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 Issue dateTitle
ML18173A1797 August 2018OEDO-17-00070 - Notice of Issuance of Director'S Decision, 2.206 Petition for Emergency Enforcement Action Per 10 CFR 2.206 at Listed U.S. Reactors with Forged Components and Parts Manufactured at France'S AREVA-Le Creusot Forge and Japan C
ML18173A1752 August 2018OEDO-17-00070/SRM-DD-18-03 - Director'S Decision, 2.206 Petition for Emergency Enforcement Action Per 10 CFR 2.206 at Listed U.S. Reactors with Forged Components and Parts Manufactured at France'S AREVA-Le Creusot Forge and Japan Casting
ML18180A2185 July 2018Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: 7/17/2018
ML18107A4046 June 2018OEDO-17-00070 - Proposed Director'S Decision on Areva Forgings 2.206
ML18107A4026 June 2018OEDO-17-00070 - Letter to Petitioner on Areva Forgings 2.206
ML20311A5936 November 20172017 Q1-Q4 ROP Inspection Findings
ML14205A31428 July 2014Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations- Published July 22, 2014
3F0712-08, Response to Second Request for Additional Information to Support NRC PRA Licensing Branch (Apla) Technical Review of the CR-3 Extended Power Uprate LAR31 July 2012Response to Second Request for Additional Information to Support NRC PRA Licensing Branch (Apla) Technical Review of the CR-3 Extended Power Uprate LAR
3F0312-01, Response to Request for Additional Information to Support NRC PRA Licensing Branch Technical Review of the CR-3 Extended Power Uprate LAR22 March 2012Response to Request for Additional Information to Support NRC PRA Licensing Branch Technical Review of the CR-3 Extended Power Uprate LAR
ML12056A04712 March 2012Enclosure 1 - Recommendation 2.1: Seismic
ML12003A2178 February 2012Nuclear Generating Plant - Request for Additional Information for Extended Power Uprate License Amendment Request
3F0811-02, Response to Request for Additional Information to Support NRC Balance of Plant Branch Acceptance Review of the CR-3 Extended Power Uprate LAR11 August 2011Response to Request for Additional Information to Support NRC Balance of Plant Branch Acceptance Review of the CR-3 Extended Power Uprate LAR
3F0811-04, Response to Request for Additional Information to Support NRC Probabilistic Risk Assessment Licensing Branch Acceptance Review of the CR-3 Extended Power Uprate LAR11 August 2011Response to Request for Additional Information to Support NRC Probabilistic Risk Assessment Licensing Branch Acceptance Review of the CR-3 Extended Power Uprate LAR
ML11207A44215 June 2011License Amendment Request #309, Revision 0, Extended Power Uprate
IR 05000302/200900712 October 2010Special Inspection Report 05000302/2009007
3F1209-04, Response to Follow-up to Progress Energy RAI Responses on CR-3 SAMA Evaluation18 December 2009Response to Follow-up to Progress Energy RAI Responses on CR-3 SAMA Evaluation
3F1009-03, Response to Request for Additional Information Regarding Severe Accident Mitigation Alternatives9 October 2009Response to Request for Additional Information Regarding Severe Accident Mitigation Alternatives
ML09197006810 August 2009Request for Additional Information Regarding Severe Accident Mitigation Alternatives for Crystal River Unit 3 Nuclear Generating Plant License Renewal Application
ML09008073130 November 2008License Renewal Application, Consisting of Applicant'S Environmental Report
3F0708-04, Response to Request for Additional Information Regarding Relief Request Request 07-001-II, Revision 0, Alternate Risk-Informed Selection and Examination Criteria for Examination Category B-F and B-J Pressure Retaining Welds In.10 July 2008Response to Request for Additional Information Regarding Relief Request Request 07-001-II, Revision 0, Alternate Risk-Informed Selection and Examination Criteria for Examination Category B-F and B-J Pressure Retaining Welds In.
3F1207-02, Request for Extension of Completion Date for Corrective Actions and Modifications Required by Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized...10 December 2007Request for Extension of Completion Date for Corrective Actions and Modifications Required by Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized...
3F0907-03, License Amendment Request 295, Revision 0: Extension of Allowed Outage Time to Seven Days and Elimination of Second Completion Times Response to Request for Additional Information4 September 2007License Amendment Request #295, Revision 0: Extension of Allowed Outage Time to Seven Days and Elimination of Second Completion Times Response to Request for Additional Information
ML07150046615 June 2007License Amendment, Issuance of Amendment to Adopt TSTF-372
3F0407-12, License Amendment Request 295, Revision 0, Extension of Allowed Outage Time to Seven Days and Elimination of Second Completion Times Limiting Time13 April 2007License Amendment Request #295, Revision 0, Extension of Allowed Outage Time to Seven Days and Elimination of Second Completion Times Limiting Time
ML05299029319 October 2005FAQ Log 10/19/2005
IR 05000302/200500929 September 2005IR 05000302-05-09, on 08/22-25/2005, Crystal River Unit 3 - NRC Annual Sample of Problem Identification and Resolution
ML05270004421 September 2005Attachment 10, FAQ Log 9/21/05
ML05236002820 September 2005Relief Request, Risk-Informed Inservice Inspection Program
ML05259004615 September 2005License Amendment, Temporary Extension of the Nuclear Services Seawater System Train Completion Time
ML05189034827 July 2005Amendment 218, Surveillance Requirements for RCP Flywheel Inspection
3F0705-09, Response to Request for Additional Information Regarding Third 10-Year Inservice Inspection Program - Risk-Informed Inservice Inspection Program for Class 1, ASME Code, Category B-J and B-F Piping Welds - Question 114 July 2005Response to Request for Additional Information Regarding Third 10-Year Inservice Inspection Program - Risk-Informed Inservice Inspection Program for Class 1, ASME Code, Category B-J and B-F Piping Welds - Question 1
3F0605-01, License Amendment Request 289, Revision 1 Revised Improved Technical Specifications (ITS) 3.5.2, Emergency Core Cooling Systems (ECCS) - Operating, 3.6.6, Reactor Building Spray and Containment Cooling Systems, 3.7.8, Decay.9 June 2005License Amendment Request #289, Revision 1 Revised Improved Technical Specifications (ITS) 3.5.2, Emergency Core Cooling Systems (ECCS) - Operating, 3.6.6, Reactor Building Spray and Containment Cooling Systems, 3.7.8, Decay.
3F0105-02, License Amendment Request 289, Revision 0 Revised Improved Technical Specifications 3.5.2, Emergency Core Cooling Systems - Operating, 3.6.6, Reactor Building Spray & Containment Cooling Systems, 3.7.8, Decay Heat Closed Cycle.13 January 2005License Amendment Request #289, Revision 0 Revised Improved Technical Specifications 3.5.2, Emergency Core Cooling Systems - Operating, 3.6.6, Reactor Building Spray & Containment Cooling Systems, 3.7.8, Decay Heat Closed Cycle.
ML05012047011 January 2005License Amendment, Mode Change Limitations (Tac No. MC1861)
3F1104-02, Third 10-Year Inservice Inspection Program - Request for Approval of Risk-Informed Inservice Inspection Program for Class 1, ASME Code, Category B-J and B-F Piping Welds10 November 2004Third 10-Year Inservice Inspection Program - Request for Approval of Risk-Informed Inservice Inspection Program for Class 1, ASME Code, Category B-J and B-F Piping Welds
3F0704-05, License Amendment Request (LAR) 283, Revision 0, Improved Technical Specification (ITS) 5.6.2.20, Containment Leakage Rate Testing Program, Integrated Leakage Rate Testing (ILRT) Surveillance Interval Extension1 July 2004License Amendment Request (LAR) #283, Revision 0, Improved Technical Specification (ITS) 5.6.2.20, Containment Leakage Rate Testing Program, Integrated Leakage Rate Testing (ILRT) Surveillance Interval Extension
ML04140028218 May 2004License Amendment 212 Regarding the Nuclear Services Seawater System
ML04026001619 January 2004Request for Review of BAW-2441, Revision 2, Risk Informed Justification for LCO End-State Changes.
3F1203-03, License Amendment Request No. 281, Revision 0 Regarding Revised Improved Technical Specification (ITS) 3.7.5, Emergency Feedwater System9 December 2003License Amendment Request No. 281, Revision 0 Regarding Revised Improved Technical Specification (ITS) 3.7.5, Emergency Feedwater System
3F0703-04, License Amendment Request 280, Rev. 0 Revised Improved Technical Specification (ITS) 3.7.9, Nuclear Services Seawater System14 July 2003License Amendment Request 280, Rev. 0 Revised Improved Technical Specification (ITS) 3.7.9, Nuclear Services Seawater System
ML03167099313 June 2003Issuance of License Amendment 207 Technical Specification Change Request for Emergency Diesel Generator Allowed Outage Time Extension
3F0303-03, Response to Request for Additional Information & Revision 1 to Proposed License Amendment Request 257, Emergency Diesel Generator Allowed Outage Time Extension20 March 2003Response to Request for Additional Information & Revision 1 to Proposed License Amendment Request #257, Emergency Diesel Generator Allowed Outage Time Extension
3F0702-07, License Amendment Request 257, Revision 0, Emergency Diesel Generator Allowed Outage Time Extension.3 July 2002License Amendment Request #257, Revision 0, Emergency Diesel Generator Allowed Outage Time Extension.
ML20196L20319 May 1999Non-proprietary Rev 0 to BAW-2346NP, Alternate Repair Criteria for Tube End Cracking in Tube-to-Tubesheet Roll Joint of Once-Through Sgs