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List of results

• LIC-08-0010, Omaha Public Power District, Response to NRC Bulletin 2007-01  + (Omaha Public Power District, Response to NRC Bulletin 2007-01)
• ML080420473  + (Omaha Public Power District, Response to NRC Bulletin 2007-01)
• LIC-13-0112, Omaha Public Power District, Response to RIS 2013-06, Preparation and Scheduling of Operator Licensing Examinations  + (Omaha Public Power District, Response to RIS 2013-06, Preparation and Scheduling of Operator Licensing Examinations)
• LIC-13-0092, Omaha Public Power District, Special Report on the Containment Tendon Prestressing System; Grease Voids Found in Helical Tendons and Lower Seal Failure on Tendon H-2067  + (Omaha Public Power District, Special Report on the Containment Tendon Prestressing System; Grease Voids Found in Helical Tendons and Lower Seal Failure on Tendon H-2067)
• LIC-12-0092, Omaha Public Power District, Submittal of Part 21 Notification - Identification of Defect  + (Omaha Public Power District, Submittal of Part 21 Notification - Identification of Defect)
• LIC-02-0043, Omaha Public Power District, Transmittal of Changes to Emergency Planning Forms (Epf)  + (Omaha Public Power District, Transmittal of Changes to Emergency Planning Forms (Epf))
• ML20237K258  + (Omaha Public Power District,Fort Calhoun Station Unit 1 Semiannual Rept for Tech Spec Section 5.9.4 for Jan-June 1987)
• ML20085K545  + (Omaha Public Power District,Fort Calhoun Station,Unit 1 Inservice Insp Program Plan for 1983-93 Interval)
• IR 05000285/2018004  + (Omaha Public Power District; Fort Calhoun Station - NRC Inspection Report 05000285/2018-004)
• LIC-05-0034, Omaha Public Power Districts 2004 Annual Financial Report  + (Omaha Public Power Districts 2004 Annual Financial Report)
• LIC-12-0048, Omaha Public Power Districts 60-Day Response to NRC Letter, 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 Insig  + (Omaha Public Power Districts 60-Day Response to NRC Letter, 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)
• LIC-12-0035, Omaha Public Power Districts Answer to March 12, 2012 Commission Order to Modify Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051)  + (Omaha Public Power Districts Answer to March 12, 2012 Commission Order to Modify Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051))
• ML12093A114  + (Omaha Public Power Districts Answer to March 12, 2012 Commission Order to Modify Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049))
• LIC-02-0050, Omaha Public Power Districts Clarification of Response to Commission Order to Modify License for Interim Safeguards and Security Measures  + (Omaha Public Power Districts Clarification of Response to Commission Order to Modify License for Interim Safeguards and Security Measures)
• LIC-13-0123, Omaha Public Power Districts First Six-Month Status Report for the Implementation of Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design Basis External Events-Redacted  + (Omaha Public Power Districts First Six-Month Status Report for the Implementation of Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design Basis External Events-Redacted)
• LIC-13-0019, Omaha Public Power Districts Overall Integrated Plan in Response to March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond Design Basis External Events (Order Number EA-12-049  + (Omaha Public Power Districts Overall Integrated Plan in Response to March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond Design Basis External Events (Order Number EA-12-049))
• LIC-04-0055, Omaha Public Power Districts Response to Request for Additional Information, Relief Request for Previous Repair of Pressurizer Nozzle  + (Omaha Public Power Districts Response to Request for Additional Information, Relief Request for Previous Repair of Pressurizer Nozzle)
• LIC-14-0023, Omaha Public Power Districts Second Six-Month Status Report for the Implementation of Order EA-12-051, Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation  + (Omaha Public Power Districts Second Six-Month Status Report for the Implementation of Order EA-12-051, Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation)
• ML14055A412  + (Omaha Public Power Districts Second Six-Month Status Report for the Implementation of Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events)
• LIC-12-0038, Omaha Public Power Districts, Fort Calhoun, 30-Day Response to March 12, 2012, Information Request  + (Omaha Public Power Districts, Fort Calhoun, 30-Day Response to March 12, 2012, Information Request)
• LIC-13-0033, Omaha Public Power Districts, Responses to Second Request for Additional Information License Amendment Request to Adopt NFPA 805 at Fort Calhoun Station  + (Omaha Public Power Districts, Responses to Second Request for Additional Information License Amendment Request to Adopt NFPA 805 at Fort Calhoun Station)
• TXX-3044, Omission of Shear Tie Reinforcing Steel,Approx Elevation 993 to 997,Unit 2 - Reactor Containment Bldg  + (Omission of Shear Tie Reinforcing Steel,Approx Elevation 993 to 997,Unit 2 - Reactor Containment Bldg)
• 05000361/FIN-2008010-03  + (Omission of Station Blackout Profile During Battery Service Tests)
• TSTF-201  + (Omit Battery Conditional Evalutations from SR 3.8.6.2)
• TSTF-157  + (Omit Duplicate EFW Alignment SR)

• TSTF-253  + (Omit Note Which Indicates That Performance of One SR Satisfies Another)

• ML20247M854  + (Omitted Cover Sheet to Rev 6 to ODCM for Plant)
• ML20202D316  + (Omitted Page 42 to Insp Repts 50-324/97-13 & 50-325/97-13 Transmitted on 980123)
• ML20071A107  + (Omitted Pages from Committee to Bridge the Gap Response to NRC & Applicant Motions for Summary Disposition)
• ML17339A251  + (Omitted Pages of Nonradiological Environ Monitoring Rept, for Jul-Dec 1978)
• ML20150C550  + (Omitted Tech Spec Page 3/4 8-2 to Amend 107 to License NPF-3,extending Due Date for Performing Tests & Insps Required by Surveillance Requirement 4.8.1.1.1.b to 880401)
• ML052170204  + (Omitted Technical Specification Page for Amendment No. 235)
• ML18283B102  + (On 02/21/75 - 02/22/75 the 120 Volt Control Power Was Off to RCIC Flow Controller, Torus Level Indicator & Drywell Pressure Indicator. Reactor Was at Rated Power)
• IR 05000528/2011006  + (On 03/23/11 - 04/29/11 Temporary Instruction 2515/183 Inspection Report 05000528/2011006, 05000529/2011006, and 05000530/2011006)
• IR 05000298/2011007  + (On 03/23/2011 – 04/28/2011, Temporary Instruction 2515/183 - Inspection Report 05000298/2011007, Followup to the Fukushima Daiichi Nuclear Station Fuel Damage Event)
• IR 05000324/2008301  + (On 04/17/08 Examination Report 05000325/08-301 and 05000324/08-301, Reactor and Senior Reactor Operator Retake Initial)
• ML19094A155  + (On 06/06/1975 a Meeting Held Between Regulatory Staff & Vepco Representatives to Discuss the Supplemental Information Submitted in a Letter of 06/06/1975, Serial No.500-S, Concerning ECCS Re-analysis)
• 05000529/LER-2004-002, On 07/14/2004 Reactor Tripped on Low Departure from Nucleate Boiling Ratio (DNBR)  + (On 07/14/2004 Reactor Tripped on Low Departure from Nucleate Boiling Ratio (DNBR))
• 05000456/LER-2004-003, On 08/16/2004, Oa Hydrogen Recombiner Identified to Be Inoperable Greater than Required Technical Specification Allowed Outage Time  + (On 08/16/2004, Oa Hydrogen Recombiner Identified to Be Inoperable Greater than Required Technical Specification Allowed Outage Time)
• ML063390040  + (On 10/02-06/2006 and 10/16-20/2006, Florida Power & Light Company, Triennial Fire Protection and Exercise of Enforcement Discretion)
• ML19093A974  + (On 11/18/1977, Surry Unit No. 2 Was Shutdown Due to a Primary to Secondary Leak Slightly Greater than 0.3 Gpm in a Steam Generator)
• ML19322C527  + (On 750613,quench Tank Rupture Disc Ruptured & Fuel Compression Curve,Cooldown Rates & Reactor Coolant Pumps NPSH Curves Violated.Caused by Lever Pin,Lever Hinge & Solenoid Bracket Corrosion.Valve Repaired)
• ML20125D892  + (On 780329,reactor Tripped on Pump Power Trip,Followed by Rapid Depressurization of Rcs.Caused by De Energizing of Vital Power Supply 2-4.Review Underway Re Isolation, Surveillance & Operating Procedures)
• ML20062D112  + (On 781024 Suffolk County Legis Authorized Preparation of Rept as Requested by Staff & Applicant.Will Attempt to Complete Rept by 781113)
• ML17317A705  + (On 781030,deluge Valves Isolated to Facilitate Drumming Room & New Fuel Receiving Area as Result of Repair on Fire Sys Headers.Followup Rept Will Be Issued on 781110)
• ML20062D302  + (On 781102 During Routine Test,Shim Arm 1 Had Drop Time in Excess of Acceptable Range Caused by Slightly Longer Clutch Release.Assembly Removed & Snap Ring on Armature Hub Replaced in Favor of a More Uniform Support)
• ML19283B794  + (On 781103,A-E Notified Util That Concrete Placement Drawings for Containment Liner Erection Do Not Contain Details Which Require Use of 3/8 X 1 Foam Strip to Be Installed on Top of 5 Vertical Liner Backing Ring)
• ML20147C518  + (On 781114 TVA Reported the Discovery of a Reverse Fault 106 Feet North of Reactors east-west Center Line.Tva Will Submit Rept Detailing Description of Reverse Fault & Faults Relationship to Regional Geology)
• ML19281A900  + (On 781128,Commission Briefed on Nov 1978 Projection of Status of Nuclear Power Reactor Licensing Schedules & on Schedule Deferrals During Oct 1978)
• ML20064G566  + (On 781129 at 4:00 Pm,Due to Problem in Heluim Circulatory Sys,There Was a Minute Release of Radioactivity in Reactor Bldg.No Hazard to Public)
• ML18113A788  + (On 781231,condenser Cooling Water Outlet Temp to James River Increased by 3.5 F & Then Decreased by 3 F.Temp Change Was in Excess of Tech Spec Max Change.No Evidence of Adverse Effects on River or Its Inhabitants)