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 Issue dateTitleTopic
RA-23-0313, Baffle-Former Bolt (Bfb) Subsequent Inspection Interval Evaluation14 December 2023Baffle-Former Bolt (Bfb) Subsequent Inspection Interval EvaluationFinite Element Analysis
Aging Management
Stress corrosion cracking
Affidavit
ML23345A1886 December 2023Fws 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 Schedule12 July 2023Revision to Reactor Vessel Surveillance Capsule Withdrawal ScheduleLicense Renewal
Subsequent License Renewal
ML23160A2969 June 2023Response to Crystal River, Unit 3 Supplemental Information Needed for Acceptance on the Application for a License Amendment Regarding Approval of the License Termination Plan
ML23160A2979 June 2023CR3 Site Characterization Survey Report (CHAR-01) Impacted Open Land Survey Areas
ML23160A2989 June 2023Site Characterization SurveysTritium Exit Sign
High Radiation Area
Locked High Radiation Area
3F0623-02, Maintenance Support Building9 June 2023Maintenance Support Building
ML23107A2737 June 2023Orise 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 3.3.231 May 2023Supplemental 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 Tube5 April 2023Refueling 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 TubeNondestructive 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 2022Technical 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 2022Technical 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 249 June 2022Inservice Inspection Program Owner'S Activity Report for Refueling Outage 24
RA-22-0134, Unit 1 Cycle 23 Mellla+ Eigenvalue Tracking Data25 May 2022Unit 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 202217 May 2022Safety Analysis Report, Quality Assurance Program and 10 CFR 50.59 - 10 CFR 72.48 Report - May 2022High 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 Inspections6 January 2022Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube InspectionsStress 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 2021Technical Specifications Section 5.6.6 Post Accident Monitoring Instrumentation Report for Inoperable Containment Sump Water Level (Wide Range)Post Accident Monitoring
IR 05000261/202100525 August 2021Updated 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 2521 June 2021Inservice Inspection Program Owner'S Activity Report for Refueling Outage 25
RA-21-0176, Cycle 24 Mellla+ Eigenvalue Tracking Data7 June 2021Cycle 24 Mellla+ Eigenvalue Tracking Data
RA-21-0097, Notification of Permit Revision Request Regarding Copper and Zinc Limits15 March 2021Notification 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 2021Proposed 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 Revisions8 December 2020CFR 50.54( Q) Screening Evaluation Form for RevisionsSpent 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 2020Response 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 Cask16 November 202010 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 202018 May 2020Safety Analysis Report, Quality Assurance Program and 10 CFR 50.59 - 10 CFR 72.48 Report - May 2020Fitness 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 202017 March 2020NRC Commitment Change Report - March 2020Safe 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 Limits6 March 2020License 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 LimitsBoric 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 Methodologies31 December 2019Supplement to Request for License Amendment Regarding Application of Advanced Framatome MethodologiesAnticipated operational occurrence
Affidavit
ML19343A8256 December 2019Letter 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 ComplexFukushima Dai-Ichi
Annual Radiological Environmental Operating Report
RA-19-0411, Supplement to Request for License Amendment Regarding Application of Advanced Framatome Methodologies23 October 2019Supplement to Request for License Amendment Regarding Application of Advanced Framatome MethodologiesShutdown 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 Z23 October 2019Submittal of the Summary Technical Report for the Reactor Pressure Vessel Surveillance Program Capsule ZAnticipated operational occurrence
Hydrostatic
RA-19-0338, Pressure and Temperature Limits Report for Unit Nos. 1 and 215 August 2019Pressure and Temperature Limits Report for Unit Nos. 1 and 2Hydrostatic
Pressure and Temperature Limits Report
License Renewal
Power Uprate
RA-19-0243, Supplement to Request for License Amendment Regarding Application of Advanced Framatome Methodologies2 July 2019Supplement to Request for License Amendment Regarding Application of Advanced Framatome MethodologiesStroke 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 50.4630 May 2019Annual 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 Request29 May 2019Response to Request for Additional Information Regarding Advanced Framatome Methodologies License Amendment RequestFeedwater Controller Failure
MELLLA
Fuel cladding
Power Uprate
Affidavit
RA-19-0139, Supplement to Request for License Amendment Regarding Application of Advanced Framatome Methodologies18 March 2019Supplement to Request for License Amendment Regarding Application of Advanced Framatome MethodologiesShutdown Margin
Affidavit
Water rod
ML19022A07622 January 2019Partial Site Release RequestOffsite Dose Calculation Manual
Annual Radioactive Effluent Release Report
Fire Protection Program
ML19029A0097 November 2018Reference 16 - Defueled Safety Analysis Report DSAR-R002Safe 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 Methodologies11 October 2018Request for License Amendment Regarding Application of Advanced Framatome MethodologiesAnticipated operational occurrence
Power Uprate
Affidavit
RA-18-0179, 90-Day Special Report4 October 201890-Day Special ReportOverspeed trip
ML18230A75618 August 2018Fault Investigation, Responses to Mr. W. R. Butler'S Letter of May 16, 1975Hydrostatic
Earthquake
ML18230A75918 August 2018Fault Investigation, Progress Report, Volume 1 of 2Coatings
Earthquake
RA-18-0131, Technical Requirements Manual, Revision 6613 August 2018Technical Requirements Manual, Revision 66Time 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
ML18249A15913 August 2018Technical Requirements Manual, Revision 73Time 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
ML18303A29421 June 2018Golder 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 Report29 May 2018Supplemental Information to Request for License Amendment to Revise the Technical Specifications to Relocate the Pressure-Temperature Limit Curves to a Pressure and Temperature Limits ReportPressure and Temperature Limits Report
3F0518-03, Safety Analysis Report and 10 CFR 50.59 - 10 CFR 72.48 Report - May 201824 May 2018Safety Analysis Report and 10 CFR 50.59 - 10 CFR 72.48 Report - May 2018Internal Flooding
Temporary Modification
Control of Heavy Loads
HNP-18-023, Report of Changes Pursuant to 10 CFR 50.59 and Summary of Commitment Changes2 May 2018Report of Changes Pursuant to 10 CFR 50.59 and Summary of Commitment ChangesFuel cladding
Overspeed trip
BSEP 18-0044, Application of Dissimilar Metal Weld Full Structural Overlay - Reactor Pressure Vessel Nozzles N4A and N4D11 April 2018Application of Dissimilar Metal Weld Full Structural Overlay - Reactor Pressure Vessel Nozzles N4A and N4DWeld Overlay
Dissimilar Metal Weld