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 Issue dateTitleTopic
ML21271A1993 August 2021License Amendment Request (LAR) 21-01, Chapter 3 16 Omaha Public Power District, Offsite Dose Calculation Manual CAC 2Offsite Dose Calculation Manual
Annual Radioactive Effluent Release Report
Annual Radiological Environmental Operating Report
Process Control Program
Annual Radiological Effluent Release Report
LIC-18-0015, CH-ODCM-0001, Revision 26, Off-Site Dose Calculation Manual.11 April 2018CH-ODCM-0001, Revision 26, Off-Site Dose Calculation Manual.Grab sample
Offsite Dose Calculation Manual
Annual Radioactive Effluent Release Report
Annual Radiological Environmental Operating Report
Process Control Program
Annual Radiological Effluent Release Report
ML18106A03811 April 2018CH-ODCM-0001, Revision 26, Off-Site Dose Calculation Manual.Grab sample
Offsite Dose Calculation Manual
Annual Radioactive Effluent Release Report
Annual Radiological Environmental Operating Report
Process Control Program
Annual Radiological Effluent Release Report
LIC-18-0015, CH-ODCM-0001, Revision 27, Off-Site Dose Calculation Manual.11 April 2018CH-ODCM-0001, Revision 27, Off-Site Dose Calculation Manual.Grab sample
Offsite Dose Calculation Manual
Annual Radioactive Effluent Release Report
Annual Radiological Environmental Operating Report
Process Control Program
Annual Radiological Effluent Release Report
ML17041A44310 February 2017Supplemental Information Needed for Acceptance of Requested Licensing Action Fort Calhoun Station Request for Exemptions from Portions of 10 CFR 50.47 and 10 CFR Part 50, Appendix E (CAC No. MF9067). (Non-Proprietary)(Part 1 of 4)
LIC-17-0024, Supplemental Information Needed for Acceptance of Requested Licensing Action Fort Calhoun Station Request for Exemptions from Portions of 10 CFR 50.47 and 10 CFR Part 50, Appendix E (CAC No. MF9067). (Non-Proprietary)(Part 4 of 4)10 February 2017Supplemental Information Needed for Acceptance of Requested Licensing Action Fort Calhoun Station Request for Exemptions from Portions of 10 CFR 50.47 and 10 CFR Part 50, Appendix E (CAC No. MF9067). (Non-Proprietary)(Part 4 of 4)
ML17041A44410 February 2017Supplemental Information Needed for Acceptance of Requested Licensing Action Fort Calhoun Station Request for Exemptions from Portions of 10 CFR 50.47 and 10 CFR Part 50, Appendix E (CAC No. MF9067). (Non-Proprietary)(Part 2 of 4)
LIC-16-0109, Request for Exemptions from Portions of 10 CFR 50.47 and 10 CFR Part 50, Appendix E (Attachments 1, 2, 4, 5 and 6)16 December 2016Request for Exemptions from Portions of 10 CFR 50.47 and 10 CFR Part 50, Appendix E (Attachments 1, 2, 4, 5 and 6)
LIC-16-0044, Calculation FC08499 Evaluation of FCS Concrete Compressive Strength Test Data1 June 2016Calculation FC08499 Evaluation of FCS Concrete Compressive Strength Test Data
LIC-08-0067, Response to Request for Additional Information Relief Request for Valve Replacement and Supplemental Information17 May 2008Response to Request for Additional Information Relief Request for Valve Replacement and Supplemental InformationNon-Destructive Examination
Stroke time
Hydrostatic
Liquid penetrant
Through-Wall Leak
ML08107032631 March 2008Calculation 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.31 March 2008Calculation 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 9031 March 2008Calculation FC05694, Calculation of Minimum Reactor Coolant Time Using Shutdown Cooling System, Attachment 2, Pages 51 Through 90
ML08107032531 March 2008Calculation 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 91 Through End31 March 2008Calculation FC05694, Calculation of Minimum Reactor Coolant Time Using Shutdown Cooling System, Attachment 2, Pages 91 Through End
ML0616402397 June 2006Tn Calculation 1121-0504, Revision 1, OS197L 75 Ton Transfer Cask Dose Rates; Calculation to Be Used with OPPD Exemption Request.Exemption Request
ML0616402426 June 2006Tn Calculation 1121-0401, Revision 1, OS197L Ton Transfer Cask Thermal Analysis to Be Used with OPPD Exemption Request (18.4 Kw/Dsc & 11.0 Kw/Dsc).Exemption Request
Fuel cladding
ML0616402415 June 2006Tn Calculation 1121-0400, Revision 1, Calculation of OS197L Cask Shell Temperature with 11.0 and 18.4 Kw Heat Loads.Exemption Request
LIC-05-0048, Additional Information for Relaxation Request for First Revised Order (EA-03-009) Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads at Pressurized Water Reactors19 April 2005Additional Information for Relaxation Request for First Revised Order (EA-03-009) Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads at Pressurized Water ReactorsHydrostatic
LIC-03-0166, Response to Request for Additional Information Regarding Measurement Uncertainty Recapture Power Uprate22 December 2003Response to Request for Additional Information Regarding Measurement Uncertainty Recapture Power Uprate
LIC-03-0067, Amendment Request for License DPR-40 Measurement Uncertainty Recapture Power Uprate18 July 2003Amendment Request for License DPR-40 Measurement Uncertainty Recapture Power UprateSafe Shutdown
Boric Acid
Shutdown Margin
Loop seal
Offsite Dose Calculation Manual
Stroke time
Anticipated operational occurrence
Hydrostatic
Probabilistic Risk Assessment
Coatings
Pressure and Temperature Limits Report
Annual Radioactive Effluent Release Report
Foreign Material Exclusion
Earthquake
Control of Heavy Loads
Turbine Missile
Fuel cladding
Fire Protection Program
Power change
Flow Induced Vibration
ML0411901953 April 2003CH-ODCM-001, Off-Site Dose Calculation Manual (Odcm).Grab sample
Offsite Dose Calculation Manual
Annual Radioactive Effluent Release Report
Annual Radiological Environmental Operating Report
Process Control Program
Annual Radiological Effluent Release Report
ML03099067331 December 2002Annual Report for Technical Specification Section 5.9.4.a, Section 2.0, Supplemental Information Through Appendix DOffsite Dose Calculation Manual
Annual Radioactive Effluent Release Report
Annual Radiological Environmental Operating Report
Process Control Program
Annual Radiological Effluent Release Report
ML03099066531 December 2002Annual Report for Technical Specification Section 5.9.4.a, Sections 6 Through 7Offsite Dose Calculation Manual
ML03099065231 December 2002Annual Report for Technical Specification Section 5.9.4.a, Table of Contents Through Section 5Grab sample
Offsite Dose Calculation Manual
Annual Radioactive Effluent Release Report
Annual Radiological Environmental Operating Report
Process Control Program
Annual Radiological Effluent Release Report