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
NOC-AE-16003351, License Amendment Request to Revise Technical Specification 5.3.2 to Allow Operation with 56 Full-Length Control Rod Assemblies
NOC-AE-15003315, Emergency License Amendment Request to Revise Technical Specification 5.3.2 to Allow Operation with 56 Full-Length Control Rod Assemblies for Cycle 20
L-2015-271, Core Operating Limits Report, Cycle 28
2CAN021501, License Amendment Request Allowance to Eliminate Movement of Control Element Assembly 18 from Surveillance Requirement 4.1.3.1.2 for the Remainder of Cycle 24
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
2CAN101201, Cycle 23, 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)
L-2009-116, Cycle 18 Core Operating Limits Report
L-2008-244, Cycle 22 Core Operating Limits Report
2CAN030801, Response to Request for Additional Information, License Amendment Request to Revise Technical Specification 6.6.5, Core Operating Limits Report
05000528/LER-1994-002, :on 940422,determined That TS 3.1.1.1,3.3.1 & 3.9.1 LCO May Not Ensure That Plant Operation Is Maintained within Safety Analysis.Caused by Groundrules Adjunct to Ts. TS Change Request Is Being Prepared
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
W3F1-2019-0014, Core Operating Limits Report-Cycle 23 Revision 0
RAIO-0219-64549, LLC Supplemental Response to NRC Request for Additional Information No. 228 (Erai No. 9034) on the NuScale Design Certification Application
L-2019-068, Core Operating Limits Report
W3F1-2019-0062, License Amendment Request to Relocate Boration Systems Technical Specifications to the Technical Requirements Manual
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
2CAN060502, Cycle 18 Startup Report - Arkansas Nuclear One, Unit 2
L-2020-034, Cycle 25 Core Operating Limits Report
W3F1-2004-0090, Ses, Technical Specification Bases Update to the NRC for the Period of 10/26/04 - 09/30/04
L-2004-181, Response to Request for Additional Information for Proposed License Amendment Inoperable Rod Position Indication
L-2004-138, Cycle 19 Core Operating Limits Report - Revision 1
W3F1-2003-0075, Ses, Unit 3, License Amendment Request NPF-38-250, Revision to Pressure/Temperature and Low Temperature Overpressure Protection Limits for 32 Effective Full Power Years
L-2004-076, Cycle 19 Core Operating Limits Report, Revision 0
W3F1-2003-0055, TS Bases Update to NRC for Period April 8, 2003 Through July 23, 2003
L-2003-083, Technical Specification Bases Control Program Periodic Report of Bases Changes TS 6.8.4.i.4
L-2005-154, Response to Request for Additional Information Regarding Proposed License Amendment for the Adoption of TSTF-95
W3F1-2003-0010, Supplement to Amendment Request NPF-38-243 Reactivity/Boron Concentration Changes
W3F1-2002-0095, License Amendment Request NPF-38-243 Reactivity/Boron Concentration Changes
L-2002-155, Proposed License Amendment Inoperable Rod Position Indication NRC Requested Referenced Documents for Review
L-2020-052, Core Operating Limits Report
L-2020-149, Submittal of Core Operating Limits Report
2CAN069806, Application for Amend to License NPF-6,modifying Requirements for Pressurizer Code Safety Valve Requirements Specified by TS 3.4.2 & Safety Tank Isolation Requirements Specified in TS 3.4.12
L-2021-187, Cycle 26 Core Operating Limits Report
L-2021-195, Submittal of Core Operating Limits Report
3F0487-21, Revised Response to Violations Noted in Insp Rept 50-302/86-38.Corrective actions:SP-421 Revised Adding Detail to Prevent Similar Mistakes in Future & LER Reporting Containment Leakage Event Issued on 870129
ST-HL-AE-1867, Forwards Justification for Proposed Tech Specs Identified for Further Comment or Resolution During 861117-21 Site Visit.Pending NRC Agreement,Revs Will Be Included in Future FSAR or Fire Hazards Analysis Rept Amend
NOC-AE-0017, Forwards Results of Control Rod Testing in Response to NRC Bulletin 96-001, Control Rod Insertion Problems. Encl Consists of Core Map,Current Unit 1 Specific Core Design Data & Units 1 & 2 Restart Evaluation Criteria
L-2022-052, Core Operating Limits Report
2CAN112104, Response to Request for Additional Information 2 Related to License Amendment Request to Adopt a Safety Function Determination Program (SFDP)
L-2022-125, Cycle 31 Core Operating Limits Report
ST-HL-AE-4260, Forwards Response to NRC 921026 Telcon Request for Addl Info Re 920928 Application for Amends to Licenses NPF-76 & NPF-80,consisting of Rev 1 to SE for Proposed Rev to Shutdown Margin in TS 3.1.1.1
ST-HL-AE-4222, Application for Amends to Licenses NPF-76 & NPF-80,changing TS 3.1.1.1 to Remove Variable Shutdown Margin Requirements for Modes 1 & 2 & Reflect That Reactivity Balance Can Only Be Performed When Reactor Critical
B14108, Application for Amend to License NPF-49,changing TS Figure 3.1-5, Required Shutdown Margin for Mode 5 W/Rcs Loops Not Filled, Section 3.4.1.3, RCS - Hot Shutdown & 4.4.1.1.3, RCS - Hot Shutdown Surveillance Requirements
B14966, Responds to NRC Re Violations Noted in Insp Repts 50-336/94-01 & 50-336/94-18 on 940105-0222.Corrective Actions:Util EP Personnel Conducted Assessment Activities Related to EAL Classification Issues & Hpes Analysis Done
L-2023-062, Cycle 33 Core Operating Limits Report
W3P86-3323, Application for Amend to License NPF-38,consisting of Tech Spec Change Requests NPF-38-40,NPF-38-41 & NPF-38-42, Revising Shutdown Margin Whenever All Full Length Control Element Assemblies Fully Inserted in Core.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
L-2008-149, Technical Specification Bases Control Program Periodic Report of Bases Changes TS 6.8.4.j.4
W3F1-2020-0064, Core Operating Limits Report (COLR) - Cycle 24, Revision 1
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-2019-076, Technical Specification Bases Control Program Periodic Report of Bases Changes TS 6.8.4.j.4
L-2023-039, Cycle 27 Core Operating Limits Report
05000370/LER-1986-008-03, :on 860620,control Rod L-3 Discovered Stuck & Unable to Drop Into Reactor Core.Caused by Small Particle Debris.Debris Removed
05000334/LER-1999-007, :on 990413,manually Initiated Reactor Trip Signal During pre-planned Shutdown of Unit While in Mode 3. Caused by Failure of Cabinet Air Conditioner.Replaced Failed Cabinet Air Conditioner.With
3F0688-06, Forwards Rept Re Environ Qualification of Neutron Flux Monitors Installed Per Reg Guide 1.97,Rev 3.Control Room Operator Informed Monitors May Not Be Reliable Under Accident Conditions
05000328/LER-1988-030, :on 880621,discovered Failure to Identify Effects of Excessive post-trip RCS Cooldowns Could Cause Noncompliance.Emergency Instruction Used to Guide Operator Action Following Reactor Trip Revised
05000320/LER-1987-012-01, :on 871009,indications of Failure of Locknut & Stemnut for Isolation Valve DH-V-4V Discovered.Caused by Failure to Stake Locknut & Drive Sleeve Assembly.Locknut & Sleeve Assembly Replaced & Locknut Staked
05000423/LER-1996-002, :on 960310,inadequate Surveillance for Determining Shutdown Margin When Unisolating Rcl Occurred Due to Procedure Inadequacy.Changes Will Be Made to Technical Requirements Manual
05000454/LER-1992-007-09, :on 920727,discovered Nonconservative Method Used to Calculate Shutdown Margin.On 920818,determined That TS 3.1.1.1 Not Met for Surveillance Performed on 900211. Caused by Procedural Flaw.Procedure Revised
05000423/LER-1996-002-02, :on 960310,inadequate Surveillance for Determining Shutdown Margin When Unisolating Rcl Identified. Caused by Inadequate Procedure.Procedures Revised
05000272/LER-1984-015-01, :on 840611,received Notification by Westinghouse of Potential Unreviewed Safety Question Re Consistency Between Safety Analysis & Tech Specs.Procedures for Mode 3 Operation Revised
05000335/LER-1982-051-03, /03L-0:on 821024,while Moving Control Rods During Ascent to Full Power,Control Element Assembly 40 Dropped to Full Insertion.Cause Undetermined.Control Element Assembly Recovered.Plant Operation Resumed
05000423/LER-1993-015-01, :on 930923,daily Surveillance Shutdown Margin Improperly Performed.Caused by Procedural Deficiency. Refueling Operations Procedure Changed to Require Updating Plant Process Computer When New Core Installed
LR-N17-0034, Salem Generating Station, Units 1 & 2, Submittal of Revision 29 to Updated Final Safety Analysis Report, and Technical Specification Bases Changes and Quality Assurance Topical Report, NO-AA-10, Rev. 85
L-2006-264, Technical Specification Bases Control Program Periodic Record of Bases Changes TS 6.8.4.j.4
05000320/LER-1980-006-01, /01L-0:on 800218,under Interim Recovery Tech Specs,In Mode 5,boric Acid Mix Tank Inventory Was Below Requirements of Newly Implemented Tech Specs.Caused by Administrative Changeover to More Restrictive Tech Specs
L-2023-107, Technical Specification Bases Control Program Periodic Report of Bases Changes TS 6.8.4.j.4
LR-N22-0078, Submittal of Technical Specification Bases Changes, Amendment No. 215
B16834, Application for Amend to License DPR-65,correcting Various TS Compliance Issues,Including Modifying Definition of Azimuthal Power Tilt,Changing Wording of SR 4.1.1.1.2 & Changing Applicability of TS 3.1.3.4
LR-N18-0129, License Amendment Request to Revise Technical Specifications to Adopt TSTF-547, Clarification of Rod Position Requirements
LR-N970627, Application for Amend to License DPR-70,changing TS for LCOs 3.1.3.1, Movable Control Assemblies & 3.1.3.2.1, Position Indication Sys
05000263/LER-1917-006, Regarding Loss of Reactor Protection System Scram Function During Main Steam Isolation Valve and Turbine Stop Valve Channel Functional Tests Due to Use of a Test Fixture
05000400/LER-1998-003, :on 980129,failure to Perform Shutdown Margin Calculation Required by TS Surveillance Requirements Occurred.Caused by Ambiguity in TS 3.1.3.1.c.Procedures Revised
HNP-96-055, Forwards 30-day Response to NRC Bulletin 96-001, Control Rod Insertion Problems
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
05000244/LER-1995-008, :on 950825,secondary Transient Occurred.Caused by Loss of B Condenser Circulating Water Pump That Resulted in Manual Rt.Returned S/G Levels to Normal Operating Levels
05000244/LER-1993-006, :on 931110,feedwater Transient Occurred,Due to Loss of Ability to Control Feedwater Regulating Valve.Caused by low-low SG Level Reactor Trip.New Screw & Nut Installed in Linkage Arm
05000244/LER-1990-013, :on 901211,turbine Trip W/Subsequent Reactor Trip Occurred.Caused by Inadvertent ATWS Mitigation Sys Actuation Circuitry (AMSAC) Actuation.Jumper,Omitted in AMSAC Circuit Design,Installed
05000244/LER-1994-007, :on 940427,feedwater Transient Occurred Due to Loss of Ability to Control Feedwater Regulating Valve, Causing Lo Lo SG Level Reactor Trip.Caused by Improperly Secured Stroke Adjust Set Screw
05000389/LER-1998-010, :on 981207,RCS Boron Sample Frequency Required by Ts,Was Exceeded by Twelve Minutes.Caused by Personnel Error.Equipment Clearance Order Was Lifted to Draw Required Sample & Operations Procedure Was Changed.With
L-81-397, Forwards Responses to NRC 810828 Telcon Request for Addl Info Re Main Steam Line Break Reanalysis
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)
W3F1-2011-0084, Core Operating Limits Report - Cycle 18 Revision 0
L-2009-099, Technical Specification Bases Control Program, Periodic Report of Bases Changes TS 6.8.4.j.4
W3F1-2006-0059, Core Operating Limits Report - Cycle 14 Revision 0 Change 1
L-2005-034, Cycle 15 Core Operating Limits Report
W3F1-2003-0094, Core Operating Limits Report, Cycle 13, Revision 1
05000260/LER-2003-003, Manual Scram Resulting from the 2B Reactor Recirculation Pump Trip with OPRM Function Inoperable
B18724, Technical Specifications Change Request 2-15-02 Changes in Technical Specifications Related to Reactivity Control Systems, Power Distribution Limits, and Special Test Exceptions
W3F1-2002-0034, Ses Core Operating Limits Report for Cycle 12
W3F1-2004-0022, Core Operating Limits Report - Cycle 13 Revision 1, Change 2
W3F1-2009-0067, Core Operating Limits Report - Cycle 17, Revision 0
L-2003-291, Technical Specification Bases Control Program, Periodic Report of Bases Changes, TS 6.8.4.j.4
W3F1-2008-0041, Core Operating Limits Report - Cycle 16 Revision 0
W3F1-2014-0047, Core Operating Limits Report - Cycle 20, Revision 1
L-2003-110, Cycle 14 Core Operating Limits Report
L-2002-209, Cycle 18 Core Operating Limits Report - Revision 0
W3F1-2003-0086, Core Operating Limits Report - Cycle 13, Revision 0
W3F1-2013-0032, Core Operating Limits Report - Cycle 19 Revision 1
W3F1-2013-0074, Core Operating Limits Report - Cycle 19 Revision 2
NOC-AE-000211, Forwards Updated Plant Incomplete Control Rod (Rcca) Insertion Evaluation Criteria Should Plant Perform Rod Drop Testing During Remainder of Current Operating Fuel Cycles, Per Util 971119 Response to NRC Bulletin 96-01
L-97-158, Application for Amend to License DPR-67,incorporating Recent Evaluation of Postulated Inadvertent Opening of MSSV Into Current Licensing Basis
L-2016-084, Response to Request for Additional Information Regarding License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-422, Revision 2, Change in Technical Specifications End States
L-2023-149, Cycle 34 Core Operating Limits Report
L-2015-182, License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-422, Revision 2, Change in Technical Specifications End States (CENPSD-1186), Using the Consolidated Line Item Improvement
L-95-169, Application for Amends to Licenses DPR-31 & DPR-41,modifying TS Per Selected Line Items from NRC GL 93-05, Line-Item TS Improvements to Reduce SRs for Testing During Power Operation
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
05000311/LER-1983-039-03, /03L-0:on 830723,control Rod 2C4 Inserted Fully & Could Not Be Withdrawn.Unit Placed in Hot Standby.Caused by Control Rod Drive Mechanism Cable Connector Pins Pushed Into Insulator,Resulting in Intermittent Connection