Category:Graphics incl Charts and Tables
MONTHYEARLIC-24-0011, Independent Spent Fuel Storage Installation - Response to Application for License Amendment Request to Revise the License Termination Plan - Supplemental Information Needed, EPID L-2024-LLA-00952024-10-0202 October 2024
Independent Spent Fuel Storage Installation - Response to Application for License Amendment Request to Revise the License Termination Plan - Supplemental Information Needed, EPID L-2024-LLA-0095
LIC-22-0001, Well Water Results with River Stage2022-01-13013 January 2022
Well Water Results with River Stage
ML16056A1392016-03-11011 March 2016
Correction to the U.S. Nuclear Regulatory Commission Analysis of Licensees' Decommissioning Funding Status Reports
ML16057A0742016-02-26026 February 2016
Response to Regulatory Information Summary (RIS) 2015-16, Planned Licensing Action Submittals for All Power Reactor Licensees.
ML15355A0872015-12-22022 December 2015
Interim Staff Response to Reevaluated Flood Hazards Submitted in Response to 10 CFR 50.54(f) Information Request- Flood Causing Mechanism Reevaluation
ML13351A4762013-12-16016 December 2013
Recommendation for NRC to Close Confirmatory Action Letter EA-13-020 Supporting the Restart of Fort Calhoun Station and Recommendation to Issue Post-Restart Confirmatory Action Letter
ML13109A3032012-12-20020 December 2012
G20120458/EDATS: OEDO-2012-0390 - Attachment 7
ML13109A3022012-12-20020 December 2012
G20120458/EDATS: OEDO-2012-0390 - Attachment 6
ML1214500142012-05-23023 May 2012
NFPA 805 LAR Status Matrix - May 2012
ML12012A2512011-06-0808 June 2011
Email from Edward Mccutchen to Louis Carson, Brownville, Ne Flood Forecast
LIC-11-0041, Transmittal of Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)2011-04-0505 April 2011
Transmittal of Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)
LIC-07-0073, Closure of NRC TAC Issues2008-07-11011 July 2008
Closure of NRC TAC Issues
LIC-08-0037, Calculation FC05694, Calculation of Minimum Reactor Coolant Time Using Shutdown Cooling System, Attachment 2, Pages 91 Through End2008-03-31031 March 2008
Calculation FC05694, Calculation of Minimum Reactor Coolant Time Using Shutdown Cooling System, Attachment 2, Pages 91 Through End
ML0810703262008-03-31031 March 2008
Calculation FC05694, Calculation of Minimum Reactor Coolant Time Using Shutdown Cooling System, Attachment 2, Pages 51 Through 90
ML0810703252008-03-31031 March 2008
Calculation FC05694, Calculation of Minimum Reactor Coolant Time Using Shutdown Cooling System.
LIC-08-0037, Calculation FC05694, Calculation of Minimum Reactor Coolant Time Using Shutdown Cooling System, Attachment 2, Pages 51 Through 902008-03-31031 March 2008
Calculation FC05694, Calculation of Minimum Reactor Coolant Time Using Shutdown Cooling System, Attachment 2, Pages 51 Through 90
LIC-08-0037, Calculation FC05694, Calculation of Minimum Reactor Coolant Time Using Shutdown Cooling System.2008-03-31031 March 2008
Calculation FC05694, Calculation of Minimum Reactor Coolant Time Using Shutdown Cooling System.
ML0728203072007-10-11011 October 2007
Electronic Distribtion Initiative Letter, Licensee List, Electronic Distribution Input Information, Division Plant Mailing Lists
LIC-06-0116, Spreadsheet File of Instructions, Time Temp Ph Input, Material Input, Materials Conversions, Results Tables2006-10-10010 October 2006
Spreadsheet File of Instructions, Time Temp Ph Input, Material Input, Materials Conversions, Results Tables
ML0628604322006-10-10010 October 2006
Spreadsheet File of Instructions, Materials Conversions, Results Table, Releases by Material, & Precipitate by Material, Reports
ML0514304242005-06-0303 June 2005
Summary of Meeting with Omaha Public Power District, Fort Calhoun - Summary of Conference Call 2005 Steam Generator Inspection
LIC-05-0040, Relaxation Request for First Revised Order (EA-03-009) Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads at Pressurized Water Reactors2005-04-0707 April 2005
Relaxation Request for First Revised Order (EA-03-009) Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads at Pressurized Water Reactors
ML18346A2461978-08-0808 August 1978
Furnishing Information Re Combustion Engineering Owners' Group Proposed Plan to Resolve the Asymmetric LOCA Loads Issue
2024-10-02
[Table view] |
