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MONTHYEARML16182A3612016-08-0404 August 2016 Staff Review of Spend Fuel Pool Evaluation Associated with Reevaluation Seismic Hazard Implementing Near-Term Task Force Recommendation 2.1 Project stage: Approval 2016-08-04
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Category:Letter
MONTHYEARML24019A1672024-01-31031 January 2024 Issuance of Amendment to Renewed Facility License to Add License Condition to Include License Termination Plan Requirements IR 05000285/20230062023-12-21021 December 2023 NRC Inspection Report 05000285/2023006 LIC-23-0007, Response to Fort Calhoun, Unit 1 & Independent Spent Fuel Storage Installation Review of License Amendment Request to Add License Condition to Include License Termination Plan Requirements Request for Additional Information2023-12-0606 December 2023 Response to Fort Calhoun, Unit 1 & Independent Spent Fuel Storage Installation Review of License Amendment Request to Add License Condition to Include License Termination Plan Requirements Request for Additional Information IR 05000285/20230052023-11-0202 November 2023 NRC Inspection Room 05000285/2023005 ML23276A0042023-09-28028 September 2023 U.S. EPA Response Letter to NRC Letter on Consultation and Finality on Decommissioning and Decontamination of Contaminated Sites MOU - Fort Calhoun Station, Unit 1 (License No. DPR-40, Docket No. 50-285) IR 05000285/20230042023-09-13013 September 2023 NRC Inspection Report 05000285/2023-004 LIC-23-0005, Response to Fort Calhoun Station, Unit No. 1 - Review of License Amendment Request to Add License Condition to Include License Termination Plan Requirements - 2nd Request for Additional Information (EPID L-2021-LIT-0000) June 2, 20232023-08-24024 August 2023 Response to Fort Calhoun Station, Unit No. 1 - Review of License Amendment Request to Add License Condition to Include License Termination Plan Requirements - 2nd Request for Additional Information (EPID L-2021-LIT-0000) June 2, 2023 ML23234A2412023-08-18018 August 2023 Email - Letter to M Porath Re Ft Calhoun Unit 1 LTP EA Section 7 Informal Consultation Request ML23234A2392023-08-18018 August 2023 Letter to B Harisis Re Ft Calhoun Unit 1 LTP EA State of Nebraska Comment Request.Pdf IR 05000285/20230032023-07-10010 July 2023 NRC Inspection Report 05000285/2023003 ML23082A2202023-06-26026 June 2023 Consultation on the Decommissioning of the Fort Calhoun Station Unit 1 Pressurized Water Reactor in Fort Calhoun, Nebraska ML23151A0032023-06-0505 June 2023 Review of License Amendment Request to Add License Condition to Include License Termination Plan Requirements 2nd Request for Additional Information (EPID L-2021-LIT-0000) June 2, 2023 IR 05000285/20230022023-06-0505 June 2023 NRC Inspection Report 05000285/2023002 LIC-23-0004, (FCS) Radiological Effluent Release Report and Radiological Environmental Operating Report2023-04-20020 April 2023 (FCS) Radiological Effluent Release Report and Radiological Environmental Operating Report LIC-23-0003, Annual Decommissioning Funding / Irradiated Fuel Management Status Report2023-03-15015 March 2023 Annual Decommissioning Funding / Irradiated Fuel Management Status Report LIC-23-0001, Response to Fort Calhoun Station, Unit No. 1 - Review of License Amendment Request to Add License Condition to Include License Termination Plan Requirements - Request for Additional Information2023-02-27027 February 2023 Response to Fort Calhoun Station, Unit No. 1 - Review of License Amendment Request to Add License Condition to Include License Termination Plan Requirements - Request for Additional Information IR 05000285/20230012023-02-24024 February 2023 NRC Inspection Report 05000285/2023001 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 LIC-23-0002, Independent Spent Fuel Storage Installation, Annual Radioactive Effluent Release Report2023-02-20020 February 2023 Independent Spent Fuel Storage Installation, Annual Radioactive Effluent Release Report ML23020A0462023-01-19019 January 2023 Threatened and Endangered Species List: Nebraska Ecological Services Field Office IR 05000285/20220062023-01-0505 January 2023 NRC Inspection Report 05000285/2022-006 ML22357A0662022-12-30030 December 2022 Technical RAI Submittal Letter on License Amendment Request for Approval of License Termination Plan IR 05000285/20220052022-10-26026 October 2022 NRC Inspection Report 05000285/2022-005 ML22276A1052022-09-30030 September 2022 Conclusion of Consultation Under Section 106 NHPA for Ft. Calhoun Station LTP ML22258A2732022-09-29029 September 2022 Letter to John Swigart, Shpo; Re., Conclusion of Consultation Under Section 106 Hnpa Fort Calhoun Station Unit 1 ML22265A0262022-09-26026 September 2022 U.S. Nuclear Regulatory Commission'S Analysis of Omaha Public Power District'S Decommissioning Status Report (License No. DPR-40, Docket No. 50-285) IR 05000285/20220042022-09-14014 September 2022 NRC Inspection Report 05000285/2022004 ML22138A1252022-08-0303 August 2022 Letter to Mr. Timothy Rhodd, Chairperson, Iowa Tribe of Kansas and Nebraska, Re., Ft Calhoun LTP Section 106 ML22138A1262022-08-0303 August 2022 Letter to Roger Trudell, Chairman, Santee Sioux Nation, Nebraska, Re., Ft Calhoun LTP Section 106 ML22101A1092022-08-0303 August 2022 Letter to Mr. Durell Cooper, Chairman, Apache Tribe of Oklahoma; Re., Ft Calhoun LTP Section 106 ML22138A1242022-08-0303 August 2022 Letter to Mr. Reggie Wassana, Governor, Cheyenne and Arapaho Tribes, Oklahoma, Re., Ft Calhoun LTP Section 106 ML22138A1292022-08-0303 August 2022 Letter to Tiauna Carnes, Chairperson, Sac and Fox Nation of Missouri in Kansas, Re., Ft Calhoun LTP Section 106 ML22138A1212022-08-0303 August 2022 Letter to Mr. Edgar Kent, Chairman, Iowa Tribe of Oklahoma, Re., Ft Calhoun LTP Section 106 ML22138A1282022-08-0303 August 2022 Letter to Victoria Kitcheyan, Chairwoman, Winnebago Tribe of Nebraska, Re., Ft Calhoun LTP Section 106 ML22138A1232022-08-0303 August 2022 Letter to Mr. Leander Merrick, Chairperson, Omaha Tribe of Nebraska, Re., Ft Calhoun LTP Section 106 ML22138A1222022-08-0303 August 2022 Letter to Mr. John Shotton, Chairman, Otoe-Missouria Tribe of Indians, Oklahoma, Re., Ft Calhoun LTP Section 106 ML22138A1272022-08-0303 August 2022 Letter to Vern Jefferson, Chairman, Sac and Fox Tribe of the Mississippi in Iowa, Re., Ft Calhoun LTP Section 106 ML22214A0922022-08-0303 August 2022 Letter to Stacy Laravie, Thpo, Ponca Tribe of Nebraska, Re., Ft Calhoun LTP Section 106 ML22138A1302022-08-0303 August 2022 Letter to Justin Wood, Principal Chief, Sac and Fox Nation, Oklahoma, Re., Ft Calhoun LTP Section 106 ML22159A2152022-06-28028 June 2022 Letter Forwarding FRN on Public Meeting and Request for Comment on License Termination Plan LIC-22-0010, Response to Fort Calhoun Station, Unit No. 1 - Review of License Termination Plan Requirements - Request for Additional Information2022-06-15015 June 2022 Response to Fort Calhoun Station, Unit No. 1 - Review of License Termination Plan Requirements - Request for Additional Information IR 05000285/20220032022-06-15015 June 2022 NRC Inspection Report 05000285/2022003 ML22119A2472022-05-0303 May 2022 Review of Amendment Request to Add a LC to Include LTP Requirements, RAI for Environmental Review IR 05000285/20220022022-04-28028 April 2022 NRC Inspection Report 050-00285/2022-002 LIC-22-0005, (FCS) Radiological Effluent Release Report and Radiological Environmental Operating Report2022-04-20020 April 2022 (FCS) Radiological Effluent Release Report and Radiological Environmental Operating Report LIC-22-0009, Annual Decommissioning Funding / Irradiated Fuel Management Status Report2022-03-30030 March 2022 Annual Decommissioning Funding / Irradiated Fuel Management Status Report 2024-01-31
[Table view] Category:Report
MONTHYEARLIC-22-0006, Reactor Head Disposition Project Overview2022-03-17017 March 2022 Reactor Head Disposition Project Overview LIC-22-0001, Well Water Results with River Stage2022-01-13013 January 2022 Well Water Results with River Stage ML22034A5942021-12-22022 December 2021 Hydrogeological Conceptual Site Model, Rev. 5 ML21271A5242021-08-0303 August 2021 License Amendment Request (LAR) 21-01, CM-244 Soil Regression and Correlation Report ML21271A2102021-08-0303 August 2021 License Amendment Request (LAR) 21-01, Chapter 4 3 Omaha Public Power District, Fort Calhoun Station Unit 1, Defueled Safety Analysis Report CAC 2 ML21271A1442021-08-0303 August 2021 License Amendment Request (LAR) 21-01, FCS LTP Rev 0. Final - All ML21271A3052021-08-0303 August 2021 License Amendment Request (LAR) 21-01, FCS Bfm Insitu Regression and Correlation Report TC-99 ML21271A2112021-08-0303 August 2021 License Amendment Request (LAR) 21-01, Chapter 5 18 Radiation Safety and Control Services, Tsd 21-043, Radionuclides of Concern in Support of the Fort Calhoun License Termination Plan ML21271A4082021-08-0303 August 2021 License Amendment Request (LAR) 21-01, FCS Buried Pipe Insitu Uncertainty Report Eu-152 ML21271A3852021-08-0303 August 2021 License Amendment Request (LAR) 21-01, FCS Buried Pipe Excavation Dsr 0.15 M ML21271A5212021-08-0303 August 2021 License Amendment Request (LAR) 21-01, CM-244 Soil Uncertainty Report ML21271A5222021-08-0303 August 2021 License Amendment Request (LAR) 21-01, CM-243 Soil Uncertainty Report ML21271A1802021-08-0303 August 2021 License Amendment Request (LAR) 21-01, Chapter 2 19, Omaha Public Power District, FC-20-012, Fort Calhoun Station Decommissioning Project Radiological Characterization Report ML21271A2722021-08-0303 August 2021 License Amendment Request (LAR) 21-01, FCS Drilling Spoils Dsr ML21271A5172021-08-0303 August 2021 License Amendment Request (LAR) 21-01, EU-154 Soil Uncertainty Report ML21271A3262021-08-0303 August 2021 License Amendment Request (LAR) 21-01, FCS Bfm Insitu Regression and Correlation Report NI-63 ML21271A6002021-08-0303 August 2021 License Amendment Request (LAR) 21-01, Chapter 8, 13, Omaha Public Power District, Offsite Dose Calculation Manual CAC2 ML21271A4502021-08-0303 August 2021 License Amendment Request (LAR) 21-01, FCS Soil AF 100 Dcgl 0.15 M.Rad ML21271A4782021-08-0303 August 2021 License Amendment Request (LAR) 21-01, Eu-152 Soil Uncertainty Report ML21271A4802021-08-0303 August 2021 License Amendment Request (LAR) 21-01, C-14 Soil Uncertainty Report ML21271A2582021-08-0303 August 2021 License Amendment Request (LAR) 21-01, Chapter 6 8 Radiation Safety and Control Services, Tsd 21-043, Radionuclides of Concern in Support of the Fort Calhoun -1 ML21271A1962021-08-0303 August 2021 License Amendment Request (LAR) 21-01, Chapter 3, 1, Omaha Public Power District, Defueled Safety Analysis Report CAC 2 ML21271A4772021-08-0303 August 2021 License Amendment Request (LAR) 21-01, CO-60 Soil Regression and Correlation Report ML21271A3212021-08-0303 August 2021 License Amendment Request (LAR) 21-01, FCS Bfm Insitu Uncertainty Report SR-90 ML21271A4852021-08-0303 August 2021 License Amendment Request (LAR) 21-01, NI-63 Soil Regression and Correlation Report ML21271A2902021-08-0303 August 2021 License Amendment Request (LAR) 21-01, FCS Bfm Insitu Uncertainty Report H-3 ML21271A4832021-08-0303 August 2021 License Amendment Request (LAR) 21-01, Eu-155 Soil Uncertainty Report ML21271A4952021-08-0303 August 2021 License Amendment Request (LAR) 21-01, CS-134 Soil Regression and Correlation Report ML21271A3012021-08-0303 August 2021 License Amendment Request (LAR) 21-01, FCS Bfm Insitu Uncertainty Report C-14 ML21271A5092021-08-0303 August 2021 License Amendment Request (LAR) 21-01, EU-152 Soil Regression and Correlation Report ML21271A2612021-08-0303 August 2021 License Amendment Request (LAR) 21-01, Chapter 6 1 Haley & Aldrich, Hydrogeological Conceptual Site Model, Rev. 2, Fort Calhoun Station, Blair, Ne, 2021 CAC2 ML21271A2652021-08-0303 August 2021 License Amendment Request (LAR) 21-01, Chapter 6 7 FC-20-007, Fort Calhoun Station Potential Radionuclides of Concern CAC2 ML21271A5052021-08-0303 August 2021 License Amendment Request (LAR) 21-01, CO-58 Soil Uncertainty Report ML21271A4872021-08-0303 August 2021 License Amendment Request (LAR) 21-01, EU-154 Soil Regression and Correlation Report ML21271A4882021-08-0303 August 2021 License Amendment Request (LAR) 21-01, CS-137 Soil Uncertainty Report ML21271A2862021-08-0303 August 2021 License Amendment Request (LAR) 21-01, FCS Bfm Insitu Regression and Correlation Report H-3 ML21271A2192021-08-0303 August 2021 License Amendment Request (LAR) 21-01, Chapter 5 12 FC-20-007, Fort Calhoun Station Potential Radionuclides of Concern CAC2 ML21271A2622021-08-0303 August 2021 License Amendment Request (LAR) 21-01, Chapter 6 2 Radiation Safety and Control Services, Tsd 20-001, Historical Site Assessment for Fort Calhoun Station - F-1 ML21271A2752021-08-0303 August 2021 License Amendment Request (LAR) 21-01, FCS Bfm Insitu Scenario Dsr ML21271A4972021-08-0303 August 2021 License Amendment Request (LAR) 21-01, CO-58 Soil Regression and Correlation Report ML21271A5042021-08-0303 August 2021 License Amendment Request (LAR) 21-01, CM-243 Soil Regression and Correlation Report ML21271A2672021-08-0303 August 2021 License Amendment Request (LAR) 21-01, Chapter 6 3 Omaha Public Power District, Fort Calhoun Station Unit 1, Defueled Safety Analysis Report CAC2 ML21271A2692021-08-0303 August 2021 License Amendment Request (LAR) 21-01, Chapter 6 19 E. A. Napier, Hanford Environmental Dosimetry Upgrade Project, Gen II the Hanford Environmental Radiation D-1 ML21271A3862021-08-0303 August 2021 License Amendment Request (LAR) 21-01, FCS Buried Pipe Excavation Dsr 1.0 M ML21271A2002021-08-0303 August 2021 License Amendment Request (LAR) 21-01, Chapter 3 14 Backfill Attachment Final CAC 2 ML21271A4572021-07-28028 July 2021 License Amendment Request (LAR) 21-01, FCS Soil AF 143 Dcgl 0.15 M ML21271A4562021-07-28028 July 2021 License Amendment Request (LAR) 21-01, FCS Soil AF 143 Dcgl 1 M ML21271A1982021-07-24024 July 2021 License Amendment Request (LAR) 21-01, Chapter 3, 6, Omaha Public Power District, FC-21-002, Description of Embedded Piping, Penetrations, and Buried Pipe to Remain in Fort Calhoun End State ML21271A2602021-07-24024 July 2021 License Amendment Request (LAR) 21-01, Chapter 6 4, Omaha Public Power District, FC-21-002, Description of Embedded Piping, Penetrations, and Buried Pipe to Remain in Fort Calhoun End State ML21271A2132021-07-23023 July 2021 License Amendment Request (LAR) 21-01, Chapter 5 9 Oddp FC-20-006 - End State Concrete Surface Areas and Volumes Rev 0 CAC2 2022-03-17
[Table view] Category:Miscellaneous
MONTHYEARML21271A2002021-08-0303 August 2021 License Amendment Request (LAR) 21-01, Chapter 3 14 Backfill Attachment Final CAC 2 ML21271A1742017-03-0202 March 2017 License Amendment Request (LAR) 21-01, Chapter 2 20 Storm Water Discharge Authorization Permit Renewal NER910677 Package for FCS cac2 ML16182A3612016-08-0404 August 2016 Staff Review of Spend Fuel Pool Evaluation Associated with Reevaluation Seismic Hazard Implementing Near-Term Task Force Recommendation 2.1 LIC-16-0031, Ft. Calhoun, Unit 1 - Annual Report for 2015 Loss-of-Coolant Accident (Loca)/Emergency Core Cooling System (ECCS) Models Pursuant to 10 CFR 50.462016-04-28028 April 2016 Ft. Calhoun, Unit 1 - Annual Report for 2015 Loss-of-Coolant Accident (Loca)/Emergency Core Cooling System (ECCS) Models Pursuant to 10 CFR 50.46 LIC-16-0013, Ft. Calhoun, Unit 1 and ISFSI - Transmittal of 10CFR72.48 Evaluation Summary Report for January 1, 2015 Through December 31, 20152016-02-10010 February 2016 Ft. Calhoun, Unit 1 and ISFSI - Transmittal of 10CFR72.48 Evaluation Summary Report for January 1, 2015 Through December 31, 2015 LIC-15-0005, (Fcs), Unit No. 1, 10 CFR 72.48 Evaluation Summary Report for January 1, 2013 Through December 31, 20142015-01-15015 January 2015 (Fcs), Unit No. 1, 10 CFR 72.48 Evaluation Summary Report for January 1, 2013 Through December 31, 2014 ML14226A5512014-08-14014 August 2014 Revision of Standard Practice Procedures Plan for Fort Calhoun Station, Unit 1 ML14157A0792014-06-24024 June 2014 Staff Assessment of the Flooding Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Fukushima Dai-Ichi Nuclear Power Plant Accident ML14105A3732014-04-22022 April 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to Fukushima Dai-Ichi Nuclear Power Plant Accident LIC-14-0047, Omaha Public Power District - Seismic Hazard and Screening Report (CEUS Sites), Response 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 Fukushi2014-03-31031 March 2014 Omaha Public Power District - Seismic Hazard and Screening Report (CEUS Sites), Response 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 ML13172A3432013-06-19019 June 2013 Integrated Performance Improvement Plan, Revision 5, Page 138 Through End LIC-13-0086, Integrated Performance Improvement Plan, Revision 5, Cover Through Page 732013-06-19019 June 2013 Integrated Performance Improvement Plan, Revision 5, Cover Through Page 73 ML13172A3422013-06-19019 June 2013 Integrated Performance Improvement Plan, Revision 5, Page 74 Through Page 137 ML12340A2542012-11-27027 November 2012 OPPD 180-day Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident. Part 2 of 3 ML12340A2552012-11-27027 November 2012 OPPD 180-day Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident. Part 2 of 3 LIC-12-0098, Integrated Performance Improvement Plan, Rev. 32012-07-0909 July 2012 Integrated Performance Improvement Plan, Rev. 3 ML11276A1202011-09-28028 September 2011 Enclosure 1 to LIC-11-0099, License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants (2001 Edition) LIC-11-0099, Table B-2 Nuclear Safety Capability Assessment Methodology Review2011-09-28028 September 2011 Table B-2 Nuclear Safety Capability Assessment Methodology Review LIC-11-0090, Post-Flooding Recovery Action Plan2011-08-10010 August 2011 Post-Flooding Recovery Action Plan ML1012704392010-05-0505 May 2010 Y020100187 - List of Historical Leaks and Spills at U.S. Commercial Nuclear Power Plants LIC-08-0120, Steam Generator Eddy Current Test Report - 2008 Refueling Outage2008-12-0909 December 2008 Steam Generator Eddy Current Test Report - 2008 Refueling Outage LIC-08-0107, Notice of Completion of Corrective Actions Taken in Response to Generic Letter 2004-02 and Response to Request for Additional Information2008-10-16016 October 2008 Notice of Completion of Corrective Actions Taken in Response to Generic Letter 2004-02 and Response to Request for Additional Information LIC-08-0071, Transmittal of Fort Calhoun, Unit 1, Reactor Coolant System Pressure and Temperature Limits Report, Revision 42008-05-27027 May 2008 Transmittal of Fort Calhoun, Unit 1, Reactor Coolant System Pressure and Temperature Limits Report, Revision 4 LIC-07-0017, Fitness-for-Duty Program Performance Data Report for July 1 Through December 31, 20062007-02-22022 February 2007 Fitness-for-Duty Program Performance Data Report for July 1 Through December 31, 2006 LIC-06-0138, Transmittal of Revision 3 of Fort Calhoun Station, Unit No. 1 (Fcs), Pressure Temperature Limits Report (PTLR)2006-11-29029 November 2006 Transmittal of Revision 3 of Fort Calhoun Station, Unit No. 1 (Fcs), Pressure Temperature Limits Report (PTLR) LIC-06-0083, Fitness-for-Duty Program Performance Report2006-07-26026 July 2006 Fitness-for-Duty Program Performance Report LIC-06-0056, Request for Exemption from Nuhoms Certificate of Compliance No. 1004, Amendment No. 82006-06-0909 June 2006 Request for Exemption from Nuhoms Certificate of Compliance No. 1004, Amendment No. 8 ML0606501772006-03-0606 March 2006 Licensed Operator Positive Drug Tests ML0535403192005-12-0505 December 2005 51-9004805-001, FCS RSG - Afas Verification - RAI Responses. LIC-05-0043, Supplemental Information for Relaxation Request for First Revised Order (EA-03-009) Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads at Pressurized Water Reactors2005-04-15015 April 2005 Supplemental Information for Relaxation Request for First Revised Order (EA-03-009) Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads at Pressurized Water Reactors LIC-05-0016, Omaha Public Power District, Fitness-for-Duty Program Performance Data Report2005-02-0404 February 2005 Omaha Public Power District, Fitness-for-Duty Program Performance Data Report ML0727008492005-01-31031 January 2005 Caldon Experience in Nuclear Feedwater Flow Measurement LIC-06-0004, Attachment 1, Engineering Analysis (EA-FC-04-010) Recommendations for Implementing of Compensatory Actions in Response to NRC Bulletin 2003-012004-11-23023 November 2004 Attachment 1, Engineering Analysis (EA-FC-04-010) Recommendations for Implementing of Compensatory Actions in Response to NRC Bulletin 2003-01 LIC-04-0081, Fitness-for-Duty Program Performance Data Report for Six Month Period from January 1 Through June 30, 20042004-07-14014 July 2004 Fitness-for-Duty Program Performance Data Report for Six Month Period from January 1 Through June 30, 2004 ML0532204612004-06-14014 June 2004 Power Reactor Status Report for 6/14/04 ML0626304082004-03-0101 March 2004 PSEG Nuclear, LLC Salem/Hope Creek Safety Culture Assessment LIC-03-0154, Relief Request Pertaining to Reactor Vessel Nozzle Inspection for Third 10-Year Interval Revision2003-11-21021 November 2003 Relief Request Pertaining to Reactor Vessel Nozzle Inspection for Third 10-Year Interval Revision LIC-03-0124, Transmittal of Fort Calhoun Station (FCS) Pressure Temperature Limits Report (Ptlr), Revision 02003-09-10010 September 2003 Transmittal of Fort Calhoun Station (FCS) Pressure Temperature Limits Report (Ptlr), Revision 0 LIC-03-0119, Fitness-for-Duty Program Performance Data Report2003-08-27027 August 2003 Fitness-for-Duty Program Performance Data Report ML0314102122003-05-20020 May 2003 Thesis (Miscellaneous Report - 134 Pages), Fort Calhoun, S107100 LIC-03-0063, Fire Modeling Analysis - Fire Area 322003-04-25025 April 2003 Fire Modeling Analysis - Fire Area 32 LIC-03-0038, Comments on Letter from Us Fish and Wildlife Service Re Impact of Plant Operation on Pallid Sturgeon2003-03-14014 March 2003 Comments on Letter from Us Fish and Wildlife Service Re Impact of Plant Operation on Pallid Sturgeon ML0232904702002-11-22022 November 2002 Issuance of Environmental Scoping Summary Report Associated with Staff'S Review of Application for Renewal of Operating License for Fort Calhoun Station, Unit 1 LIC-02-0104, Omaha Public Power District Fitness-for-Duty Program Performance Data Report2002-08-29029 August 2002 Omaha Public Power District Fitness-for-Duty Program Performance Data Report LIC-02-0054, Annual Report for 2001 Loss of Coolant Accident (Loca)/Emergency Core Cooling System (ECCS) Models Pursuant to 10CFR50.462002-04-30030 April 2002 Annual Report for 2001 Loss of Coolant Accident (Loca)/Emergency Core Cooling System (ECCS) Models Pursuant to 10CFR50.46 LIC-02-0046, Special Report on Inoperability of Main Steam Line Radiation Monitor RM-064 for Post-Accident Monitoring2002-04-16016 April 2002 Special Report on Inoperability of Main Steam Line Radiation Monitor RM-064 for Post-Accident Monitoring LIC-02-0023, Fitness-for-Duty Program Performance Data Report from Omaha Public Power District, July 1 Through December 31, 20012002-02-26026 February 2002 Fitness-for-Duty Program Performance Data Report from Omaha Public Power District, July 1 Through December 31, 2001 2021-08-03
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 August4,2016 Mr. Shane M. Marik Site Vice President and Chief Nuclear Officer Omaha Public Power District Fort Calhoun Station Mail Stop FC-2-4 9610 Power Lane Blair, NE 68008
SUBJECT:
FORT CALHOUN STATION, UNIT 1 - STAFF REVIEW OF SPENT FUEL POOL EVALUATION ASSOCIATED WITH REEVALUATED SEISMIC HAZARD IMPLEMENTING NEAR-TERM TASK FORCE RECOMMENDATION 2.1 (CAC NO. MF3735)
Dear Mr. Marik:
The purpose of this letter is to inform Omaha Public Power District (OPPD, the licensee) of the results of the U.S. Nuclear Regulatory Commission (NRG) staff's review of the spent fuel pool (SFP) evaluation tor Fort Calhoun Station, Unit 1 (Fort Calhoun), which was submitted in response to Item 9 of the NRC's March 12, 2012, request for information issued pursuant to Title 10 of the Code of Federal Regulations Part 50, Section 50.54(f) (hereafter referred to as the 50.54(f) letter). The NRG staff concludes that the licensee's assessment was performed consistent with the NRG-endorsed SFP Evaluation Guidance Report and has provided sufficient information to complete the response to Item 9 of the 50.54(f) request for information.
BACKGROUND By letter dated March 12, 2012 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML12053A340), the NRG issued a request for information. The request was issued as part of implementing lessons learned from the accident at the Fukushima Dai-ichi nuclear power plant. Enclosure 1 to the 50.54(f) letter requested that licensees reevaluate seismic hazards at their sites using present-day methodologies and guidance. , Item 4, of the 50.54(f) letter requested that licensees perform a comparison of the ground motion response spectrum (GMRS) and safe shutdown earthquake (SSE). The staff's assessment of the information provided in response to Items 1-7 of the 50.54(f) is provided by letter dated December 8, 2015 (ADAMS Accession No. ML15329A181 ). Enclosure 1, Item 9, of the 50.54(f) letter requested that, when the GMRS exceeds the SSE in the 1 to 1O Hertz frequency range, a seismic evaluation be made of the SFP. More specifically, plants were asked to consider " ... all seismically induced failures that can lead to draining of the SFP."
S. Marik By letter dated February 23, 2016 (ADAMS Accession No. ML16055A021 ), the Nuclear Energy Institute (NEI) staff submitted Electric Power Research Institute (EPRI) Report No. 3002007148 entitled , "Seismic Evaluation Guidance: Spent Fuel Pool Integrity Evaluation" (SFP Evaluation Guidance Report). The SFP Evaluation Guidance Report provides criteria for evaluating the seismic adequacy of a SFP to the reevaluated GMRS hazard levels. This report supplements the guidance in the Seismic Evaluation Guidance, Screening, Prioritization and Implementation Details (SPID) (ADAMS Accession No. ML12333A170), for plants where the GMRS peak spectral acceleration is less than or equal to 0.8g (low GMRS sites). The NRC endorsed the SFP Evaluation Guidance Report by letter dated March 17, 2016 (ADAMS Accession No. ML15350A158), as an acceptable method for licensees to use when responding to NRC Item 9 in Enclosure 1 of the 50.54(f) letter.
By letter dated October 27, 2015 (ADAMS Accession No. ML15194A015) , the NRC staff stated that SFP evaluation submittals for low GMRS sites are expected by December 31 , 2016.
REVIEW OF LICENSEE SPENT FUEL POOL EVALUATION By letter dated May 25, 2016 (ADAMS Accession No. ML16146A545), OPPD submitted its SFP evaluation for Fort Calhoun for NRC review. The NRC staff assessed the licensee's implementation of the SFP Evaluation Guidance through the completion of a reviewer checklist, which is included in Enclosure 1 to this letter.
TECHNICAL EVALUATION Section 3.0 of the SFP Evaluation Guidance Report develops SFP evaluation criteria for plants with a GMRS peak spectral acceleration less than or equal to 0.8g. These criteria address SFP structural elements (e.g., floors, walls , and supports); non-structural elements (e.g.,
penetrations) ; seismic-induced SFP sloshing; and water loses due to heat-up and boil-off.
Section 3 also provides applicability criteria, which will enable licensees to determine if their site-specific conditions are within the bounds considered in developing the evaluation criteria this report. The staff's review consists of confirming that these SFP site-specific conditions are within the bounds considered for the evaluation criteria specified in the SFP Evaluation Guidance Report.
1.1 Spent Fuel Pool Structural Evaluation Section 3.1 of the SFP Evaluation Guidance Report provides a SFP structural evaluation approach used to demonstrate that the SFP structure is sufficiently robust against the reevaluated seismic hazard. This approach supplements the guidance in Section 7 of the SPID and followed acceptable methods used to assess the seismic capacity structures, systems, and components (SSCs) of nuclear power plants as documented in EPRI NP-6041 1 . Table 3-2 of the SFP Evaluation Guidance Report (reproduced from Table 2.3 of EPRI NP-6041) provides the structural screening criteria to assess the SFPs and their supporting structures.
The licensee stated that it followed the SFP structural evaluation approach presented in the SFP Evaluation Guidance Report and provided site-specific data to confirm its applicability. The NRC staff reviewed the structural information provided, which included the requested site-1 A Methodology for Assessment of Nuclear Plant Seismic Margin, Revision 1. EPRI , Palo Alto, CA: 199 1. NP-6041-SL.
S. Marik specific data in Section 3.3 of the SFP Evaluation Guidance Report, and confirmed that the evaluation criteria are applicable to the Fort Calhoun site. The staff concludes that SFP SSCs were appropriately evaluated and screened based on the seismic capacity criteria in EPRI NP-6041 , and that the licensee has demonstrated that the SFP structure is sufficiently robust and can withstand ground motions with peak spectral acceleration less than or equal to 0.8g.
1.2 Spent Fuel Pool Non-Structural Evaluation Section 3.2 of the SFP Evaluation Guidance Report provides criteria for evaluating the non-structural aspects of the spent fuel pool , such as piping connections, fuel gates, and anti-siphoning devices, as well as SFP sloshing and heat up and boil-off of SFP water inventory.
Specifically, Table 3-4 of the SFP Evaluation Guidance Report provides a summary of the SFP non-structural evaluation criteria derived in Section 3.2, along with applicability criteria to demonstrate that site-specific conditions are suitable for applying the evaluation criteria.
The licensee stated that it followed the SFP non-structural evaluation approach presented in the guidance report and provided site-specific data to confirm its applicability. The staff reviewed the non-structural information provided, which included the requested site-specific data in Table 3-4 of the SFP Evaluation Guidance Report, and confirmed that the evaluation criteria are applicable to the Fort Calhoun site. Therefore, the staff concludes that the licensee acceptably evaluated the non-structural considerations for SSCs whose failure could lead to potential drain-down of the SFP due to a seismic event.
CONCLUSION The NRC staff reviewed OPPD's SFP evaluation report. Based on its review, the NRC staff concludes that the licensee's implementation of the SFP integrity evaluation met the SFP Evaluation Guidance for Fort Calhoun and therefore , OPPD responded appropriately to Item 9 in Enclosure 1 of the NRC's 50.54(f) letter.
S. Marik If you have any questions , please contact me at (30 1) 415- 1617 or via e-mail at Frankie.Vega@nrc.gov.
Sincerely, Franki ega, Project Manager Hazards Management Branch Japan Lessons-Learned Division Office of Nuclear Reactor Regulation Docket No. 50-285
Enclosure:
Technical Review Checklist cc w/encl : Distribution via Listserv
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, O.C. 20555-0001 TECHNICAL REVIEW CHECKLIST BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO SPENT FUEL POOL EVALUATIONS FOR LOW GROUND MOTION RESPONSE SPECTRUM SITES IMPLEMENTING NEAR-TERM TASK FORCE RECOMMENDATION 2.1 SEISMIC FORT CALHOUN STATION, UNIT 1 DOCKET NO. 50-285 BACKGROUND By letter dated March 12, 2012 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML12053A340), the U.S. Nuclear Regulatory Commission (NRC) issued a request for information to all power reactor licensees and holders of construction permits in active or deferred status, pursuant to Title 1O of the Code of Federal Regulations (1 O CFR) , Section 50.54(f), "Conditions of License" (hereafter referred to as the "50.54(f) letter). of the 50.54(f) letter requests addressees to reevaluate the seismic hazard at their site using present-day methods and guidance for licensing new nuclear power plants, and identify actions to address or modify, as necessary, plant components affected by the reevaluated seismic hazards. Enclosure 1, Item 4, of the 50.54(f) letter requested that licensees perform a comparison of the ground motion response spectrum (GMRS) with the safe shutdown earthquake (SSE). Enclosure 1, Item 9, requests that, when the GMRS exceeds the SSE in the 1 to 1O Hertz (Hz) frequency range, a seismic evaluation be made of the spent fuel pool (SFP) .
More specifically, plants were asked to consider " ... all seismically induced failures that can lead to draining of the SFP."
Additionally, by letter dated February 23, 2016 (ADAMS Accession No. ML16055A021 ), the Nuclear Energy Institute (NEI) submitted Electric Power Research Institute (EPRI) Report No. 3002007148 entitled, "Seismic Evaluation Guidance: Spent Fuel Pool Integrity Evaluation" (SFP Evaluation Guidance Report). The SFP Evaluation Guidance Report supports the completion of SFP evaluations for sites with reevaluated seismic hazard exceedance in the 1-1 O Hz frequency range. Specifically, the SFP Evaluation Guidance Report addressed those sites where the GMRS peak spectral acceleration (Sa) is less than or equal to 0.8g (low GMRS sites). The NRC endorsed the SFP Evaluation Guidance Report by letter dated March 17, 2016 (ADAMS Accession No. ML15350A158), as an acceptable method for licensees to use when responding to Item 9 in Enclosure 1 of the 50.54(f) letter. Licensee deviations from the SFP Evaluation Guidance should be discussed in their SFP evaluation submittal.
By letter dated May 25, 2016 (ADAMS Accession No. ML16146A545), Omaha Public Power District (OPPD, the licensee) provided a SFP report in a response to Enclosure 1, Item 9, of the 50.54(f) letter, for the Fort Calhoun Station, Unit 1 (FCS) .
Enclosure
2 The staff performed its review of the licensee's submittal to assess whether the licensee responded appropriately to Item 9 in Enclosure 1 of the 50.54(f) letter. A multidisciplinary team checked whether the site-specific parameters are within the bounds of the criteria considered in the SFP Evaluation Guidance Report, verified the SFP's seismic adequacy to withstand the reevaluated GMRS hazard levels, and confirmed that the requested information in response to Item 9 of the 50.54(f) was provided .
A review checklist was used for consistency and scope. The application of this staff review is limited to the SFP evaluation as part of seismic review of low GMRS sites as part of Near Term Task Force Recommendation 2.1.
NTTF Recommendation 2.1 Spent Fuel Pool Evaluations .
Technical Review Checklist for Fort Calhoun Station (FCS)
Site Parameters:
I. Site-Specific GMRS The licensee:
- Provided the site-specific GMRS consistent with the information Yes provided in the Seismic Hazard and Screening Report (SHSR) , or its update, and evaluated by the staff in its staff assessment.
- Stated that the GMRS peak Sa is less than or equal to 0.8g for any Yes frequency.
Notes from the reviewer:
- 1. The staff confirmed that the site-specific peak Sa = 0.42g (ADAMS Accession No. ML14097A087).
Deviation(s) or Deficiency(ies), and Resolution :
No deviations or deficiencies identified.
The NRC staff concludes:
- The site-specific GMRS peak Sa at any frequency is less than 0.8g . Yes
- The licensee's GMRS used in this evaluation is consistent with the information provided in the SHSR. Yes Structural Parameters:
II. Seismic Design of the SFP Structure The licensee:
- Specified the building housing the SFP. Yes
- Specified the plant's peak ground acceleration (PGA). Yes
- Stated that the building housing the SFP was designed using an SSE with a PGA of at least 0.1 g. Yes 3
Notes from the reviewer:
- 1. The staff confirmed that the SFP is housed in the auxiliary building.
- 2. The staff confirmed that the auxiliary building is a Class I structure and was designed to the SSE with PGA of 0.17g (Updated Final Safety Analysis Report (UFSAR),
Appendix F).
Deviation(s) or Deficiency(ies), and Resolution:
No deviations or deficiencies identified.
The NRC staff concludes that:
- The structure housing the SFP was designed using an SSE with a Yes PGA of at least 0.1g.
Ill. Structural Load Path to the SFP The licensee:
- Provided a description of the structural load path from the Yes foundation to the SFP.
- Performed screening based on EPRI NP-6041 Table 2-3 screening Yes criteria.
Notes from the reviewer:
- 1. The staff verified the structural load path to the SFP.
- 2. The staff confirmed that the pool is located directly on foundation and the structural path consists of reinforced concrete shear walls .
Deviation(s) or Deficiency(ies), and Resolution:
No deviations or deficiencies identified.
The NRC staff concludes that:
- Licensee appropriately described the structural load path to the Yes SFP.
- Structures were appropriately screened based on the screening criteria in EPRI NP-6041. Yes 4
IV. SFP Structure Included in the Civil Inspection Program Performed in Accordance with Maintenance Rule The licensee:
- Stated that the SFP structure is included in the Civil Inspection Yes Program performed in accordance with Maintenance Rule (1 O CFR 50.65).
Notes from the reviewer:
None Deviation(s) or Deficiency(ies), and Resolution:
No deviations or deficiencies identified.
The NRC staff concludes that:
- SFP structure is included in the Civil Inspection Program performed Yes in accordance with Maintenance Rule (1 O CFR 50.65).
Non-Structural Parameters:
V. Applicability of Piping Evaluation The licensee:
- Stated that piping attached to the SFP is evaluated to the SSE. Yes Notes from the reviewer:
- 1. The staff confirmed that the SFP cooling system is designated as seism ic Class 1 (UFSAR Appendix F).
Deviation(s) or Deficiency(ies), and Resolution:
No deviations or deficiencies identified.
The NRC staff concludes that:
- The piping attached to the SFP is evaluated to the SSE . Yes
- Applicability criteria specified in Table 3-4 of SFP evaluation Yes guidance has been met.
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VI. Siphoning Evaluation The licensee:
- Stated that anti-siphoning devices are installed on piping systems that could lead to siphoning inventory from the SFP. No
- In cases where anti-siphoning devices were not included on the applicable piping , a description documenting the evaluation performed to determined the seismic adequacy of the piping is Yes provided.
- Stated that the piping of the SFP cooling system cannot lead to rapid drain down due to siphoning. Yes
- Provided a seismic adequacy evaluation , in accordance with NP-6041 , for cases where active siphoning devices are attached to 2" or No smaller piping with extremely large extended operators.
- Stated that no anti-siphoning devices are attached to 2" or smaller Yes piping with extremely large extended operators.
Notes from the reviewer:
- 1. UFSAR Section 9.6.1 states that piping of the SFP cooling system is so arranged that failure of any piping connected to the pool will not drain the pool below the top of the spent fuel racks.
- 2. Licensee stated that no active anti-siphoning devices are attached to 2" or smaller piping with extremely large extended operator.
Deviation(s) or Deficiency(ies), and Resolution:
No deviations or deficiencies identified.
The NRC staff concludes:
- Failure of piping of the SFP cooling system cannot lead to rapid Yes drain down due to siphoning.
- No active anti-siphoning devices are attached to 2" or smaller piping Yes with extremely large extended operator.
- Applicability criteria specified in Table 3-4 of SFP evaluation Yes guidance has been met.
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VII. Sloshing Evaluation The licensee:
- Specified the SFP dimensions (length, width , and depth). Yes
- Specified that the SFP dimensions are bounded by the dimensions Yes specified in the report (i.e., SFP length and width <125ft.; SFP depth >36ft.).
- Stated that the peak Sa in the frequency range less than 0.3 Hz is Yes less than 0.1g.
Notes from the reviewer:
- 1. Verified the SFP dimensiones:
- SFP Length - 33'-3"
- SFP width - 20'7"
- SFP Depth - 43.5'
- 2. The staff confirmed in the SHSR that the peak Sa in the frequency range less than 0.3 Hz is less than 0.1 g (SHSR)
Deviation(s) or Deficiency(ies), and Resolution:
No deviations or deficiencies identified .
The NRC staff concludes:
- SFP dimensions are bounded by the dimensions specified in the report (i.e. SFP length and width <125ft. ; SFP depth >36ft.). Yes
- The peak Sa in the frequency range less than 0.3 Hz is less than 0.1g. Yes
- Applicability criteria specified in Table 3-4 of SFP evaluation guidance has been met. Yes VIII. Evaporation Evaluation The licensee:
- Provided the surface area of the plant's SFP. Yes
- Stated that the surface area of the plant's SFP is greater than Yes 500 ft 2 .
- Provided the licensed reactor core thermal power. Yes
- Stated that the reactor core thermal power is less than 4,000 Yes MW1per unit.
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Notes from the reviewer:
- 1. Surface area of pool = 684 ft 2
- 2. Reactor thermal power = 1,500 MW1 Deviation(s) or Deficiency(ies), and Resolution:
No deviations or deficiencies identified The NRC staff concludes:
- The surface area of the plant's SFP is greater than 500 ft 2
- The reactor core thermal power is less than 4,000 MW1per unit. Yes
- Applicability criteria specified in Table 3-4 of SFP evaluation Yes guidance has been met
==
Conclusions:==
The NRC staff reviewed OPPD's SFP evaluation report. Based on its review, the NRC staff concludes that the licensee's implementation of the SFP integrity evaluation met the SFP Evaluation Guidance for Fort Calhoun and therefore OPPD responded appropriately to Item 9 in of the 50.54(f) letter.
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ML16182A361 *via e-mail OFFICE NRR/JLD/JHMB/PM NRR/JLD/LA ,OGC (NLO)
NAME FVega SLent BHarris DATE 07/14/2016 07/01/2016 07/19/2016 OFFICE NRR/JLD/JHMB/BC(A) NRR/JLD/JHMB/PM NAME GBowman FVega DATE 08/04/2016 08/04/2016