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L-2023-078, License Amendment Request 278, Incorporate Advanced Fuel Products, Extend Surveillance Intervals and 10 CFR 50.46 Exemption Request to Facilitate Transition to 24-Month Fuel Cycles15 November 2023License Amendment Request 278, Incorporate Advanced Fuel Products, Extend Surveillance Intervals and 10 CFR 50.46 Exemption Request to Facilitate Transition to 24-Month Fuel Cycles
ML23151A43624 May 2023License Amendment Request Revision 3 for the Technical Specifications Conversion to NUREG - 1431 Revision 5
ML23151A43724 May 2023Attachment 3: Turkey Point Nuclear Plant, Units 3 and 4, Improved Technical Specifications Conversion License Amendment Request NRC Request for Additional Information and FPL Responses Database
ML23151A44624 May 2023Enclosure 2, Volume 8: Turkey Point Nuclear Plant, Units 3 and 4, Improved Technical Specifications Conversion, Section 3.3, Instrumentation, Revision 3
ML22089A20630 March 2022Enclosure 2 - Volume 8, Turkey Point Nuclear Generating Station, Units 3 and 4, Improved Technical Specifications Conversion, ITS Section 3.3, Instrumentation, Revision 1
ML21265A37922 September 2021Improved Technical Specifications Conversion, Volume 8, Revision 0, Section 3.3, Instrumentation
L-2017-149, Updated Final Response to NRC Generic Letter 2004-0229 December 2017Updated Final Response to NRC Generic Letter 2004-02
ML16271A08327 September 2016301 Final SRO Written Exam
ML15119A52629 April 2015Initial Exam 2015-301 Final Sim In-Plant JPMs
ML15119A49129 April 2015Initial Exam 2015-301 Draft Sim In-Plant JPMs
L-2012-332, Emergency Response Data System (ERDS) Maintenance17 August 2012Emergency Response Data System (ERDS) Maintenance
ML12166A06614 June 2012Initial Exam 2011-302 Draft RO Written Exam
ML12166A08114 June 2012Initial Exam 2011-302 Draft SRO Written Exam
L-2011-438, Response to NRC Reactor Systems Branch Request for Additional Information Regarding Extended Power Uprate License Amendment Request No. 20515 October 2011Response to NRC Reactor Systems Branch Request for Additional Information Regarding Extended Power Uprate License Amendment Request No. 205
L-2010-115, 10 CFR 50.59 Summary Report Changes, Tests, and Experiments Implemented as Allowed by 10 CFR 50.59 for the Period Covering May 11, 2008 Through December 4, 20094 June 201010 CFR 50.59 Summary Report Changes, Tests, and Experiments Implemented as Allowed by 10 CFR 50.59 for the Period Covering May 11, 2008 Through December 4, 2009
L-2008-245, Transmittal of 10 CFR 50.59 Summary Report of Changes, Tests and Experiments Made Without Prior Commission Approval for Period 12/09/06 - 05/11/0810 November 2008Transmittal of 10 CFR 50.59 Summary Report of Changes, Tests and Experiments Made Without Prior Commission Approval for Period 12/09/06 - 05/11/08
L-2008-058, Emergency Response Data System Maintenance25 March 2008Emergency Response Data System Maintenance
L-2007-129, Emergency Response Data System (ERDS) Maintenance20 August 2007Emergency Response Data System (ERDS) Maintenance
L-2003-317, SRO Written License Examination Comments18 December 2003SRO Written License Examination Comments
Information Notice 1999-14, Unanticipated Reactor Water Draindown at Quad Cities Unit 2, Arkansas Nuclear One Unit 2, & FitzPatrick5 May 1999Unanticipated Reactor Water Draindown at Quad Cities Unit 2, Arkansas Nuclear One Unit 2, & FitzPatrick
NRC Generic Letter 1998-0228 May 1998NRC Generic Letter 1998-002: Loss of Reactor Coolant Inventory and Associated Potential for Loss of Emergency Mitigation Functions While in a Shutdown Condition
Information Notice 1997-83, Recent Events Involving Reactor Coolant System Inventory Control During Shutdown5 December 1997Recent Events Involving Reactor Coolant System Inventory Control During Shutdown
Information Notice 1996-65, Undetected Accumulation of Gas in Reactor Coolant System and Inaccurate Reactor Water Level Indication During Shutdown11 December 1996Undetected Accumulation of Gas in Reactor Coolant System and Inaccurate Reactor Water Level Indication During Shutdown
Information Notice 1996-56, Problems Associated with Testing, Tuning, or Resetting of Digital Control Systems While at Power22 October 1996Problems Associated with Testing, Tuning, or Resetting of Digital Control Systems While at Power
Information Notice 1996-42, Unexpected Opening of Multiple Safety Relief Valves5 August 1996Unexpected Opening of Multiple Safety Relief Valves
Information Notice 1996-37, Inaccurate Reactor Water Level Indication and Inadvertent Draindown During Shutdown18 June 1996Inaccurate Reactor Water Level Indication and Inadvertent Draindown During Shutdown
Information Notice 1996-05, Partial Bypass of Shutdown Cooling Flow from Reactor Vessel18 January 1996Partial Bypass of Shutdown Cooling Flow from Reactor Vessel
Information Notice 1994-52, Inadvertent Containment Spray and Reactor Vessel Draindown at Millstone Unit 115 July 1994Inadvertent Containment Spray and Reactor Vessel Draindown at Millstone Unit 1
Information Notice 1994-36, Undetected Accumulation of Gas in Reactor Coolant System24 May 1994Undetected Accumulation of Gas in Reactor Coolant System
ML07104001728 April 199459 FRN 12990, Biweekly Notice; Applications and Amendments to Facility Operating Licenses Involving No Significant Hazards Considerations
Information Notice 1993-89, Potential Problems with BWR Level Instrumentation Backfill Modifications26 November 1993Potential Problems with BWR Level Instrumentation Backfill Modifications
Information Notice 1993-62, Thermal Stratification of Water in BWR Reactor Vessels10 August 1993Thermal Stratification of Water in BWR Reactor Vessels
Information Notice 1993-27, Level Instrumentation Inaccuracies Observed During Normal Plant Depressurization8 April 1993Level Instrumentation Inaccuracies Observed During Normal Plant Depressurization
NRC Generic Letter 1992-0419 August 1992NRC Generic Letter 1992-004 - Resolution of Issues Related to Reactor Vessel Water Level Instrumentation in BWRs Pursuant to 10 CFR 50.54(F)
Information Notice 1992-16, Loss of Flow from the Residual Heat Removal Pump During Refueling Cavity Draindown25 February 1992Loss of Flow from the Residual Heat Removal Pump During Refueling Cavity Draindown
Information Notice 1990-22, Unanticipated Equipment Actuations Following Restoration of Power to Rosemount Transmitter Trip Units23 March 1990Unanticipated Equipment Actuations Following Restoration of Power to Rosemount Transmitter Trip Units
ML20247A89716 March 1989Summary of Operating Reactors Events Meeting 89-11 on 890315.List of Attendees,Events Discussed & Significant Elements of Events & Four Events Identified for Input to NRC Performance Indicator Program & Summary of Scrams Encl
ML20211G9366 June 1986Summary of Operating Reactor Events Meeting 86-18 on 860602 Re Events Occurring Since 860519 Meeting.Attendee List, Events,Significant Elements of Events & Completion Dates for Assignments Encl
NRC Generic Letter 1985-0923 May 1985NRC Generic Letter 1985-009: Technical Specifications for Generic Letter 1983-028, Item 4.3
NRC Generic Letter 1985-0823 May 1985NRC Generic Letter 1985-008: 10 CFR 20.408 Termination Reports - Format
NRC Generic Letter 1985-072 May 1985NRC Generic Letter 1985-007: Implementation of Integrated Schedules for Plant Modifications
NRC Generic Letter 1985-0217 April 1985NRC Generic Letter 1985-002: Staff Recommended Actions Stemming from NRC Integrated Program for the Resolution of Unresolved Safety Issues Regarding Steam Generator Tube Integrity
NRC Generic Letter 1985-0531 January 1985NRC Generic Letter 1985-005: Inadvertent Boron Dilution Events
ML03115058529 January 1985Withdrawn NRC Generic Letter 1985-004: Operator Licensing Examinations
ML17341A27025 June 1981Forwards Conceptual Design Description of Sys Intended to Monitor Reactor Vessel Water Level,Per NUREG-0737,Item II.F.2.Ltr of Intent Issued to Purchase Sys Developed by C-E Owners Group
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