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 Issue dateTitleFromTo
NRC Generic Letter 1988-0517 March 1988NRC Generic Letter 1988-005: Boric Acid Corrosion of Carbon Steel Reactor Pressure Boundary Components in PWR PlantsMiraglia F
Office of Nuclear Reactor Regulation
NRC Generic Letter 1988-077 April 1988NRC Generic Letter 1988-007: Modified Enforcement Policy Relating to 10 CFR 50.49 Environmental Qualification of Electrical Equipment Important to Safety for Nuclear Power Plants.Miraglia F
Office of Nuclear Reactor Regulation
ML17222A27831 May 1988Responds to Generic Ltr 88-05 Re Boric Acid Corrosion of Carbon Steel Reactor Pressure Boundary Components.Principle Locations Where Leakage Could Degrade RCS Pressure Boundary Will Be Identified & Included in New ProcedureNextEra Energy
Conway W
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
NRC Generic Letter 1988-12, Removal of Fire Protection Requirements from Technical Specification2 August 1988NRC Generic Letter 1988-012: Removal of Fire Protection Requirements from Technical SpecificationsMiraglia F
Office of Nuclear Reactor Regulation
NRC Generic Letter 1991-1717 October 1991NRC Generic Letter 1991-017: Generic Safety Issue 29, Bolting Degradation or Failure in Nuclear Power Plants.Partlow J
Office of Nuclear Reactor Regulation
ML17227A57726 August 1992Proposes to Eliminate Dynamic Effects Associated W/High Energy Pipe Rupture in RCS Piping from Licensing & Design Bases by Application of leak-before-break Technology,Per Topical Rept CEN-367.Supporting Info EnclNextEra Energy
Sager D
Office of Information Resources Management
Information Notice 1986-10, Degradation of Reactor Coolant System Pressure Boundary Resulting from Boric Acid Corrosion.5 January 1995Degradation of Reactor Coolant System Pressure Boundary Resulting from Boric Acid Corrosion.Grimes B
Office of Nuclear Reactor Regulation
Information Notice 1986-10, Degradation of Reactor Coolant System Pressure Boundary Resulting From Boric Acid Corrosion.5 January 1995Degradation of Reactor Coolant System Pressure Boundary Resulting From Boric Acid Corrosion.Grimes B K
Office of Nuclear Reactor Regulation
ML17229A42825 July 1997Provides 120-day Response to NRC GL 97-01, Degradation of Control Rod Drive Mechanism Nozzle & Other Vessel Closure Head Penetrations. Util Plans to Utilize Info from Industry Effort & Submit Written Response to Items 1 & 2 by 970730Stall J
Pennsylvania Power and Light Company
Office of Information Resources Management
L-2002-061, Response to NRC Bulletin 2002-01, Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity2 April 2002Response to NRC Bulletin 2002-01, Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary IntegrityNextEra Energy
Advisory Committee on Reactor Safeguards
Stall J
Office of Nuclear Reactor Regulation
Document Control Desk
ML02326026022 November 2002Request for Additional Information Regarding Bulletin 2002-01, 60-Day ResponseEllen Brown
NRC/NRR/DLPM/LPD2
NextEra Energy
Stall J
IR 05000335/200500227 April 2005IR 05000335-05-002, 05000389-05-002, on 01/01/2005 - 03/31/2005; St. Lucie Nuclear Plant, Units 1 & 2; Routine Integrated ReportJoel Munday
NRC/RGN-II/DRP/RPB3
NextEra Energy
Stall J
IR 05000335/200500530 January 2006IR 05000335-05-005, IR 05000389-05-005 on 10/01/2005 - 12/31/2005 for St. Lucie Nuclear Plant, Units 1 & 2; Refueling and Other Outage Activities, Inservice Inspection Activities, Radiation Safety, and PI&R Annual Sample ReviewJoel Munday
NRC/RGN-II/DRP/RPB3
NextEra Energy
Stall J
IR 05000033/200600327 July 2006IR 0500033-06-003, 05000389-06-003, on 04/01/2006 - 06/30/2006, St. Lucie, Units 1 & 2Joel Munday
NRC/RGN-II/DRP/RPB3
NextEra Energy
Stall J
IR 05000335/20070051 February 2008IR 05000335-07-005 & 05000389-07-005; Florida Power & Light Company; on 10/01/2007 - 12/31/2007; St. Lucie Nuclear Plant, Units 1 & 2; Occupational Radiation Safety and Public Radiation Safety, NRC Integrated Inspection ReportNRC/RGN-II/DRP/RPB3
Vias S
NextEra Energy
Stall J
IR 05000335/200900329 July 2009IR 05000335-09-003, 05000389-09-003, on 04/01/2009 - 06/30/2009, St. Lucie, Units 1 & 2, Maintenance Risk Assessment and Emergent Work Control, Identification and Resolution of Problems, Other ActivitiesMarvin Sykes
NRC/RGN-II/DRP/RPB3
NextEra Energy
Nazar M
IR 05000335/201200430 October 2012IR 05000335-12-004, 05000389-12-004; 07/01/2012 - 09/30/2012; St. Lucie Nuclear Plant, Units 1 & 2; Shipment of Radioactive Materials, Problem Identification and ResolutionNRC/RGN-II/DRP/RPB3
Rich D
NextEra Energy
Nazar M
IR 05000335/201300531 January 2014IR 05000335-13-005, 05000389-13-005 2013005, 05000335/2013502 and 05000389/2013502; 10/01/2013 - 12/31/2013; St. Lucie Nuclear Plant, Units 1 & 2; Integrated InspectionNRC/RGN-II/DRP/RPB3
Rich D
NextEra Energy
Nazar M
IR 05000335/20140082 May 2014IR 05000389-14-008; on 03/10/2014 - 04/28/2014; Saint Lucie Plant Unit 2; Inservice Inspection Activities and Plant ModificationsNRC/RGN-II/DRS/EB3
Lopez-Santiago O R
NextEra Energy
Nazar M
IR 05000389/20140082 May 2014IR 05000389-14-008; on 03/10/2014 - 04/28/2014; Saint Lucie Plant Unit 2; Inservice Inspection Activities and Plant ModificationsNRC/RGN-II/DRS/EB3
Omar Lopez-Santiago
NextEra Energy
Nazar M
IR 05000335/20150024 August 2015IR 05000335/2015002, 05000389/2015002 & 05000335/2015011, 05000389/2015011; Assessment Follow-up Letter; 04/01/2015 -06/30/2015; St. Lucie Nuclear Plant, Units 1 & 2; Follow-up of Events and Notice of Enforcement Discretion; Radioactive GasNRC/RGN-II/DRP/RPB3
Ladonna Suggs
NextEra Energy
Nazar M
IR 05000335/20150104 January 2016IR 05000335/2015010, November 220, 2015, Saint Lucie Plant, Unit 1,NRC/RGN-II/DRS/EB3
Walker S A
NextEra Energy
Nazar M
IR 05000335/20150045 February 2016NRC Integrated Inspection Report 05000335/2015004 and 05000389/2015004NRC/RGN-II/DRP/RPB3
Ladonna Suggs
NextEra Energy
Nazar M
IR 05000335/20170019 May 2017NRC Integrated Inspection Report 05000335/2017001 and 05000389/2017001NRC/RGN-II/DRP/RPB3
Ladonna Suggs
NextEra Energy
Nazar M
L-2020-043, Amendment 30 to Updated Final Safety Analysis Report, Chapter 18, Aging Management Programs and Time-Limited Aging Analyses Activities4 May 2020Amendment 30 to Updated Final Safety Analysis Report, Chapter 18, Aging Management Programs and Time-Limited Aging Analyses ActivitiesNextEra EnergyOffice of Nuclear Reactor Regulation
L-2020-123, Amendment 26 to Updated Final Safety Analysis Report, Chapter 18, Aging Management Programs and Time-Limited Aging Analyses Activities11 September 2020Amendment 26 to Updated Final Safety Analysis Report, Chapter 18, Aging Management Programs and Time-Limited Aging Analyses ActivitiesNextEra EnergyOffice of Nuclear Reactor Regulation
ML22013A66811 November 2021Amendment 31 to Updated Final Safety Analysis Report, Chapter 18, Aging Management Programs and Time-Limited Aging Analysis ActivitiesNextEra EnergyOffice of Nuclear Reactor Regulation
ML22111A1144 March 2022Amendment 27 to Updated Final Safety Analysis Report, Chapter 18, Aging Management Programs and Time-Limited Aging Analyses ActivitiesNextEra EnergyOffice of Nuclear Reactor Regulation
ML23096A0331 April 2023Amendment 32 to Updated Final Safety Analysis Report, Chapter 18, Aging Management Programs and Time-Limited Aging Analyses ActivitiesNextEra EnergyOffice of Nuclear Reactor Regulation