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Category:Letter
MONTHYEARIR 05000305/20240032024-11-0606 November 2024 NRC Inspection Report No. 05000305/2024003 ML24240A1692024-09-18018 September 2024 Cy 2023 Summary of Decommissioning Trust Fund Status IR 05000305/20240022024-08-22022 August 2024 NRC Inspection Report 05000305/2024002 ML24151A6482024-06-0303 June 2024 Changes in Reactor Decommissioning Branch Project Management Assignments for Some Decommissioning Facilities ML24136A1952024-05-14014 May 2024 2023 Annual Radiological Environmental Operating Report ML24130A0022024-05-0909 May 2024 Summary of Facility Changes, Tests and Experiments and Commitment Changes IR 05000305/20240012024-05-0202 May 2024 NRC Inspection Report No. 05000305/2024001 ML24121A2472024-04-29029 April 2024 And Three Mile Island, Unit 2 - 2023 Occupational Radiation Exposure Annual Report ML24101A0422024-04-22022 April 2024 Solutions Inc. – Exemption from Select Requirements of 10 CFR Part 73 ((Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML24106A0492024-04-15015 April 2024 2023 Annual Radioactive Effluent Release Report ML24080A0702024-03-20020 March 2024 Decommissioning Trust Fund Annual Report ML24079A0162024-03-19019 March 2024 Annual Property Insurance Status Report ML24073A2312024-03-13013 March 2024 And Three Mile Island Nuclear Station, Unit 2 - Management Change ML24061A0202024-02-15015 February 2024 (Ksp) ISFSI, Submittal of Security Plan, Training and Qualification Plan and Safeguards Contingency Plan, Revision 6 ML23339A1332024-01-26026 January 2024 Exemption from the Req of 10 CFR Part 50.82(a)(8)(i)(A) to Use the Kewaunee Decommissioning Trust Fund for the Management of Site Restoration Activities IR 05000305/20230022023-12-27027 December 2023 NRC Inspection Report 05000305/2023002 (Drss); 07200064/2023001 (Drss) ML23332A1922023-11-28028 November 2023 Solutions, Inc., Request for Exemptions from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23278A1002023-10-0505 October 2023 Response to Request for Additional Information (RAI) Application for Kewaunee Solutions (Ks) Site Restoration Activities ML23222A1522023-08-29029 August 2023 Letter RAI KPS Exemption Site Restoration Final Repaired IR 05000305/20230012023-08-17017 August 2023 NRC Inspection Report No. 05000305/2023001-Kewaunee Power Station ML23171B0822023-07-0505 July 2023 Letter - Kewaunee Power Station - Issuance of Exemption from Certain Requirements from 10 CFR Part 20, Appendix G, Section Iii.E ML23132A0012023-05-11011 May 2023 2022 Annual Radiological Environmental Operating Report ML23116A2182023-04-26026 April 2023 2022 Annual Radioactive Effluent Release Report ML23089A3042023-03-30030 March 2023 Decommissioning Fund Status Report ML23093A0312023-03-29029 March 2023 Solutions, Inc., Request for Exemptions from 10 CFR 50.82(a)(8)(i)(A) and 50.75(h)(1)(iv) for Site Restoration Activities ML23088A2752023-03-29029 March 2023 Solutions, Inc., Request for Exemption from 10 CFR 20, Appendix G, Section Iii.E ML23087A0292023-03-27027 March 2023 2022 Annual Report of Occupational Radiation Exposure ML23087A0402023-03-27027 March 2023 Annual Property Insurance Status Report ML23066A3232023-03-0707 March 2023 Energysolutions, LLC, Notification of Closing of Transaction ML22361A1022023-02-24024 February 2023 Reactor Decommissioning Branch Project Management Changes for Some Decommissioning Facilities and Establishment of Backup Project Manager for All Decommissioning Facilities ML23024A0122023-01-26026 January 2023 Letter to Energysolutions Transmitting Threshold Determination for Merger/Restructuring IR 05000305/20220022023-01-0303 January 2023 NRC Inspection Report Nos. 05000305/2022002(DRSS) – Kewaunee Power Station ML22292A2302022-11-25025 November 2022 U.S. Nuclear Regulatory Commission’S Analysis of Dominion Energy Kewaunee‘S Decommissioning Funding Status Report for Kewaunee Power Station, Docket No. 50-305 ML22290A0052022-10-13013 October 2022 Resubmittal of Kewaunee Power Station Independent Spent Fuel Storage Installation (ISFSI) Only Emergency Plan (Ioep) and IOEP- Emergency Action Level (EAL) Basis Document, Revision 0KS ML22241A0302022-08-25025 August 2022 (Ksp) ISFSI Submittal of Security Plan, Training and Qualification Plan and Safeguards Contingency Plan, Revision 5 ML24061A0182022-08-25025 August 2022 (Ksp) ISFSI Submittal of Security Pla11, Training and Qualification Plan and Safeguards Contingency Plan Revision 5 IR 05000305/20220012022-08-0101 August 2022 NRC Inspection Report Nos. 05000305/2022001(DNMS) - Kewaunee Power Station ML22215A1512022-07-27027 July 2022 Executed Financial Assurance Instruments for the Kewaunee License Transfer License No. DPR-43 (Docket Nos. 50-305, 72-64) ML22209A1252022-07-26026 July 2022 Amendment No. 11 to Indemnity Agreement No. B-53 for Kewaunee Power Station (KPS) - Signed by Kewaunee Solutions, Inc ML22175A1132022-06-30030 June 2022 Solutions, Inc. - Letter for Review and Acceptance of the Energysolutions, LLC Decommissioning Quality Assurance Program with Enclosure ML22160A5282022-06-28028 June 2022 Enclosure 2 - Amendment No. 11 to Indemnity Agreement B-53 ML22160A5262022-06-28028 June 2022 Letter - KPS - Issuance of Conforming License Amendment Regarding Indirect Transfer of License from DEK, Inc. to Kewaunee Solutions, Inc ML22160A5272022-06-28028 June 2022 Enclosure 1 - Amendment No. 221 to Renewed Facility Operating License No. DPR-43 ML22188A0812022-06-23023 June 2022 ISFSI, Virgil C. Summer Nuclear Station, Unit 1 & ISFSI, North Anna Power Station, Units 1 & 2 & ISFSI, Surry Power Station, Units 1 & 2 & ISFSI - Submission of Revision 32 of the Quality Assurance Topical Report ML22172A2452022-06-22022 June 2022 Notification of Planned Closing Date and Required Regulatory Approvals for the Kewaunee License Transfer Transaction ML22175A0662022-06-17017 June 2022 Designation of Additional Reviewing Official for ISFSI and 10 CFR Part 37 Program Security Background Investigations ML22166A3392022-06-13013 June 2022 Notification of Nuclear Insurance ML22158A2112022-05-10010 May 2022 Summary of Facility Changes, Tests and Experiments and Summary of Commitment Changes ML22138A2552022-05-10010 May 2022 Submittal of 2021 Annual Radiological Environmental Operating Report ML22108A0352022-04-0101 April 2022 License Transfer to Kewaunee Solutions, Inc 2024-09-18
[Table view] Category:Test/Inspection/Operating Procedure
MONTHYEARML22158A2112022-05-10010 May 2022 Summary of Facility Changes, Tests and Experiments and Summary of Commitment Changes ML14163A1202014-05-29029 May 2014 Summary of Facility Changes, Tests and Experiments and Commitment Changes ML13154A0142013-05-29029 May 2013 Summary of Facility Changes, Tests and Experiments and Commitment Changes 2022-05-10
[Table view] |
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Dominion Energy Kewaunee, Inc.
N490 Hwy 42, Kewaunee, WI 54216 Web Address: www.dominionenergy.com MAY l O 2022 ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555-0001 DOMINION ENERGY KEWAUNEE, INC.
KEWAUNEE POWER STATION ft Dominion
,.., Energy Serial No.22-148 LIC/RR/R0 Docket Nos.: 50-305, 72-64 License No.: DPR-43
SUMMARY
OF FACILITY CHANGES, TESTS AND EXPERIMENTS AND
SUMMARY
OF COMMITMENT CHANGES Pursuant to 10 CFR 50.59( d){2) and 10 CFR 72.48( d)(2), a report containing a brief description of any changes, tests, and experiments, including a summary of the evaluation of each, must be submitted to the NRC at intervals not to exceed 24 months..
There were no 1 0 CFR 50.59 Evaluations completed and implemented during the period since our prior submittal dated May 11, 2020 (Reference 1 ). Attachment 1 provides a summary description of Facility Changes, Tests and Experiments identified in 1 0 CFR 72.48 evaluations performed for the Kewaunee Power Station (KPS) during the last 24 months.
No commitment changes occurred during the last 24 months.
If you have any questions or require additional information, please contact Mr. William Zipp at 920-304-9729.
Sincerely, Bradly. J. McMahon Director Kewaunee Site Commitments made by this letter: NONE
Reference:
- 1. Letter from Bradly J. McMahon (Dominion Energy Kewaunee, Inc.) to Document Control Desk (NRC), "Summary of Facility Changes, Tests and Experiments and Summary of Commitment Changes," dated May 11, 2020.
Serial No.22-148 ATTACHMENT 1
SUMMARY
OF FACILITY CHANGES, TESTS AND EXPERIMENTS AND
SUMMARY
OF COMMITMENT CHANGES KEWAUNEE POWER STATION DOMINION ENERGY KEWAUNEE, INC.
72.48 Evaluation - NAC International CAR 21-02 Activity Evaluated Serial No.22-148 Page 11 NAC International, MAGNASTOR Final Safety Analysis Report, per licensing design change request DCR(L) 71160-FSAR-11A and 72.48 evaluation number NAC-21-MAG-029.
Brief Description of Change MAGNASTOR FSAR Section 4, Thermal Evaluatjon, subsections 4.4, 4.9, 4.10, 4.11 and various Tables in subsection 4.4 were revised to reflect corrections made to thermal models. Specifically, the value used for fuel pellet size as an input to the thermal modeling was corrected, and this affected thermal evaluations and their results.
Reason for Change In NAC thermal modeling used to determine the effective thermal properties for PWR fuel assemblies in NAC dry fuel storage systems including the MAGNASTOR system in use at Kewaunee Power Station, incorrect fuel rod dimensions were used. Fuel rod cladding outside diameter was used in error as fuel pellet diameter. This produces non-conservative thermal results (e.g., higher peak cladding temperatures) for transient conditions such as vacuum drying and Transportable Storage Canister transfer conditions. Revisions were made in several areas of FSAR Section 4 to correct the modeling error. For the NAC MAGNASTOR system the reanalyzed results remained within the established limits for maximum fuel cladding temperature in the current KPS FSAR Rev. 8 Table 2.1-1 of 752 deg.F. for normal and transfer conditions; and 1058 deg.F. for off-normal and accident conditions.
Summary of the Evaluation The effective thermal properties were updated and the effective properties for PWR 14x14 fuel are shown in Table 4.4-1. Thermal analysis were re-performed. The updated system temperatures remain less than the applicable temperature limits for normal, off-normal and accident conditions as described in the FSAR (as updated) and cask CoC. The updated system temperatures do not have any impact on the operating procedures and the system meets the applicable NRC requirements and design standards as detailed in the FSAR (as updated).
Therefore, the change in system temperatures is considered a minimal increase and does not affect the frequency of occurrence of an accident previously evaluated in the FSAR (as updated).
The changes do not involve a revision to the design, fabrication, construction, testing and performance standards previously used for the MAGNASTOR storage system. The temperatures remain below the allowable temperatures and do not affect the functional requirement of the MTC /
PMTC for transfer operation or the concrete cask for the storage condition. The updated temperatures do not require changes of the operational time limits for the system (such as LCO 3.1.1) or thermal contingency events (potential malfunction) as described in the FSAR (as updated).
The changes do not reduce the system I equipment redundancy, diversity, separation, or independence, nor substitute any manual actions for an automatic action for performing design functions described in the FSAR (as updated).
The radiological consequences of accidents or malfunctions previously evaluation in the FSAR (as update) are not impacted, by the updated fuel cladding temperatures for the transfer operation or storage condition.
Thermal evaluations for storage and transfer conditions were reperformed. Updated fuel clad temperatures remain below the allowable temperatures, though the updated temperatures are in some cases higher than those presented in the existing FSAR sections, tables, and figures.
The modeling method used is consistent with the thermal models used for the concrete cask, TSC, and transfer cask as described in the FSAR. Only the effective properties used as input
Serial No.22-148 Page 12 were changed. Also, the methodology for how the effective thermal property is calculated is not revised or replaced. Only the input parameters into the method are changed (i.e., fuel rod physical dimensions). Therefore, the change does not result in a departure from a method of evaluation described in the FSAR (as updated).