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ML22081A04110 March 2022Independent Spent Fuel Storage Installation, DSAR, Part 1 of 4
ML22081A04010 March 2022Independent Spent Fuel Storage Installation, 10 CFR 50.59 Report, Quality Assurance Program Changes, Technical Specification Basis Changes, 10 CFR 71.106 Quality Assurance Program Approval, Aging Management Review
ML21271A1963 August 2021License Amendment Request (LAR) 21-01, Chapter 3, 1, Omaha Public Power District, Defueled Safety Analysis Report CAC 2
ML21271A2103 August 2021License Amendment Request (LAR) 21-01, Chapter 4 3 Omaha Public Power District, Fort Calhoun Station Unit 1, Defueled Safety Analysis Report CAC 2
ML21271A2673 August 2021License Amendment Request (LAR) 21-01, Chapter 6 3 Omaha Public Power District, Fort Calhoun Station Unit 1, Defueled Safety Analysis Report CAC2
ML21271A1833 August 2021License Amendment Request (LAR) 21-01, Chapter 2 11 Omaha Public Power District, Fort Calhoun Station Unit 1, Defueled Safety Analysis Report cac2
ML21271A1503 August 2021License Amendment Request (LAR) 21-01, Defueled Safety Analysis Report
ML20170A40130 April 2020Independent Spent Fuel Storage Installation Updated Decommissioning Safety Analysis Report, DSAR 5.11, Rev. 1, Structures Other than Containment
ML20170A44930 April 2020Independent Spent Fuel Storage Installation Updated Decommissioning Safety Analysis Report, DSAR-Appendix F, Rev. 2, Classification of Structures and Equipment and Seismic Criteria
IR 05000285/201900512 March 2020Independent Spent Fuel Storage Installation (ISFSI) - NRC Inspection Report 050-00285/2019-005 and 072-00054/2019-001
LIC-16-0108, License Amendment Request 16-07, Revise the Emergency Plan to the Permanently Defueled Emergency Plan and Permanently Defueled Emergency Action Level Scheme16 December 2016License Amendment Request 16-07, Revise the Emergency Plan to the Permanently Defueled Emergency Plan and Permanently Defueled Emergency Action Level Scheme
LIC-16-0093, License Amendment Request LAR-16-04 to Revise Current Licensing Basis to Use Aci Ultimate Strength Requirements25 October 2016License Amendment Request LAR-16-04 to Revise Current Licensing Basis to Use Aci Ultimate Strength Requirements
LIC-16-0022, Response to NRC Request for Additional Information Revise Current Licensing Basis to Allow Use of Equipment Classification Methodology from ANSI/ANS-58.14-20118 April 2016Response to NRC Request for Additional Information Revise Current Licensing Basis to Allow Use of Equipment Classification Methodology from ANSI/ANS-58.14-2011
LIC-15-0142, Supplement of License Amendment Request 15-03; Revise Current Licensing Basis to Use Aci Ultimate Strength Requirements23 December 2015Supplement of License Amendment Request 15-03; Revise Current Licensing Basis to Use Aci Ultimate Strength Requirements
LIC-15-0077, License Amendment Request 15-03; Revise Current Licensing Basis to Use Aci Ultimate Strength Requirements31 August 2015License Amendment Request 15-03; Revise Current Licensing Basis to Use Aci Ultimate Strength Requirements
ML15111A39930 June 2015Issuance of Amendment No. 282, Revise Updated Safety Analysis Report for Controlling Raw Water Pump Operation and Safety Classification of Components During a Flood
IR 05000285/201500716 April 2015IR 05000285/2015007, on 02/09/2015 - 03/13/2015, Fort Calhoun Station, Component Design Basis Inspection (CDBI)
LIC-15-0041, Regulatory Commitment Regarding License Amendment Request (LAR) 13-03, Revising Method for Controlling Raw Water Intake Cell Level24 March 2015Regulatory Commitment Regarding License Amendment Request (LAR) 13-03, Revising Method for Controlling Raw Water Intake Cell Level
LIC-15-0013, Revised Response to NRC Request for Additional Information Regarding License Amendment Request (LAR) 13-03, Revising Method for Controlling Raw Water Intake Cell Level, Dated August 13, 2014 (ML14226A738)(LIC-14-0092)13 February 2015Revised Response to NRC Request for Additional Information Regarding License Amendment Request (LAR) 13-03, Revising Method for Controlling Raw Water Intake Cell Level, Dated August 13, 2014 (ML14226A738)(LIC-14-0092)
IR 05000285/201400918 September 2014IR 05000285/2014009 and Notice of Violation, July 7 Through September 12, 2014, Fort Calhoun, NRC Confirmatory Action Letter Follow Up Inspection and Problem Identification and Resolution
ML14177A64527 June 2014Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations
IR 05000285/201400714 May 2014IR 05000285-14-007; on 02/16/2014 - 03/31/2014; Fort Calhoun Station; Integrated Resident Inspection Report and Confirmatory Action Letter Closeout Items
LIC-14-0036, License Amendment Request (LAR) 14-05; Design and Evaluation of Seismic Class I Structures Using Ascm Developed Floor Response Spectra25 April 2014License Amendment Request (LAR) 14-05; Design and Evaluation of Seismic Class I Structures Using Ascm Developed Floor Response Spectra
ML14007A69327 February 2014Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies)
ML14049A36125 February 2014Mega-Tech Services, LLC Technical Evaluation Report Regarding the Overall Integrated Plan for Fort Calhoun Station, TAC MF0969
LIC-13-0070, Engineering Report EA12-021, Revision 1, Seismic Walkdown Submittal Report for Resolution of Fukushima Near-Term Force Recommendation 2.3: Seismic. Part 1 of 226 April 2013Engineering Report EA12-021, Revision 1, Seismic Walkdown Submittal Report for Resolution of Fukushima Near-Term Force Recommendation 2.3: Seismic. Part 1 of 2
ML12340A25427 November 2012OPPD 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
ML12122A07114 May 2012Enclosure 1: April 2012 Report on the Status of Public Petitions Under Title 10 of the Code of Federal Regulations, Section 2.206
IR 05000282/201100913 May 2011IR 05000282-11-009, 05000306-11-009, on 03/23/2011 - 04/29/2011; Prairie Island Nuclear Generating Plant, Units 1 and 2, Temporary Instruction 2515/183 - Followup to the Fukushima Daiichi Nuclear Station Fuel Damage Event
LIC-08-0021, Supplemental Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors29 February 2008Supplemental Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors
LIC-06-0056, Request for Exemption from Nuhoms Certificate of Compliance No. 1004, Amendment No. 89 June 2006Request for Exemption from Nuhoms Certificate of Compliance No. 1004, Amendment No. 8
ML03120048729 April 2003Issuance of Amendment No. 217 Modifying TS 2.3.a, to Extend the Allowed Outage Time for a Single Low Pressure Safety Injection Pump from the Existing 24 Hours to 7 Days
LIC-02-0137, License Amendment Request, Low Pressure Safety Injection System Allowed Outage Time - Additional Information3 December 2002License Amendment Request, Low Pressure Safety Injection System Allowed Outage Time - Additional Information
ML20206M2606 May 1999SER Concluding That Licensee IPEEE Complete Re Info Requested by Suppl 4 to GL 88-20 & IPEEE Results Reasonable Given FCS Design,Operation & History
ML20236V48930 July 1998Safety Evaluation Relating to Response to GL 87-02,suppl 1 for Fort Calhoun Station,Unit 1
ML20248C06721 May 1998Safety Evaluation Granting Licensee Request for Exemption from Technical Requirements of 10CFR50,App R, Fire Protection Program for Nuclear Power Facilities Operating Prior to 790101
LIC-98-0063, Submits Clarification to Request for Exemption from Requirements of 10CFR50,App R Re Reactor Coolant Pump Motor Lube Oil Collection Sys,As Requested in 980417 Telcon23 April 1998Submits Clarification to Request for Exemption from Requirements of 10CFR50,App R Re Reactor Coolant Pump Motor Lube Oil Collection Sys,As Requested in 980417 Telcon
ML20147D0997 February 1997Forwards Util Responses to Questions Proposed in Ltr Re RCP Lube Oil Collection Sys & 10CFR50,App R as Proposed in Insp Rept 50-285/96-16
LIC-96-0121, Responds to RAI Re Resolution of USI A-4623 August 1996Responds to RAI Re Resolution of USI A-46
ML20097C3081 February 1996Proposed Tech Specs,Allowing Increase in Initial Nominal U-235 Enrichment Limit of Fuel Assemblies That May Be Stored in Spent Fuel Pool
ML20117C00631 October 1994USI A-46/IPEEE,Outlier Resolution & Detailed HCLPF for Tanks AC-1C & AC-1D
ML20117C09628 September 1992Seismic Qualification of Diesel Fuel Tanks & Summary of Calculation for Blockwall No 9
ML20065T36019 December 1990Proposed Tech Specs Re Limiting Condition for Operation for Radioactive Effluents/Liquid Gaseous Effluents & Radwaste Sampling & Monitoring
05000285/LER-1990-0071 August 1990LER 90-007-02:on 900228,determined That Main Feedwater & Main Steam Piping Outside Design Basis.Caused by Design Deficiency & Failure of Engineer to Consider Loads Induced on Piping.Piping Supports modified.W/900801 Ltr
LIC-90-0564, Forwards Updated, Position Paper Re Seismic Capability of Welded Steel Piping. Documentation Demonstrates No Generic Thermal or Seismic Safety Issue Exists for Welded Steel Small Diameter Piping at Facility29 June 1990Forwards Updated, Position Paper Re Seismic Capability of Welded Steel Piping. Documentation Demonstrates No Generic Thermal or Seismic Safety Issue Exists for Welded Steel Small Diameter Piping at Facility
ML20042G9888 May 1990Rev 0 to Interim Operability Criteria (Ioc) Criteria for Performing Safety Analysis for Interim Operability of Piping.
ML20042E68723 April 1990LER 90-007-01:on 900228,determined That Several Supports Would Be Overloaded During Seismic Event on Nonsafety Related & safety-related Main Steam Piping.Caused by Design Deficiency.Piping Supports modified.W/900423 Ltr
ML19327C0607 November 1989Forwards Response Tp NRC Technical Evaluation Rept on NUREG-0737, Item II.D.2, Performance Testing of Relief & Safety Valves. Operability of PORV Block Valves Judged to Be Low Risk Issue for Listed Reasons
ML20247J91030 June 1989Rev 1 to Technical Evaluation Rept TMI Action--NUREG-0737 (II.D.1) Relief & Safety Valve Testing,Fort Calhoun
IR 05000285/198803118 October 1988Insp Rept 50-285/88-31 on 880912-16.Violations & Deviations Noted.Major Areas Inspected:Action on Previous Insp Findings,Welding,Design Changes & Mods,Procurement & Receipt,Storage & Handling of Equipment & Matls
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