L-2017-036, Core Operating Limits Report, Cycle 29
L-2016-176, Submittal of Core Operating Limits Report Cycle 28 and Cycle 29
L-2016-081, Core Operating Limits Report
L-2015-271, Core Operating Limits Report, Cycle 28
L-2015-180, Proposed TS Changes for TSTF-523 LAR Incorporating Approved TSTF-425 LAR
L-2015-034, Response to Requests for Additional Information (Rais) Regarding License Amendment Request to Adopt TSTF-426, Revise or Add Actions to Preclude Entry Into LCO 3.0.3 - RITSTF Initiatives 6b & 6c (MF4631 and MF4632)
L-2014-029, St, Lucie Nuclear Plant, Units 1 and 2, License Amendment Request, Application to Revise Technical Specifications to Adopt Technical Specifications Task Force (TSTF) Traveler -523, Generic Letter 2008-01, Managing Gas Accumulation, Using
L-2014-069, Core Operating Limits Report
L-2013-034, Core Operating Limits Report for Unit 4 Cycle 27
L-2012-356, Revised Core Operating Limits Report
2CAN071201, License Amendment Request - Supplemental Technical Specification (TS) Change Related to Revised Fuel Assembly Drop Analysis and Adoption of TSTF-51, TSTF-272, TSTF-286, and TSTF-471
L-2012-258, Core Operating Limits Report
L-2012-180, Revised Core Operating Limits Report
2CAN041201, License Amendment Request, Technical Specification (TS) Change Related to Revised Fuel Assembly Drop Analysis and Adoption of TSTF-51, TSTF-272, TSTF-286, and TSTF-471
L-2011-438, Response to NRC Reactor Systems Branch Request for Additional Information Regarding Extended Power Uprate License Amendment Request No. 205
L-2011-006, License Amendment Request No. 209; Relocation of Cycle Specific Parameters to the Core Operating Limits Report (COLR)
L-2010-078, Attachment 9, St. Lucie License Amendment Request Extended Power Uprate, Core Operating Limits Report (COLR) Markups (for Information Only)
TMI-10-021, Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (Adoption of TSTF-425, Revision 3)
L-2009-116, Cycle 18 Core Operating Limits Report
L-2008-244, Cycle 22 Core Operating Limits Report
HNP-07-178, Shearon Harris, Submittal of Information in Support of NFPA 805 Pilot Observation Reviews
L-2007-183, Cycle 17 Core Operating Limits Report, Rev. 0
L-2007-175, Rod Position Indication Systems
L-2007-168, Technical Specifications Bases Control Program Periodic Report of Bases Changes TS 6.8.4.j.4
L-2007-083, License Amendment Request (LAR 192) Inoperable Rod Position Indication
L-2007-066, Transmittal of Cycle 21 Core Operating Limits Report
L-2006-209, License Amendment Request Inoperable Rod Position Indication
L-2018-195, Core Operating Limits Report
SBK-L-18094, License Amendment Request 18-02, Application to Revise the Technical Specifications Associated with Movable Control Rods
L-2019-068, Core Operating Limits Report
2CAN081903, License Amendment Request Technical Specification (TS) Change Related to Revised Fuel Handling Accident Analysis and Adoption of TS Improvements Consistent with NUREG-1432
L-2005-232, Cycle 20 Core Operating Limits Report
NOC-AE-05001921, License Amendment Request - Proposed Amendment to Technical Specifications to Incorporate Best Estimate Analyzer for Core Operations - Nuclear
L-2005-132, Proposed License Amendments Request for Additional Information Response Control Room Ventilation System and Miscellaneous Minor Changes
L-2020-034, Cycle 25 Core Operating Limits Report
L-2004-138, Cycle 19 Core Operating Limits Report - Revision 1
L-2004-076, Cycle 19 Core Operating Limits Report, Revision 0
L-2003-083, Technical Specification Bases Control Program Periodic Report of Bases Changes TS 6.8.4.i.4
L-2002-155, Proposed License Amendment Inoperable Rod Position Indication NRC Requested Referenced Documents for Review
W3F1-2002-0013, Supplement to Amendment Request NPF-38-234 Replacement of Part-Length Control Element Assemblies
L-2020-052, Core Operating Limits Report
L-2020-149, Submittal of Core Operating Limits Report
L-2021-187, Cycle 26 Core Operating Limits Report
L-2021-195, Submittal of Core Operating Limits Report
L-2022-052, Core Operating Limits Report
TMI-22-015, Submittal of Changes to Technical Specifications Bases
L-2022-125, Cycle 31 Core Operating Limits Report
TMI-20-012, Island Nuclear Station, Unit 1 - Submittal of Changes to Technical Specifications Bases
L-2023-062, Cycle 33 Core Operating Limits Report
B14803, Application for Amend to License NPF-49,proposing Changes to Ts,Addressing Shutdown Margins,Reactor Trip Sys & Heat Flux Hot Channel Factor
W3P87-2049, Application for Amend to License NPF-38,changing Axial Shape Index to Implement Power Dependent Limits & Providing Administrative Changes to Shutdown Margin Requirements to Remove Mode 2 Applicability of Tech Spec 3.1.1.2.Fee Paid
W3P86-3328, Boric Acid Concentration Reduction Effort,Technical Bases & Operational Analysis,Waterford Nuclear Power Plant Unit 3
L-2016-198, Turkey Point, Units 3 & 4, Updated Final Safety Analysis Report, Chapter 14, Safety Analysis, Appendix 14A Thru Appendix 14G
W3F1-2008-0021, RAI Response to Amendment Request NPF-38-271 to Support Next Generation Fuel
L-2004-222, Technical Specification Bases Control Program Periodic Report of Bases Changes TS 6.8.4.i.4
L-2006-128, Cycle 16 Core Operating Limits Report
NOC-AE-02001368, E-mail Kenneth Taplett to Mohan Thadani, Replacement Page NOC-AE-02001368
W3P86-3379, Forwards Response to Request for Addl Info Re Tech Spec Change Requests to Implement Bypass for nonsafety-related High Speed Generator Level Trip & to Support Cycle 2 Operation
L-2023-039, Cycle 27 Core Operating Limits Report
05000339/LER-1987-014-02, :on 871022,accumulator Tank Inadvertently Injected Borated Water Into Rcs.Caused by Personnel Error. Administrative Procedure 5.8 Will Be Revised & Event Will Be Reviewed W/Operations Personnel
05000338/LER-1987-022-01, :on 871010,pressurizer PORV Opened Due to Actuation of Overpressure Protection Sys.Caused by Reduction in Primary Sys Temp During Inservice Insp Test.Insp Procedure Will Be Revised
L-2003-199, Proposed License Amendments Regarding Control Room Ventilation System and Miscellaneous Minor Changes
05000338/LER-1987-022, :on 871010,pressurizer PORV Opened Due to Actuation of Overpressure Protection Sys.Caused by Brief Reduction in Primary Sys Temp During Performance of Inservice Insp Test of RHR Sys Valves
05000382/LER-1992-010-01, :on 920919,noncompliance W/Ts 3.1.2.9 Identified Due to Inadequate Procedure.Procedure OP-010-001, General Plant Operations Will Be Revised
05000244/LER-1982-008-01, /01T-0:on 820303,emergency Cooldown Occurred. Caused by Cooldown/Depressurization of Primary Sys Following Rupture of Tube B Steam Generator Resulting in Calculated Delta T of Approx 280 F.No Action Neccessary
05000382/LER-1992-019-01, :on 920327,indicated That Actual RCS Boron Concentration Below Required Concentration.Caused by Inadequate Procedure Guidance.C/A Included Procedure Changes to Account for Training of Personnel
05000346/LER-1979-050-01, /01T-1:on 790423,while in Mode 5,boron Batch Flow Controller Valve MU-39 Leaked,Causing 3,000 Gallons of Demineralized Water to Enter Rcs.Caused by Combination of Mechanical,Personnel & Procedural Errors.Valve Closed
05000320/LER-1980-036-01, /01L-0:on 800808,failed to Perform RCS Coolant Dissolved Boron & Hydrogen Analyses.Cause by Contamination of B&W R&D Facility.Util in Process of Establishing Onsite Capabilities for Performing RCS Coolant Analyses
HNP-95-016, Proposed Tech Specs 3.1.1.2 Re Relocating Shutdown Margin Vs Boron Concentration Curve to COLR
05000528/LER-1995-002, :on 950303,identified That Slb Analyses Failed to Consider as Initial Condition One Percent SDM for All Rods in (ARI) Due to Lack of Coordination & Unclear Div of Responsibilities.Ari Core Data Book SDM Curves Modified
DCL-89-182, Application for Amends to Licenses DPR-80 & DPR-82, Consisting of License Amend Request 89-08,reducing Boron Concentration in Boric Acid Sys from 12 to 4 Weight Percent
2CAN031303, License Amendment Request - Adoption of Technical Specification Task Force (TSTF)-422, Revision 2 ‘‘Change in Technical Specifications End States (CE NPSD-1186)
L-2009-099, Technical Specification Bases Control Program, Periodic Report of Bases Changes TS 6.8.4.j.4
L-2005-034, Cycle 15 Core Operating Limits Report
B18991, Response to Request for Additional, License Basis Document Change Request (LBDCR) 3-01-03, Selective Implementation of the Alternative Source Term - Fuel Handling Accident Analyses
L-2003-110, Cycle 14 Core Operating Limits Report
L-2002-209, Cycle 18 Core Operating Limits Report - Revision 0
TMI-12-027, License Amendment Request to Revise Steam Generator Program Inspection Frequencies and Tube Sample Selection
L-2023-149, Cycle 34 Core Operating Limits Report
2CAN061302, License Amendment Request - Supplemental Technical Specification (TS) Change Related to Revised Fuel Assembly Drop Analysis and Adoption of TSTF-51, TSTF-272, TSTF-286, and TSTF-471
05000338/LER-1991-023, :on 911227,w/unit in Cold Shutdown,Pzr Level Increased from 60 to 82% Cold Calibr Level.Caused by Personnel Error Due to Failure to Maintain Configuration Control After Type C Test.Personnel Cautioned