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 Issue dateTitleTopic
LIC-09-0046, Extended Power Uprate (EPU) Input Deck for Nuclear Regulation (NRR) Confirmatory Analyses30 June 2009Extended Power Uprate (EPU) Input Deck for Nuclear Regulation (NRR) Confirmatory Analyses
LIC-09-0043, Response to Request for Additional Information Concerning License Amendment Request (LAR) 09-01, Steam Generator Blowdown Isolation Operability and Testing Requirements30 June 2009Response to Request for Additional Information Concerning License Amendment Request (LAR) 09-01, Steam Generator Blowdown Isolation Operability and Testing RequirementsTime of Discovery
Offsite Dose Calculation Manual
Stroke time
ML09168013830 June 2009Summary of Conference Call Regarding Issues Related to the Cracking of Mitsubishi Heavy Industries Ltd.-Fabricated Replacement Steam Generators for San Onofre Nuclear Station, Unit 3
Press Release-IV-09-025, NRC Names New Resident Inspector at Fort Calhoun Nuclear Plant29 June 2009Press Release-IV-09-025: NRC Names New Resident Inspector at Fort Calhoun Nuclear PlantNew Resident Inspector
ML09168058917 June 2009Request for Additional Information, License Amendment Request, Modify Technical Specifications to Add Operability and Testing Requirements for Steam Generator Blowdown Isolation on a Reactor TripTime of Discovery
ML09168058617 June 2009Email, Request for Additional Information, License Amendment Request, Modify Technical Specifications to Add Operability and Testing Requirements for Steam Generator Blowdown Isolation on a Reactor Trip
ML0915206581 June 2009Initial Information Request for NRC Triennial Baseline Component Design Bases Inspection NRC Inspection Report 05000285-09-006Probabilistic Risk Assessment
Temporary Modification
ML0915205301 June 2009G20090007/OEDO-2009-0007 -Email Record of 6/1/09 Phone Call with Tom Lakosh, Informing of Prb'S Initial Recommendation to Reject Petition Request Pursuant 10 CFR 2.206 Reactors Near Yellowstone Caldera Eruptions Response Due by 6/8/09High winds
Probabilistic Risk Assessment
Earthquake
TAC:ME03521 June 2009
LIC-09-0037, Transmittal of Core Operating Limit Report (Colr), Revision 3729 May 2009Transmittal of Core Operating Limit Report (Colr), Revision 37Boric Acid
Shutdown Margin
LIC-09-0036, License Amendment Request 09-03,Revision to Technical Specifications Sections 2.0.1 & 2.7 for Inoperable System, Subsystem or Component Due to Inoperable Power Source & Deletion of Diesel Generator Surveillance Requirements 3.7(1)e29 May 2009License Amendment Request 09-03,Revision to Technical Specifications Sections 2.0.1 & 2.7 for Inoperable System, Subsystem or Component Due to Inoperable Power Source & Deletion of Diesel Generator Surveillance Requirements 3.7(1)eTime of Discovery
Offsite Circuit
ML09167046628 May 2009Transmittal of Fort Calhoun Station Technical Data Book (TDB)-IV, Revision 37, Core Operating Limit ReportBoric Acid
Shutdown Margin
Pressure and Temperature Limits Report
IR 05000285/200940212 May 2009IR 05000285-09-402, on 04/10/2009, for Fort Calhoun Nuclear Station - Security InspectionSignificance Determination Process
Affidavit
ML08326069712 May 2009Issuance of Amendment No. 259, Revise Technical Specifications to Correct Typographical Errors and Make Administrative ClarificationsAnnual Radioactive Effluent Release Report
Process Control Program
Safeguards Contingency Plan
Fire Protection Program
LIC-09-0034, Revision to License Amendment Request (LAR) 08-03, Clarify Technical Specification 2.7(2) Regarding Preferred Offsite Power Source, Transformer Allowed Outage Time (AOT)8 May 2009Revision to License Amendment Request (LAR) 08-03, Clarify Technical Specification 2.7(2) Regarding Preferred Offsite Power Source, Transformer Allowed Outage Time (AOT)Safe Shutdown
Offsite Circuit
IR 05000285/20093017 May 2009Er 05000285-09-301, on March 27-April 15, 2009, Fort Calhoun Station, NRC Examination ReportJob Performance Measure
ML0912502755 May 2009Replacement Page TS 2.1 - Page 8, License Amendment Request for Administrative Revisions
ML0912502695 May 2009Email from Licensee, Question on the Basis of TS 2.1.1 License Amendment Request for Administrative Revisions
ML0912405964 May 2009Meeting Summary, 2008 EOC Public Meeting with Omaha Public Power District on Fort Calhoun Station
IR 05000285/200900230 April 2009IR 05000285-09-002 on 01/01/09 - 03/31/2009 for Fort Calhoun StationStroke time
Internal Flooding
Condition Adverse to Quality
Significance Determination Process
Large early release frequency
Frazil ice
Fire Protection Program
ML09128037024 April 2009Transmittal of 2008 Fort Calhoun Station (FCS) Radiological Effluent Release Report and Radiological Environment Operating ReportOffsite Dose Calculation Manual
Annual Radiological Environmental Operating Report
Annual Radiological Effluent Release Report
LIC-09-0032, Transmittal of 2008 Fort Calhoun Station (FCS) Radiological Effluent Release Report and Radiological Environment Operating Report24 April 2009Transmittal of 2008 Fort Calhoun Station (FCS) Radiological Effluent Release Report and Radiological Environment Operating ReportOffsite Dose Calculation Manual
Annual Radiological Environmental Operating Report
Annual Radiological Effluent Release Report
LIC-09-0020, Response to NRC Regulatory Issue Summary 2006-2121 April 2009Response to NRC Regulatory Issue Summary 2006-21
LIC-09-0027, Special Report on Inoperability of Wide Range Noble Gas Stack Monitor RM-063 for Post Accident Monitoring10 April 2009Special Report on Inoperability of Wide Range Noble Gas Stack Monitor RM-063 for Post Accident MonitoringPost Accident Monitoring
LIC-09-0028, Omaha Public Power District - 30-Day Report of a Significant Change/Error in the Loss of Coolant Accident (Loca)/Emergency Core Cooling System (ECCS) Models Pursuant to 10 CFR 50.468 April 2009Omaha Public Power District - 30-Day Report of a Significant Change/Error in the Loss of Coolant Accident (Loca)/Emergency Core Cooling System (ECCS) Models Pursuant to 10 CFR 50.46Fuel cladding
Press Release-IV-09-012, NRC to Discuss 2008 Performance Assessment for Fort Calhoun Nuclear Plant8 April 2009Press Release-IV-09-012: NRC to Discuss 2008 Performance Assessment for Fort Calhoun Nuclear Plant
LIC-09-0032, Fort Calhoun, Unit 1, Annual Report for Technical Specification Section 5.9.4.a, January 1, 2008 to December 31, 20088 April 2009Fort Calhoun, Unit 1, Annual Report for Technical Specification Section 5.9.4.a, January 1, 2008 to December 31, 2008Grab sample
Offsite Dose Calculation Manual
Annual Radioactive Effluent Release Report
Annual Radiological Environmental Operating Report
Process Control Program
Annual Radiological Effluent Release Report
ML0912803718 April 2009Annual Report for Technical Specification Section 5.9.4.a, January 1, 2008 to December 31, 2008Grab sample
Offsite Dose Calculation Manual
Annual Radioactive Effluent Release Report
Annual Radiological Environmental Operating Report
Process Control Program
Annual Radiological Effluent Release Report
ML0911103797 April 2009Ltr to Linda Howell, Chief, Rcb, from David L. Miller, Administrator, Iowa Homeland Security and Emergency Management Division, Participation in Fort Calhoun Nuclear Power Plant Exercise to Be Held on July 21, 2009, 04/07/2009
LIC-09-0029, Omaha Public Power District, 2008 Annual Report7 April 2009Omaha Public Power District, 2008 Annual ReportDecommissioning Funding Plan
LIC-09-0024, 2009-03-Post Exam Comments-Analysis7 April 20092009-03-Post Exam Comments-Analysis
ML0909607756 April 2009Notice of End-of-Cycle Meeting with Omaha Public Power District - Fort Calhoun Station to Present and Discuss the Performance Results for the Fort Calhoun Station for the Period of January 1 Though December 31, 2008
LIC-09-0021, Clarification of B.5.b Commitments3 April 2009Clarification of B.5.b CommitmentsBoric Acid
Severe Accident Management Guideline
B.5.b Mitigating Strategies
LIC-09-0026, Annual Report for 2008 Loss (Loca)/Emergency Core Cooling Pursuant to 10 CFR 50.46 of Coolant Accident System (ECCS) Models3 April 2009Annual Report for 2008 Loss (Loca)/Emergency Core Cooling Pursuant to 10 CFR 50.46 of Coolant Accident System (ECCS) Models