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 Issue dateTitle
ML22111A1134 March 2022Amendment 27 to Updated Final Safety Analysis Report, Chapter 5, Reactor Coolant System and Connected Systems
ML20268A12511 September 2020Amendment 26 to Updated Final Safety Analysis Report, Chapter 5, Reactor Coolant System and Connected Systems
L-2019-111, Attachments 1 Through 5: Evaluation of Proposed Changes, EAL Technical Bases Document, Mark-Up of EAL, EAL Comparison Matrix and Emergency Action Level Matrix Wall Charts30 September 2019Attachments 1 Through 5: Evaluation of Proposed Changes, EAL Technical Bases Document, Mark-Up of EAL, EAL Comparison Matrix and Emergency Action Level Matrix Wall Charts
L-2018-091, Radiological Emergency Plan - Revision 6712 April 2018Radiological Emergency Plan - Revision 67
L-2017-076, Radiological Emergency Plan - Revision 653 May 2017Radiological Emergency Plan - Revision 65
05000335/LER-2016-00129 July 2016Inadequate Legacy Evaluation for Containment High Range Radiation Monitor Nonconformance with Design Accuracy Requirements Resulted in Latent Inoperability and Operation Prohibited by Technical Specifications
LER 16-001-00 for St. Lucie Units 1 and 2 Regarding Inadequate Legacy Evaluation for Containment High Range Radiation Monitor Nonconformance with Design Accuracy Requirements Resulted in Latent Inoperability and Operation Prohibited by Technical....
L-2016-152, LER 16-001-00 for St. Lucie Units 1 and 2 Regarding Inadequate Legacy Evaluation for Containment High Range Radiation Monitor Nonconformance with Design Accuracy Requirements Resulted in Latent Inoperability and Operation Prohibited by Te29 July 2016LER 16-001-00 for St. Lucie Units 1 and 2 Regarding Inadequate Legacy Evaluation for Containment High Range Radiation Monitor Nonconformance with Design Accuracy Requirements Resulted in Latent Inoperability and Operation Prohibited by Tech
ML16042A1491 February 2016St. Lucie, Units 1 and 2 - Radiological Emergency Plan, Revision 64. Part 1 of 2
L-2016-021, St. Lucie, Units 1 and 2 - Radiological Emergency Plan, Revision 64. Part 1 of 21 February 2016St. Lucie, Units 1 and 2 - Radiological Emergency Plan, Revision 64. Part 1 of 2
ML15097A2677 April 2015301 Final SRO Written Exam
L-2015-011, Radiological Emergency Plan - Revision 639 January 2015Radiological Emergency Plan - Revision 63
ML14084A56825 March 2014Updated Final Safety Analysis, Chapter 5, Section 5.0, 5.1, 5.2. 5.4; Includes Up to UFSAR Amendment No. 21
ML0806704197 March 2008CDBI Findings
NOC-AE-07002231, Request for Relaxation of Requirements from Revision 1 of Order EA-03-009 Establishing Interim Inspection Requirements for Reactor Pressure Vessel Head Penetrations (Relief Request RR-ENG-2-46)7 November 2007Request for Relaxation of Requirements from Revision 1 of Order EA-03-009 Establishing Interim Inspection Requirements for Reactor Pressure Vessel Head Penetrations (Relief Request RR-ENG-2-46)
IR 05000335/200200429 January 2003IR 05000335-02-004 & IR 05000389-02-004 on 09/29/2002 - 01/4/2003; Florida Power & Light; St. Lucie, Units 1 and 2; Refueling and Outage Activities, Event Followup
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
ML20137L31425 April 1995Advises That Changes to St Lucie Nuclear Plant Emergency Plan,Rev 27 Consistent W/Provision of 10CFR50.54(b) 10CFR50.47(b),10CFR50,App E & Section II of NUREG-0654, W/Exception for Issues of Modes 5 & 6 EALs
ML20137K91015 August 1994Rev 0 to JPN-PSL-SENP-94-029, Safety Evaluation,Shutdown Operations Criteria for Reduced Inventory & Draining Reactor Coolant Sys
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
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
L-92-300, Forwards Data Point Library Revisions to Support Installation by NRC Onto Emergency Response Data Sys Computer22 October 1992Forwards Data Point Library Revisions to Support Installation by NRC Onto Emergency Response Data Sys Computer
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
ML17309A6746 October 1991Rept of Changes Made to Facility Under Provisions of 10CFR50.59 for Period 901007 to 911006. W/920406 Ltr
ML17223B22916 July 1991Forwards Description & Summary of Safety Evaluation of Plant Changes/Mods Made,Reportable Per 10CFR50.59.Rept Includes Plant Changes/Mods Completed Between 900123-910122
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
ML17308A47922 January 1989Rept of Changes Made Under Provision of 10CFR50.59 for Period Ending 890122. W/890720 Ltr
ML17308A4686 October 1988Rept of Changes Made Under Provisions of 10CFR50.59 for Period Ending 881006. W/890406 Ltr
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
ML18041A12330 December 1985LER 85-011-00:on 851129,Train a Engineered Safeguards Actuation Occurred.Caused by Poor Contact in Fuse Holder While Alternate Power Supply Deenergized for Mod.Fuse Holder Replaced & Actuation Signal reset.W/851230 Ltr
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
L-83-274, Final Deficiency Rept Re Loss of Continuity on Mineral Insulated Cable Assemblies.Initially Reported on 830330. Twenty-three Cable Assemblies W/Defective Connectors Repaired.Deficiencies Not Reportable Per 10CFR50.55(e)29 April 1983Final Deficiency Rept Re Loss of Continuity on Mineral Insulated Cable Assemblies.Initially Reported on 830330. Twenty-three Cable Assemblies W/Defective Connectors Repaired.Deficiencies Not Reportable Per 10CFR50.55(e)
ML17207A50522 October 1979Forwards Response to NRC 790913 Ltr Re Followup Actions Resulting from NRC Review of Tmi.Requirements Re Emergency Operations Ctr Insufficiently Defined to Designate Dedicated Primary & Alternate Locations