05000266/LER-2005-007, Regarding Control Rod Movement with Refueling Cavity Water Level Below TS 3.9.6 Limit
ONS-2017-019, Technical Specification Bases Change 2015-09
0CAN041702, Annual Radioactive Effluent Release Report for 2016
AEP-NRC-2017-30, Response to Request for Additional Information Regarding the License Amendment Request to Revise Technical Specification 3.9.3, Containment Penetrations
CNS-17-033, Technical Specification Bases Changes
NL-17-1067, Response to Request for Additional Information Regarding Alternative Source Term License Amendment Request
NL-17-1367, Response to the Second Request for Additional Information Regarding Alternative Source Term License Amendment Request
RA-16-0028, Application to Revise Technical Specifications to Adopt Multiple Technical Specification Task Force Travelers
RS-16-228, License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition
RA-16-0019, Duke Energy Progress - Application to Revise Technical Specifications to Adopt TSTF-522, Revision 0, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month Using the Consolidated Line Item Improvement Proces
NL-16-0098, Response to Request for Additional Information for Adoption of Technical Specifications Task Force Traveler 312
PNP 2017-067, Submittal of Changes to Palisades Nuclear Plant Technical Specifications Bases
LR-N15-0084, License Amendment Request Modifying Chilled Water System Requirements
MNS-15-022, Renewed Facility Operating License Nos. NPF-35 and NPF-52 Removal of Superseded Technical Specification (TS) Requirements
NOC-AE-15003265, Response to Request for Additional Information and Supplement to South Texas Project (Stp), Units 1 and 2 License Amendment Request for Emergency Action Level Scheme Change
ONS-2014-007, Emergency Plan Implementing Procedures Manual, Volume C, Revision 2014-003
NUREG-1432, Request for Additional Information, Round 3, Request to Revise Technical Specifications to Eliminate Use of the Term Core Alteration Consistent w/TSTF-471 and NUREG-1432, Rev. 3 (TAC ME8160-ME8162)
PNP 2012-097, Report to NRC of Changes to Technical Specifications Bases
NG-12-0034, Supplemental Information to an Application to Adopt Technical Specifications Task Force Traveler TSTF-425, Revision 3, to Relocate Specific Surveillance Frequencies to a Licensee Controlled Program
1CAN061101, Response to Request for Additional Information Concerning License Amendment Request, Change to Technical Specification 3.9.3, Technical Change Traveler - TSTF-312, Revision 1
W3F1-2018-0025, (Waterford 3) - Supplemental Information Supporting the License Amendment Request Regarding Proposed Change to Technical Specification 3/4.7.4 for Ultimate Heat Sink Design Basis Update
RA-18-000, Duke Energy Progress, LLC and Duke Energy Carolinas, LLC - Submittal of License Amendment Application to Remove Heaters from Ventilation System Technical Specifications
RS-16-248, Byron/Braidwood Nuclear Stations, Revision 16 to Updated Final Safety Analysis Report, Chapter 7, Instrumentation and Controls
NL-16-2280, Vogtle Electric Generating Plant, Units 1 & 2, Updated Final Safety Analysis Report, Bases for Improved Technical Specifications
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 8 of 9
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 7 of 8
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 5 of 8
NL-14-121, Indian Point, Unit 2, Updated Final Safety Analysis Report (Ufsar), Revision 25, Technical Specification Bases List of Effective Sections
RS-12-221, Braidwood, Units 1 and 2 and Byron, Units 1 and 2, Updated Final Safety Analysis Report, Revision 14, Chapter 7.0 - Instrumentation and Controls
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
1CAN081002, License Amendment Request, Changes to Technical Specification 3.9.3, Technical Change Traveler - TSTF-312, Rev. 1
L-2010-137, NAI-1396-045, Revision 2, AST Licensing Technical Report for Turkey Point Units 3 and 4
WO 10-0010, Updated Safety Analysis Report, Revision 23
W3F1-2010-0010, . Technical Specification Change Regarding Containment Building Penetrations During Refueling Operations
L-2009-258, Issuance of Amendment Regarding Spent Fuel Boraflex Remedy Supplement 4 to Request for a Change in Implementation Date
L-09-086, License Amendment Request No. 08-027, Spent Fuel Pool Rerack
RS-08-161, Braidwood, Units 1 and 2 - Technical Specification Bases
NL-08-1124, Response to Request for Additional Information License Amendment Request to Technical Specifications 3.9.3, Containment Penetrations, Personnel Air Locks Doors Open During Fuel Movement
NL-08-0517, License Amendment Request to Technical Specification 3.9.3, Containment Penetrations - Personnel Air Locks Doors Open During Fuel Movement
RNP-RA/07-0108, Transmittal of Technical Specifications Bases Revisions
L-2007-087, Proposed License Amendment, Alternative Source Term and Conforming Amendment
L-2007-085, Alternative Source Term and Conforming Amendment
NRC 2007-0034, License Amendment Request 249, Technical Specification 3.6.3, Containment Isolation Valves
NL-07-0067, License Amendment Request to Technical Specification 3.9.3, Containment Penetrations, Personnel Air Locks Doors Open During Fuel Movement
L-07-017, License Amendment Requests Nos. 334 and 205
NRC 2006-0040, License Amendment Request 246 - Deletion of Core Alterations
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
LR-N06-0309, Request for Changes to Technical Specifications Refueling Operations - Decay Time
DCL-06-050, 10 CFR 50.59 Report of Changes, Tests, and Experiments for Period January 1, 2004, Through December 31, 2005
L-06-070, Request for Notice of Enforcement Discretion Loss of Supplemental Leak Collection and Release System Filters
ULNRC-05269, Proposed Revision to Technical Specification 3.9.2 Unborated Water Source Isolation Valves and Associated Revisions to Technical Specification 3.3.9 Boron Dilution Mitigation System (Bdms) (License Amendment Request OL 1238)
ULNRC-05233, Application for Amendment to Facility Operating License NPF-30
NRC-2016-0273, Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations; Publication Date: January 3, 2017
NRC-2011-0187, Biweekly Sholly Report - Applications and Amendments to Facility Operating Licenses Involving No Significant Hazards Considerations; Fr Publication Date: 8/23/2011
NRC-2010-0309, FRN: General Notice. Biweekly Notice, Applications and Amendments to Facility Operating Licenses Involving No Significant Hazards Considerations, NRC-2010-0309
WBL-19-023, Periodic Submission for Changes Made to the WBN Technical Specification Bases and Technical Requirements Manual
0CAN041903, Submittal of Annual Radioactive Effluent Release Report for 2018
LR-N19-0047, License Amendment Request to Relocate Technical Specifications (TS) 3.9.3 and 3.9.12 to the Technical Requirements Manual (TRM)
RA-18-0282, Technical Specification Bases Changes
L-PI-05-081, License Amendment Request (LAR) to Clarify Technical Specification Requirements for Surveillance Requirements for Installed Spare Components and Miscellaneous Corrections
NRC 2005-0094, Request for Review of Heavy Load Analysis
NRC 2004-0062, Technical Specifications Bases Revisions
NRC 2003-0106, Response to RAI Regarding License Amendment Request 234, Selective Scope Implementation of Alternative Source Term for Fuel Handling Accident
L-2003-224, Proposed License Amendments Regarding Alternate Source Term and Conforming Amendments
NL-03-1740, Request to Revise Technical Specifications Containment Equipment Hatch
L-03-099, Response to a Request for Additional Information in Support of License Amendment Request No. 300 & 172
NL-03-103, Response to Request for Additional Information Regarding Section 3.7, Plant Systems, of the Improved Technical Specifications (ITS)
LR-N03-0136, Response to Request for Additional Information Re Change to Technical Specification Related to Containment Closure and Fuel Handling Ventilation
LR-N03-0086, Correction of Information Provided in Request for License Amendment
NRC 2003-0009, Request for Withdrawal of License Amendment Request 224, Control Room Habitability
NRC 2002-0108, Technical Specification Bases Revisions
NRC-02-0043, Proposed Technical Specification Change (License Amendment) - Refueling Equipment Interlocks
ULNRC-04721, Technical Specification Bases Revision 3
L-02-038, Technical Specification Bases Change Submittal
RA-20-0012, License Amendment Request to Revise Technical Specifications Related to Accident Monitoring Instrumentation, Refueling Operations Instrumentation, and Electrical Equipment Protective Devices
NRC 2002-0019, License Amendment Request 224 Control Room Habitability
WO 02-0004, Revision to Technical Specifications Re Suspension of Positive Reactivity Additions
ND-20-0122, Request for License Amendment: Main Control Room Emergency Habitability System (Ves) Pressure Regulating Valve and Source Range Neutron Flux Doubling Surveillance Changes, and Other Miscellaneous.
NLS2021015, (CNS) - Technical Specification Bases Changes
L-PI-21-032, Response to Request for Additional Information Amendment Request to Adopt TSTF-471 and 571-T for Prairie Island
3F1198-06, LAR 244,rev 0,for License DPR-72,proposing Changes to Improved TS LCO 3.9.3 to Allow Both Doors in Personnel Air Locks & Single Door in Oeh to Be Open During Refueling Operations
L-2022-000, License Amendment Request for the Technical Specifications Conversion to NUREG- 1432 Revision 5 - Request for Supplemental Information (Rsi) Response
L-2022-010, License Amendment Request for the Technical Specifications Conversion to NUREG-1431, Revision 5 -Request for Supplemental Information Response
0CAN129603, Submits Proposed TS Change Request Re Control Room Ventilation Sys
RBG-42766, Application for Amends to Licenses NPF-29 & NPF-47,adding Addl Acceptable Method of Fuel Movement,Control Rods Removed or Withdrawn from Defueled Core Cells
0CAN049501, Application for Amends to Licenses DPR-51 & NPF-6,revising TS Associated W/Control Room Ventilation Sys
LD-92-017, Forwards Response to NRC Re Addl Info for NRC Staff Review of CESSAR Design Certification
RS-14-338, Byron, Units 1 and 2, and Braidwood, Units 1 and 2, Updated Final Safety Analysis Report (Ufsar), Revision 15, Updated Fire Protection Report (Fpr), Amendment 26, Chapter 7 - Instrumentation and Controls
NL-17-0643, Response to Request for Additional Information Regarding Alternative Source Term License Amendment Request
W3F1-2010-0009, License Amendment Request to Revise the Technical Specifications Based Upon Revised Fuel Handling Accident Analysis
NRC 2003-0028, License Amendment Request 234, Selective Scope Implementation of Alternative Source Term for Fuel Handling Accident
NL-04-1746, Response to Request for Additional Information Related to Request to Revise Technical Specifications - Control Room Habitability
LR-N07-0023, Response to RAIs on LCR S06-07 Refueling Operations - Decay Time
CP-202400335, License Amendment Request to Adopt TSTF-51, TSTF-471, and TSTF-571-T to Eliminate Use of the Term Core Alterations and Revise Requirements During Handling of Irradiated Fuel
ND-19-1416, Report of 10 CFR 50.59 Changes, Tests and Experiments and 10 CFR 52 Appendix D Departure Report
NL-16-0388, Draft License Amendment Request Regarding Alternative Source Team
B17004, Application for Amend to License NPF-49,revising TS Table 3.7-6, Area Temp Monitoring & Revising FSAR to Describe Full Core off-load Condition as Normal Evolution.Proprietary Rev 2 to HI-971843,encl.Proprietary Info Withheld
NL-03-1563, TS Revision to Allow Fuel Movement with Refueling Interlock Inoperable
CPSES-200203861, License Amendment Request (LAR) 02-09 Revision to Technical Specifications Regarding Suspension of Positive Reactivity Additions
ND-22-0831, Comments on AP1000 Standard Technical Specifications (STS) – Draft NUREG-2194, Revision 1
05000315/LER-2020-001, Containment Closure Requirements Not Met During Refueling Operations
LR-N16-0055, Response to Request for Additional Information Regarding Chilled Water System Modifications
AEP-NRC-2016-65, License Amendment Request Regarding Technical Specification 3.9.3, Containment Penetrations
AEP-NRC-2016-29, Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3 and to Request an Alternative to the ASME Code
05000304/LER-1987-008-09, :on 870908,discharge Stop Valve Deenergized in Throttled Position,Rendering Valve Inoperable Contrary to Requirements of Tech Spec 3.9.3.Caused by Out of Svc Auxiliary Feedwater Discharge Stop Valve
RNP-RA/02-0118, Response to Request for Additional Information on Technical Specifications Change Re Selective Implementation of Alternative Radiological Source Term
05000311/LER-1987-001-01, :on 870113,RHR Injection Capability to Two Cold Legs Lost.Caused by Inadequate Tech Specs.Surveillance Procedure Will Be Revised to Reflect Injection Requirements
05000302/LER-1995-025, :on 951102,personnel Errors by Architect Engineer Result in Operation Outside Design Basis.Caused by Inadequate safety/non-safety Circuit Isolation.Evaluated Control Power Scheme for AHV-1A-1D
05000295/LER-1997-002-01, :on 970117,containment Isolation Valves Were Not Tested Prior to Leaving Cold Shutdown.Caused by Mgt Deficiencies in TS Implementation Process.Containment Isolation Valves Will Be Verified Tested Prior to Mode 4
05000346/LER-1996-010, :on 961212,CREV Sys Were Not Realized as Inoperable When Radiation Monitors Were Inoperable.Caused by Misinterpretation of Relationship Between Radiation Monitors & Crevs.Standing Order 96-006 Issued
05000304/LER-1988-008-03, :on 881013,isolation Valve Seal Water Tank Level Discovered to Be 13 Inches,In Violation of TS 3.9.1.B, Due to Inoperable Cv.Level Switch Cleaned & Recalibrated & Sys Returned to Svc
05000327/LER-1981-090-03, /03L-0:on 810722,during Prerelease Source Check, Liquid Radwaste Effluent Monitor Would Not Source Check. Caused by Contaminated Sample Chamber Due to Background Buildup.Chamber Replaced
L-2003-220, Proposed License Amendments Regarding Alternate Source Term and Conforming Amendments
CP-201101065, Comanche Peak Units 1 & 2 Final Safety Analysis Report (Fsar), Amendment 104, Technical Specifications Bases
0CAN042401, Radioactive Effluent Release Report for the 2023 Calendar Year
0CAN042301, Radioactive Effluent Release Report for 2022
ND-19-1129, Supplement to the Request for License Amendment Regarding Protection and Safety Monitoring System Surveillance Requirement Reduction Technical Specification .
CP-200801015, Technical Specification Bases for Comanche Peak Steam Electric Station Units 1 & 2
05000255/LER-1979-035-01, /01T-0:on 790905,during Release of Contents of Waste Gas Decay Tank T-68B,waste Gas Monitor Alarmed & Terminated Release.Caused by Personnel Error.Review Step Added to Release Form
05000250/LER-1989-021, :on 890721,discrepancies in Process Control Program Identified.Caused by Document Not Specifying That Containers Must Be Among Those Listed in Process Control Program.Operating Procedure 11550.48 Revised
05000316/LER-1997-004, Re Analysis Which Demonstrates Design Basis Impact of Inadequate Refueling Outage SE Negligible.Ler 97-004-01 Retracted
L-96-222, Application for Amends to Licenses DPR-67 & NPF-16, Requesting to Revise TS 3/4.9.9 Re Refueling Requirements & TS 3/4.9.10 Re Refueling Operations,Water level-reactor Vessel
05000244/LER-1996-006, :on 960521,discovered Containment Penetration Not in Required Status.Caused by Personnel Error.Installed Flange Inside Containment Penetration 2
05000390/LER-2015-006, Regarding Source Range Level Trip Channels (N-31 and N-32) Inoperable During Plant Startup
PNO-II-79-003, on 790923 & 25,radioactive Liquid Waste Discharges Were Made Above Max Permissible Concentration. Caused by Inadequate Dilution Water Flow,Because Keowee Hydro Units Were Out of Svc
05000323/LER-2013-002, Both Source Range Nuclear Instruments Inoperable While in Mode 6
05000482/LER-2013-003, Regarding Movement of Irradiated Fuel Progressed After Non-Conservative Decision Making Resulted in Removal of One Source Range Monitor from Service
05000482/LER-2011-005, Regarding Procedure Weakness Allowed Entry Into Mode 6 with One Source Range Monitor Inoperable
L-02-094, Technical Specifications Bases Change Submittal
CP-201300130, Comanche Peak, Units 1 & 2, Technical Specification Bases, Revision 67
L-05-015, Unit Nos. I and 2, License Amendment Request Numbers,325 and 195 Re Control Room Emergency Habitability Systems
TSTF-06-26, Submittal of TSTF-431, Revision 1, Change in Technical Specifications End States (BAW-2441)
05000313/LER-2005-001, Unit 1 Movement of Irradiated Fuel Assemblies in Reactor Building W/ Reactor Building Purge Effluent Monitor Inoperable & Purge Isolation Valves Open Resulted in Operation Prohibited by Technical
TSTF-05-07, Submittal and Request for Fee Waiver for Review of TSTF-343, Revision 1, Containment Structural Integrity
3F1002-03, License Amendment Request 272, Revision 0 Revision to Improved Technical Specifications 3.3.15 Reactor Building (RB) Purge Isolation-High Radiation, Bases 3.7.15 Spent Fuel Assembly Storage, 3.9.3 Containment Penetration,
3F0502-06, Technical Specifications Bases Control Program
L-91-008, Technical Specification Bases Change
NL-04-0213, Supplemental Information on Technical Specification Change Request for Interlocks Limiting Condition for Operation
CP-201000212, Technical Specifications Bases for Comanche Peak Steam Electric Station, Units 1 and 2
CPSES-200202892, 10CFR50.59 Evaluation Summary Report 0010 and Commitment Material Change Evaluation Report 0005
L-08-240, Improved Technical Specification Conversion License Amendment Request, Volume 14, Revision 1, ITS Section 3.9, Refueling Operations
RNP-RA/03-0061, Transmittal of TS Bases Revisions
3F0404-03, Technical Specifications Bases Control Program
LR-N08-0046, Request for Changes to Technical Specifications Refueling Operations - Decay Time, License Amendment Request (LAR) S08-01
NL-03-039, Reply to Request for Additional Information Proposed Amendment for Selective Adoption of Alternate Source Term
L-22-053, Request for an Amendment to Consolidate Fuel Decay Time Technical Specifications in a New Limiting Condition for Operation Titled Decay Time
0CAN042202, Radioactive Effluent Release Report for 2021
TSTF-04-09, TSTF-426, Revision 0, Revise or Add Actions to Preclude Entry Into LCO 3.0.3 - RITSTF Initiatives 6b & 6c
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
0CAN042102, Radioactive Effluent Release Report for 2020
L-PI-21-007, Application to Revise Technical Specifications to Adopt TSTF-471, Eliminate Use of the Term Core Alterations in Actions and Notes
NL-16-109, Indian Point 2 Improved Technical Specifications Bases
NRC 2010-0075, License Amendment Request 265 Revision to the Reactor Vessel Head Drop Methodology
RS-25-016, License Amendment Request to Adopt TSTF-286, TSTF-471, TSTF-571-T
PMNS20230863, Meeting with Vistra Operations Company LLC Proposed License Amendment Request to Relocate Refueling Operations Technical Specification 3.9.3, Nuclear Instrumentation, to the Technical Requirements Manual
L-PI-21-016, Application for License Amendment to Implement 24-Month Operating Cycle
U-602569, Application for Amend to License NPF-62,revising Listed TS to Eliminate Core Alterations as Applicable Condition for Which Associated LCO Must Be Met
05000530/LER-1998-004, Forwards LER 98-004-00 Prepared & Submitted Pursuant to 10CFR50.73.LER Reports TS Violation Due to non-compliance with TS 3.9.3 for Not Establishing Containment Penetration Isolation During Core Alterations
05000295/LER-1987-016-08, :on 871130,determined That Reactor Containment Fan Cooler Outlet Isolation Valve 1MOV-SW0009 Failed Partially Open & Inoperable.Caused by Insufficient Torque on Valve Block Bolts.Valve Block Design Changed
BSEP-93-0132, Application for Amends to Licenses DPR-71 & DPR-62, Requesting Definition of Core Alterations & Use of Terminology W/Respect to Tech Spec 3.9.3
CP-202300349, License Amendment Request (Lar) 23-004 Technical Specifications (TS) 3.9.3, Nuclear Instrumentation
NL-17-0534, Joseph M. Farley Nuclear Plant, Technical Specifications Bases
L-09-218, Submittal of Technical Specification Bases, Revision 7
PMNS20210522, NRC Public Meeting with the Pressurized Water Reactor Owners Group (PWROG) About Its Plan to Relocate Technical Specification (TS) 3.9.3, Nuclear Instrumentation, in NUREG-1431, Standard Technical Specifications Westinghouse Plants
DCL-02-049, 10 CFR 50.59 Report of Changes, Tests, and Experiments for the Period January 1, 2000, Through December 31, 2001