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 850601 | Crystal River | 22 March 1985 | 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 850601 | |
3F0387-02, Forwards Info Re Generic Issue 124,auxiliary Feedwater Sys Reliability,Per NRC 870218 request.W/75 Oversize Drawings | Crystal River | 5 March 1987 | Forwards 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 Performed | Crystal River | 14 March 1989 | Responds 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 to | Crystal River | 22 March 1991 | Provides NRC W/Updated Design Info About Auxiliary Feedwater Pump Addition at Crystal River Unit 3 & Providing Revs to | |
3F0403-04, TS Bases Control Program | Crystal River | 10 April 2003 | TS 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 System | Crystal River | 27 April 2004 | Modified 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 Uprate | Crystal River | 25 April 2007 | License 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 Time | Crystal River | 13 April 2007 | License 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 LAR | Crystal River | 16 April 2012 | Response 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 Underway | Crystal River | 30 April 1986 | 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 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 River | 6 May 2005 | 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. | |
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 River | 3 May 2007 | Ninety-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 Program | Crystal River | 27 May 2015 | Technical Specifications Bases Control Program | |
3F0516-05, Final Safety Analysis Report Revision 38 & May 2016 10 CFR 50.59 and 10 CFR 72.48 Report | Crystal River | 25 May 2016 | Final 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 Request | Crystal River | 6 May 1987 | Submits 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,Initiated | Crystal River | 24 May 1989 | 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,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 Basis | Crystal River | 28 May 1998 | 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 Basis | |
3F0607-05, License Amendment Request 296, Revision 1, Measurement Uncertainty Recapture Uprate | Crystal River | 28 June 2007 | License 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 Considerations | Crystal River | 15 June 2011 | 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 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 Installed | Crystal River | 26 June 1984 | 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 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 Valve | Crystal River | 1 June 1998 | 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 Valve | |
3F0703-04, License Amendment Request 280, Rev. 0 Revised Improved Technical Specification (ITS) 3.7.9, Nuclear Services Seawater System | Crystal River | 14 July 2003 | License 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 & Concurrence | Crystal River | 25 July 1985 | Forwards 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 Limits | Crystal River | 5 July 1988 | 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 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 Rept | Crystal River | 14 July 1988 | 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 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 Developed | Crystal River | 20 July 1989 | 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 Developed | |
3F0794-07, Requests Discretionary Enforcement Re Replacement of Rotating Element for Motor Driven EFP-1 | Crystal River | 7 July 1994 | Requests 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, Discussed | Crystal River | 3 July 1997 | Forwards 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 Period | Crystal River | 28 July 1998 | 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 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 LAR | Crystal River | 11 August 2011 | Response 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 7 | Crystal River | 15 August 2011 | Submittal 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 LAR | Crystal River | 30 August 2012 | 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 LAR | |
3F0817-03, Rev. 0, Defueled Safety Analysis Report | Crystal River | 31 August 2017 | Rev. 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 VI | Crystal River | 31 August 1984 | 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 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 Noted | Crystal River | 11 August 1986 | 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 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 Meeting | Crystal River | 11 August 1989 | Forwards 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 87-02 | Crystal River | 15 August 1994 | 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 87-02 | |
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 Analysis | Crystal River | 5 August 1997 | 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 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 Reviews | Crystal River | 13 August 1997 | 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 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 Valves | Crystal River | 11 August 1997 | 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 Valves | |
3F0903-03, NRC Inspection Report 50-302/02-05, Triennial Fire Protection Inspection, August 23, 2002 | Crystal River | 5 September 2003 | NRC 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 System | Crystal River | 16 September 2004 | Supplemental 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 Information | Crystal River | 4 September 2007 | 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 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.1.1 | Crystal River | 21 September 1984 | 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.1.1 | |
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 Position | Crystal River | 20 September 1984 | 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 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 Encl | Crystal River | 24 September 1984 | 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 Encl | |
3F0987-02, Forwards Info Re Operation of Target Rock Electrically Positioned Control Valves in Emergency Feedwater Sys,Per 870901 Request | Crystal River | 4 September 1987 | Forwards 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 Breaks | Crystal River | 27 September 1988 | 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 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 Necessary | Crystal River | 22 September 1988 | 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 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 931015 | Crystal River | 7 September 1993 | 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 931015 | |