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IR 05000285/202200526 October 2022NRC Inspection Report 05000285/2022-005
LIC-22-0010, Response to Fort Calhoun Station, Unit No. 1 - Review of License Termination Plan Requirements - Request for Additional Information15 June 2022Response to Fort Calhoun Station, Unit No. 1 - Review of License Termination Plan Requirements - Request for Additional Information
ML21271A5993 August 2021License Amendment Request (LAR) 21-01, Chapter 8, 12, Omaha Public Power District, FCS-SAF-103, FCS Deconstruction Health and Safety Plan CAC2
ML20202A65416 July 2020Response for Fort Calhoun Station Fort Calhoun Station, Unit No. 1, Revised Post-Shutdown Decommissioning Activities Report
LIC-20-0013, License Amendment Request (LAR) 21-01, Response Re Revised Post-Shutdown Decommissioning Activities Report, Chapter 8 2 Updated Environmental Report, File No. 127690-003 (LIC-20-0013, ML 20202A654)16 July 2020License Amendment Request (LAR) 21-01, Response Re Revised Post-Shutdown Decommissioning Activities Report, Chapter 8 2 Updated Environmental Report, File No. 127690-003 (LIC-20-0013, ML 20202A654)
LIC-19-0007, Post-Shutdown Decommissioning Activities Report16 December 2019Post-Shutdown Decommissioning Activities Report
ML21271A60116 December 2019License Amendment Request (LAR) 21-01, Chapter 8, 5, Omaha Public Power District, Fort Calhoun Station Unit 1, Post Shutdown Decommissioning Activity Report
ML18215A22830 April 2018FCS Partial Site Release Survey Packages and Preparation Instructions (Reference 14)
LIC-18-0023, FCS Partial Site Release Survey Packages and Preparation Instructions (Reference 14)30 April 2018FCS Partial Site Release Survey Packages and Preparation Instructions (Reference 14)
ML17089A75930 March 2017Post-Shutdown Decommissioning Activities Report
ML15232A00321 August 2015Relief Request RR-14, Relief from ASME Code Case N-729-1 Requirements for Reactor Vessel Head Penetration Nozzle Welds, Fourth 10-Year Inservice Inspection Interval
LIC-15-0066, Relief Request Number RR-14, Request for Relief from Paragraph -3142.1(c) of ASME Code Case N-729-1 for Reactor Vessel Head Penetration Nozzle Welds9 May 2015Relief Request Number RR-14, Request for Relief from Paragraph -3142.1(c) of ASME Code Case N-729-1 for Reactor Vessel Head Penetration Nozzle Welds
LIC-14-0128, License Amendment Request (LAR) 14-10; One- Time Extension of Technical Specification Surveillance Requirements7 November 2014License Amendment Request (LAR) 14-10; One- Time Extension of Technical Specification Surveillance Requirements
ML14098A09216 June 2014Issuance of Amendment No. 275, Adopt National Fire Protection Association Standard 805, Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants (2001 Edition)
LIC-14-0075, Request Clarifications to Draft National Fire Protection Association (NFPA) 805 Safety Evaluation Report11 June 2014Request Clarifications to Draft National Fire Protection Association (NFPA) 805 Safety Evaluation Report
ML14156A0016 May 2014NRR E-mail Capture - Request for NFPA 805 License Amendment Facutrual Accuracy Review
LIC-13-0172, Response to Request for Additional Information Associated with Near-Term Task Force Recommendation 2.3, Seismic Walkdowns27 November 2013Response to Request for Additional Information Associated with Near-Term Task Force Recommendation 2.3, Seismic Walkdowns
LIC-13-0060, Omaha Public Power District - Remaining Responses to Second Request for Additional Information License Amendment Request to Adopt NFPA 805 at Fort Calhoun Station21 May 2013Omaha Public Power District - Remaining Responses to Second Request for Additional Information License Amendment Request to Adopt NFPA 805 at Fort Calhoun Station
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
ML13193A23726 April 2013Engineering Report EA12-021, Revision 1, Seismic Walkdown Submittal Report for Resolution of Fukushima Near-Term Force Recommendation 2.3: Seismic. Part 2 of 2
IR 05000285/201300724 April 2013IR 05000285-13-007 and 07200054-13-001, 1/14-17/2013, Fort Calhoun Station Independent Spent Fuel Storage Installation (ISFSI)
LIC-13-0033, Omaha Public Power District'S, Responses to Second Request for Additional Information License Amendment Request to Adopt NFPA 805 at Fort Calhoun Station23 April 2013Omaha Public Power District'S, Responses to Second Request for Additional Information License Amendment Request to Adopt NFPA 805 at Fort Calhoun Station
LIC-13-0046, Omaha Public Power District Response to NRC RAI Regarding Request for Work Hours Exemption11 April 2013Omaha Public Power District Response to NRC RAI Regarding Request for Work Hours Exemption
ML13053A22622 February 2013Email, Second Round Draft Request for Additional Information, Request to Adopt National Fire Protection Association Standard 805, Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants.
ML13010A10510 January 2013M130108 Transcript for Briefing on Fort Calhoun Public Meeting, January 8, 2013
ML12340A25527 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
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
ML12318A34113 November 2012IR 05000285-12-005 and Notice of Violation, 08/19/2012 09/30/2012, Fort Calhoun Station, Integrated Resident, Inservice Inspection, and Confirmatory Action Letter Report
LIC-12-0135, Responses to Requests for Additional Information License Amendment Request 10-07 to Adopt NFPA 805, Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants, 2001 Edition, at Fort Calhoun Station27 September 2012Responses to Requests for Additional Information License Amendment Request 10-07 to Adopt NFPA 805, Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants, 2001 Edition, at Fort Calhoun Station
ML12325A39821 September 20122012-09 Draft Retake Written Exam
ML12132A39511 May 2012IR 05000285-12-002; 01/01/2012 - 03/31/2012; Fort Calhoun Station, Integrated Resident and Regional Report; Adverse Weather Protection, Emergency Plan Biennial Exercise, Mc 0350
IR 05000285/201100616 March 2012IR 05000285-11-006; Omaha Public Power District; on November 14, 2011, ?February 2, 2012; Fort Calhoun Station Biennial Team Inspection of the Identification and Resolution of Problems.
LIC-11-0099, Table B-2 Nuclear Safety Capability Assessment Methodology Review28 September 2011Table B-2 Nuclear Safety Capability Assessment Methodology Review
ML11276A12028 September 2011Enclosure 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-11-0095, Post-Flooding Recovery Action Plan, Revision 130 August 2011Post-Flooding Recovery Action Plan, Revision 1
IR 05000285/201100311 August 2011IR 05000285-11-003; 04/01/2011 06/30/2011; Fort Calhoun Station, Integrated Resident and Regional Report; Radiological Hazard Assessment and Exposure Controls, Surveillance Testing, Emergency Action Level and Emergency Plan Changes, Fire ..
LIC-11-0090, Post-Flooding Recovery Action Plan10 August 2011Post-Flooding Recovery Action Plan
ML12012A16621 July 2011E-mail from Susan E. Baughn to Kriss Kennedy, Jeff Clark, Subject: E-mailing: Ft Calhoun POD
ML12012A16520 July 2011E-mail from Susan E Baughn to Kriss Kennedy, Jeff Clark, Subject: Ft Calhoun POD (7/20/11)
ML12012A14721 June 2011E-mail from Erick Matze to John Kirkland, Jeff Clark, Subject: This May Help
IR 05000285/201100210 May 2011IR 05000285-11-002; 01/01/2011 - 03/31/2011; Fort Calhoun Station, Integrated Resident and Regional Report; Adverse Weather Protection, Refueling and Other Outage Activities, and Surveillance Testing
ML11020019314 January 2011Withdrawal of Response to Request for Additional Information (RAI) Regarding Request for Relief from ASME Code Case N-722 Requirements for Visual Examination of Reactor Vessel Hot Leg Nozzle-to-Safe End Dissimilar Metal Butt Welds
LIC-08-0106, Omaha Public Power District, Fort Calhoun Station (Fcs), Response to NRC Generic Letter 2008-0114 October 2008Omaha Public Power District, Fort Calhoun Station (Fcs), Response to NRC Generic Letter 2008-01
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
IR 05000285/200600514 February 2007IR 05000285-06-005; 10/01/2006 - 12/31/2006; Fort Calhoun Station, Integrated Resident and Regional Report; Operability Evaluations, Refueling and Other Outage Activities, Access Control to Radiologically Significant Areas, ALARA Planning A
ML0603804079 February 2006RAI Re Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design-Basis Accidents at Pressurized-Water Reactors.
ML0626304081 March 2004PSEG Nuclear, LLC Salem/Hope Creek Safety Culture Assessment
IR 05000285/20030064 February 2004IR 05000285-03-006 on 09/21/2003 - 12/31/2003 for Fort Calhoun Station, Integrated Resident and Regional Report; Maintenance Rule Implementation, Nonroutine Evolutions and Events, Refueling Activities, Access Control, Event Followup
IR 05000285/200300414 July 2003IR 05000285-03-004, on 03/23/2003 - 06/21/2003; for Fort Calhoun Station, Integrated Resident and Regional Report
LIC-99-0016, Requests Relief from Certain Requirements of Paragraphs IWA- 5242(a) & IWA-5250(a)(2) of ASME Section Xi,For Remainder of Third 10-year Insp Interval on Basis of Attached Proposed Alternatives1 March 1999Requests Relief from Certain Requirements of Paragraphs IWA- 5242(a) & IWA-5250(a)(2) of ASME Section Xi,For Remainder of Third 10-year Insp Interval on Basis of Attached Proposed Alternatives
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