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	Issue date	Title	Topic
3F0112-04, Response to Request for Additional Information to Support NRC Steam Generator Tube Integrity and Chemical Engineering Branch Technical Review of the CR-3 Extended Power Uprate LAR	5 January 2012	Response to Request for Additional Information to Support NRC Steam Generator Tube Integrity and Chemical Engineering Branch Technical Review of the CR-3 Extended Power Uprate LAR	Coatings Flow Accelerated Corrosion License Renewal Power Uprate
3F0113-08, Attachment D: ANP-3195(NP), Revision 0, Response for Crystal River Unit 3, EPU Licensing Amendment Report NRC Reactor Systems Branch Requests for Additional Information (Non-Proprietary) and Attachment E: Location of Reactor Systems RAI Re	31 January 2013	Attachment D: ANP-3195(NP), Revision 0, Response for Crystal River Unit 3, EPU Licensing Amendment Report NRC Reactor Systems Branch Requests for Additional Information (Non-Proprietary) and Attachment E: Location of Reactor Systems RAI Res	Shutdown Margin Anticipated operational occurrence Fuel cladding Power Uprate Manual Operator Action
3F0508-14, NRC Commitment Change Report - May 2008	28 May 2008	NRC Commitment Change Report - May 2008
3F0511-02, Response to Request for Additional Information Required for the Development of the Confirmatory LOCA and Non-LOCA Models	6 May 2011	Response to Request for Additional Information Required for the Development of the Confirmatory LOCA and Non-LOCA Models	Power Uprate
3F0512-01, NRC Commitment Change Report - May 2012	14 May 2012	NRC Commitment Change Report - May 2012	Stress corrosion cracking
3F0602-05, Response to Request for Additional Information 263, Revision 0, Relocation of Reactor Coolant System Parameters to Core Operating Limits Report & 20 Percent Steam Generator Tube Plugging	5 June 2002	Response to Request for Additional Information #263, Revision 0, Relocation of Reactor Coolant System Parameters to Core Operating Limits Report & 20 Percent Steam Generator Tube Plugging	Shutdown Margin FLEX Flow Induced Vibration Unidentified leakage Power Uprate Exclusive Use Affidavit
3F0616-02, Nrg Commitment Change Report - June 2016	14 June 2016	Nrg Commitment Change Report - June 2016	Safe Shutdown Boric Acid Offsite Dose Calculation Manual Time to boil B.5.b Pressure Boundary Leakage Backfit Operability Assessment
3F0702-11, Reporting Required by Environmental Protection Plan	16 July 2002	Reporting Required by Environmental Protection Plan
3F0902-09, Submittal of Core Operating Limits Report, Cycle 13, Revision 1, for Crystal River Unit 3	24 September 2002	Submittal of Core Operating Limits Report, Cycle 13, Revision 1, for Crystal River Unit 3	Shutdown Margin
3F0910-01, CFR 50.46 Notification of Change in Peak Cladding Temperature for Small Break Loss of Coolant Accident Analysis	8 September 2010	CFR 50.46 Notification of Change in Peak Cladding Temperature for Small Break Loss of Coolant Accident Analysis
3F1102-08, Sea Turtle Mortality Report Submitted to the U. S. National Marine Fisheries Service	19 November 2002	Sea Turtle Mortality Report Submitted to the U. S. National Marine Fisheries Service
3F1205-03, Special Report 05-01: Once-Through Steam Generator (OTSG) Notifications Required Prior to Mode 4	3 December 2005	Special Report 05-01: Once-Through Steam Generator (OTSG) Notifications Required Prior to Mode 4	Fuel cladding
3F1205-04, 10 CFR 50.46 Loss-Of-Coolant Accident Evaluation Model Change and Peak Cladding Temperature Change Report	12 December 2005	10 CFR 50.46 Loss-Of-Coolant Accident Evaluation Model Change and Peak Cladding Temperature Change Report
3F1207-03, Engineering Report ER-608NP, Revision 2, LEFM + Meter Factor Calculation and Accuracy Assessment for Crystal River Unit 3 Nuclear Power Station.	13 December 2007	Engineering Report ER-608NP, Revision 2, LEFM + Meter Factor Calculation and Accuracy Assessment for Crystal River Unit 3 Nuclear Power Station.	Power Uprate Measurement Uncertainty Recapture
3F1209-11, 10 CFR 50.46 Loss-of-Coolant Accident Evaluation Model Change and Peak Cladding Temperature Change Report	16 December 2009	10 CFR 50.46 Loss-of-Coolant Accident Evaluation Model Change and Peak Cladding Temperature Change Report
3F1211-14, Summary of Changes to Evaluation Models and Peak Cladding Temperature for Large Break Loss of Coolant Analysis and Small Break Loss of Coolant Analysis	14 December 2011	Summary of Changes to Evaluation Models and Peak Cladding Temperature for Large Break Loss of Coolant Analysis and Small Break Loss of Coolant Analysis
BSEP 05-0018, Occupational Radiation Exposure Report for 2004	20 April 2005	Occupational Radiation Exposure Report for 2004
BSEP 05-0110, Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors	31 August 2005	Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors
BSEP 05-0137, Core Operating Limits Report, Revision 2, Cycle 15	14 November 2005	Core Operating Limits Report, Revision 2, Cycle 15	Anticipated operational occurrence
BSEP 06-0075, Groundwater Questionnaire	28 July 2006	Groundwater Questionnaire	Offsite Dose Calculation Manual
BSEP 06-0095, Report of 10 CFR 50.59 Evaluation and Commitment Changes	24 August 2006	Report of 10 CFR 50.59 Evaluation and Commitment Changes	Offsite Dose Calculation Manual Excess Flow Check Valve Fire Watch Power change
BSEP 08-0121, Submittal of Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors	24 September 2008	Submittal of Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors
BSEP 09-0022, Special Report - Technical Requirements Manual Section 3.4, Accident Monitoring Instrumentation	23 February 2009	Special Report - Technical Requirements Manual Section 3.4, Accident Monitoring Instrumentation
BSEP 10-0097, Report of 10 CFR 50.59 Evaluations and Commitment Changes	18 August 2010	Report of 10 CFR 50.59 Evaluations and Commitment Changes	Shutdown Margin Temporary Modification
BSEP 11-0038, Renewed Facility Operating License and Cycle 20 Core Operating Limits Report	8 April 2011	Renewed Facility Operating License and Cycle 20 Core Operating Limits Report	Safety Limit Minimum Critical Power Ratio
BSEP 12-0127, Recommendation 2.3 Seismic Walkdown of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi Accident	27 November 2012	Recommendation 2.3 Seismic Walkdown of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi Accident	Safe Shutdown Unanalyzed Condition High Radiation Area Ultimate heat sink Probabilistic Risk Assessment Operating Basis Earthquake Fukushima Dai-Ichi Design basis earthquake Scram Discharge Volume Earthquake Scaffolding Seismic Walkdown Report
BSEP 12-0128, Special Report - Technical Requirements Manual Section 3.4, Accident Monitoring Instrumentation	14 November 2012	Special Report - Technical Requirements Manual Section 3.4, Accident Monitoring Instrumentation
BSEP 13-0030, 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	28 February 2013	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	Safe Shutdown High winds Ultimate heat sink Safe Shutdown Earthquake Operating Basis Earthquake Operator Manual Action FLEX Design basis earthquake Spent Fuel Pool Instrumentation Coast down
BSEP 14-0007, 1707-01-F03, Rev. 3, Operability Assessment (CR2013-8241)	8 September 2011	1707-01-F03, Rev. 3, Operability Assessment (CR#2013-8241)	Operability Assessment
BSEP 14-0093, Report of 10 CFR 50.59 Evaluations and Commitment Changes	14 August 2014	Report of 10 CFR 50.59 Evaluations and Commitment Changes	Aging Management License Renewal Commercial Grade Control of Heavy Loads Through-Wall Leak
BSEP 14-0101, Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors	4 September 2014	Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors
BSEP 14-0131, Expedited Seismic Evaluation Process Report in Response to 10 CFR 50.54(f) Request for Information Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-lchi Accident	18 December 2014	Expedited Seismic Evaluation Process Report in Response to 10 CFR 50.54(f) Request for Information Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-lchi Accident	High Radiation Area Safe Shutdown Earthquake Probabilistic Risk Assessment FLEX Fukushima Dai-Ichi Earthquake Power-Operated Valves Power Operated Valves
BSEP 15-0004, Enclosure 3 - Areva Operability Assessment. (CR 2014-7395)	13 January 2015	Enclosure 3 - Areva Operability Assessment. (CR #2014-7395)	Safety Limit Minimum Critical Power Ratio Operability Assessment
BSEP 18-0044, Application of Dissimilar Metal Weld Full Structural Overlay - Reactor Pressure Vessel Nozzles N4A and N4D	11 April 2018	Application of Dissimilar Metal Weld Full Structural Overlay - Reactor Pressure Vessel Nozzles N4A and N4D	Weld Overlay Dissimilar Metal Weld
HNP-04-083, Day Special Report, Steam Generator Tube Plugging	27 May 2004	Day Special Report, Steam Generator Tube Plugging	Eddy Current Testing
HNP-05-059, Emergency Response Data System (ERDS) Data Point Library Changes	12 May 2005	Emergency Response Data System (ERDS) Data Point Library Changes	Reactor Vessel Water Level Met Tower
HNP-05-067, Emergency Core Cooling System Evaluation Changes	25 May 2005	Emergency Core Cooling System Evaluation Changes
HNP-06-031, Notification of NPDES Permit Renewal Application	10 February 2006	Notification of NPDES Permit Renewal Application	Boric Acid Grab sample Hydrostatic Biofouling
HNP-06-073, Day Special Report Steam Generator Tube Plugging During RFO-13	5 May 2006	Day Special Report Steam Generator Tube Plugging During RFO-13
HNP-07-068, Day Special Report of the Metal Impact Monitoring System	14 May 2007	Day Special Report of the Metal Impact Monitoring System