Semantic search

Jump to navigation Jump to search
 Issue dateTitle
ML23275A1152 October 2023Improved Technical Specifications Conversion, Section 3.0, LCO and SR Applicability, Revision 2 - Volume 5
IR 05000335/20210033 November 2021Integrated Inspection Report 05000335/2021003 and 05000389/2021003
ML21265A29015 September 2021Enclosure 2 - Volume 5 - St. Lucie Plant, Units 1 and 2, Improved Technical Specifications Conversion ITS Section 3.0 LCO and SR Applicability, Revision 0
ML21034A5193 February 20211A -PSL L-20-1 RO and SRO Student Exam Final as Given with Key
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
ML19148A74431 July 2019Issuance of Amendment Nos. 161, 249, 200, 287, and 281 to Add Technical Specification Limiting Condition for Operation 3.0.6
L-2019-034, In-Service Inspection Plans Fourth Ten-Year Interval: Unit 1 Relief Requests 15 and 167 February 2019In-Service Inspection Plans Fourth Ten-Year Interval: Unit 1 Relief Requests 15 and 16
L-2018-049, Application to Add Limiting Condition for Operation (LCO) 3.0.6 to the Technical Specifications29 May 2018Application to Add Limiting Condition for Operation (LCO) 3.0.6 to the Technical Specifications
ML18150A48223 April 2018NRR E-mail Capture - (External_Sender) LCO 3.0.6 LAR Pre-submittal Call
ML17027A0787 April 2017Issuance of Amendments Regarding Technical Specifications for Inservice Testing Programs (CAC Nos. MF8202 Through MF8209)
ML16214A27628 July 2016NextEra Energy Resources, LLC, Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing, and to Request an Alternative to t
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 Gas
ML15097A2677 April 2015301 Final SRO Written Exam
ML14343A91827 February 2015Issuance of Amendments to Revise Limiting Condition for Operation 3.0.4 and Surveillance Requirement 4.0.4
L-2014-239, Units I and 2, Clarification Regarding License Amendment Request for Technical Specification Change Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process -25 July 2014Units I and 2, Clarification Regarding License Amendment Request for Technical Specification Change Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process -
L-2014-207, Inservice Inspection Plan Third Ten-Year Interval Unit 2 Relief Request No. 1630 June 2014Inservice Inspection Plan Third Ten-Year Interval Unit 2 Relief Request No. 16
L-2014-144, Response to Request for Additional Information (RAI) Regarding License Amendment Request for Technical Specification Change Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process29 May 2014Response to Request for Additional Information (RAI) Regarding License Amendment Request for Technical Specification Change Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process
L-2013-233, Application for Technical Specification Change Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process26 February 2014Application for Technical Specification Change Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process
ML13018A01318 January 2013Initial Exam 2012-301 Post Exam Comments
L-2012-427, Q4116-R-002, Rev. 0, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Force Recommendation 2.3: Seismic30 November 2012Q4116-R-002, Rev. 0, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Force Recommendation 2.3: Seismic
IR 05000335/201000429 October 2010IR 05000335-10-004, 05000389-10-004; 07/01/2010-09/30/2010; St. Lucie Nuclear Plant, Units 1 & 2; Equipment Alignment, Identification and Resolution of Problems Other Activities
L-2009-169, Response to Request for Additional Information, Third Interval Relief Request 3220 July 2009Response to Request for Additional Information, Third Interval Relief Request 32
L-2009-035, Third Interval Relief Requests 31 and 326 February 2009Third Interval Relief Requests 31 and 32
IR 05000335/200700423 October 2007IR 05000335-07-004 & IR 05000389-07-004, on 07/01/2007 - 09/30/2007, St. Lucie Nuclear Plant, Units 1 & 2; Event Followup
L-2007-147, Comment (11) of D. E. Grissette, on Behalf of Florida Power & Light Company on Draft Regulatory Guide DG-5019, Reporting of Safeguards Events.1 October 2007Comment (11) of D. E. Grissette, on Behalf of Florida Power & Light Company on Draft Regulatory Guide DG-5019, Reporting of Safeguards Events.
L-2004-180, in Service Inspection Plan, Closeout of Second Ten-Year Interval, Revised Relief Requests 1A and 1OA6 August 2004in Service Inspection Plan, Closeout of Second Ten-Year Interval, Revised Relief Requests 1A and 1OA
ML0527906542 October 2003Current Facility Operating License DPR-067, Tech Specs, Revised 01/31/2020
ML0327316612 October 2003DPR-67 Appendix a
ML0328008462 October 2003NPF-16 Appendix a
ML0230903714 November 2002Technical Specification Pages for Amendments 186 and 129 Regarding Missed Surveillances
L-2002-117, to Proposed License Amendments Re Consolidated Line Item Improvement Process from Florida Power & Light Company15 August 2002to Proposed License Amendments Re Consolidated Line Item Improvement Process from Florida Power & Light Company
IR 05000335/200200229 July 2002IR 05000335-02-002, IR 05000389-02-002, on 06/29/02 for Florida Power & Light Company, St. Lucie Plant, Units 1 & 2. Resident Integrated Inspection Report
L-2002-002, Florida Power and Light Letter Re St. Lucie Units 1 and 2, Proposed License Amendments - Supplement Consolidated Line Item Improvement Process TSTF-358 - Missed Surveillance Requirements25 January 2002Florida Power and Light Letter Re St. Lucie Units 1 and 2, Proposed License Amendments - Supplement Consolidated Line Item Improvement Process TSTF-358 - Missed Surveillance Requirements
ML17229B0797 April 1999LER 99-001-00:on 990309,discovered Inadequate Design & IST SRs for Iodine Removal Sys (Irs).Caused by Original Design Inadequacies & Personnel Error.Naoh Tank Vent Valve V07233 Was Tagged Open.With 990407 Ltr
ML17309A97211 February 1999Requests Approval of Revised Relief Requests 1 & 4 & New Relief Requests 21 & 22 as Part of Closeout of Second ten-yr ISI Interval for St Lucie,Unit 1.Subject Relief Requests Encl
L-98-104, Responds to Violations Noted in Insp Rept 50-335/97-16. Corrective Actions:Performed Review of Remaining Setpoints for Rps,Afas & ESFAS Which Concluded Setpoints & Loop Calibrations Meet TS Requirements & Revised Procedures20 April 1998Responds to Violations Noted in Insp Rept 50-335/97-16. Corrective Actions:Performed Review of Remaining Setpoints for Rps,Afas & ESFAS Which Concluded Setpoints & Loop Calibrations Meet TS Requirements & Revised Procedures
ML17229A67326 March 1998LER 98-002-00:on 980224,radiation Monitor Surveillance Inadequacies Led to Operating of Facility Prohibited by Tss. Caused by Congnitive Personnel Error.Permanent Procedure Changes Were implemented.W/980326 Ltr
ML17229A3752 June 1997LER 97-006-00:on 970501,operation Was Prohibited by TS Due to Inadequately Tested Degraded Voltage Sys.Revised Unit 1 ESFAS Surveillance Test procedure.W/970602 Ltr
ML17229A1939 January 1997LER 96-007-00:on 961211,operation Prohibited by TSs Occurred Due to Inadequate Surveillance of MSIS Actuation Logic. Testing of MSIS High Containment Pressure 2/4 Actuation Logic Was Satisfactorily Performed on 961211.W/970109 Ltr
L-96-296, LER 96-S02-00:on 961011,failed to Terminate Access of Temporary Licensee Employee.Caused by Cognitive Personnel Error.Security Unassigned Card Key & Plant Administrative Procedure 0010509 Revised7 November 1996LER 96-S02-00:on 961011,failed to Terminate Access of Temporary Licensee Employee.Caused by Cognitive Personnel Error.Security Unassigned Card Key & Plant Administrative Procedure 0010509 Revised
Information Notice 1996-44, Failure of Reactor Trip Breaker from Cracking of Phenolic Material in Secondary Contact Assembly5 August 1996Failure of Reactor Trip Breaker from Cracking of Phenolic Material in Secondary Contact Assembly
ML20137N79128 June 1996Scoping Document for Implementation of Maint Rule for Monitoring Effectiveness of Maint on Structures
ML20137M41621 December 1995Independent Assessment of Maint Rule Implementation at Plant, 951211-15
ML17228B30930 October 1995LER 95-004-00:on 951010,RCS Instrument Nozzle Leakage Occurred.Caused by Primary Water Stress Corrosion Cracking. Completed Visual Insp of Other RCS Instrument Nozzles. W/951030 Ltr
L-94-016, Forwards Safeguards Event Log Entries for Fourth Quarter 1993.Log Does Not Contain Safeguards Info as Defined by 10CFR73.2125 January 1994Forwards Safeguards Event Log Entries for Fourth Quarter 1993.Log Does Not Contain Safeguards Info as Defined by 10CFR73.21
ML17223A32413 September 1989LER 89-006-00:on 890816,diesel Generator 2B Placed Out of Svc W/Hydrogen Analyzer 2A Also Out of Svc.Caused by Cognitive Personnel Error by util-licensed Operator. Generator & Analyzer Returned to svc.W/890913 Ltr
ML17222A49215 September 1988LER 87-018-00:on 870131,util Identified That Specific Masonry Block Walls Which Were Assumed to Be 3 H Fire Barriers May Not Have Been Completely Filled W/Grout.Caused by Const Practices.Fire Watch established.W/880915 Ltr
ML17221A68619 March 1988LER 88-002-00:on 880218,reactor Containment Bldg Polar Crane Power Supply Breaker Found in Tagged Open Position.Caused by Personnel Error.Reactor Containment Bldg Polar Crane Power Supply Breaker Locked open.W/880321 Ltr
ML17221A4976 November 1987LER 87-014-00:on 871008,unidentified RCS Leakage Greater than Tech Spec Limit Discovered.Caused by Weld Joint Failure Due to Previous Misalignment of Listed Flanges.Reactor Shut Down & Required Repairs performed.W/871106 Ltr
ML17216A48810 April 1986LER 86-006-00:on 860312,both Emergency Diesel Generators Out of Svc.Caused by Damaged Idler Pulley Wheel & Loose Locknut in Friction Clutch Assembly.Generators Repaired & Remaining Generators inspected.W/860410 Ltr