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	Issue date	Title	Topic
ML23345A188	6 December 2023	Fws to NRC Crystal River Species List of Threatened and Endangered Species That May Occur in Your Proposed Project Location or May Be Affected by Your Proposed Project
ML23160A296	9 June 2023	Response to Crystal River, Unit 3 Supplemental Information Needed for Acceptance on the Application for a License Amendment Regarding Approval of the License Termination Plan
ML23160A297	9 June 2023	CR3 Site Characterization Survey Report (CHAR-01) Impacted Open Land Survey Areas
3F0623-02, Maintenance Support Building	9 June 2023	Maintenance Support Building
ML23160A298	9 June 2023	Site Characterization Surveys	Tritium Exit Sign High Radiation Area Locked High Radiation Area
ML23107A273	7 June 2023	Orise Independent Survey Report Dcn 5366-SR-01-0
3F0522-01, Safety Analysis Report, Quality Assurance Program and 10 CFR 50.59 - 10 CFR 72.48 Report - May 2022	17 May 2022	Safety Analysis Report, Quality Assurance Program and 10 CFR 50.59 - 10 CFR 72.48 Report - May 2022	High Radiation Area Non-Destructive Examination Offsite Dose Calculation Manual Annual Radioactive Effluent Release Report Process Control Program Commercial Grade Fire Protection Program Grace period Overexposure
3F0520-01, Safety Analysis Report, Quality Assurance Program and 10 CFR 50.59 - 10 CFR 72.48 Report - May 2020	18 May 2020	Safety Analysis Report, Quality Assurance Program and 10 CFR 50.59 - 10 CFR 72.48 Report - May 2020	Fitness for Duty High Radiation Area Non-Destructive Examination Offsite Dose Calculation Manual Annual Radioactive Effluent Release Report Process Control Program Exemption Request Commercial Grade Fatigue Rule Fire Protection Program Overexposure
3F0320-01, NRC Commitment Change Report - March 2020	17 March 2020	NRC Commitment Change Report - March 2020	Safe Shutdown Nondestructive Examination B.5.b Control of Heavy Loads Liquid penetrant
ML19343A825	6 December 2019	Letter from Erika Bailey, Oak Ridge Institute for Science and Education, to John Hickman, NRC, Forwarding Independent Confirmatory Survey Summary and Results for the 3,854-Acre Area Partial Site Release at the Crystal River Energy Complex	Fukushima Dai-Ichi Annual Radiological Environmental Operating Report
ML19022A076	22 January 2019	Partial Site Release Request	Offsite Dose Calculation Manual Annual Radioactive Effluent Release Report Fire Protection Program
ML19029A009	7 November 2018	Reference 16 - Defueled Safety Analysis Report DSAR-R002	Safe Shutdown Boric Acid Fitness for Duty High winds High Radiation Area Non-Destructive Examination Offsite Dose Calculation Manual Fire Barrier Tornado Missile Emergency Lighting Tornado Generated Missile Annual Radioactive Effluent Release Report Process Control Program Safeguards Contingency Plan Exemption Request Earthquake Commercial Grade Fatigue Rule Fire Protection Program Flow Induced Vibration Overexposure
ML18303A294	21 June 2018	Golder Associates, Inc. - Citrus Combined Cycle Project - CFR 122.21(r) Report
3F0518-03, Safety Analysis Report and 10 CFR 50.59 - 10 CFR 72.48 Report - May 2018	24 May 2018	Safety Analysis Report and 10 CFR 50.59 - 10 CFR 72.48 Report - May 2018	Internal Flooding Temporary Modification Control of Heavy Loads
ML16176A339	28 October 2016	Decommissioning Lessons Learned Report and Transmittal Memorandum	Safe Shutdown Fitness for Duty Anticipated operational occurrence Cyber Security Aging Management Fukushima Dai-Ichi Containment Hardened Vent Exemption Request Fire Protection Program
ML19029A010	28 June 2016	Reference 3 - Crystal River, Unit 3, Historical Site Assessment Rev. 00	Time of Discovery High Radiation Area Non-Destructive Examination Offsite Dose Calculation Manual Locked High Radiation Area B.5.b Annual Radioactive Effluent Release Report Annual Radiological Environmental Operating Report Annual Radiological Effluent Release Report Scaffolding Troxler Thermal fatigue
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
ML13343A178	31 December 2013	Report P23-1680-001, Rev. 0, Site-Specific Decommissioning Cost Estimate for Crystal River Unit 3 Nuclear Generating Plant.	High Radiation Area Fuel cladding Fire Watch Scaffolding 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
3F1112-01, Alion Technical Report ALION-PLN-ENER-8706-02, Rev. 0, Crystal River 3: Bypass Fiber Quantity Test Plan	7 November 2012	Alion Technical Report ALION-PLN-ENER-8706-02, Rev. 0, Crystal River 3: Bypass Fiber Quantity Test Plan
ML12314A392	31 October 2012	17877-0001-100, Rev. 1, CR-3 Inadequate Core Cooling Mitigation System Reliability Assessment, Task 1, Page 1 of 250 Through Page 80 of 250	Mission time Post Accident Monitoring Power Uprate
ML12314A393	31 October 2012	17877-0001-100, Rev. 1, CR-3 Inadequate Core Cooling Mitigation System Reliability Assessment, Task 1, Page 81 of 250 Through Page 173 of 250
3F1112-02, 17877-0001-100, Rev. 1, CR-3 Inadequate Core Cooling Mitigation System Reliability Assessment, Task 1, Page 174 of 250 Through Page 250 of 250	31 October 2012	17877-0001-100, Rev. 1, CR-3 Inadequate Core Cooling Mitigation System Reliability Assessment, Task 1, Page 174 of 250 Through Page 250 of 250
3F0912-01, ANP-3156 Np, Crystal River 3 EPU Boric Acid Precipitation RAI Responses, Attachment C	30 September 2012	ANP-3156 Np, Crystal River 3 EPU Boric Acid Precipitation RAI Responses, Attachment C	Boric Acid Loop seal Ultimate heat sink Fuel cladding Power Uprate Manual Operator Action
3F0712-03, Attachment E to 3F0712-03, Technical Report, ANP-3052, Rev. 2, CR-3 EPU Feedwater Line Break Analysis with Failure of First Safety Grade Trip.	30 June 2012	Attachment E to 3F0712-03, Technical Report, ANP-3052, Rev. 2, CR-3 EPU Feedwater Line Break Analysis with Failure of First Safety Grade Trip.
ML12314A391	31 May 2012	17877-0002-100, CR-3 Inadequate Core Cooling Mitigation System Reliability Assessment 2	Post Accident Monitoring Power Uprate
ML12205A358	31 May 2012	Attachment D to 3F0712-03, Technical Report, ANP-3114(NP), Rev. 0, CR-3 EPU - Feedwater Line Break Analysis Sensitivity Studies.	Shutdown Margin Power Uprate
ML12284A138	25 May 2012	Report EGS-TR-HC589-01, Seismic Qualification Test Report for Structural Verification Testing of Iccms Cabinet Assembly.
3F0512-01, NRC Commitment Change Report - May 2012	14 May 2012	NRC Commitment Change Report - May 2012	Stress corrosion cracking
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
ML12205A357	15 December 2011	Attachment a to 3F0712-03, CR-3 LOCA Summary Report - EPU/ROTSG/Mark-B-HTP, Revision 4	Boric Acid Loop seal Stroke time Safe Shutdown Earthquake Earthquake Fuel cladding Coast down Power Uprate Manual Operator Action
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
3F1011-08, ANP-3052, Rev. 0, CR-3 EPU Feedwater Line Break Analysis with Failure of First Safety Grade Trip	25 October 2011	ANP-3052, Rev. 0, CR-3 EPU Feedwater Line Break Analysis with Failure of First Safety Grade Trip	Stroke time Power Uprate
ML11237A068	5 August 2011	Siemens Technical Report CT-27438, Missile Probability Analysis Report Progress Energy Crystal River 3, Revision 1A	Finite Element Analysis Stress corrosion cracking Turbine Missile Affidavit Overspeed trip
ML11207A444	15 June 2011	Attachment 7- Crystal River Unit 3 Extended Power Uprate Technical Report	Power Uprate
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
ML110190667	4 October 2010	Levy, Units 1 and 2, Cola (Sensitive Material), Rev. 2 - Levy County Emergency Plan Part 02 - Draft (Redacted)
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
ML101930417	6 May 2010	Tritium Database Report	Offsite Dose Calculation Manual Hydrostatic
ML101060347	9 April 2010	5.2.2.4.4. Quality Control and Nondestructive Testing	Design basis earthquake Liquid penetrant Operational leakage
ML102871088	12 March 2010	7.6 Vibration Due to Cutting Tendons	Fire Barrier Finite Element Analysis Fire Watch
ML102871111	25 February 2010	7.11 Added Stress from Pulling Tendons	Offsite Dose Calculation Manual Fire Barrier Coatings Fire Protection Program Fire Watch
ML102871110	23 February 2010	6.3 Thermal Effects of Greasing
ML102871121	19 February 2010	7.10 Hydrodemolition Induced Cracking	Hydrostatic Coatings Thermography
ML102871113	19 February 2010	7.9 Inadequate Hydro Blasting Nozzles Rate Part 2	Finite Element Analysis
ML102871112	19 February 2010	7.9 Inadequate Hydro Blasting Nozzles Rate Part 1	Hydrostatic Coatings Thermography
ML102880468	19 February 2010	7.9 Inadequate Hydro Blasting Nozzles Rate Part 3
ML102880458	18 February 2010	7.8 Excessive Water Jet Pressure Part 3
ML102871146	18 February 2010	7.8 Excessive Water Jet Pressure Part 2	Finite Element Analysis
ML102871145	18 February 2010	7.8 Excessive Water Jet Pressure Part 1	Hydrostatic Coatings Thermography

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