05000529/LER-2012-001, Regarding Technical Specification LCO 3.1.7 Completion Time Exceeded
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-2016-056, Response to Request for Additional Information Regarding License Amendment Request 240, Conditional Exemption from End-of-Life Moderator Temperature Coefficient Measurement
L-2015-271, Core Operating Limits Report, Cycle 28
L-2015-189, License Amendment Request 240, Conditional Exemption from End-of-Life Moderator Temperature Coefficient Measurement
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
L-2012-258, Core Operating Limits Report
L-2012-180, Revised Core Operating Limits Report
L-2011-118, Core Operating Limits Report
L-2014-366, St. Lucie, Unit 2 - Application for Technical Specification Change and Exemption Request Regarding the Transitioning to Areva Fuel
L-2010-230, Core Operating Limits Report
L-2009-240, Core Operating Limits Report for Turkey Point Unit 4
L-2009-116, Cycle 18 Core Operating Limits Report
L-2009-076, Submittal of Core Operating Limits Report
L-2008-244, Cycle 22 Core Operating Limits Report
L-08-228, Core Operating Limits Report, Revision 1, Supports the Implementation of License Amendment 278, Measurement Uncertainty Recapture (MUR) Power Uprate
L-2008-087, Core Operating Limits Report, Cycle 24
HNP-99-107, Application for Amend to License NPF-63,revising TS to Incorporate Analytical Methodology References in TS 6.9.1.6.2 Which Are Used to Determine Core Operating Limits
L-2007-183, Cycle 17 Core Operating Limits Report, Rev. 0
L-2007-175, Rod Position Indication Systems
L-2007-150, Submittal of Core Operating Limits Report
L-2007-083, License Amendment Request (LAR 192) Inoperable Rod Position Indication
L-2007-066, Transmittal of Cycle 21 Core Operating Limits Report
L-2006-247, Core Operating Limits Report
L-2006-209, License Amendment Request Inoperable Rod Position Indication
L-2006-088, Core Operating Limits Report
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
L-2005-232, Cycle 20 Core Operating Limits Report
L-2005-088, Core Operating Limits Report
W3F1-2005-0032, License Amendment Request NPF-38-249-1 Extended Power Uprate (Amendment 199) License Condition Regarding Instrument Uncertainty
05000324/LER-1981-035-03, /03L-0:on 810225,during Normal Startup,While Moving Control Rods,Rod Overtravel Annunciator Was Received During Verification of rod-drive Coupling for Rod 30-23. Cause Will Be Determined During Outage
L-2020-034, Cycle 25 Core Operating Limits Report
L-2004-219, Core Operating Limits Report
L-04-124, License Amendment Request Nos. 318 and 191
L-2004-138, Cycle 19 Core Operating Limits Report - Revision 1
L-2004-076, Cycle 19 Core Operating Limits Report, Revision 0
L-2003-254, Core Operating Limits Report for Cycle 21
L-03-020, License Amendment Request Nos. 303 and 174
L-2020-052, Core Operating Limits Report
L-2020-044, Report of 10 CFR 50.59 Plant Changes
L-2020-124, Report of 10 CFR 50.59 Plant Changes
L-2020-149, Submittal of Core Operating Limits Report
05000369/LER-1983-117, Forwards Rev 1 to LER 83-117/03L-1.Rev Submitted in Same Format as Original,Per NUREG-1022,Suppl 1,Section 14.8. Incident Attributed to Design Oversight.Procedure Revised to Prevent Further Violation of Tech Spec 3.1.3.6
L-2021-077, Cycle 30 Core Operating Limits Report
B13151, Proposed Tech Specs 3/4.1, Reactivity Control Sys
L-2021-187, Cycle 26 Core Operating Limits Report
L-2021-195, Submittal of Core Operating Limits Report
LR-N970217, Application for Amend to License NPF-7,revising Sections of TSs to Delete Reference to Rod Sequence Control Sys & Reduce Rod Worth Minimizer Low Power Setpoint from 20% to 10%
L-2022-000, License Amendment Request for the Technical Specifications Conversion to NUREG- 1432 Revision 5 - Request for Supplemental Information (Rsi) Response
ST-HL-AE-3224, Forwards Rev 0 to Core Operating Limits Rept, Unit 2, Cycle 1,dtd 890804,per Tech Spec 6.9.1.6
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
L-2022-052, Core Operating Limits Report
2CAN108509, Forwards Addl Info Re 850830 Tech Spec Change Request Concerning CPC Sys Response to CEA Inward Deviation,In Response to NRC Questions.Colss Monitors DNB Limiting Conditions for Operation
L-2022-125, Cycle 31 Core Operating Limits Report
B13903, Application for Amend to License DPR-65,changing Index & Tech Spec Sections 3.1.3.6,3.4.11,3.9.18,3.9.19 & 3.9.20 & Bases Sections 3/4.9.17,3/4.9.18.3/4.9.19 & 3/4.9.20 to Resolve Editorial Errors & Typos
2CAN049504, Application for Amend to License NPF-6,deleting Requirement Associated W/Part Length CEAs (Plceas) from TS & Replacing Plceas W/Full Length,Full Strength CEAs
L-2023-062, Cycle 33 Core Operating Limits Report
L-2016-198, Turkey Point, Units 3 & 4, Updated Final Safety Analysis Report, Chapter 14, Safety Analysis, Appendix 14A Thru Appendix 14G
L-05-009, License Amendment Request Nos. 310 and 182
L-2003-040, Core Operating Limits Report
L-2006-128, Cycle 16 Core Operating Limits Report
L-2023-039, Cycle 27 Core Operating Limits Report
05000352/LER-1989-035, :on 890506,control Rods Improperly Verified as Coupled to Drives During Facility Second Fuel Cycle.Caused by Misalignment During Original Installation.Installation Procedures Revised to Prevent Recurrence
05000368/LER-1987-009, :on 871114,subcritical Reactor Trip Occurred While Performing Reactor Shutdown.Caused by Procedural Deficiency.Proper Actuation of Reactor Protection Sys Verified.Procedure Will Be Revised
05000328/LER-1988-013-01, :on 880316 & 17,rod Control Sys Deficiencies Caused Inaccuracies in Rod Group Demand Position Indication Resulting in Manual Reactor Trips.Caused by Demand Step Counter Circuitry Failure & Internal Binding
05000373/LER-1996-010, :on 960829,violations of TS & Design Basis Occurred.Caused by Inadequate Standards for TS Clarification.Deleted Clarifications in Question on 960829 & Revised One Clarification
05000373/LER-1996-010-06, :on 960829,determined Conditions Outside of Design Basis.Caused by Inadequate Standards for TS Clarifications.Implemented Development of TS Clarifications & Evaluates TS Interpretations
05000328/LER-1984-018-02, :on 840910,three Reactor Trips Occurred.Caused by Steam Generator lo-lo Level.Engineering Design Issued to Consider Westinghouse Design for Automation of Steam Generator Level Control at Low Reactor Power
05000328/LER-1984-017-02, :on 840906,during Startup,Reactor Tripped While Switching Control of Steam Generator Levels from Manual to Automatic.Caused by Reduction in Reactor Power to Slow Swell of Steam Generator 3
05000369/LER-1992-002-02, :on 920117,error Detected in Results from Computer Program Used to Perform Power Distribution Surveillance Calculations.Caused by Design Deficiency. Program Corrected
05000362/LER-1983-087-01, /01T-0:on 831026,plant Monitoring Sys Computer Failed While Entering Limiting Condition of Operation 3.10.2.Caused by Moving Head Disk Error in Computer.Cause of Disk Error Unknown
05000362/LER-1983-112-03, /03L-0:on 831130,regulating Group 6 Control Element Assemblies Exceeded Time Allowed Below long-term steady-state Insertion Limit.Caused by Need to Control Axial Shape Index Oscillations
05000361/LER-1983-075-03, /03L-0:on 830828,regulating Control Element Assembly Group 6 Exceeded Time Allowed for long-term steady-state Insertion Limit.Caused by Use of Assemblies to Control Axial Shape Index Oscillations
05000373/LER-1983-121-03, /03L-0:on 831014,while Performing LOS-AA-W1, Control Rod Drive at Core Location 30-19 Indicated Overtravel When Withdrawn to Full Out Position.Caused by Excessive Crud Buildup on Filter
05000373/LER-1983-126-03, /03L-0:on 831027,control Rod Drive at Core Location 30-19 Indicated Overtravel When Withdrawn to Full Out Position During Unit Startup.Caused by Inner Filter Retainer Spring Damage Due to Crud Buildup
05000373/LER-1983-024-03, /03L-0:on 830312,control Rod Drive at Core Location 18-15 Indicated Overtravel When Withdrawn to Full Out Position for Startup.Caused by Inner Filter Retainer Spring Damage Due to Excessive Crud Buildup.Drive Recoupled
05000373/LER-1983-056-03, /03L-0:on 830529,w/unit in Condition 2,rod 30-19 Went to over-travel Position While Being Withdrawn for Startup.Possibly Caused by Excessive Crud Buildup &/Or Undue Force Applied Directly to Inner Filter
05000445/LER-1994-004-01, :on 940822,unit 1 Load Reduction QPTR Exceeded TS 3/4.2.4 Limits of 1.02.Caused by QPTR Was Inoperable. Plant Computer Database Was Corrected to Resolve QPTR Annunciator Problem
05000324/LER-1982-129-03, /03L-0:on 821028,while Verifying Rod Drive Coupling for Rod 18-07,rod Overtravel Annunciator Received. Cause Unknown.Rod Will Be Inspected for Irregularities During Next Scheduled Control Rod Drive Rebuilding Outage
A02204, Provides Addl Info Requested by NRC to Facilitate Review of Cycle 5 Operation
05000395/LER-1983-090-03, /03L-0:on 830818,while Increasing Reactor/Turbine Power from 14 to 20%,rod Insertion Limit Violated.Caused by Operating Personnel Failure to Establish Plant Parameters. Emergency Boration Initiated
05000324/LER-1981-077-03, /03L-0:on 810814,rod Overtravel Annunciator Received During Verification of rod-drive Coupling for Rod 18-47.Cause Unknown.Rod Reinserted & Deactivated.Drive Will Be Removed & Inspected During Next Outage
05000302/LER-1981-035-03, /03L-0:on 810616,regulating Rod Groups 6 & 7 Exceeded Overlap Requirements.Caused by Procedural Deficiencies Resulting in Failure to Note Loss of Permissive Logic When Transferring Power Supplies
05000327/LER-1989-026-01, :on 891107,Limiting Condition for Operation 3.0.3 Entered as Result of More than One Rod Position Indicator (RPI) Per Bank Being Inoperable.Caused by Lack of Preventive Maint.Rpis Adjusted
05000302/LER-1980-054-03, /03L-0:on 801210,regulating Rod Group Insertion Limits Exceeded.Caused by Anticipated Rod Movements to Control Reactor Power Burnout.Boron Added to Reactor Coolant
05000324/LER-1981-046-03, /03L-0:on 810417,during Verification of rod-drive Coupling for Rod 30-23,rod Overtravel Annunciator Was Received.Cause Not Stated.Rod Will Be Inspected During Next Control Rod Drive Rebuilding Outage
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
05000324/LER-1979-093-03, /03L-1:on 791120,during Normal Reactor Startup, Rods 42-33 & 26-07 Gave Rod Overtravel Alarm When Withdrawn to Notch 48.Probably Caused by Loose Inner Filter on Drive Engaging Uncoupling Rod.Units to Be Overhauled
05000302/LER-1979-009-03, /03L-0 on 790124:while Performing Reactor Protection Sys Functional Testing,Rod Group 6 Dropped Into Core,Rod Group Overlap Was Exceeded.Caused by a AC Power Breaker Being Left Open
05000346/LER-1979-087-03, /03L-0:on 790731,operators Twice Received Control Rod Sequence Fault Alarm.Caused by Faulty Integrated Circuit in Auxiliary Power Supply of Command Logic String.Circuit Replaced & Proper Operation Verified
L-95-160, Application for Amends to Licenses DPR-31 & DPR-41,revising TS 3/4.1.3.1, Movable Control Assemblies - Group Height & 3/4.1.3.2, Position Indication Sys - Operating & Asociated Bases
L-94-128, Application for Amends to Licenses DPR-31 & DPR-41,modifying TS 3.1.3.6, Reactivity Control Sys CR Insertion Limits, 3/4.2.2, Heat Flux Hot Channel Factor - Fq(Z) & 6.9.1.7, COLR & Associated Bases,Per GL 88-16.COLRs Encl
L-97-280, Application for Amend to License NPF-16,modifying Specifications for Selected cycle-specific Reactor Physics Parameters to Provide Reference to St Lucie Unit 2 COLR for Limiting Values
05000530/LER-1991-008-01, :on 911114,lighting Induced Electrical Fault on a Phase Main Transformer Caused Generator Trip,Turbine Trip & Reactor Power Cutback.Caused by Problem W/Calculator Software.Lightning Protection Sys Evaluated
05000528/LER-1988-016, :on 880514,reactor Trip Occurred.Caused by Nonconservative Operator Performance During Reactor Startup. Info Utilized for Estimated Critical Condition Will Be Corrected
05000328/LER-2011-001-01, For Sequoyah Nuclear Plant, Unit 2 Regarding Nuclear Instrumentation System Power Range Neutron Flux Trip Low Range Bistable Incorrectly Calibrated - Revision 1
05000328/LER-2011-001, Regarding Nuclear Instrumentation System Power Range Neutron Flux Trip Low Range Bistable Incorrectly Calibrated
L-02-094, Technical Specifications Bases Change Submittal
L-2005-034, Cycle 15 Core Operating Limits Report
B18952, Changes to Technical Specifications Bases
B18835, Response to Request for Additional Information Re TS Change Request 2-15-02
B18724, Technical Specifications Change Request 2-15-02 Changes in Technical Specifications Related to Reactivity Control Systems, Power Distribution Limits, and Special Test Exceptions
L-2002-063, Core Operating Limits Report for Turkey Point, Unit 4
L-2003-110, Cycle 14 Core Operating Limits Report
L-2002-209, Cycle 18 Core Operating Limits Report - Revision 0
B18898, Technical Specifications Change Request 2-15-02, Changes in Technical Specifications Related to Reactivity Control Systems, Power Distribution Limits, and Special Test Exceptions, Response to Second Request for Additional Information
L-2023-149, Cycle 34 Core Operating Limits Report