05000289/LER-2002-002, TMI-1 Pressurizer Code Safety Valve Setpoint Outside Tolerance During Plant Operation Due to Mechanical Setpoint Drift
05000336/LER-2008-002, Regarding Unplanned LCO Entry - Three Charging Pumps Aligned for Injection with the Reactor Coolant System Temperature Less than 300 Degrees F
L-2017-060, License Amendment Request 249: Elimination of Certain Technical Specification Reporting Requirements, Revised Action for Emergency Core Cooling System, and Changes to Administrative Technical Specifications
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
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-2011-006, License Amendment Request No. 209; Relocation of Cycle Specific Parameters to the Core Operating Limits Report (COLR)
L-2010-113, Turkey Point, Units 3 and 4 - License Amendment Request for Extended Power Uprate, Attachment 1; Descriptions and Technical Justifications for the Renewed Operating License, Technical Specifications, and Licensing Basis Changes
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
W3F1-2007-0031, Technical Specification Bases Update to the NRC for the Period 07/02/2006 Through 06/01/2007
L-2018-195, Core Operating Limits Report
L-2019-068, Core Operating Limits Report
05000289/LER-1977-004, Forwards LER 77-004/01T.Provides Supplemental Info
2CAN081903, License Amendment Request Technical Specification (TS) Change Related to Revised Fuel Handling Accident Analysis and Adoption of TS Improvements Consistent with NUREG-1432
RA-19-0417, Supplement to License Amendment Request to Eliminate Certain Technical Specification Requirements in Alignment with Improved Standard Technical Specifications
W3F1-2005-0073, License Amendment Request NPF-38-263 to Modify Technical Specification 3.1.1.3 Surveillance Requirements as Allowed by WCAP-16011-P-A, Startup Test Activity Reduction Program
W3F1-2005-0072, License Amendment Request NPF-38-264 to Modify Technical Specification 3.1.1.4, Minimum Temperature for Criticality
NOC-AE-04001827, Cycle 12 End-of-Life Moderator Temperature Coefficient Limit Report
NOC-AE-03001449, Cycle 11 End of Life Moderator Temperature Coefficient Limit Report
W3F1-2002-0064, Ses Startup and Power Escalation Report for Cycle 12
NOC-AE-02001315, Conditional Exemption from Measurement of End of Life Moderator Temperature Coefficient
L-2020-052, Core Operating Limits Report
L-2020-149, Submittal of Core Operating Limits Report
W3F1-2020-0058, Core Operating Limits Report (COLR) - Cycle 24, Revision 0
IA-97-382, Package Consisting of Various Printouts of Publicly Available Records Re SFP Leakage
B17310, Application for Amend to License DPR-65,changing TS Bases 3/4.9.1,3/4.1.1.1,3/4.7.1.6,3/4.7.7,3/4.5.4 & 3/4.3.3.10 by Resolving Miscellaneous Condition Repts
B16595, Application for Amend to License DPR-65,incorporating Various Compliance Issues Identified in TS
L-2021-195, Submittal of Core Operating Limits Report
ELV-00431, Special Rept 89-001 Re Positive Moderator Temp Coefficient Measured During Low Power Physics Testing.Calculations Performed to Determine Control Rod Withdrawal Limits & Duration of Effect Time
ELV-00770, Application for Amends to Licenses NPF-68 & NPF-81,revising Tech Spec 3.1.1.3 to Allow Operation of Unit 2 W/Slightly Positive Moderator Temp Coefficient Below 100% Power
B13051, Application for Amend to License NPF-49,revising Limit for More Negative end-of-life Moderator Temp Coefficient.Fee Paid
ST-HL-AE-1715, Forwards Comments Clarifying & Correcting Answers & Questions from Senior Reactor Operator Exam Administered on 860723,for Consideration When Scoring Exams.Related Correspondence
L-2022-052, Core Operating Limits Report
3F0891-08, Application for Amend to License DPR-72,consisting of Tech Spec Change Request 191,Rev 0,relocating Negative Moderator Temp Coefficient Limit from Tech Specs to Core Operating Limits Rept Per Generic Ltr 88-16
L-2023-062, Cycle 33 Core Operating Limits Report
B14559, Application for Amend to License DPR-65,revising TS to Provide Consistency W/Proposed Changes to GL 90-06 Re Resolution of Generic Issues 70 & 94
1CAN108206, Discusses Operability of Dresser Model 31739A Pressurizer Safety in Util & Vendor Documentation.Ring Settings Should Not Cause Valve Chatter & Mechanical Damage.Analytical Models Being Developed for plant-specific Data
W3P86-3384, Forwards Response to NRC Request for Addl Info Re Part B of Cycle 2 Reload Analysis,Submitted on 861001
W3P87-0176, Responds to NRC Request for Summary of Events & Conditions Associated W/Request for Emergency Change in Tech Specs for Moderator Temp Coefficient
W3P86-0171, Forwards Response to 860329 Request for Addl Info Re 851202 Tech Spec Change Request for Monitoring Plant Operation When COLSS Out of Svc
PMNS20231101, Meeting Notice with Entergy Operations, Inc. Regarding a Presubmittal License Amendment Request for Arkansas Nuclear One, Unit 2 and Waterford Steam Electric Station, Unit 3
L-2016-198, Turkey Point, Units 3 & 4, Updated Final Safety Analysis Report, Chapter 14, Safety Analysis, Appendix 14A Thru Appendix 14G
05000313/LER-1986-007, :on 861221,pressurizer Code Safety Valves Declared Inoperable Due to Incorrect Set Pressure.No Root Cause Could Be Determined.Valves Set Pressure Adjusted to Tech Specs Requirements
05000315/LER-1985-031, :on 850709,RHR Sys Local Flow Measurements Did Not Coincide W/Process Instrumentation Installed in Safety Injection Path.Similar Discrepancy Discovered on 850715 Re RHR Cooldown Flow Indication
05000382/LER-1995-001-02, :on 950406,inability to Perform Moderator Temp Coefficient Testing Due to Movement of Main Turbine Rotor After Startup from Refuel 6 Outage & Initial Mispositioning in Thrust Bearing.Stopped All Mtc Tests
05000370/LER-1983-039-03, /03L-0:on 830809,during Unit Startup,Rod Withdrawal Limits Established to Prevent Exceeding Positive Moderator Temp Coefficient.Caused by Control Operator Failure to Follow Startup Procedure
TXX-9014, Special Rept 1-SR-90-005-00:on 900404,positive Moderator Temp Coefficient Noted During Low Physics Testing Due to High Boron Concentration in Moderator.Rod Withdrawal Limits Imposed Per Tech Spec 3.1.1.3a,Action a.1
05000328/LER-1981-152-01, /01T-0:on 811221,control Rod Withdrawal Limits Exceeded.Caused by Omission from Appropriate Startup Procedures.Withdrawal Limits Will Be Added to Appropriate Procedures Until Reliance on Action Statement Unnecessary
2CAN121901, License Amendment Request Technical Specification Deletions, Additions, and Relocations
LR-N18-0106, Core Operating Limits Report - Cycle 24
LR-N970150, Application for Amends to Licenses DPR-70 & DPR-75, Correcting Editorial & Administrative Errors in Ts,Which Existed Since Initial Issuance
LR-N970298, Forwards Description of Proposed TS Changes Identified by Pse&G Which Do Not Impact Restart or Operation of Units
05000244/LER-1995-001, :on 950203,pressurizer Safety Valves Lift Settings Found Above TS Tolerance During post-svc Test,Due to Setpoint Shifts That Resulted in Independent Trains Being Considered Inoperable
LR-N17-0101, Core Operating Limits Report, Cycle 23
LR-N15-0233, Core Operating Limits Report - Cycle 22
L-2012-115, Review Comments on Safety Evaluation Report and Technical Specifications for Amendments 247 and 243, Relocation of Cycle Specific Parameters to the Core Operating Limits Report (Colr)
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
SBK-L-05055, License Amendment Request 05-03 Exemption from the End of Life Moderator Temperature Coefficient Measurement
05000250/LER-2004-004, Regarding Plant Shutdowns Due to Drop of Shutdown Bank Rod E-11 During Low Power Physics Testing
NOC-AE-04001698, Cycle 10 End of Life Moderator Temperature Coefficient Limit Report
RA-19-0123, License Amendment Request to Eliminate Certain Technical Specification Requirements in Alignment with Improved Standard Technical Specifications
05000413/LER-1985-006, :on 850120,hot Standby Initiated After Reactor Coolant Average Temp Could Not Be Increased to Greater than 541 F 15 Minutes After Temp Decrease During Performance of Natural Circulation Verification Test
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