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3F0385-18, Forwards Addl Request for Relief from ASME Section XI Inservice Insp Requirements for Emergency Feedwater Piping Between Steam Generators & First Valves Upstream That Provide Isolation.Response Requested by 850601Crystal River22 March 1985Forwards Addl Request for Relief from ASME Section XI Inservice Insp Requirements for Emergency Feedwater Piping Between Steam Generators & First Valves Upstream That Provide Isolation.Response Requested by 850601
3F0387-02, Forwards Info Re Generic Issue 124,auxiliary Feedwater Sys Reliability,Per NRC 870218 request.W/75 Oversize DrawingsCrystal River5 March 1987Forwards Info Re Generic Issue 124,auxiliary Feedwater Sys Reliability,Per NRC 870218 request.W/75 Oversize Drawings
3F0389-07, Responds to Violations Noted in Insp Rept 50-302/89-01. Corrective Actions:Required Actions of AP-450, Emergency Feedwater Actuation PerformedCrystal River14 March 1989Responds to Violations Noted in Insp Rept 50-302/89-01. Corrective Actions:Required Actions of AP-450, Emergency Feedwater Actuation Performed
3F0391-15, Provides NRC W/Updated Design Info About Auxiliary Feedwater Pump Addition at Crystal River Unit 3 & Providing Revs toCrystal River22 March 1991Provides NRC W/Updated Design Info About Auxiliary Feedwater Pump Addition at Crystal River Unit 3 & Providing Revs to
3F0403-04, TS Bases Control ProgramCrystal River10 April 2003TS Bases Control Program
3F0404-11, Modified Proposed License Condition, License Amendment Request 280, Revision 1, Revised Improved Technical Specification (ITS) 3.7.9, Nuclear Services Seawater SystemCrystal River27 April 2004Modified Proposed License Condition, License Amendment Request #280, Revision 1, Revised Improved Technical Specification (ITS) 3.7.9, Nuclear Services Seawater System
3F0407-10, License Amendment Request 296, Revision 0, Measurement Uncertainty Recapture UprateCrystal River25 April 2007License Amendment Request #296, Revision 0, Measurement Uncertainty Recapture Uprate
3F0407-12, License Amendment Request 295, Revision 0, Extension of Allowed Outage Time to Seven Days and Elimination of Second Completion Times Limiting TimeCrystal River13 April 2007License Amendment Request #295, Revision 0, Extension of Allowed Outage Time to Seven Days and Elimination of Second Completion Times Limiting Time
3F0412-06, Response to Request for Additional Information to Support NRC Electrical Systems Branch (Eeeb) Technical Review of the CR-3 Extended Power Uprate LARCrystal River16 April 2012Response to Request for Additional Information to Support NRC Electrical Systems Branch (Eeeb) Technical Review of the CR-3 Extended Power Uprate LAR
3F0486-15, Advises That Since Installation of Emergency Feedwater Initiation & Control Sys,Per NUREG-0737,Item II.E.1.2, Several Actuations Occurred.Temporary Fix of Installing Time Delay Relay Mfg by Logitek,Inc UnderwayCrystal River30 April 1986Advises That Since Installation of Emergency Feedwater Initiation & Control Sys,Per NUREG-0737,Item II.E.1.2, Several Actuations Occurred.Temporary Fix of Installing Time Delay Relay Mfg by Logitek,Inc Underway
3F0505-07, Supplemental Information & Additional Commitment Regarding License Amendment Request No. 289, Revision 0, Revised Improved Technical Specifications 3.5.2, Emergency Core Cooling System - Operating, 3.6.6, Reactor Building Spray.Crystal River6 May 2005Supplemental Information & Additional Commitment Regarding License Amendment Request No. 289, Revision 0, Revised Improved Technical Specifications 3.5.2, Emergency Core Cooling System - Operating, 3.6.6, Reactor Building Spray.
3F0507-06, Ninety-Day Response to GL 2007-01, Inaccessible or Underground Power Cable Failures That Disable Accident Mitigation Systems or Cause Plant Transients.Crystal River3 May 2007Ninety-Day Response to GL 2007-01, Inaccessible or Underground Power Cable Failures That Disable Accident Mitigation Systems or Cause Plant Transients.
3F0515-05, Technical Specifications Bases Control ProgramCrystal River27 May 2015Technical Specifications Bases Control Program
3F0516-05, Final Safety Analysis Report Revision 38 & May 2016 10 CFR 50.59 and 10 CFR 72.48 ReportCrystal River25 May 2016Final Safety Analysis Report Revision 38 & May 2016 10 CFR 50.59 and 10 CFR 72.48 Report
3F0587-02, Submits Addl Info Re NUREG-0737,Item II.E.1.1, Emergency Feedwater Sys Review, Per NRC 870331-0402 Meeting RequestCrystal River6 May 1987Submits Addl Info Re NUREG-0737,Item II.E.1.1, Emergency Feedwater Sys Review, Per NRC 870331-0402 Meeting Request
3F0589-20, Forwards Addl Info Re Bases for Exemption Request for Schedular Relief from Requirements of GDC 4 Re High Energy Line Break.Design Work on 10 Break Locations,Including Jet Shield & Pipe Whip Restraints,InitiatedCrystal River24 May 1989Forwards Addl Info Re Bases for Exemption Request for Schedular Relief from Requirements of GDC 4 Re High Energy Line Break.Design Work on 10 Break Locations,Including Jet Shield & Pipe Whip Restraints,Initiated
3F0598-01, Application for Amend to License DPR-72,proposing Changes to FSAR to Include Description of Use of GL 87-11, Relaxation in Arbitrary Intermediate Pipe Rupture Requirements & NUREG/CR-2913,as Part of Licensing & Design BasisCrystal River28 May 1998Application for Amend to License DPR-72,proposing Changes to FSAR to Include Description of Use of GL 87-11, Relaxation in Arbitrary Intermediate Pipe Rupture Requirements & NUREG/CR-2913,as Part of Licensing & Design Basis
3F0607-05, License Amendment Request 296, Revision 1, Measurement Uncertainty Recapture UprateCrystal River28 June 2007License Amendment Request #296, Revision 1, Measurement Uncertainty Recapture Uprate
3F0611-02, Attachments 1, 2 & 3, 4 & 6 Crystal River Unit 3, License Amendment Request 309, Revision 0 Attachment 1, Description of Proposed Change, Background, Justification for the Request, Determination of No Significant Hazards ConsiderationsCrystal River15 June 2011Attachments 1, 2 & 3, 4 & 6 Crystal River Unit 3, License Amendment Request #309, Revision 0 Attachment 1, Description of Proposed Change, Background, Justification for the Request, Determination of No Significant Hazards Considerations
3F0684-10, Clarifies 831118 Commitment to Install Redundant safety- Grade Level Indications on Emergency Feedwater Tank by Refuel VI Instead of Condensate Storage Tank by Refuel V. Emergency Feedwater Valves 3 & 4 Will Not Be InstalledCrystal River26 June 1984Clarifies 831118 Commitment to Install Redundant safety- Grade Level Indications on Emergency Feedwater Tank by Refuel VI Instead of Condensate Storage Tank by Refuel V. Emergency Feedwater Valves 3 & 4 Will Not Be Installed
3F0698-17, Submits Results of Evaluation to NRC Re GL 87-02, Verification of Seismic Adequacy of Mechanical of Condenser & Electrical Equipment in Operating Reactors (USI A-46) for Evaluation of Condenser Hotwell Suction Isolation ValveCrystal River1 June 1998Submits Results of Evaluation to NRC Re GL 87-02, Verification of Seismic Adequacy of Mechanical of Condenser & Electrical Equipment in Operating Reactors (USI A-46) for Evaluation of Condenser Hotwell Suction Isolation Valve
3F0703-04, License Amendment Request 280, Rev. 0 Revised Improved Technical Specification (ITS) 3.7.9, Nuclear Services Seawater SystemCrystal River14 July 2003License Amendment Request 280, Rev. 0 Revised Improved Technical Specification (ITS) 3.7.9, Nuclear Services Seawater System
3F0785-31, Forwards Fire Protection Evaluations Re Fire Barrier Deviations,Emergency Lights & Protection Against Spurious Actuation of Automatic Fire Suppression Sys,For Review & ConcurrenceCrystal River25 July 1985Forwards Fire Protection Evaluations Re Fire Barrier Deviations,Emergency Lights & Protection Against Spurious Actuation of Automatic Fire Suppression Sys,For Review & Concurrence
3F0788-04, Submits Course of Action Util Commits to After Review of Situation Re Leakage of Emergency Feedwater Valve-18.Util Will Continue to Keep Penetration 109 & Associated Piping within Design Temp LimitsCrystal River5 July 1988Submits Course of Action Util Commits to After Review of Situation Re Leakage of Emergency Feedwater Valve-18.Util Will Continue to Keep Penetration 109 & Associated Piping within Design Temp Limits
3F0788-12, Forwards Suppl to Util Re Emergency Feedwater Leaks & Summary of Presentation During 880708 Meeting in Rockville,Md,Per 880706 Confirmation of Action Ltr. Corrective Actions Associated W/Stated Insp ReptCrystal River14 July 1988Forwards Suppl to Util Re Emergency Feedwater Leaks & Summary of Presentation During 880708 Meeting in Rockville,Md,Per 880706 Confirmation of Action Ltr. Corrective Actions Associated W/Stated Insp Rept
3F0789-20, Responds to NRC Re Violations Noted in Insp Rept 50-302/89-09.Corrective Actions:Licensee Will Continue to Conduct High Energy Line Break Program to Resolve Deficiency & Long Term Equipment Qualification Program DevelopedCrystal River20 July 1989Responds to NRC Re Violations Noted in Insp Rept 50-302/89-09.Corrective Actions:Licensee Will Continue to Conduct High Energy Line Break Program to Resolve Deficiency & Long Term Equipment Qualification Program Developed
3F0794-07, Requests Discretionary Enforcement Re Replacement of Rotating Element for Motor Driven EFP-1Crystal River7 July 1994Requests Discretionary Enforcement Re Replacement of Rotating Element for Motor Driven EFP-1
3F0797-38, Forwards Evaluation of Potentially Unreviewed Safety Questions in CR-3 FSAR Rev 23 & List of Regulatory Commitments Re Ltrs & 1018.Issues Re Ltrs, DiscussedCrystal River3 July 1997Forwards Evaluation of Potentially Unreviewed Safety Questions in CR-3 FSAR Rev 23 & List of Regulatory Commitments Re Ltrs & 1018.Issues Re Ltrs, Discussed
3F0798-07, Forwards Rev 25,vols 1-4,to Crystal River Unit 3 FSAR, Incorporating Exception to 10CFR50.4(b)(6) as Stated in .W/Summary of Changes & Summary of SEs Performed During Submittal PeriodCrystal River28 July 1998Forwards Rev 25,vols 1-4,to Crystal River Unit 3 FSAR, Incorporating Exception to 10CFR50.4(b)(6) as Stated in .W/Summary of Changes & Summary of SEs Performed During Submittal Period
3F0811-02, Response to Request for Additional Information to Support NRC Balance of Plant Branch Acceptance Review of the CR-3 Extended Power Uprate LARCrystal River11 August 2011Response to Request for Additional Information to Support NRC Balance of Plant Branch Acceptance Review of the CR-3 Extended Power Uprate LAR
3F0811-08, Submittal of Snubber Inspection and Testing Program Manual, Revision 7Crystal River15 August 2011Submittal of Snubber Inspection and Testing Program Manual, Revision 7
3F0812-06, Response to Second Request for Additional Information to Support NRC Mechanical and Civil Engineering Branch (Emcb) Technical Review of the CR-3 Extended Power Uprate LARCrystal River30 August 2012Response to Second Request for Additional Information to Support NRC Mechanical and Civil Engineering Branch (Emcb) Technical Review of the CR-3 Extended Power Uprate LAR
3F0817-03, Rev. 0, Defueled Safety Analysis ReportCrystal River31 August 2017Rev. 0, Defueled Safety Analysis Report
3F0884-16, Revises Schedule for Installing Portion of RCS Water Level Instrumentation,Per NUREG-0737,Item II.F.2, Instrumentation for Detection of Inadequate Core Cooling, to Refuel VICrystal River31 August 1984Revises Schedule for Installing Portion of RCS Water Level Instrumentation,Per NUREG-0737,Item II.F.2, Instrumentation for Detection of Inadequate Core Cooling, to Refuel VI
3F0886-08, Responds to SALP Rept 50-302/86-13.Quality Audit Program Considered Essential Element of Nuclear Program.Recognition of Strong Maint Program Appreciated.Actions Taken to Resolve Security Deficiencies NotedCrystal River11 August 1986Responds to SALP Rept 50-302/86-13.Quality Audit Program Considered Essential Element of Nuclear Program.Recognition of Strong Maint Program Appreciated.Actions Taken to Resolve Security Deficiencies Noted
3F0889-04, Forwards Response to NRC 890721 Request for Addl Info Re Plant Emergency Diesel Generator Upgrade Program.Util Anticipates Finalizing Resolution of NRC Concerns at MeetingCrystal River11 August 1989Forwards Response to NRC 890721 Request for Addl Info Re Plant Emergency Diesel Generator Upgrade Program.Util Anticipates Finalizing Resolution of NRC Concerns at Meeting
3F0894-02, Provides Response to NRC Request for Addl Info Re Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors,Unresolved Safety Issue,Per GL 87-02Crystal River15 August 1994Provides Response to NRC Request for Addl Info Re Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors,Unresolved Safety Issue,Per GL 87-02
3F0897-12, Responds to NRC Re Violations Noted in Insp Rept 50-302/97-07.Corrective actions:CP-111 Will Be Clarified to Include That Extensions Are Appropriate When Emergent Higher Priority Requirements Do Not Permit Completion of AnalysisCrystal River5 August 1997Responds to NRC Re Violations Noted in Insp Rept 50-302/97-07.Corrective actions:CP-111 Will Be Clarified to Include That Extensions Are Appropriate When Emergent Higher Priority Requirements Do Not Permit Completion of Analysis
3F0897-19, Revised Response to Violations Noted in Insp Rept 50-302/96-15.Corrective Actions:Reviewed Event W/Personnel Responsible for Preparation & Review of Rev to SP-349A & SP-338 and Revised Procedure A1-400C Re Procedure ReviewsCrystal River13 August 1997Revised Response to Violations Noted in Insp Rept 50-302/96-15.Corrective Actions:Reviewed Event W/Personnel Responsible for Preparation & Review of Rev to SP-349A & SP-338 and Revised Procedure A1-400C Re Procedure Reviews
3F0897-23, Provides Supplemental Info on Three Valves in Crystal River Unit 3 Efs Subject to Pressure Locking as Described in GL 95-07, Pressure Locking & Thermial Binding of SR Power-Operated Gate ValvesCrystal River11 August 1997Provides Supplemental Info on Three Valves in Crystal River Unit 3 Efs Subject to Pressure Locking as Described in GL 95-07, Pressure Locking & Thermial Binding of SR Power-Operated Gate Valves
3F0903-03, NRC Inspection Report 50-302/02-05, Triennial Fire Protection Inspection, August 23, 2002Crystal River5 September 2003NRC Inspection Report 50-302/02-05, Triennial Fire Protection Inspection, August 23, 2002
3F0904-05, Supplemental Information and Regulatory Commitments for License Amendment Request 281, Revision 0, Revised Improved Technical Specification (ITS) 3.7.5, Emergency Feedwater SystemCrystal River16 September 2004Supplemental Information and Regulatory Commitments for License Amendment Request #281, Revision 0, Revised Improved Technical Specification (ITS) 3.7.5, Emergency Feedwater System
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 InformationCrystal River4 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
3F0984-03, Defines Action Underway & Schedule for Continuing Analysis Re Reliability of Steam Admission Valve ASV-5 to Turbine Driven Emergency Feedwater Pump,Per NUREG-0737,Item II.E.1.1Crystal River21 September 1984Defines Action Underway & Schedule for Continuing Analysis Re Reliability of Steam Admission Valve ASV-5 to Turbine Driven Emergency Feedwater Pump,Per NUREG-0737,Item II.E.1.1
3F0984-04, Clarifies Statement on Page 1-8,Item D of Safety Evaluation of Emergency Feedwater Sys Upgrade,Per NUREG-0737,Item II.E.1.1.Air Operated Valves Not in Use.Motor Operated Valves Will Be Determinated in Locked Open PositionCrystal River20 September 1984Clarifies Statement on Page 1-8,Item D of Safety Evaluation of Emergency Feedwater Sys Upgrade,Per NUREG-0737,Item II.E.1.1.Air Operated Valves Not in Use.Motor Operated Valves Will Be Determinated in Locked Open Position
3F0984-06, Forwards Exemption Request from Requirements of 10CFR50.48, App R.General Info Re Definitions,Interpretation of Certain App R Requirements & Evaluation of Existing Decay Heat Pump Fire Protection Capabilities EnclCrystal River24 September 1984Forwards Exemption Request from Requirements of 10CFR50.48, App R.General Info Re Definitions,Interpretation of Certain App R Requirements & Evaluation of Existing Decay Heat Pump Fire Protection Capabilities Encl
3F0987-02, Forwards Info Re Operation of Target Rock Electrically Positioned Control Valves in Emergency Feedwater Sys,Per 870901 RequestCrystal River4 September 1987Forwards Info Re Operation of Target Rock Electrically Positioned Control Valves in Emergency Feedwater Sys,Per 870901 Request
3F0988-16, Forwards Results of Risk Assessment Associated W/High Energy Line Break Review Reported on 880907.Util Will Seek NRC Approval to Include Relief Granted in Generic Ltr 87-11 Re Elimination of Arbitrary Intermediate Pipe BreaksCrystal River27 September 1988Forwards Results of Risk Assessment Associated W/High Energy Line Break Review Reported on 880907.Util Will Seek NRC Approval to Include Relief Granted in Generic Ltr 87-11 Re Elimination of Arbitrary Intermediate Pipe Breaks
3F0988-18, Requests Establishment of mini-purge of Reactor Bldg to Reduce Worker Exposure to Radiation & Radioactive Matl & to Assure That Every Measure Taken to Improve Individual Personnel Safety.Insps NecessaryCrystal River22 September 1988Requests Establishment of mini-purge of Reactor Bldg to Reduce Worker Exposure to Radiation & Radioactive Matl & to Assure That Every Measure Taken to Improve Individual Personnel Safety.Insps Necessary
3F0993-04, Forwards Response to 5 of 6 RAIs in NRC Re Floor Response Spectra for Resolution of USI A-46.Floor Response Spectra for Upper Two Floors in Reactor Bldg in Process of Development & Will Be Provided by 931015Crystal River7 September 1993Forwards Response to 5 of 6 RAIs in NRC Re Floor Response Spectra for Resolution of USI A-46.Floor Response Spectra for Upper Two Floors in Reactor Bldg in Process of Development & Will Be Provided by 931015
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