Page 1 of 11 LaSalle County Station, Units 1 & 2 Response to Request for Additional Information RAI #: TR-01 Category: Spent Fuel Transportation Statement of Question:
Provide an evaluation of the heat load for an irradiated fuel shipment for comparison to Title 10 of the Code of Federal Regulations (10 CFR) Part 51, Table S-4.
An analysis of the heat load is contained in 10 CFR 51, Table S-4, but is not contained in the LaSalle County Station (LSCS), Units 1 and 2, Environmental Report (ER) (Section 4.13), the Transportation Calculation Package, or CALC-194-4735-02.
Response
Exelon Generation used the ORIGEN code to estimate the decay heat at 5 years after discharge from the reactor for spent fuel with burnup of 75,000 MWD/MTU. The estimated heat load for a cask containing 0.5 MTU of such higher burnup fuel is approximately 2,160 W or 7,370 BTU/hr. This amount of heat is small and released over the entire transportation route.
Under separate correspondence to the NRC, Exelon Generation is providing a revised version of all text and tables in Section 4.13 of the LSCS License Renewal ER. The heat load information provided above will be included therein along with Exelon Generations evaluation of its significance. That submission is planned to occur during July 2015.
RS-15-201 Enclosure Page 2 of 11 LaSalle County Station, Units 1 & 2 Response to Request for Additional Information RAI #: TR-02 Category: Spent Fuel Transportation Statement of Question:
The data is not used consistently between CALC-194-4735-02 and the actual RADTRAN run.
Clarify and provide a revised analysis of the incident-free dose at stops.
In CALC-194-4735-02, the incident-free dose at stops is 2.51E-1 person-rem/shipment (see Table 3 and the RADTRAN output). However, in the Transportation Calculation Package, 2.15E-1 person-rem/shipment is used for the incident-free dose at stops, which results in the dose to general public (onlookers) being underestimated.
Page 5 of CALC-194-4735-02 states that the population density used at stops was 23,933 people/km2. However, in the RADTRAN runs contained in Appendix C of CALC-194-4735-02, a population density of 19,944 people/km2 was used.
Response
Exelon Generation has revised both CALC-194-4735-02 and the Transportation Calculation Package using an updated RADTRAN analysis for LSCS high-burnup spent fuel. In conjunction with these revisions, all dose-per-shipment values in the Transportation Calculation Package were verified to be consistent with the revised CALC-194-4735-02 (CALC-194-4735-02, Revision 1). Also, the updated RADTRAN analysis was performed using the correct population density at stops, which is 23,933 people/km2.
Under separate correspondence to the NRC, Exelon Generation is providing a revised version of all text and tables in Section 4.13 of the LSCS License Renewal ER. The ER revisions describe all results from the updated RADTRAN analysis, CALC-194-4735-02, Revision 1 and the revised Transportation Calculation Package. That submission is planned to occur during July 2015.
RS-15-201 Enclosure Page 3 of 11 LaSalle County Station, Units 1 & 2 Response to Request for Additional Information RAI #: TR-03 Category: Spent Fuel Transportation Statement of Question:
Provide rationale and justification for the 5 normalized shipments of spent nuclear fuel (SNF) per year used in the impact calculation. The NRC staff considers that the number of shipments are to be of irradiated fuel normalized to the 1100 MW(e) reference reactor with a capacity factor of 0.8. When normalizing the shipments, consider for the following and revise the calculations as appropriate:
- a. Provide the number of irradiated fuel shipments using a shipping container capacity of 0.5 MTU/container. For the purposes of comparison to Table S-4, a cask capacity of 0.5 MTU/cask, based on WASH-1238, should be used.
- b. In the Transportation Calculation Package, incident-free impacts were calculated based on 5 normalized shipments of SNF per year. The 5 normalized shipments appear to have been calculated based on 5.65 shipments/year (unnormalized), which appears to be based on 28.27 MTU/year annual reload/5 fuel assemblies/cask= 5.65. Instead, the calculation should have started with 28.27 MTU/year annual reload/(5 fuel assemblies/shipment x 0.1767 MTU/fuel assembly)= 32 shipments/year (unnormalized).
- c. The spent fuel cask capacity used in the analysis was 9 assemblies, derated to 5 assemblies, or 0.884 MTU/cask (5 fuel assemblies/cask x 0.1767 MTU/fuel assembly=
0.884 MTU/shipment). Again, for the purposes of comparison to Table S-4, a cask capacity of 0.5 MTU/cask, based on WASH-1238, should be used.
- d. Using a cask capacity of 0.5 MTU/shipment would result in 46.5 normalized shipments per year. {28.27 MTU/year annual reload/0.5 MTU/shipment x (1100 MWe x 0.8)
[reference reactor]/(1163.5 MWe x 0.92)= 46.5 shipments}.
Response
Exelon Generation has revised both CALC-194-4735-02 and the Transportation Calculation Package using an updated RADTRAN analysis for LSCS high-burnup spent fuel. The following items indicate how each of the corresponding items listed in the RAI above is addressed by the revisions.
- a. CALC-194-4735-02 and the Transportation Calculation Package were revised to use a cask capacity of 0.5 MTU per cask.
- b. Based on updated information concerning the amount of fuel replaced during a typical refueling outage (i.e., 36% of the 764 fuel assembly core inventory in each unit on staggered 24-month refueling cycles), the number of spent fuel shipments annually per reactor was calculated as follows:
(0.36 x 764 fuel assemblies/refueling) x (0.1767 MTU/fuel assembly) x (1 refueling/2 yrs) ÷ 0.5 MTU/shipment = 48.60 shipments/yr (unnormalized).
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- c. CALC-194-4735-02 and the Transportation Calculation Package were revised to use a cask capacity of 0.5 MTU per cask.
- d. The normalized number of shipments per year was calculated as follows:
(24.30 MTU/yr [annual reload]) (0.5 MTU/shipment) x (1100 MWe x 0.8 [reference reactor]) (1163.5 MWe x 0.92 [LSCS per unit])
= 39.95 shipments/yr.(normalized)
Incident-free Transportation The revised normalized population dose estimates for 39.95 incident-free LSCS spent fuel shipments per year at the peak rod burnup are summarized below.
Population dose (person-rem per shipment)
Transportation workers General public (onlookers) General public (along route) 0.0357 0.439 0.0335 Population dose (person-rem per reactor year)
Transportation workers General public (onlookers) General public (along route) 1.43 17.6 1.34 The population dose estimates shown above for transportation workers and the general public living along the transportation route are within the bounds of the 10 CFR 51.52, Table S-4 population dose levels, which are 4 person-rem per year and 3 person-rem per year respectively. However, the conservatively predicted population dose shown above for onlookers is higher than the corresponding Table S-4 value, which is 3 person-rem per year. Nevertheless, Exelon Generation concludes that impacts to human health or the environment from incident-free LSCS high-burnup spent fuel transport would be similar to the impacts envisioned in the 2013 GEIS, and would therefore be SMALL because the conservatively predicted population dose to onlookers would likely be below Table S-4 values if it were more realistically estimated.
Accidents during Transportation Assuming shipments containing 0.5 MTU of spent fuel at the peak rod burnup, the normalized postulated accident risk associated with transportation of spent fuel is provided below.
Population dose-risk Population dose-risk (person-rem per shipment)1 (person-rem per reference reactor year) 5.64x10-7 2.25x10-5 The population dose shown above for accidents during transportation of LSCS high-burnup spent fuel to a repository is very small. However, no direct comparison can be made between 10 CFR 51.52, Table S-4 values and the values shown above because Table S-4 does not numerically quantify radiological effects stemming from transportation accidents. Rather, it characterizes such effects as Small. Even so, no detectable increase in environmental effects that otherwise occur from average 1
The value presented is probability multiplied by collective dose.
RS-15-201 Enclosure Page 5 of 11 background radiation exposure in the U.S. (i.e., 162,000 person-rem per year) is expected to result from adding the population dose values projected for accidents during transportation of LSCS high-burnup spent fuel. Therefore, Exelon Generation concludes that impacts to human health or the environment from accidents during LSCS high-burnup spent fuel transport would be similar to the impacts envisioned in the 2013 GEIS, and would therefore be SMALL.
Under separate correspondence to the NRC, Exelon Generation is providing a revised version of all text and tables in Section 4.13 of the LSCS License Renewal ER. The ER revisions describe all results from the updated RADTRAN analysis, CALC-194-4735-02, Revision 1 and the revised Transportation Calculation Package, as well as detailed discussions of the bases for Exelon Generations conclusions regarding the impacts from incident-free transportation of high-burnup spent fuel and from accidents during transportation of such spent fuel. Submission of the ER revisions is planned to occur during July 2015.
RS-15-201 Enclosure Page 6 of 11 LaSalle County Station Units 1 & 2 Response to Request for Additional Information RAI #: TR-04 Category: Spent Fuel Transportation Statement of Question:
Explain the following inconsistencies and if appropriate, provide a revised analysis of transportation accident impacts.
Table 3 on page A7 of CALC-194-4735-02 contains a highway accident rate of 8.37E-6 accidents/km for Nevada. However, in the RADTRAN runs contained in Appendix C of CALC-194-4735-02, an accident rate of 8.37E-5 accidents/km was used for Nevada.
For high burnup, GNF2 fuel in Table 2 on page 6 of CALC-194-4735-02 lists the RADTRAN source term. Several values in this table do not match the values used in the RADTRAN analysis. For example, Ce-144 is 1.21E+4 Ci/cask in the table, but 2.44E+4 Ci/cask in the RADTRAN run; Cs-137 is 1.82E+5 Ci/cask in the table, but 3.55E+5 Ci/cask in the RADTRAN run; and Kr-85 is 1.20E+4 Ci/cask in the table, but 1.02E+4 Ci/cask in the RADTRAN run. The footnotes to Table 2 on page 6 of CALC-194-4735-02 indicate that Ba-137m is included as Cs-137, and that Pr-144 and Pr-144m are included as Ce-144, i.e., the Cs-137 and Ba-137m inventories are added and entered in the RADTRAN run for total Cs-137, and the Ce-144, Pr-144, and Pr-144m inventories are added and entered in the RADTRAN run as total Ce-144.
Determine if the dose conversion factors used in RADTRAN for Cs-137 and Ce-144 include the contributions from the short-lived progeny radionuclides Ba-137m, Pr-144, and Pr-144m, and provide the technical justification for adding these inventories as indicated in the footnote, and provide a revised analysis of transportation accident impacts.
Response
Exelon Generation has revised both CALC-194-4735-02 and the Transportation Calculation Package using an updated RADTRAN analysis for LSCS high-burnup spent fuel. In conjunction with these revisions, the error in the highway accident rate for Nevada has been corrected.
The RADTRAN library contains dose conversion factors and other radionuclide specific parameters for 149 radionuclides and allows for user-defined data to be defined in addition to utilizing the preset library values. Per the RADTRAN User Guide (Ref. 1, page 92), the dose conversion factor (DCF) for Cs-137 includes the weighted contributions from its short-lived daughter product, Ba-137m. Similarly, the Ce-144 DCFs in the RADTRAN library include the weighted contribution from short-lived daughter products Pr-144 and Pr-144m. Since the DCFs are already weighted for the dose increase due to the daughter products, there is no need to create user defined DCF inputs to separately account for the daughters. Simply adding the activities of the daughters to the activity of the parent isotope is conservative since the conversion factors were already weighted to account for the increase in dose due to the contributions of the daughter products.
References
- 1. Weiner, R.F.; Hinojosa, D.; Heames, T.J.; Ottinger Farnum, K.; Kalinina, E.A. RADTRAN 6/RADCAT 6 User Guide. Albuquerque, NM: Sandia National Laboratories; 2013 Sep; SAND2013-8095.
RS-15-201 Enclosure Page 7 of 11 LaSalle County Station, Units 1 & 2 Response to Request for Additional Information RAI #: TR-05 Category: Spent Fuel Transportation Statement of Question:
Clarify the source of the Am-242m listed in Table 2 of CALC-194-4735-02.
Am-242m is listed in Table 2 of CALC-194-4735-02. However, Am-242m is not listed in the ORIGEN output in of CALC-194-4735-02.
Response
An Excel function was utilized to automate the reduction of the ORIGEN output into the RADTRAN source term presented in Table 2 of CALC-194-4735-02. However, one of the parameters for the function was left unspecified, which caused the function to default to looking for closest match instead of exact match. As a result, the Am-242 data were incorrectly specified as Am-242m. Exelon Generation has revised both CALC-194-4735-02 and the Transportation Calculation Package using an updated RADTRAN analysis for LSCS high-burnup spent fuel. In conjunction with these revisions, the erroneous RADTRAN source term for Am-242m in Table 2 of the revised CALC-194-4735-02 (CALC-194-4735-02, Revision 1) has been corrected to reflect 0 Ci of Am-242m. In addition, the remainder of the RADTRAN source term data in Table 2 of CALC-194-4735-02, Revision 1 has been line-by-line verified to assure its accuracy.
RS-15-201 Enclosure Page 8 of 11 LaSalle County Station, Units 1 & 2 Response to Request for Additional Information RAI #: TR-06 Category: Spent Fuel Transportation Statement of Question:
Clarify whether the light elements Co-58, Co-60, Fe-55, Fe-59, Mn-54, and Cr-51 listed in Table 2 on page 6 of CALC-194-4735-02 are from actual crud (i.e., exterior deposits on the fuel assembly) or if they are structural material. If they are structural material, the crud inventory for these radionuclides should also be provided.
The inventory for the light elements Co-58, Co-60, Fe-55, Fe-59, Mn-54, and Cr-51 is taken from CALC-194-4735-01 and appears to be from structural material, not crud deposits on the irradiated fuel.
Response
The inventory for the light elements listed in Table 2 of CALC-194-4735-02 is assumed to be crud. As stated in the question, the inventory for the light elements is taken from CALC-194-4735-01 and is structural material. However, the structural material is all assumed to be turned into crud, which is conservative. This was done because no actual crud data were available.
RS-15-201 Enclosure Page 9 of 11 LaSalle County Station, Units 1 & 2 Response to Request for Additional Information RAI #: TR-07 Category: Spent Fuel Transportation Statement of Question:
Clarify the Sb-125 inventory in Table 2 of on page 6 of CALC-194-4735-02.
Table 2, page 6 of CALC-194-4735-02 lists a Sb-125 inventory of 7.19E+2 Ci/assembly.
However, CALC-194-4735-01 lists two Sb-125 inventories, 7.19E+2 Ci/assembly from fission products (p. 15) and 1.69E+2 Ci/assembly from light elements (p. 14).
Response
An Excel function was utilized to automate the reduction of the ORIGEN output into the RADTRAN source term presented in Table 2 of CALC-194-4735-02. The function originally utilized was not coded properly to look for duplicate inventory listings and stopped searching once a single row of data was found. As a result, the second Sb-125 inventory was inadvertently missed in the creation of the RADTRAN source term in Table 2 of CALC-194-4735-02.
Exelon Generation has revised both CALC-194-4735-02 and the Transportation Calculation Package using an updated RADTRAN analysis for LSCS high-burnup spent fuel. In conjunction with these revisions, the RADTRAN source term in Table 2 of CALC-194-4735-02 has been revised (CALC-194-4735-02, Revision 1). In addition, the ORIGEN data files were re-examined, and three isotopes in Table 2 - Sb-125, Sr-89, and Y that were also affected by this issue were corrected.
RS-15-201 Enclosure Page 10 of 11 LaSalle County Station, Units 1 & 2 Response to Request for Additional Information RAI #: TR-08 Category: Spent Fuel Transportation Statement of Question:
Provide a reference for the gamma fraction of 0.91 and the neutron fraction of 0.09 used in CALC-194-4735-02.
No reference is listed for the gamma and neutron fractions.
Response
NUREG-1437, Addendum 1 (pages 27-28) discusses the potential impacts of higher fuel burnup on gamma-ray and neutron emissions from a spent fuel transport cask. This document states that [f]or nominal burnups, the dose rates at the surface and 2-m from the surface are approximately 90 percent gamma-rays and 10 percent neutrons. This is the justification for the gamma and neutron fractions used in CALC-194-4735-02. Since the high burnup shipments were derated to 0.5 MTU per shipment, but kept at the regulatory dose rate limits, the split between gamma and neutron fractions was not changed for the higher burnup case. This is further justified by the fact that neutron and gamma radiation are similarly attenuated in air up to about 700 m (2,296 feet). As a result, the transportation dose results are insensitive (less than a few percent) to the difference between 90% and 100% gamma fraction.
In addition to the attenuation of neutrons in air, transportation casks are designed to absorb neutrons and thus limit the neutron dose in the vicinity of the cask. As a result, several well know transportation analyses for spent fuel simply assume that the incident-free dose consists entirely of gamma radiation. A sensitivity study was performed using the high burnup case from CALC-194-4735-02. In this sensitivity study, the only parameter that was changed was the gamma/neutron fraction in the VEHICLE and the PACKAGE rows of the input file, which were changed from 0.91 and 0.09 to 1.0 and 0.0, respectively. The results of this sensitivity study are summarized below and show that the difference in the different components of the incident-free dose is less than 2%.
CALC-194-4735-02 Sensitivity Case % Difference 100% gamma Case 91% gamma / 9% neutron Incident-Free Doses CREW (person-rem) 3.54E-02 3.57E-02 -0.42%
OFF LINK (person-rem) 3.48E-02 3.35E-02 1.90%
ON LINK (person-rem) 6.23E-02 6.30E-02 -0.56%
STOPS (person-rem) 3.73E-01 3.76E-01 -0.40%
MAX IND (rem) 1.49E-06 1.49E-06 0.00%
RS-15-201 Enclosure Page 11 of 11 LaSalle County Station, Units 1 & 2 Response to Request for Additional Information RAI #: TR-09 Category: Spent Fuel Transportation Statement of Question:
Provide a revised analysis of incident-free and transportation accident impacts by applying the TRAGIS highway route controlled quantity (HRCQ) option and TRAGIS state-specific distances and population densities in urban, suburban, and rural areas.
The TRAGIS analysis for LSCS to Yucca Mountain was run using the assumption that a commercial route would be used with state-specific distances and generic population densities in urban, suburban, and rural areas. However, prior NRC sponsored or reviewed spent nuclear fuel shipment assessments (e.g., NRCs NUREG-2125 and the Department of Energys Yucca Mountain EIS) analyzed the routing as a HRCQ shipment as well as applied state-specific distances and population densities in urban, suburban, and rural areas. Both features are available in current online version of TRAGIS.
Response
Exelon Generation has revised both CALC-194-4735-02 and the Transportation Calculation Package using an updated RADTRAN analysis for LSCS high-burnup spent fuel. The revised RADTRAN analysis uses routing from WebTRAGIS that specifies HRCQ routesan option not available at the time the original RADTRAN analysis for the LSCS License Renewal Environmental Report was done. The HRCQ routing and associated state-specific distances and population densities are presented in the revised CALC-194-4735-02 (CALC-194-4735-02, Revision 1).