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Issue date | Title | Topic | |
---|---|---|---|
LIC-09-0046, Extended Power Uprate (EPU) Input Deck for Nuclear Regulation (NRR) Confirmatory Analyses | 30 June 2009 | Extended 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 Requirements | 30 June 2009 | Response to Request for Additional Information Concerning License Amendment Request (LAR) 09-01, Steam Generator Blowdown Isolation Operability and Testing Requirements | Time of Discovery Offsite Dose Calculation Manual Stroke time |
ML091680138 | 30 June 2009 | Summary 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 Plant | 29 June 2009 | Press Release-IV-09-025: NRC Names New Resident Inspector at Fort Calhoun Nuclear Plant | New Resident Inspector |
ML091680589 | 17 June 2009 | 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 | Time of Discovery |
ML091680586 | 17 June 2009 | Email, 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 | |
ML091520658 | 1 June 2009 | Initial Information Request for NRC Triennial Baseline Component Design Bases Inspection NRC Inspection Report 05000285-09-006 | Probabilistic Risk Assessment Temporary Modification |
ML091520530 | 1 June 2009 | G20090007/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 6/8/09 | High winds Probabilistic Risk Assessment Earthquake |
TAC:ME0352 | 1 June 2009 | ||
LIC-09-0037, Transmittal of Core Operating Limit Report (Colr), Revision 37 | 29 May 2009 | Transmittal of Core Operating Limit Report (Colr), Revision 37 | Boric 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)e | 29 May 2009 | 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)e | Time of Discovery Offsite Circuit |
ML091670466 | 28 May 2009 | Transmittal of Fort Calhoun Station Technical Data Book (TDB)-IV, Revision 37, Core Operating Limit Report | Boric Acid Shutdown Margin Pressure and Temperature Limits Report |
IR 05000285/2009402 | 12 May 2009 | IR 05000285-09-402, on 04/10/2009, for Fort Calhoun Nuclear Station - Security Inspection | Significance Determination Process Affidavit |
ML083260697 | 12 May 2009 | Issuance of Amendment No. 259, Revise Technical Specifications to Correct Typographical Errors and Make Administrative Clarifications | Annual 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 2009 | Revision 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 05000285/2009301 | 7 May 2009 | Er 05000285-09-301, on March 27-April 15, 2009, Fort Calhoun Station, NRC Examination Report | Job Performance Measure |
ML091250275 | 5 May 2009 | Replacement Page TS 2.1 - Page 8, License Amendment Request for Administrative Revisions | |
ML091250269 | 5 May 2009 | Email from Licensee, Question on the Basis of TS 2.1.1 License Amendment Request for Administrative Revisions | |
ML091240596 | 4 May 2009 | Meeting Summary, 2008 EOC Public Meeting with Omaha Public Power District on Fort Calhoun Station | |
IR 05000285/2009002 | 30 April 2009 | IR 05000285-09-002 on 01/01/09 - 03/31/2009 for Fort Calhoun Station | Stroke time Internal Flooding Condition Adverse to Quality Significance Determination Process Large early release frequency Frazil ice Fire Protection Program |
ML091280370 | 24 April 2009 | Transmittal of 2008 Fort Calhoun Station (FCS) Radiological Effluent Release Report and Radiological Environment Operating Report | Offsite 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 Report | 24 April 2009 | Transmittal of 2008 Fort Calhoun Station (FCS) Radiological Effluent Release Report and Radiological Environment Operating Report | Offsite Dose Calculation Manual Annual Radiological Environmental Operating Report Annual Radiological Effluent Release Report |
LIC-09-0020, Response to NRC Regulatory Issue Summary 2006-21 | 21 April 2009 | Response 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 Monitoring | 10 April 2009 | Special Report on Inoperability of Wide Range Noble Gas Stack Monitor RM-063 for Post Accident Monitoring | Post 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 50.46 | 8 April 2009 | 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 50.46 | Fuel cladding |
Press Release-IV-09-012, NRC to Discuss 2008 Performance Assessment for Fort Calhoun Nuclear Plant | 8 April 2009 | Press 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, 2008 | 8 April 2009 | Fort Calhoun, Unit 1, Annual Report for Technical Specification Section 5.9.4.a, January 1, 2008 to December 31, 2008 | Grab sample Offsite Dose Calculation Manual Annual Radioactive Effluent Release Report Annual Radiological Environmental Operating Report Process Control Program Annual Radiological Effluent Release Report |
ML091280371 | 8 April 2009 | Annual Report for Technical Specification Section 5.9.4.a, January 1, 2008 to December 31, 2008 | Grab sample Offsite Dose Calculation Manual Annual Radioactive Effluent Release Report Annual Radiological Environmental Operating Report Process Control Program Annual Radiological Effluent Release Report |
ML091110379 | 7 April 2009 | Ltr 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 Report | 7 April 2009 | Omaha Public Power District, 2008 Annual Report | Decommissioning Funding Plan |
LIC-09-0024, 2009-03-Post Exam Comments-Analysis | 7 April 2009 | 2009-03-Post Exam Comments-Analysis | |
ML090960775 | 6 April 2009 | Notice 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 Commitments | 3 April 2009 | Clarification of B.5.b Commitments | Boric 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) Models | 3 April 2009 | Annual Report for 2008 Loss (Loca)/Emergency Core Cooling Pursuant to 10 CFR 50.46 of Coolant Accident System (ECCS) Models |