RA-23-0313, Baffle-Former Bolt (Bfb) Subsequent Inspection Interval Evaluation | 14 December 2023 | Baffle-Former Bolt (Bfb) Subsequent Inspection Interval Evaluation | Finite Element Analysis Aging Management Stress corrosion cracking Affidavit |
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 | |
RA-23-0141, Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule | 12 July 2023 | Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule | License Renewal Subsequent License Renewal |
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 | |
ML23160A298 | 9 June 2023 | Site Characterization Surveys | Tritium Exit Sign High Radiation Area Locked High Radiation Area |
3F0623-02, Maintenance Support Building | 9 June 2023 | Maintenance Support Building | |
ML23107A273 | 7 June 2023 | Orise Independent Survey Report Dcn 5366-SR-01-0 | |
RA-23-0120, Supplemental Information Regarding Addition of Feedwater Isolation on Steam Generator Level High-High to Technical Specification 3.3.2 | 31 May 2023 | Supplemental Information Regarding Addition of Feedwater Isolation on Steam Generator Level High-High to Technical Specification 3.3.2 | |
RA-23-0080, Refueling Outage 32 Steam Generator Tube Inspection Report Supplement Pursuant to Technical Specifications Task Force (TSTF) Traveler TSTF-577, Revision 1, Revised Frequencies for Steam Generator Tube | 5 April 2023 | Refueling Outage 32 Steam Generator Tube Inspection Report Supplement Pursuant to Technical Specifications Task Force (TSTF) Traveler TSTF-577, Revision 1, Revised Frequencies for Steam Generator Tube | Nondestructive Examination |
RA-22-0302, Technical Specifications (TS) Section 5.6.6, Post Accident Monitoring Instrumentation Report for Inoperable Containment Sump Water Level (Wide Range) | 1 November 2022 | Technical Specifications (TS) Section 5.6.6, Post Accident Monitoring Instrumentation Report for Inoperable Containment Sump Water Level (Wide Range) | Post Accident Monitoring |
RA-22-0239, Technical Specifications Section 5.6.6. Post Accident Monitoring Instrumentation Report for Inoperable Safety Valve Position (Primary) | 9 August 2022 | Technical Specifications Section 5.6.6. Post Accident Monitoring Instrumentation Report for Inoperable Safety Valve Position (Primary) | Post Accident Monitoring |
RA-22-0165, Inservice Inspection Program Owner'S Activity Report for Refueling Outage 24 | 9 June 2022 | Inservice Inspection Program Owner'S Activity Report for Refueling Outage 24 | |
RA-22-0134, Unit 1 Cycle 23 Mellla+ Eigenvalue Tracking Data | 25 May 2022 | Unit 1 Cycle 23 Mellla+ Eigenvalue Tracking Data | |
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 |
RA-22-0017, Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections | 6 January 2022 | Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections | Stress corrosion cracking Eddy Current Testing |
RA-21-0312, Technical Specifications Section 5.6.6 Post Accident Monitoring Instrumentation Report for Inoperable Containment Sump Water Level (Wide Range) | 22 November 2021 | Technical Specifications Section 5.6.6 Post Accident Monitoring Instrumentation Report for Inoperable Containment Sump Water Level (Wide Range) | Post Accident Monitoring |
IR 05000261/2021005 | 25 August 2021 | Updated Inspection Plan for H. B. Robinson Steam Electric Plant, Unit 2 (Report 05000261/2021005) | Fitness for Duty Cyber Security Exemption Request COVID-19 |
RA-21-0198, Inservice Inspection Program Owner'S Activity Report for Refueling Outage 25 | 21 June 2021 | Inservice Inspection Program Owner'S Activity Report for Refueling Outage 25 | |
RA-21-0176, Cycle 24 Mellla+ Eigenvalue Tracking Data | 7 June 2021 | Cycle 24 Mellla+ Eigenvalue Tracking Data | |
RA-21-0097, Notification of Permit Revision Request Regarding Copper and Zinc Limits | 15 March 2021 | Notification of Permit Revision Request Regarding Copper and Zinc Limits | |
RA-20-0353, Proposed Alternative to ASME Boiler & Pressure Vessel Code Section XI Requirements for Repair/Replacement of Service Water (SW) System Buried Piping in Accordance with 10 CFR 50.55a(z)(1) | 24 February 2021 | Proposed Alternative to ASME Boiler & Pressure Vessel Code Section XI Requirements for Repair/Replacement of Service Water (SW) System Buried Piping in Accordance with 10 CFR 50.55a(z)(1) | Fitness for Duty Ultimate heat sink Non-Destructive Examination Safe Shutdown Earthquake Coatings Operating Basis Earthquake Finite Element Analysis Foreign Material Exclusion Exemption Request Affidavit |
RA-20-0381, CFR 50.54( Q) Screening Evaluation Form for Revisions | 8 December 2020 | CFR 50.54( Q) Screening Evaluation Form for Revisions | Spent Fuel Pool Instrumentation Exemption Request Earthquake Grace period |
RA-20-0335, Response to Request for Additional Information Regarding License Amendment Request to Reduce the Minimum Required Reactor Coolant System Flow Rate and Update the List of Analytical Methods Used in . | 24 November 2020 | Response to Request for Additional Information Regarding License Amendment Request to Reduce the Minimum Required Reactor Coolant System Flow Rate and Update the List of Analytical Methods Used in . | Time Critical Operator Action Exemption Request Fuel cladding Exclusive Use Affidavit |
RA-20-0347, 10 CFR 71.95 Report on the 3-60B Cask | 16 November 2020 | 10 CFR 71.95 Report on the 3-60B Cask | |
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 |
RA-20-0032, License Amendment Request to Reduce the Minimum Required Reactor Coolant System Flow Rate and Update the List of Analytical Methods Used in the Determination of Core Operating Limits | 6 March 2020 | License Amendment Request to Reduce the Minimum Required Reactor Coolant System Flow Rate and Update the List of Analytical Methods Used in the Determination of Core Operating Limits | Boric Acid Shutdown Margin Loop seal Anticipated operational occurrence Hydrostatic Nondestructive Examination Surveillance Frequency Control Program Fuel cladding Exclusive Use Affidavit Loss of condenser vacuum |
RA-19-0479, Supplement to Request for License Amendment Regarding Application of Advanced Framatome Methodologies | 31 December 2019 | Supplement to Request for License Amendment Regarding Application of Advanced Framatome Methodologies | Anticipated operational occurrence Affidavit |
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 |
RA-19-0411, Supplement to Request for License Amendment Regarding Application of Advanced Framatome Methodologies | 23 October 2019 | Supplement to Request for License Amendment Regarding Application of Advanced Framatome Methodologies | Shutdown Margin Safety Limit Minimum Critical Power Ratio Anticipated operational occurrence Feedwater Controller Failure MELLLA Exclusive Use Affidavit Water rod |
RA-19-0403, Submittal of the Summary Technical Report for the Reactor Pressure Vessel Surveillance Program Capsule Z | 23 October 2019 | Submittal of the Summary Technical Report for the Reactor Pressure Vessel Surveillance Program Capsule Z | Anticipated operational occurrence Hydrostatic |
RA-19-0338, Pressure and Temperature Limits Report for Unit Nos. 1 and 2 | 15 August 2019 | Pressure and Temperature Limits Report for Unit Nos. 1 and 2 | Hydrostatic Pressure and Temperature Limits Report License Renewal Power Uprate |
RA-19-0243, Supplement to Request for License Amendment Regarding Application of Advanced Framatome Methodologies | 2 July 2019 | Supplement to Request for License Amendment Regarding Application of Advanced Framatome Methodologies | Stroke time Post Accident Monitoring Fuel cladding Affidavit |
RA-19-0223, Annual Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models Pursuant to 10CFR 50.46 | 30 May 2019 | Annual Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models Pursuant to 10CFR 50.46 | |
RA-19-0240, Response to Request for Additional Information Regarding Advanced Framatome Methodologies License Amendment Request | 29 May 2019 | Response to Request for Additional Information Regarding Advanced Framatome Methodologies License Amendment Request | Feedwater Controller Failure MELLLA Fuel cladding Power Uprate Affidavit |
RA-19-0139, Supplement to Request for License Amendment Regarding Application of Advanced Framatome Methodologies | 18 March 2019 | Supplement to Request for License Amendment Regarding Application of Advanced Framatome Methodologies | Shutdown Margin Affidavit Water rod |
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 |
RA-18-0100, Request for License Amendment Regarding Application of Advanced Framatome Methodologies | 11 October 2018 | Request for License Amendment Regarding Application of Advanced Framatome Methodologies | Anticipated operational occurrence Power Uprate Affidavit |
RA-18-0179, 90-Day Special Report | 4 October 2018 | 90-Day Special Report | Overspeed trip |
ML18230A756 | 18 August 2018 | Fault Investigation, Responses to Mr. W. R. Butler'S Letter of May 16, 1975 | Hydrostatic Earthquake |
ML18230A759 | 18 August 2018 | Fault Investigation, Progress Report, Volume 1 of 2 | Coatings Earthquake |
RA-18-0131, Technical Requirements Manual, Revision 66 | 13 August 2018 | Technical Requirements Manual, Revision 66 | Time of Discovery Reactor Vessel Water Level Ultimate heat sink Non-Destructive Examination Offsite Dose Calculation Manual Safe Shutdown Earthquake Post Accident Monitoring Hydrostatic Operating Basis Earthquake Functionality Assessment Scram Discharge Volume Process Control Program Stress corrosion cracking Excess Flow Check Valve Operability Determination Earthquake Pressure Boundary Leakage Offsite Circuit Operational leakage |
ML18249A159 | 13 August 2018 | Technical Requirements Manual, Revision 73 | Time of Discovery Reactor Vessel Water Level Ultimate heat sink Offsite Dose Calculation Manual Safe Shutdown Earthquake Post Accident Monitoring Hydrostatic Operating Basis Earthquake Functionality Assessment Scram Discharge Volume Process Control Program Stress corrosion cracking Excess Flow Check Valve Operability Determination Earthquake Pressure Boundary Leakage Offsite Circuit Operational leakage |
ML18303A294 | 21 June 2018 | Golder Associates, Inc. - Citrus Combined Cycle Project - CFR 122.21(r) Report | |
RA-18-0024, Supplemental Information to Request for License Amendment to Revise the Technical Specifications to Relocate the Pressure-Temperature Limit Curves to a Pressure and Temperature Limits Report | 29 May 2018 | Supplemental Information to Request for License Amendment to Revise the Technical Specifications to Relocate the Pressure-Temperature Limit Curves to a Pressure and Temperature Limits Report | Pressure and Temperature Limits 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 |
HNP-18-023, Report of Changes Pursuant to 10 CFR 50.59 and Summary of Commitment Changes | 2 May 2018 | Report of Changes Pursuant to 10 CFR 50.59 and Summary of Commitment Changes | Fuel cladding Overspeed trip |
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 |