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Issue date | Title | |
---|---|---|
LIC-16-0110, Emergency Plan Update | 30 November 2016 | Emergency Plan Update |
LIC-16-0093, License Amendment Request LAR-16-04 to Revise Current Licensing Basis to Use Aci Ultimate Strength Requirements | 25 October 2016 | License Amendment Request LAR-16-04 to Revise Current Licensing Basis to Use Aci Ultimate Strength Requirements |
ML16182A361 | 4 August 2016 | Staff Review of Spend Fuel Pool Evaluation Associated with Reevaluation Seismic Hazard Implementing Near-Term Task Force Recommendation 2.1 |
LIC-16-0039, Ft. Calhoun, Unit 1 - Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force (NTTF) Review of Insights from the Fukushima Dai-ichi Accident | 25 May 2016 | Ft. Calhoun, Unit 1 - Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force (NTTF) Review of Insights from the Fukushima Dai-ichi Accident |
ML16061A301 | 2 March 2016 | Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: March 15, 2016 |
LIC-15-0142, Supplement of License Amendment Request 15-03; Revise Current Licensing Basis to Use Aci Ultimate Strength Requirements | 23 December 2015 | Supplement of License Amendment Request 15-03; Revise Current Licensing Basis to Use Aci Ultimate Strength Requirements |
LIC-15-0119, ISFSI - Quality Assurance Program Approval for Radioactive Material Packages | 9 December 2015 | ISFSI - Quality Assurance Program Approval for Radioactive Material Packages |
ML15329A181 | 8 December 2015 | Staff Assessment of Information Provided Pursuant of Title 10 of the Code of Federal Regulations Part 50, Section 50.54(f)Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task Force Review of Insights.. |
LIC-15-0077, License Amendment Request 15-03; Revise Current Licensing Basis to Use Aci Ultimate Strength Requirements | 31 August 2015 | License Amendment Request 15-03; Revise Current Licensing Basis to Use Aci Ultimate Strength Requirements |
ML15111A399 | 30 June 2015 | Issuance of Amendment No. 282, Revise Updated Safety Analysis Report for Controlling Raw Water Pump Operation and Safety Classification of Components During a Flood |
IR 05000285/2015007 | 16 April 2015 | IR 05000285/2015007, on 02/09/2015 - 03/13/2015, Fort Calhoun Station, Component Design Basis Inspection (CDBI) |
ML15022A653 | 26 January 2015 | Biweekly Sholly FRN - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: February 3, 2015 |
LIC-14-0098, License Amendment Request 14-06 to Adopt Emergency Action Level Scheme Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors | 26 December 2014 | License Amendment Request 14-06 to Adopt Emergency Action Level Scheme Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors |
ML14310A033 | 15 December 2014 | NRC Response to Licensees Notification of Revised Regulatory Commitments Associated with Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Revie |
ML14224A526 | 22 September 2014 | Screening and Prioritization Results of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50, Section 50.54(f), Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task Force |
ML14175A518 | 11 August 2014 | Summary of Category 1 Public Meeting with Exelon to Discuss Seismic Hazard Reevaluations Associated with Implementation of Japan Lessons Learned Near-Term Task Force Recommendation 2.1, Seismic |
ML14209A027 | 7 August 2014 | Issuance of Amendment No. 276, Request to Revise Updated Safety Analysis Report for Westinghouse Plant-Specific Leak-Before-Break Analysis |
ML14206B064 | 25 July 2014 | Response to NRC Request for Additional Information Re Seismic Hazard and Screening Report |
ML14195A086 | 16 July 2014 | Request for Additional Information Associated with Near-Term Task Force Recommendation 2.1, Seismic Hazard and Screening Report |
ML14111A147 | 9 May 2014 | Seismic Screening and Prioritization Results Regarding Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task Force Review of Insights |
ML14105A373 | 22 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 Fukushi | 31 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 |
ML14007A693 | 27 February 2014 | Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies) |
ML14049A361 | 25 February 2014 | Mega-Tech Services, LLC Technical Evaluation Report Regarding the Overall Integrated Plan for Fort Calhoun Station, TAC MF0969 |
ML13317A583 | 25 November 2013 | Interim Staff Evaluation and Request for Additional Information Regarding Overall Integrated Plan for Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051) |
LIC-13-0144, Omaha Public Power District Response to NRC Request for Additional Information Regarding the Overall Integrated Plan in Response to Order EA-12-051 Reliable Spent Fuel Pool Instrumentation | 18 October 2013 | Omaha Public Power District Response to NRC Request for Additional Information Regarding the Overall Integrated Plan in Response to Order EA-12-051 Reliable Spent Fuel Pool Instrumentation |
LIC-13-0148, Response to Request for Additional Information (RAI) for Fort Calhoun Station (FCS) Exigent License Amendment Request (LAR) to Revise Current Licensing Basis of Pipe Break Criteria for High Energy Piping Outside of Containment | 15 October 2013 | Response to Request for Additional Information (RAI) for Fort Calhoun Station (FCS) Exigent License Amendment Request (LAR) to Revise Current Licensing Basis of Pipe Break Criteria for High Energy Piping Outside of Containment |
LIC-13-0126, Omaha Public Power District (OPPD) Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Acciden | 12 September 2013 | Omaha Public Power District (OPPD) Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident - |
LIC-13-0100, WCAP-17262-NP, Rev 1, Technical Bases for Eliminating Large Primary Loop Pipe Rupture as the Structural Design Basis for Fort Calhoun, Unit 1 | 31 July 2013 | WCAP-17262-NP, Rev 1, Technical Bases for Eliminating Large Primary Loop Pipe Rupture as the Structural Design Basis for Fort Calhoun, Unit 1 |
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 2 | 26 April 2013 | Engineering Report EA12-021, Revision 1, Seismic Walkdown Submittal Report for Resolution of Fukushima Near-Term Force Recommendation 2.3: Seismic. Part 1 of 2 |
LIC-13-0011, Spent Fuel Pool Instrumentation Overall Integrated Plan | 28 February 2013 | Spent Fuel Pool Instrumentation Overall Integrated Plan |
ML12340A254 | 27 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 |
ML12053A340 | 12 March 2012 | Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3, and 9.3, of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi Accident |
ML12056A049 | 12 March 2012 | Enclosure 3 - Recommendation 2.3: Seismic |
ML12056A047 | 12 March 2012 | Enclosure 1 - Recommendation 2.1: Seismic |
IR 05000285/2011003 | 11 August 2011 | IR 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-11-0016, Response to Second NRC 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 | 4 March 2011 | Response to Second NRC 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 |
ML110610217 | 3 March 2011 | Request for Additional Information, Round 2, Relief Request RR-12 from ASME Code Case N-722 Visual Examination Requirements for 4th 10-Year Inservice Inspection Interval |
ML110540449 | 23 February 2011 | Request for Additional Information, Round 2, Relief Request RR-12 from ASME Code Case N-722 Visual Examination Requirements for 4th 10-Year Inservice Inspection Interval |
LIC-10-0065, LTR-PAFM-10-123-NP, Rev. 0, Technical Justification to Support Alternative Visual Examination Intervals for Fort Calhoun Reactor Vessel Outlet Nozzle to Safe End Dissimilar Metal Welds, Enclosure 2 | 31 July 2010 | LTR-PAFM-10-123-NP, Rev. 0, Technical Justification to Support Alternative Visual Examination Intervals for Fort Calhoun Reactor Vessel Outlet Nozzle to Safe End Dissimilar Metal Welds, Enclosure 2 |
IR 05000285/2009006 | 30 December 2009 | IR 05000285-09-006; August 24-28, 2009, and September 8-18, 2009; Fort Calhoun Station: Baseline Inspection, NRC Inspection Procedure 71111.21, Component Design Basis Inspection |
LIC-08-0107, Notice of Completion of Corrective Actions Taken in Response to Generic Letter 2004-02 and Response to Request for Additional Information | 16 October 2008 | Notice of Completion of Corrective Actions Taken in Response to Generic Letter 2004-02 and Response to Request for Additional Information |
ML071830005 | 18 July 2007 | Summary of Meeting with Omaha Public Power District for Fort Calhoun Station on Licensee'S Plans to Upgrade or Uprate the Auxiliary Building and Building Crane for the Crane to Lift a 100-Ton Spent Fuel Cask |
IR 05000285/2006013 | 19 July 2006 | IR 05000285-06-013; 07200054-06-002; on 03/13/2006 - 05/05/2006, Omaha Public Power District, Fort Calhoun |
ML060670320 | 1 March 2006 | License Amendment 238 Regarding Inoperability of Snubbers |
ML20206M260 | 6 May 1999 | SER Concluding That Licensee IPEEE Complete Re Info Requested by Suppl 4 to GL 88-20 & IPEEE Results Reasonable Given FCS Design,Operation & History |
IR 05000285/1998020 | 5 October 1998 | Insp Rept 50-285/98-20 on 980816-0926.No Violations Noted. Major Areas Inspected:Operations,Maint & Engineering |
ML20236V489 | 30 July 1998 | Safety Evaluation Relating to Response to GL 87-02,suppl 1 for Fort Calhoun Station,Unit 1 |
ML20248C049 | 21 May 1998 | Exemption from Requirements of 10CFR50,App R for Plant, Unit 1.Exemption Re Unpressurized Leakage Sites in RCP Lube Oil Collection Sys Granted |
ML20206M286 | 31 March 1998 | Final Rept, Technical Evaluation Rept on 'Submittal-Only' Review of Individual Plant Exam of External Events at Fort Calhoun Station |