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| Issue date | Title | |
|---|---|---|
| ML16008A981 | 15 January 2016 | Review of the Spring 2015 Steam Generator Tube Eddy Current Test Report |
| ML15232A003 | 21 August 2015 | Relief 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 |
| IR 05000285/2015002 | 30 July 2015 | IR 05000285/2015002; 4/01/2015 - 6/30/2015; Fort Calhoun Station, Integrated, Inservice Inspection Activities, EAL and Emergency Plan Changes, Follow-up of Events |
| LIC-15-0069, Response to NRC Request for Additional Information Regarding Relief Request RR-14 | 13 May 2015 | Response to NRC Request for Additional Information Regarding Relief Request RR-14 |
| 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 Welds | 9 May 2015 | 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 Welds |
| ML14030A591 | 28 January 2014 | Response to NRC Request for Additional Information (RAI) Leak Before Break LAR |
| IR 05000285/2013009 | 25 July 2013 | IR 05000285-13-009; 05/13/2013 -07/12/2013; Fort Calhoun Station, NRC Post-Approval License Renewal Inspection Report |
| ML12318A341 | 13 November 2012 | IR 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-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 |
| ML110200193 | 14 January 2011 | Withdrawal 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-11-0004, Wesdyne Report No. 1305120-Rpt.1 Fort Calhoun RPV Outlet Nozzle Eddy Current Data Normalization, Dated December 2010 | 31 December 2010 | Wesdyne Report No. 1305120-Rpt.1 Fort Calhoun RPV Outlet Nozzle Eddy Current Data Normalization, Dated December 2010 |
| ML102300641 | 16 August 2010 | 10 CFR 50.55a Request Number RR-12, Request for Relief from Code Case N-722 Visual Examination of the Reactor Vessel Hot Leg Nozzle to Safe End Dissimilar Metal Welds |
| 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 05000285/2009005 | 5 February 2010 | IR 05000285-09-005, 10/31/2009 - 12/31/2009; Fort Calhoun Station, Integrated Resident and Regional Report; Access Control to Radiologically Significant Areas |
| LIC-09-0083, Response to Request for Additional Information Regarding Steam Generator Tube Inservice Inspections During 2008 Refueling Outage | 16 October 2009 | Response to Request for Additional Information Regarding Steam Generator Tube Inservice Inspections During 2008 Refueling Outage |
| LIC-08-0120, Steam Generator Eddy Current Test Report - 2008 Refueling Outage | 9 December 2008 | Steam Generator Eddy Current Test Report - 2008 Refueling Outage |
| IR 05000285/2008003 | 12 August 2008 | IR 05000285-08-003, on 04/01/2008-06/30/2008, Fort Calhoun Station, Integrated Resident and Regional Report, Inservice Inspection Activities, Access Control to Radiologically Significant Areas, ALARA Planning & Controls, Event follow-up, Ot |
| IR 05000285/2008002 | 16 May 2008 | IR 05000285-08-002; on 01/01/2008 - 03/31/2008; Fort Calhoun Station, Integrated Resident and Regional Report; Flood Protection Measures, Operability Evaluations, Postmaintenance Testing, Identification and Resolution of Problems |
| ML071920158 | 27 June 2007 | Comment (23) of Charles A. Tomes on Proposed Rules Pr 50 Regarding Industry Codes and Standards; Amended Requirements |
| ML071770248 | 15 June 2007 | Comment (16) Submitted by Charles A. Tomes on Proposed Rule Pr 50 Regarding Industry Codes and Standards; Amended Requirements |
| 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 |
| IR 05000285/2005005 | 6 February 2006 | IR 05000285-05-005; on 10/01/2005 - 12/31/2005; Omaha Public Power District, Fort Calhoun Station, Integrated Resident and Regional Report; Operator Performance During Nonroutine Evolutions and Events; Operability Evaluations |
| IR 05000285/2005009 | 7 December 2005 | IR 05000285-05-009; 9/12/2005 - 11/30/2005; Fort Calhoun Station; Biennial Baseline Inspection of Problem Identification and Resolution |
| LIC-05-0121, License Amendment Request, Deletion of Sleeving as a Steam Generator Tube Repair Method. | 10 November 2005 | License Amendment Request, Deletion of Sleeving as a Steam Generator Tube Repair Method. |
| LIC-05-0118, Generator Eddy Current Test Report - 2005 Refueling Outage | 23 September 2005 | Generator Eddy Current Test Report - 2005 Refueling Outage |
| IR 05000285/2005003 | 5 August 2005 | IR 05000285-05-003, on 04/01/2005 Through 06/30/2005 for Fort Calhoun Station, Integrated Resident and Regional Report and Occupational Radiation Safety |
| LIC-05-0092, 60 Days After Plant Restart Report - First Revised NRC Order EA-03-009 Interim Inspection Requirement for Reactor Pressure Vessel Heads at Pressurized Water Reactors | 29 July 2005 | 60 Days After Plant Restart Report - First Revised NRC Order EA-03-009 Interim Inspection Requirement for Reactor Pressure Vessel Heads at Pressurized Water Reactors |
| ML051430424 | 3 June 2005 | Summary of Meeting with Omaha Public Power District, Fort Calhoun - Summary of Conference Call 2005 Steam Generator Inspection |
| ML051440735 | 24 May 2005 | 5/24/05 Fort Calhoun - Relaxation Request from U.S. NRC Order EA-03-009 for the Control Element Drive Mechanism Nozzles |
| LIC-05-0057, Revised Relaxation Request for First Revised Order (EA-03-009) Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads at Pressurized Water Reactors | 14 May 2005 | Revised Relaxation Request for First Revised Order (EA-03-009) Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads at Pressurized Water Reactors |
| LIC-05-0050, (FCS) Steam Generator Tube Plugging Report - 2005 Refueling Outage | 22 April 2005 | (FCS) Steam Generator Tube Plugging Report - 2005 Refueling Outage |
| LIC-05-0043, Supplemental Information for Relaxation Request for First Revised Order (EA-03-009) Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads at Pressurized Water Reactors | 15 April 2005 | Supplemental Information for Relaxation Request for First Revised Order (EA-03-009) Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads at Pressurized Water Reactors |
| LIC-05-0040, Relaxation Request for First Revised Order (EA-03-009) Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads at Pressurized Water Reactors | 7 April 2005 | Relaxation Request for First Revised Order (EA-03-009) Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads at Pressurized Water Reactors |
| ML043170494 | 22 November 2004 | Ft. Calhoun, Request for Additional Information Regarding SG Inspections |
| LIC-04-0080, Response to Item 1 of NRC Bulletin 2004-01, Inspection of Alloy 82/182/600 Materials Used in the Fabrication of Pressurizer Penetrations and Steam Space Piping Connections at Pressurized Water Reactors. | 27 July 2004 | Response to Item 1 of NRC Bulletin 2004-01, Inspection of Alloy 82/182/600 Materials Used in the Fabrication of Pressurizer Penetrations and Steam Space Piping Connections at Pressurized Water Reactors. |
| LIC-04-0040, (FCS) Steam Generator Eddy Current Test Report - 2003 Refueling Outage | 26 March 2004 | (FCS) Steam Generator Eddy Current Test Report - 2003 Refueling Outage |
| ML040580502 | 25 February 2004 | & 10/02/2003 Summary of Conference Calls with Omaha Public Power District (OPPD) Regarding Fort Calhoun, Unit 1 - 2003 Steam Generator Inspection |
| ML040220181 | 20 February 2004 | Issuance of Revised NRC Order EA-03-009 Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads at Pressurized Water Reactors |
| IR 05000285/2003008 | 17 June 2003 | IR 05000285-03-008; on 04/28 - 05/08/03, for Omaha Public Power District, Fort Calhoun Station; Biennial Baseline Inspection of the Problem Identification and Resolution |
| ML031080100 | 17 April 2003 | Summary of Telecommunication with Omaha Public Power District (OPPD) to Discuss Draft Requests for Additional Information (Rais) for the Renewal of the Operating License for Fort Calhoun Station, Unit 1 (FCS) |
| LIC-02-0106, Revised Response to NRC Bulletin 2002-02, Reactor Pressure Vessel Head Degradation & Vessel Head Penetration Nozzle Inspection Programs | 17 February 2003 | Revised Response to NRC Bulletin 2002-02, Reactor Pressure Vessel Head Degradation & Vessel Head Penetration Nozzle Inspection Programs |
| ML030380470 | 11 February 2003 | Issuance of Order Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads at Pressurized Water Reactors |
| LIC-03-0008, Response to NRC Bulletin 2002-01 Request for Additional Information | 17 January 2003 | Response to NRC Bulletin 2002-01 Request for Additional Information |
| LIC-02-0139, Generator Eddy Current Test Report - 2002 Refueling Outage | 3 December 2002 | Generator Eddy Current Test Report - 2002 Refueling Outage |
| ML022400798 | 1 February 2002 | E-mail from Beth Wetzel Bulletin 2001-01 Status Report |
| ML022400781 | 18 January 2002 | E-mail from Jacob Zimmerman, Bulletin 2001-01 Status Report |
| ML022400774 | 10 January 2002 | E-mail from Jacob Zimmerman, Bulletin 2001-01 Status Report |
| ML20196G244 | 31 October 1998 | Changes,Tests & Experiments Carried Out Without Prior Commission Approval. with USAR Changes Other than Those Resulting from 10CFR50.59 |
| LIC-98-0141, SG Eddy Current Test Rept for 1998 Refueling Outage. with | 27 October 1998 | SG Eddy Current Test Rept for 1998 Refueling Outage. with |
| LIC-98-0072, Informs That OPPD Completed Eddy Current Testing of SG Tubes on 980427 During Seventeenth Refueling Outage.Specific Details Re SG Tube Plugging Will Be Provided in Six Months IAW TS 3.17(5)(ii) | 26 May 1998 | Informs That OPPD Completed Eddy Current Testing of SG Tubes on 980427 During Seventeenth Refueling Outage.Specific Details Re SG Tube Plugging Will Be Provided in Six Months IAW TS 3.17(5)(ii) |