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
LG-17-065, Issuance of the Core Operating Limits Report (COLR) for Reload 14, Cycle 15
L-2017-091, License Amendment Request 252, Application for Technical Specifications Change Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process
RBG-47775, Revisions to the Technical Requirements Manual and the Technical Specification Bases
CNL-16-148, Application to Revise Technical Specifications to Adopt TSTF-547, Revision 1, Clarification of Rod Position Requirements (WBN-TS-16-025)
NL-16-0630, Resubmittal of Clean-Typed Pages for Multiple Technical Specifications Task Force Traveler Adoption
CNS-16-031, Technical Specification Bases Changes
1CAN021601, Cycle 26 Core Operating Limits Report, Revision 1
L-18-024, Core Operating Limits Report, Cycle 20, Revision 1
GO2-15-152, Response to Second Request for Additional Information on License Amendment Request for Adoption of Technical Specification Task Force (TSTF)-425, Revision 3
1CAN081504, Cycle 26 Core Operating Limits Report (COLR)
RBG-47567, Submittal of Nineteenth Fuel Cycle Core Operating Limits Report (COLR)
L-15-045, Core Operating Limits Report, Cycle 19, Revision 1
1CAN021501, Unit 1 - Submits Revision 0 of Cycle 26 Core Operating Limits Report
1CAN101408, Cycle 25 Core Operating Limits Report
NL-14-0635, License Amendment Request to Revise Technical Specifications Reactor Trip System Instrumentation
RNP-RA/14-0042, Transmittal of Technical Specifications Bases Revisions
L-14-107, Core Operating Limits Report, Cycle 19
RBG-47402, Eighteenth Fuel Cycle Core Operating Limits Report (Colr), Revision 1
GO2-13-138, License Amendment Request for Adoption of TSTF-493, Revision 4, Option a
1CAN081301, Unit 1, ANO-1 Cycle 25 COLR, Revision 1
1CAN061303, Cycle 25 Core Operating Limits Report
GO2-13-075, Response to Request for Additional Information Regarding License Amendment to Implement Prnm/Arts/Mellla
1CAN101202, Unit 1: Cycle 24 Core Operating Limits Report (Colr), Revision 5
1CAN081203, Cycle 24 Core Operating Limits Report (Colr), Revision 4
1CAN041201, Unit 1, ANO-1 Cycle 24 COLR, Revision 3
1CAN111103, Unit 1, ANO-1 Cycle 24 Core Operating Limits Report (Colr), Revision 1
1CAN101101, Submittal of Cycle 24 Core Operating Limits Report (COLR)
RBG-47120, Unit 1, Seventeenth Fuel Cycle Core Operating Limits Report (COLR)
TSTF-15-13, TSTF Comments on Draft Model Safety Evaluation of Traveler TSTF-547, Revision 0, Clarification of Rod Position Requirements, and Transmittal of TSTF-547, Revision 1
TSTF-14-06, Transmittal of TSTF-547, Revision 0, Clarification of Rod Position Requirements
TSTF-13-05, Transmittal of TSTF-536, Revision 0, Resolve CE Digital TS Inconsistencies Regarding CPCs and Ceacs
NL-16-2280, Vogtle Electric Generating Plant, Units 1 & 2, Updated Final Safety Analysis Report, Bases for Improved Technical Specifications
NL-18-021, Supplement to Sequoyah Nuclear Plant, Units 1 and 2 and Watts Bar Nuclear Plants, Units 1 and 2 License Amendment Request to Modify Technical Specification (TS) Surveillance Requirement 2.4, Qptr, and TS 3.3.1, 'Reactor Trip System (RTS) .
NL-17-008, Sequoyah and Watts Bar - License Amendment Request to Modify Technical Specification (TS) Surveillance Requirement 3.2.4, Qptr, and TS 3.3.1, Reactor Trip System (RTS) Instrumentation, Condition D (SQN-TS-17-02 and WBN-TS-17-014)
NL-16-109, Indian Point 2 Technical Requirements Manual
NL-15-156, Sequoyah Nuclear Plants, Units 1 and 2 - Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 3. Part 1 of 9
NL-15-128, Sequoyah Nuclear Plants, Units 1 and 2 Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 2. Part 3 of 8
NL-14-121, Indian Point, Unit 2, Updated Final Safety Analysis Report (Ufsar), Revision 25, Technical Specification Bases List of Effective Sections
05000335/LER-2078-021, For St. Lucie Unit 1, on 06/08/78 Concerning During PWR Ascension Testing Following Refueling Outage CEA 65 Dropped Four Times Due to Failure of One or More of Its Coil PWR Programmer Timing Module, Integral Timer
RS-12-221, Byron, Units 1 and 2, Updated Final Safety Analysis Report, Revision 14, Technical Requirements Manual
NL-10-107, Indian Point 2 (IP2) Nuclear Power Plant Amendment Update to the Final Safety Analysis Report (Fsar), Revision 22, Technical Requirements Manual
NL-10-107, Indian Point 2 (IP2) Nuclear Power Plant Amendment Update to the Final Safety Analysis Report (Fsar), Revision 22, Improved Technical Specifications Bases
RS-11-100, Dresden, Units 2 and 3, Updated Final Safety Analysis Report (Ufsar), Revision 9, Technical Specification Bases
RCF 10-03, Response to Request for Additional Information Regarding the Renewal of Facility Operating License
L-10-083, Core Operating Limits Report for Cycle 17
L-PI-10-052, License Amendment Request to Use Beacon Power Distribution Monitoring System
1CAN041005, Submittal of Rev. 1 to Cycle 23 Core Operating Limits Report
1CAN041001, Cycle 23 Core Operating Limits Report
RBG-46965, Submittal of Sixteenth Fuel Cycle Core Operating Limits Report
RBG-46958, Unit 1, Fifteenth Fuel Cycle Core Operating Limits Report (COLR)
RC-09-0081, Initial Operator License Examination Post Examination Submittal
L-09-072, License Amendment Request to Incorporate the Use of Alternate Methodologies for Development of Reactor Pressure Vessel Pressure-Temperature Limit Curves and Request for Exemption from Certain Requirements Contained in 10 Cfr
RS-08-161, Braidwood, Units 1 and 2 - Technical Specification Bases
1CAN110801, Cycle 22 Core Operating Limits Report (COLR)
LR-N08-0205, Clarifications to Final Safety Evaluation for Extended Power Uprate, License Amendment No. 174
L-08-228, Core Operating Limits Report, Revision 1, Supports the Implementation of License Amendment 278, Measurement Uncertainty Recapture (MUR) Power Uprate
CP-200800411, Supplement to License Amendment Request (LAR) 07-003 Response to Request for Additional Information Related to Review Associated with Large and Small Break LOCA Analyses
RBG-46792, Unit 1, Fifteenth Fuel Cycle Core Operating Limits Report (COLR)
GO2-18-102, Response to Supplemental Information Needed for Acceptance of Requested Licensing Action Re-Renewed Facility Operating License and Technical Specification Clean-Up
RNP-RA/07-0124, Request for Technical Specifications Change to Section 3.1.7 Rod Position Indication
CNL-19-051, Application to Implement the Full Spectrum LOCA (Fsloca) Methodology for Loss-of-Coolant Accident (LOCA) Analysis and New LOCA-specific Tritium Producing Burnable Absorber Rod Stress Analysis Methodology
1CAN050701, Arkansas - Unit 1 - Cycle 21 Core Operating Limits Report
CPSES-200700605, License Amendment Request (LAR) 07-003, Revision to Technical Specifications 3.1, Reactivity Control Systems, 3.2, Power Distribution Limits, 3.3, Instrumentation, & 5.6.5b, Core Operating Limits Report
L-07-010, License Amendment Request Nos. 296 and 169, Improved Standard Technical Specification Conversion, Draft Amendment and Safety Evaluation Comments
JAFP-06-0180, Core Operating Limits Report, Revision 22
ULNRC-05322, Application for Amendment to License No. NPF-30, Relocation of Technical Specification Cycle-Specific Parameters to the Core Operating Limits Report Adoption of Industry Travelers TSTS-339 and TSTS-363
ULNRC-05297, Proposed Revision to Technical Specifications for Use of Beacon Power Distribution Monitoring System
RBG-46568, Thirteenth Fuel Cycle Core Operating Limits Report
JAFP-05-0187, Core Operating Limits Report Revisions 19 & 20 (Cycle 17 Update)
1CAN121804, Core Operating Limits Report (COLR) Cycle 28 COLR, Revision 2
CNRO-2019-00009, Stations - Application to Revise Technical Specifications to Adopt TSTF-564, Safety Limit MCPR, Revision 2
WBL-19-023, Periodic Submission for Changes Made to the WBN Technical Specification Bases and Technical Requirements Manual
L-19-162, Submittal of Core Operating Limits Report, Cycle 21, Revision 1
L-19-245, Core Operating Limits Report, Cycle 21, Revision 2
1CAN120503, Unit 1, Cycle 20 Core Operating Limits Report (COLR) Per Technical Specification 5.6.5
JAFP-05-0125, Core Operating Limits Report Revisions 17 & 18 (Cycle 17 Updates)
L-2005-007, Proposed License Amendment Third Request for Additional Information Supplement WCAP-9272 Reload Methodology and WCAP-9272 Reload Methodology and Implementing 30% Steam Generator Tube Plugging Limit
CPSES-200500155, License Amendment Request (LAR) 04-015 Revision to Technical Specification 3.3.1 Reactor Trip System Instrumentation and 3.3.2 Engineered Safety Feature Actuation System Instrumentation (Esffas)
JAFP-05-0039, Core Operating Limits Report, Revision 16 (Cycle 17 Update)
L-PI-19-041, Application to Revise Technical Specifications to Adopt TSTF-547, Clarification of Rod Position Requirements
L-PI-20-001, License Amendment Request to Address Issues Identified in Westinghouse Nuclear Safety Advisory Letter NSAL-09-5, Revision 1, and NSAL-15-1
ND-18-0067, Request for License Amendment: Fuel Management Related Technical Specifications (LAR-18-005)
2CAN099304, Application for Amend to License NPF-6,revising LCO for Unit 2 Incore Detection Sys Re TS 3.3.3.2
3F1109-10, Core Operating Limits Report, Cycle 17, Revision 0
ET 09-0019, Proposed Revision to Technical Specifications for Use of Beacon Power Distribution Monitoring System
3F1208-03, Core Operating Limits Report, Cycle 16, Revision 3
CNL-19-115, Non-Voluntary License Amendment Request to Modify Watts Bar Nuclear Plant Units 1 and 2 Technical Specifications 3.2.1, Fq(Z), to Implement Methodology from WCAP-17661, Revision 1, Improved RAOC and CAOC Fq Surveillance Technical Specific
L-20-063, Submittal of Core Operating Limits Report, Cycle 21, Revision 3
3F0108-15, Core Operating Limits Report, Cycle 16, Revision 2
3F1107-07, Core Operating Limits Report, Cycle 16, Revision 0 and Revision 1
3F1007-14, Core Operating Limits Report, Cycle 15, Revision 2
3F1205-05, Core Operating Limits Report, Cycle 15, Revision 0 and Revision 1
3F0905-01, Core Operating Limits Report, Cycle 14, Revision 3
3F0605-06, Core Operating Limits Report (Colr), Cycle 14, Revision 2
GNRO-2004/00061, Application for Technical Specification Improvement to Eliminate Requirements to Provide Monthly Operating Reports and Occupational Radiation Exposure Reports
L-2004-287, Proposed License Amendment Second Request for Additional Information Response WCAP-9272 Reload Methodology and Implementing 30% Steam Generator Tube Plugging Limit
JAFP-04-0172, Core Operating Limits Report, Revision 15 (Cycle 17 Update)
RS-04-160, Request for Amendment to Technical Specifications to Eliminate Requirements to Provide Monthly Operating Reports and Annual Occupational Radiation Exposure Reports
WO 04-0042, Supplemental Information for Revision to Technical Specification 3.3.1, Reactor Trip System Instrumentation, and Technical Specification 3.3.2, Engineered Safety Feature Actuation System Instrumentation
L-04-124, License Amendment Request Nos. 318 and 191
NOC-AE-04001792, Withdrawal of Proposed Changes to Loss of Power Instrumentation and AC Sources Technical Specifications
L-2004-193, Proposed License Amendment Request for Additional Information Response WCAP-9272 Reload Methodology and Implementing 30% Steam Generator Tube Plugging Limit
CPSES-200400149, License Amendment Request (LAR) 03-08 Common Stars License Amendment Implementation of WCAP-14333 and WCAP-15376 RTS and ESFAS Test Times, Completion Times, and Surveillance Test Intervals
ULNRC-04929, Common Stars License Amendment Regarding Implementation of WCAP-14333 and WCAP-15379, RTS and ESFAS Test Times, Completion Times, and Surveillance Test Intervals
3F1003-13, Core Operating Limits Report, Cycle 14, Revision 0 and Revision 1
RBG-46184, Twelfth Fuel Cycle Core Operating Limits Report (COLR)
3F1003-04, Core Operating Limits Report, Cycle 13, Revision 2
DCL-03-118, License Amendment Request 03-13 Application for Technical Specification Change Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process
L-PI-03-042, Supplement to License Amendment Request (LAR) Dated 03/25/2003, Safety Analyses Transition
NL-03-1140, Changes to Technical Specification Bases
RS-20-010, Application to Revise Technical Specifications 5.6.5, Core Operating Limits Report (COLR)
L-03-020, License Amendment Request Nos. 303 and 174
L-2005-154, Response to Request for Additional Information Regarding Proposed License Amendment for the Adoption of TSTF-95
NRC 2002-0108, Technical Specification Bases Revisions
JAFP-02-0193, Core Operating Limits Report Revision 13 (Cycle 15 Update)
3F0902-09, Submittal of Core Operating Limits Report, Cycle 13, Revision 1, for Crystal River Unit 3
GNRO-2002/00030, License Amendment Request, Corrections and Clarifications to Certain Requirerments and Information
1CAN070203, Submittal of Revision to Arkansas Nuclear One, Unit 1 Core Operating Limits Report
SVP-02-041, Core Operating Limits Report Revision for Cycle 17A
SVP-02-008, Core Operating Limits Report for Cycle 17A
L-20-085, Core Operating Limits Report, Cycle 22, Revision 0
L-20-151, License Amendment Request to Correct Non-conservative Technical Specifications 3.2 .1, Heat Flux Hot Channel Factor Fa(Z) and 5.6.3, Core Operating Limits Report (COLR)
RBG-48078, Core Operating Limits Report (COLR) - Cycle 22, Revision 0
1CAN042101, Cycle 30 Core Operating Limits Report (COLR)
W3F1-2021-0032, Revised License Amendment Request - Digital Upgrade to the Core Protection Calculator (CPC) System and Control Element Assembly Calculator (Ceac) System
RBG-44133, Provides Util Proposed Administrative Controls to Be Issued as Part of Plant Amend Request 96-23 Re Change to Tech Specs Concerning Reactivity Anomalies,Aprm Setpoints & RPS Instrumentation
NSD-NRC-96-4833, Forwards Roadmap for Content of AP600 Tech Specs Vs NUREG-1431 & Description of General or Overall Changes Whose Explanations Apply to Multiple TS
B17621, Application for Amend to License DPR-21,reflecting Permanently Defueled Condition of Unit 1,Tech Specs Administrative Controls Section as Allowed by Guidance Contained in NRC Administrative Ltr 95-06
RBG-44593, Application for Amend to License NPF-47,implementing BWROG Enhanced Option I-A Reactor Stability Long Term Solution as Documented in NEDO-32339,Rev 1, Reactor Stability Long-Term Solution,Enhanced Option I-A
2CAN088501, Application for Amend to License NPF-6,revising Tech Specs to Modify Core Protection Calculator Sys Response to Eliminate Unnecessary Reactor Trips Due to Control Element Assembly Inward Deviation Events.Fee Paid
RBG-43608, Application for Amend to License NPF-47,to Enhance Operation of Plant,Thereby Yielding Economic Benefit to RBS Through Extended Power production.NEDC-32611P Encl.Rept Withheld
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
LG-22-040, Issuance of the Core Operating Limits Report (COLR) for Unit 1 Reload 19, Cycle 20
L-22-047, Unit No.1 - Core Operating Limits Report, Cycle 23, Revision O and Revision 1
RBG-43161, Application for Amend to License NPF-47 Revising TS Re Engineered Safety Systems Which Address Core Reactivity & Power
3F1291-07, Requests Temporary Waiver of Compliance W/Ts 3.0.4 Re LCO 3.2.4 Re Quadrant Power Tilt,Per Guidance in Generic Ltr 87-09
3F1291-08, Tech Spec Change Request 193 to License DPR-72,changing Quadrant Power Tilt Spec 3.2.4 to Provide Exclusion for Spec 3.0.4 to Reflect steady-state Limits in Excess of 7% at 15% Full Power
3F1291-09, Requests Temporary Waiver of Compliance from TS 3.0.4 as Applies to TS 3.2.4 Quadrant Power Tilt. Plant Restricted from Ascending Power Above 15% Rated Thermal Power W/Tilt Condition Present,Per Generic Ltr 87-09
3F1191-12, Requests Temporary Waiver of Compliance from TS 3.0.4, Quadrant Power Tilt to Permit Unlimited Continued Plant Operation in Mode 1 W/Power Level Restricted to Less than 60% Rated Thermal Power,Per Generic Ltr 87-09
2CAN098311, Forwards Nonproprietary & Proprietary Responses to 830802 Telcon Request for Addl Info Re Proposed Tech Spec Change Concerning in-core Detectors.Affidavit Encl.Proprietary Rept Withheld (Ref 10CFR2.790)
L-94-025, Ter,Audit of Plant Specific License Conversion to STS: Crystal River Unit 3
NRC 2022-0025, License Amendment Request 295, Beacon Power Distribution Monitoring System
AECM-82-574, Forwards Balance of Info to Close Humphrey Containment Concerns,Including Evaluation Rept on Modified SOLA-VOF Code & Survey of Tests & Analyses on Effectiveness of RHR Sys in Pool-Cooling Mode & Proprietary Figures 18 - 25
RBG-48226, Core Operating Limits Report (COLR) - Cycle 23, Revision 0
W3P87-2304, Application for Amend to License NPF-38,revising Linear Heat Rate & DNBR Margin Action Statements in Effect When Core Operating Limits Supervisory Sys Out of Svc.Fee Paid
LD-93-159, Forwards Matl Closing follow-on Questions to Dser Responses Re Sys 80+ Info.Matl Includes Vulnerability Analysis Rept & Emergency Guidelines for Standard Recovery Actions
NL-24-0238, RIPE License Amendment Request to Change Containment Air Temperature Actions, Supplemental Information
L-2024-070, Cycle 32 Core Operating Limits Report
L-08-317, Core Operating Limits, and Pressure and Temperature Limits Report
CNL-19-084, Second Supplement to Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program.
DCL-03-069, License Amendment Request 03-09, Revision of TS 3.1.7, Rod Position Indication 3.2.1, Heat Flux Hot Channel Factor, 3.2.4, Quadrant Power Tilt Ratio, & 3.3.1, Reactor Trip System Instrumentation for Beacon Implementation
2CAN019107, Application for Amend to License NPF-6,revising TS 3.2.1 & 3.2.4 to Increase Time Limit That Core Operating Limit Supervisory Sys May Be Out of Svc Before Action Requirements Apply
L-05-009, License Amendment Request Nos. 310 and 182
1CAN101902, Cycle 29 Core Operating Limits Report (COLR)
RBG-46938, Fifteenth Fuel Cycle Core Operating Limits Report (COLR)
1CAN102203, Cycle 31 Core Operating Limits Report
WO 03-0059, Application for Amendment for Revision to Technical Specification 3.3.1, Reactor Trip System Instrumentation, and Technical Specification 3.3.2, Engineered Safety Feature Actuation System Instrumentation (Common Stars License Amendment.)
SVP-02-064, Core Operating Limits Report for Cycle 17A
JAFP-02-0200, Core Operating Limits Report Revision 14 (Cycle 16)
DCL-04-153, Supplement to License Amendment Request 03-17, Common Stars License Amendment Implementation of WCAP-14333 and WCAP-15376, RTS and ESFAS Test Times, Completion Times, and Surveillance Test Intervals
NL-23-0152, License Amendment Request: Technical Specification Revision to Adopt TSTF-339-A, Relocate Technical Specification Parameters to the COLR Consistent with WCAP-14483
L-2024-140, Cycle 28 Core Operating Limits Report
LG-24-040, Unit - Issuance of the Core Operating Limits Report (COLR) for Unit 1 Reload 20, Cycle 21
RBG-44968, Submits Addl Info Re 981008 LAR 1998-02 Re Implementation of Bwrog/Ge Enhanced Option I-A (EI-A) Reactor Stability long- Term Solution.Clarifies Certain Aspects of Proposed Ts,Per 990406 Telcon with NRC
RC-96-0076, Application for Amend to License NPF-12,consisting of Change Request 95-03,enhancing LCO & SRs & Revises Bases for QPTR
NOC-AE-030014, Proposed Change to Loss of Power and AC Sources Technical Specifications
1CAN052401, Cycle 32 Core Operating Limits Report
RBG-46102, Unit 1, Twelfth Fuel Cycle Core Operating Limits Report (COLR)
NL-05-0233, Request to Revise Technical Specifications to Delete Reactor Trip System, Function 11. Reactor Coolant Pump Breaker Position
RBG-48264, Core Operating Limits Report (COLR) - Cycle 23, Revision 1
L-2005-008, Proposed License Amendment Adoption of Improved Standard Technical Specification (ISTS) Travelers
LG-23-040, Issuance of the Core Operating Limits Report (COLR) for Unit 2 Reload 17, Cycle 18
DCL-04-013, License Amendment Request 03-17, Common Stars Amendment, Implementation of WCAP-14333 and WCAP-15376, RTS and ESFAS Test Times, Completion Times, and Surveillance Test Intervals
CNL-17-008, License Amendment Request to Modify Technical Specification (TS) Surveillance Requirement 3.2.4, QPTR, and TS 3.3.1, Reactor Trip System (RTS) Instrumentation, Condition D (SQN-TS-17-02 and WBN-TS-17-014)
DCL-04-178, License Amendment Request 04-09, Relocation of Technical Specification Cycle Specific Parameters to the Core Operating Limits Report
CNL-17-123, Supplement to Application to Revise Technical Specifications to Adopt TSTF-547, Revision 1, Clarification of Rod Position Requirements (WBN-TS-16-025)
DCL-02-097, License Amendment Request 02-05, Revision to Technical Specification Table 3.3.1-1, Reactor Trip System Instrumentation, & Revised Reactor Coolant System Flow Measurement
05000323/LER-1986-013, :on 860418,limiting Condition for Operation & Action Statement 2.C of Tech Spec 3.3.1,Table 3.3-1 Not Met When Quadrant Power Tilt Ratio Determination Could Not Be Performed in Time
05000336/LER-1988-009-01, :on 880607,CEA Dropped Into Core.Caused by Upper Gripper Coil Failure from Overheating Condition Resulting in Degraded Coil Insulation.Total of 60 Coils Either Replaced or New Coil Stack Installed
05000412/LER-1996-009-01, :on 961220,determined That Missed Surveillance Test of Manual Calculation of Quandrant Power Tilt Ration (QPTR) Occurred.Caused by Inadequate Procedures.Qptr Calculation Performed & Procedures Revised
05000368/LER-1985-012, :on 850617,core Operating Limits Supervisory Sys (COLSS) Declared Inoperable Due to Error in Calculation of DNBR Power Operating Limit.Caused by Input Error During Cycle 5 COLSS Update.Coding Error Corrected
05000425/LER-1996-003-02, :on 960707,RO Failed to Perform Quadrant Power Tilt Ratio Calculation.Caused by Cognitive Personnel Error. Personnel Involved Has Been Counseled.Event Will Be Discussed in Next Session of Training
NL-03-2451, Request for Surveillance Test Interval Extensions for Components of the Reactor Protection System
05000302/LER-1991-017, :on 911202,quadrant Power Tilt Exceeded Steady State Limit in TS & Reactor Tripped on High Pressure.Caused by Incorrect Operator Training & Lack of Cautions in Procedure.Lesson Plan Revised
05000302/LER-1991-016, :on 911125,loss of Intergrated Control Sys Power Experienced.Cause Unfounded.Control of Feedwater Sys Regained
05000395/LER-1983-144-03, /03L-0:on 831223,during Normal Operation,Erratic Behavior from Power Range Nuclear Instrument NI-42 Necessitated Quadrant Power Tilt Ratio Measurement.Cause Unknown.Bistables Placed in Trip
05000361/LER-1983-121-03, /03L-0:on 830927,calculations Indicated That DNBR Margin Not within Allowable Limits.Cause Unknown.Acceptable DNBR Margin Verified within 15 Minutes by Restoring Core Operating Limit Supervisory Sys
05000361/LER-1983-131-03, /03L-0:on 831001,DNBR Margin Noted Not within Tech Spec Limits.Caused by Inherent Conservatism in Procedure SO23-3-3.b Causing DNBR to Be Outside Limits During Small Power Changes.No Corrective Actions Planned
05000361/LER-1983-129-03, /03L-0:on 831016,calculations Indicated That DNBR Margin Not within Allowable Limits.Cause & Corrective Action to Prevent Recurrence Under Review.Dnbr Margin Verified within 1 H by Restoring Core Limit
05000362/LER-1983-106-03, /03L-0:on 831117,Surveillance Test 5023-3-3.6 Indicated That DNBR Margin Not within Allowable Limits. Caused by Conservatism Inherent in Procedure.Acceptable DNBR Margin Verified within 1 H
05000361/LER-1983-116-03, /03L-0:on 830823,0902,04 & 08,calculations Indicated DNBR Margin Not within Limits.Acceptable Margin Verified within 15 Minutes by Restoring Core Operating Limit Supervisory Sys to Svc
05000362/LER-1983-118-03, /03L-0:on 831229,DNBR Outside Allowable Limits. Caused by Core Operating Limit Supervisory Sys Being Out of Svc.Sys Returned to Svc
05000346/LER-1983-014-03, /03L-0:on 830305,rod 12 of Group 7 Began to Ratchet Trip Into Core.Caused by Blown Fuse in Transfer Switch Module Assembly B Phase.Blown Fuse Replaced.Control Rod 7-12 Successfully Latched & Pulled
05000321/LER-1982-065-03, /03L-0:on 820730,reactor Vessel Level Instrumentation Switch 2,contributing to Actuation Logic of Automatic Depressurization Sys,Found Inoperable During Surveillance Test.Caused by Fouled Contact on Switch
05000302/LER-1978-048-03, /03L-0:on 780918.quadrant Power Tilt Exceeded Transient Limit But Not Max Limit.Caused by Uncoupling of Group 5,rod 1.CRD Test Procedure Revised
05000382/LER-1993-011-02, :on 931220,determined That Two of Three Lea Position Indications Inoperable Since 931219 Due to Weak man-machine Interface.Enhancement to Plant Monitoring Computer CEA Processing Will Be Made
05000346/LER-1982-011-03, /03L-0:on 820225,while Performing Control Rod Exercising Test,Control Rod 5-2 Dropped to 0% Withdrawn. Caused by Blown Fuse in Transfer Switch Module Assembly B Phase.Blown Fuse Replaced
05000370/LER-1990-004-03, :on 900213,reactor Power Mismatch Exceeded Tech Spec Interpretation Requirement for Power Maneuvers After 50 % Main Turbine Runback Occurrence.Caused by Design Deficiency.Design Study Performed
05000346/LER-1983-024-03, /03L-0:on 830511,while Starting Up from 830510 Reactor Trip,Quadrant Power Tilt in Quadrant Yz Exceeded Tech Spec steady-state Limit.Caused by Inherent Design of B&W NSSS & Negative Moderator Temp Coefficient
05000302/LER-1981-040-03, /03L-0:on 810627,during Power Escalation Following Reactor Startup,Quadrant Power Tilt Exceeded Tech Spec Steady State Limit.Cause Attributed to Xenon Transient Following Earlier Reactor Trip & Plant Startup
GO2-12-017, License Amendment Request to Change Technical Specification in Support of Prnm/Arts/Mellla Implementation
05000325/LER-1980-086-03, /03L-0:on 801207,during Testing,Linear Heat Generation Rate Found at 13.359 kW/ft.OD-1 Performed & Rate Exceeded Limit.Apparently Caused by Low Power Range Monitor D Drifting W/Inlet Subcooling
RS-16-248, Braidwood Nuclear Stations, Revision 16 to Updated Final Safety Analysis Report, Technical Requirements Manual
CP-201101065, Comanche Peak Units 1 & 2 Final Safety Analysis Report (Fsar), Amendment 104, Technical Specifications Bases
05000346/LER-1978-014-03, /03L-0:on 780123,quandrant Power Tilt in Excess of Steady State & Transient Limits Indicated by Unit Process Computer.Caused by Detector Inadvertently Left Off Scan After Testing.Test Procedure Being Modified
05000309/LER-1979-030-99, /99X-0:on 791105,reactor Coolant Dose Equivalent Iodine Exceeded Tech Spec Limit.Caused by Unscheduled Plant Trip.Monitoring Program Established to Follow Iodine Trends
05000302/LER-1978-074-03, /03L-0 on 781229:noted That During Heat Balance Calculation surveillance(SP-312)an Excessive Quadrant Power Tilt Existed.Caused by Improper Selection of Temp Channel for Delta T Cold Control
CP-202200355, Application to Revise Technical Specifications to Apply the Westinghouse Full Spectrum Loss of Coolant Accident Evaluation Model LAR 22-002
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
CP-200801015, Technical Specification Bases for Comanche Peak Steam Electric Station Units 1 & 2
05000324/LER-1979-092-03, /03L-1:on 791214,after Performing OD-1,found Fuel Bundles 9-26 & 43-28 Exceeded Linear Generation Rate.Caused by Approaching Limit with One Transient in-core Probe Not Available.Power Increases to Be Halted at 5%
05000338/LER-1979-079-03, /03L-0 on 790608:quadrant Power Tilt Ratio of 1.0292 in Upper Core & 1.0285 in Lower Core Obtained from ex-core Detector Current Calculations.Figures Exceed Tech Spec Limits.Cause Unknown.Investigation Initiated
05000325/LER-1979-022-03, /03L-0 on 790723:linear Heat Generation Rate Found to Be 0.29 Kw/Ft Above Limit During Daily Core Parameter Check After Reaching 99% Power.Caused by Faulty Computer Reading.After Evaluation 1-3% Power Derate Imposed
05000272/LER-2078-016-03, Excessive Tilt Ratio of Quadrant Power
05000272/LER-2078-041-03, Excessive Quadrant Power Tilt Ratio During Power Escalation
05000272/LER-2078-011-03, Inadequate Air Flow Through No. 11 HEPA Train
05000272/LER-2078-043-03, LER 1978 for Reportable Occurrence 78-43/03L on Quadrant Power Tilt Ratio Greater than 1.02
05000272/LER-2078-017-03, Tilt Ratio During Power Escalation
05000335/LER-2078-020, For St. Lucie Unit 1, on 06/07/78 Concerning Pwer Ascension Physics Testing Following a Refueling Outage, CEA 65 Dropped
LG-18-057, Issuance of the Core Operating Limits Report (Cola) for Unit 1 Reload 17, Cycle 18
CNL-18-021, Supplement to Sequoyah Nuclear Plant, Units 1 and 2 and Watts Bar Nuclear Plants, Units 1 and 2 License Amendment Request to Modify Technical Specification (TS) Surveillance Requirement 2.4, QPTR, and TS 3.3.1, Reactor Trip System (RTS) .
L-87-540, Forwards Summary of mgt-on-shift Repts,Per NRC 871019 Order
05000316/LER-1987-014-01, :on 871215,programming Error Causing Alarm to Be Inoperable,Discovered.Caused by Personnel Error.Computer Operators Counseled in Proper Method of Computer Software Troubleshooting & Program Installation
GO2-97-197, Informs NRC of Change to Plant Reactor Stability Long Term Solution from Option I-A to Option III & to Provide Update to Implementation Schedule
L-17-223, Application to Revise Technical Specifications to Adopt TSTF-547-A, Revision 1, Clarification of Rod Position Requirements
L-89-304, Cycle 5 Startup Physics Testing Rept. W/
TSTF-17-09, TSTF Comments on Draft Safety Evaluation for Traveler TSTF-546, Revision 0, Revise APRM Channel Adjustment Surveillance Requirement
LG-16-074, Issuance of a Revision to the Core Operating Limits Report (Cola) for Reload 13, Cycle 14
LG-16-049, Issuance of the Core Operating Limits Report (COLR) for Reload 16, Cycle 17
TSTF-15-06, Transmittal of TSTF-546, Revision 0, Revise APRM Channel Adjustment Surveillance Requirement
LG-15-067, Issuance of the Core Operating Limits Report (COLR) for Reload 13, Cycle 14
05000530/LER-2013-002, Condition Prohibited by Technical Specifications During Dropped Control Element Assembly Recovery
3F0913-02, License Amendment Request 313, Revision 1, Revision to Improved Technical Specifications Administrative Controls for Permanently Defueled Conditions and Response to Requests for Additional Information
DCL-12-002, Revision to the Updated Final Safety Analysis Report Section 4.3.2.2, Power Distribution; and Technical Specification Bases 3.1.7, Rod Position Indication; 3.2.1, Heat Flux Hot Channel Factor (Fo(Z)),3.2.2,.
RS-17-058, License Amendment Request to Incorporate Changes Supported by TSTF-547, Clarification of Rod Position Requirements
L-02-094, Technical Specifications Bases Change Submittal
CP-201300130, Comanche Peak, Units 1 & 2, Technical Specification Bases, Revision 67
NL-20-0170, Non-Voluntary License Amendment Request: Technical Specification Revision to Adopt WCAP-17661-P-A, Improved RAOC
3F0209-05, License Amendment Request 307, Revision 0, Methodology for Rod Ejection Accident Analysis Under Extended Power Uprate Conditions
DCL-06-136, License Amendment Request 06-05 Revision to Technical Specification 3.4.1, Reactor Coolant System Pressure, Temperature, and Flow Departure from Nucleate Boiling Limits, and Technical Specification 5.6.5, Core Operating..
CPSES-200402744, Request for Additional Information to License Amendment Request 03-008: Common Stars License Amendment, Implementation of WCAP-14333 and WCAP-I5376 RTS and ESFAS Test Times, Completion Times & Surveillance Test
TSTF-04-04, TSTF-467, Revision 0, Add Restriction for Lowest Loop T(Ave) During Mode 2 Physics Testing
B18835, Response to Request for Additional Information Re TS Change Request 2-15-02
JAFP-02-0139, Core Operating Limits Report, Revision 12 (Cycle 15 Update)
NUREG-1433, Part 1- Edwin I. Hatch, Units 1 & 2, License Amendments, Replace Current Technical Specification & Associated Bases
RBG-45910, License Amendment Request 2002-01 Re Reporting Requirements for Operating License Condition Violations and Monthly Operating Reports
LG-18-041, Issuance of a Revision to the Core Operating Limits Report (Cola) for Unit 2 Reload 14, Cycle 15
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
CP-201000212, Technical Specifications Bases for Comanche Peak Steam Electric Station, Units 1 and 2
3F0404-03, Technical Specifications Bases Control Program
RS-24-043, Application to Remove Power Distribution Monitoring System (Pdms) Details from Technical Specifications
DCL-18-100, License Amendment Request 18-02 - License Amendment Request to Revise Technical Specification 5.6.5b1 Core Operating Limits Report (COLR) for Full Spectrum Loss-of-Coolant Accident Methodology
DCL-15-047, License Amendment Request 15-02 Revision of Updated Final Safety Analysis Report for Beacon Power Distribution Monitoring System Methodology and Technical Specification 5.6.5. Core Operating Limits Report (Colr), For.
RBG-46129, Revision to License Amendment Request (LAR) 2002-01, Reporting Requirements for Operating License Condition Violations and Monthly Operating Reports
RA-23-0079, Cycle 29, Revision 0, Core Operating Limits Report (COLR)
NL-02-160, Response to Request for Additional Information Regarding Sections 1.0, 2.0, 3.0, 3.1, 3.2, 3.3, 3.4, 3.5, 3.6, 3.7, 3.9, 4.0, & 5.0 of Improved TS
ULNRC-05087, Common Stars License Amendment Implementation of WCAP-14333 and WCAP-15376 RTS and ESFAS Test Times, Completion Times, and Surveillance Test Intervals
NL-21-0042, Units 1 and 2, Vogtle Electric Generating Plant - Units 1 and 2, Voluntary License Amendment Request to Use Beacon Power Distribution Monitoring System
LG-25-001, Core Operating Limits Report for Limerick Generating Station, Unit 1, Reload 20, Cycle 21
DCL-24-111, License Amendment Request 24-05 Revision to Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times – RITSTF Initiative 4b for TS 3.3.1 and 3.3.2
NL-16-109, Indian Point 2 Improved Technical Specifications Bases
RBG-48350, State Core Operating Limits Report (COLR) - Cycle 24, Revision 0
3F0603-02, Renewal of the Crystal River Units 1, 2 & 3 Industrial Wastewater Permit FL0000159
CNL-21-010, Correction of Application to Implement the Full Spectrum LOCA (Fsloca) Methodology for Loss-of-Coolant Accident (LOCA) Analysis and New LOCA-specific Tritium Producing Burnable Absorber Rod Stress Analysis Methodology (WBN-TS-19-04) (EPID
1CAN062102, Cycle 30 Core Operating Limits Report (COLR) Revision 1
RBG-48110, Core Operating Limits Report (COLR) - Cycle 22, Revision 1
TXX-9400, Proposed Tech Specs Replacing Existing Spec & Bases Re QPTR W/Spec & Bases Consistent W/Improved Stds TS for Westinghouse Plants (NUREG-1431)
05000309/LER-1979-029-99, /99X-0:on 791025,during Routine Shutdown Operations for Repair of Leaking Valve,Reactor Coolant Dose Equivalent Iodine Exceeded Tech Specs.Caused by Minor Fuel Cladding Degradation
1CAN111104, Unit 1, ANO-1 Cycle 24 Core Operating Limits Report (Colr), Revision 2
NL-17-0534, Joseph M. Farley Nuclear Plant, Technical Specifications Bases
RBG-46358, Thirteenth Fuel Cycle Core Operating Limits Report (COLR)
LG-25-083, Issuance of the Core Operating Limits Report (COLR) for Unit 2 Reload 18, Cycle 19
PMNS20240862, Notice of NRC Public Meeting on Requests for Additional Information for PWROG-22021 Revision 0, Justifications for the Proposed Changes to the Technical Specification (TS) 3.2.4, Quadrant Power Tilt Ratio (QPTR)
PMNS20230944, Closed Pre-submittal Meeting to Discuss PWROG-22021-P Revision 0, Justifications for the Proposed Changes to the Technical Specification (TS) 3.2.4, Quadrant Power Tilt Ratio (Qptr),
PMNS20220718, Closed Pre-Submittal Meeting on Topical Report Associated with Updates for Technical Specification 3.2.4, Quadrant Power Tilt Ratio in NUREG-1431
NL-14-121, Indian Point, Unit 2, Updated Final Safety Analysis Report (Ufsar), Revision 25, Technical Requirements Manual
L-09-225, Supplemental Information Related to a License Amendment Request to Incorporate the Use of Alternate Methodologies for the Development of Reactor Pressure Vessel Pressure-Temperature Limit Curves, and Request for Exemption from