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Issue date | Title | |
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ML22111A113 | 4 March 2022 | Amendment 27 to Updated Final Safety Analysis Report, Chapter 5, Reactor Coolant System and Connected Systems |
ML20268A125 | 11 September 2020 | Amendment 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 Charts | 30 September 2019 | 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 Charts |
L-2018-091, Radiological Emergency Plan - Revision 67 | 12 April 2018 | Radiological Emergency Plan - Revision 67 |
L-2017-076, Radiological Emergency Plan - Revision 65 | 3 May 2017 | Radiological Emergency Plan - Revision 65 |
05000335/LER-2016-001 | 29 July 2016 | Inadequate 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 Te | 29 July 2016 | 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 Tech |
ML16042A149 | 1 February 2016 | St. 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 2 | 1 February 2016 | St. Lucie, Units 1 and 2 - Radiological Emergency Plan, Revision 64. Part 1 of 2 |
ML15097A267 | 7 April 2015 | 301 Final SRO Written Exam |
L-2015-011, Radiological Emergency Plan - Revision 63 | 9 January 2015 | Radiological Emergency Plan - Revision 63 |
ML14084A568 | 25 March 2014 | Updated Final Safety Analysis, Chapter 5, Section 5.0, 5.1, 5.2. 5.4; Includes Up to UFSAR Amendment No. 21 |
ML080670419 | 7 March 2008 | CDBI 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 2007 | 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) |
IR 05000335/2002004 | 29 January 2003 | IR 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, & FitzPatrick | 5 May 1999 | Unanticipated Reactor Water Draindown at Quad Cities Unit 2, Arkansas Nuclear One Unit 2, & FitzPatrick |
NRC Generic Letter 1998-02 | 28 May 1998 | NRC 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 Shutdown | 5 December 1997 | Recent 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 Shutdown | 11 December 1996 | Undetected 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 Power | 22 October 1996 | Problems Associated with Testing, Tuning, or Resetting of Digital Control Systems While at Power |
Information Notice 1996-42, Unexpected Opening of Multiple Safety Relief Valves | 5 August 1996 | Unexpected Opening of Multiple Safety Relief Valves |
Information Notice 1996-37, Inaccurate Reactor Water Level Indication and Inadvertent Draindown During Shutdown | 18 June 1996 | Inaccurate Reactor Water Level Indication and Inadvertent Draindown During Shutdown |
Information Notice 1996-05, Partial Bypass of Shutdown Cooling Flow from Reactor Vessel | 18 January 1996 | Partial Bypass of Shutdown Cooling Flow from Reactor Vessel |
ML20137L314 | 25 April 1995 | Advises 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 |
ML20137K910 | 15 August 1994 | Rev 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 1 | 15 July 1994 | Inadvertent Containment Spray and Reactor Vessel Draindown at Millstone Unit 1 |
Information Notice 1994-36, Undetected Accumulation of Gas in Reactor Coolant System | 24 May 1994 | Undetected Accumulation of Gas in Reactor Coolant System |
Information Notice 1993-89, Potential Problems with BWR Level Instrumentation Backfill Modifications | 26 November 1993 | Potential Problems with BWR Level Instrumentation Backfill Modifications |
Information Notice 1993-62, Thermal Stratification of Water in BWR Reactor Vessels | 10 August 1993 | Thermal Stratification of Water in BWR Reactor Vessels |
Information Notice 1993-27, Level Instrumentation Inaccuracies Observed During Normal Plant Depressurization | 8 April 1993 | Level 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 Computer | 22 October 1992 | Forwards Data Point Library Revisions to Support Installation by NRC Onto Emergency Response Data Sys Computer |
NRC Generic Letter 1992-04 | 19 August 1992 | NRC 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 Draindown | 25 February 1992 | Loss of Flow from the Residual Heat Removal Pump During Refueling Cavity Draindown |
ML17309A674 | 6 October 1991 | Rept of Changes Made to Facility Under Provisions of 10CFR50.59 for Period 901007 to 911006. W/920406 Ltr |
ML17223B229 | 16 July 1991 | Forwards 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 Units | 23 March 1990 | Unanticipated Equipment Actuations Following Restoration of Power to Rosemount Transmitter Trip Units |
ML17308A479 | 22 January 1989 | Rept of Changes Made Under Provision of 10CFR50.59 for Period Ending 890122. W/890720 Ltr |
ML17308A468 | 6 October 1988 | Rept of Changes Made Under Provisions of 10CFR50.59 for Period Ending 881006. W/890406 Ltr |
ML20211G936 | 6 June 1986 | Summary 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 |
ML18041A123 | 30 December 1985 | LER 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 1985-08 | 23 May 1985 | NRC Generic Letter 1985-008: 10 CFR 20.408 Termination Reports - Format |
NRC Generic Letter 1985-07 | 2 May 1985 | NRC Generic Letter 1985-007: Implementation of Integrated Schedules for Plant Modifications |
NRC Generic Letter 1985-02 | 17 April 1985 | NRC 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 1985-05 | 31 January 1985 | NRC Generic Letter 1985-005: Inadvertent Boron Dilution Events |
ML031150585 | 29 January 1985 | Withdrawn 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 1983 | 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) |
ML17207A505 | 22 October 1979 | Forwards 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 |