05000278/LER-2004-002, Loss of High Pressure Coolant Injection System Automatic High Level Trip as a Result as a Result of Lifted Lead
NRC-17-0010, License Amendment Request to Revise Technical Specifications for Emergency Core Cooling System Instrumentation and Reactor Core Isolation Cooling System Instrumentation
NG-17-0086, Transmittal of Revision 24 of the DAEC Updated Final Safety Analysis Report and the Current DAEC Technical Specifications Bases
NLS2017033, Technical Specification Bases Changes
NRC-17-0036, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications for Emergency Core Cooling System Instrumentation and Reactor Core Isolation Cooling System Instrumentation
NLS2017048, Submittal of Application to Revise Technical Specifications to Adopt TSTF-542, Revision 2, Reactor Pressure Vessel Water Inventory Control
L-MT-17-058, Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control
NMP2L2634, Emergency License Amendment Request - Proposed Changes to the High Pressure Core Spray System and Reactor Core Isolation Cooling System Actuation Instrumentation Technical Specifications
RS-16-228, License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition
CNL-16-133, Response to NRC Request for Additional Information Related to License Amendment Request for Adding New Specifications to Technical Specification 3.3.8.3 (BFN-TS-486) (CAC Nos. MF6738, MF6739, and MF6740) - Letter 7
CNL-16-092, Response to NRC Request for Additional Information Related to License Amendment Request for Adding New Specifications to Technical Specification 3.3.8.3 (BFN-TS-486) (CAC Nos. MF6738, MF6739, and MF6740)- Letter 5
GO2-16-087, License Amendment Request for Changes to Technical Specification 2.1.1, Reactor Core SLs
GO2-16-086, Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3
NRC-16-0036, License Amendment Request to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing, Using the Consolidated Line Item Improvement Pro
CNL-16-066, Response to NRC Request for Additional Information Related to License Amendment Request for Adding New Specifications to Technical Specification 3.3.8.3 (BFN-TS-486) - Letter 1
NG-16-0080, Response to Request for Additional Information, License Amendment Request (TSCR-153) to Reduce the Reactor Steam Dome Pressure Specified in the Reactor Core Safety Limits
RBG-47801, Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control
RS-17-145, Supplement to Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control
NG-15-0048, License Amendment Request (TSCR-153) to Reduce the Reactor Steam Dome Pressure Specified in the Reactor Core Safety Limits
NLS2015055, Correction to License Amendment Request to Revise Technical Specifications to Add Residual Heat Removal System Containment Spray Function
NLS2014087, License Amendment Request to Revise Technical Specifications to Add Residual Heat Removal System Containment Spray Function
GO2-14-164, Response to NRC Request for Additional Information Re License Amendment Request for Adoption of TSTF-493, Revision 4, Option a
GNRO-2014/00058, Letter GNRO-2012/00146, Technical Requirements Manual and Technical Specification Bases Update (ML12361A330)
NLS2014035, License Amendment Request to Eliminate Requirements for Post Accident Sampling System for Boiling Water Reactors Using the Consolidated Line Item Improvement Process
GO2-14-103, Proposed Revision to License Amendment Request to Adopt TSTF-493, Revision 4, Option a, and Response to Request for Additional Information
PLA-7125, Response to Request for Additional Information on Change to Technical Specification Surveillance Requirement 3.5.1.12
PLA-6977, Proposed Amendment No. 313 to License NPF-14 and Proposed Amendment No. 285 to License NPF-22: Change to Technical Specification Surveillance Requirement (SR) 3.5.1.12
NL-13-0214, Southern Nuclear Operating Companys Overall Integrated Plan in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events
L-MT-13-019, Calculation 03-036, Revision 1, Instrument Setpoint Calculation - Reactor Low Pressure Permissive Bypass Timer
L-MT-12-091, Extended Power Uprate: Supplement to Revise Technical Specification Setpoint for the Automatic Depressurization System Bypass Timer
GNRO-2012/00096, License Amendment Request for Implementing a 24-Month Fuel Cycle, Grand Gulf Nuclear Station, Unit 1
NG-12-0309, Response to Request for Additional Information (RAI) Regarding License Amendment Request (TSCR-135): Application for One-Time Technical Specification Change Regarding Core Spray Operability During Shutdown
L-MT-12-028, License Amendment Request: Revise Allowable Value for the Automatic Depressurization System Bypass Timer
NLS2011026, License Amendment Request for Administrative Revisions to Technical Specifications and to Remove an Expired One-Time Exception to the Five-Year Test Frequency for a Single Safety Valve
RS-17-126, Quad Cities Nuclear Power Station, Units 1 & 2, Technical Requirements Manual
NL-15-1898, Enclosure 4: EAL Verification and Validation Documents - License Amendment Request for Changes to EAL Schemes to Adopt NEI 99-01 Rev. 6 and to Modify Radiation Monitors at Farley Nuclear Plant. Part 3 of 6
RA-15-019, Attachment 5 - EP-AA-1004, Revised Radiological Emergency Plan Annex Information for Dresden Station
NL-11-1812, Edwin I. Hatch, Unit 1 - Technical Requirements Manual
RS-11-159, Quad Cities, Units 1 and 2 - Technical Requirements Manual
RS-11-100, Dresden, Units 2 and 3, Updated Final Safety Analysis Report (Ufsar), Revision 9, Technical Specification Bases
U-603987, Transmittal of Revision 13 to Technical Specification Bases
RS-10-039, License Amendment Request to Administratively Revise Technical Specifications
NLS2010029, Technical Specifications Bases Changes
JAFP-10-0039, Response to Request for Additional Information Application for Amendment to Modify the Technical Specifications Requirements for Testing of Safety/Relief Valves
RBG-47006, Revisions to the Technical Requirements Manual and the Technical Specification Bases
BSEP 09-0019, Application to Revise Technical Specifications Regarding Primary Containment Isolation Instrumentation in Accordance with TSTF-306, Revision 2
RS-09-147, Response to Request for Additional Information Regarding Generic Letter 2008-01
PLA-6561, Amendment Request No. 296 to Unit 1 and Amendment Request No. 266 to Unit 2 Re Emergency Core Cooling System Instrumentation - Technical Specification (TS) Table 3.3.5.1-1 and Editorial Change to TS 3.10.8.F, Response to RAI
JAFP-09-0087, Application for Amendment to Modify the Technical Specifications Requirements for Testing of Safety/Relief Valves
RBG-46925, License Amendment Request, Technical Specification Change to Revise ASME Code Reference for Inservice Test Requirements
PLA-6235, Emergency Core Cooling System Instrumentation - Technical Specification (TS) Table 3.3.5.1+1 and Editorial Change to TS 3.10.8.f
BVY 08-084, Technical Specifications Proposed Change No. 273, Supplement 5, Response to Request for Additional Information
RS-08-132, LaSalle County Station, Units 1 and 2 - Transmittal Letter of Additional Information Regarding Request for License Amendment Regarding Application of Alternative Source Term. Attachments 1 - 5
BVY 08-062, Technical Specifications Proposed Change No. 273, Supplement 2, Response to Request for Additional Information
GO2-08-124, License Amendment Request for Proposed Changes to Columbia Technical Specification 3.3.3.1; Change Group 1 Primary Containment Isolation Valves Reactor Water Level Isolation Signal from Level 2 to Level 1
NRC-18-0045, Response to NRC Requests for Additional Information for License Amendment Request to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control
NEI 99-01, Dresden, Units 2 & 3, Attachment 5, Discussion of Revision to the Radiological Emergency Plan Annex, EP-AA-1004, NEI 99-01, Rev. 6, Development of Emergency Action Levels for Non-Passive Reactors, Enclosure 5B and 5C, Dr 3-77 - Dr 3-160
GO2-07-111, License Amendment Request for Proposed Changes to Columbia Technical Specifications: Adoption of Approved Generic Technical Specification Changes Associated with Containment Isolation Valves
PLA-6250, Proposed License Amendment Nos. 285 and 253, for Extended Power Uprate Application Reactor Systems Technical Review Request for Additional Information Responses
GO2-07-109, License Amendment Request to Technical Specifications Associated with Condensate Storage Tank Level
NLS2007036, Technical Specification Bases Changes
NOC-AE-06002095, Request for Enforcement Discretion for Technical Specifications 3.3.3.6 and 3.7.1.2
L-MT-06-054, Supplemental Submittal Regarding Full Scope Application of an Alternative Source Term (AST)
U-603781, Transmittal of Revision 10 to the Clinton Power Station Technical Specifications Bases
GO2-06-080, Proposed Amendment of Facility Operating License to Remove Operating Mode Restrictions for Performing Emergency Diesel Generator Surveillance Testing
BSEP 06-0044, Submittal of Technical Specification Bases Revisions
JAFP-02-0098, Part 7 of 7, James A. FitzPatrick Nuclear Power Plant - Revision J to Proposed Technical Specification Change (License Amendment) Conversion to Improved Standard Technical Specifications, Bases
GNRO-2018/00051, Supplement to Revise Technical Specifications to Adopt Technical Specification Task Force Traveler TSTF-542, Reactor Pressure Vessel Water Inventory Control
RA-19-0015, Request for License Amendment: Surveillance Requirements for Safety Relief Valves
NRC-19-0001, License Amendment Request to Revise Technical Specification 3.3.5.3, Reactor Pressure Vessel (RPV) Water Inventory Control Instrumentation
TSTF-19-05, Transmittal of TSTF-541, Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position
JAFP-01-0133, ITS: 3.3.4.1 Anticipated Transient Without Scram Recirulation Pump Trip (ATWS-RPT) Instrumentation
NLS2005061, Letter to Provide Changes to Plant Technical Specification Bases Implemented Without NRC Approval
U-603708, Transmittal of Revision 9 to the Clinton Power Station Technical Specification Bases
RS-03-199, Request for License Amendment Related to Revision of Instrument Channel Trip Setpoint Allowable Values
TSTF-19-09, Technical Specifications Task Force - Transmittal of TSTF-576, Revision 0, Revise Safety/Relief Valve Requirements
NLS2004122, License Amendment Request to Revise the Required Channels Per Trip System for Primary and Secondary Containment Isolation and Control Room Emergency Filter System Instrumentation
PLA-5756, Proposed Amendment No. 266 to License NPF-14 and Proposed Amendment No. 231 to License NPF-22: Incorporation of TSTF-16 and Editorial Changes
PLA-5722, Proposed License Amendments Regarding ADS-LPCI Discharge Pressure, TS 3.3.5.1-1, Function 4.f and 5.f
RS-04-005, Request for Amendment to Technical Specifications Surveillance Requirements for the Main Steam Line Valves and Associated Relief Requests
RBG-46179, Revisions to the Technical Requirements Manual and the Technical Specification Bases
RS-03-090, Request for Amendment to Technical Specifications Surveillance Requirements for the Main Steam Relief Valves and Relief Request RV-30E
NRC-03-0007, Proposed License Amendment for Implementation of Alternative Radiological Source Term Methodology
RBG-46052, License Amendment Request, Revised Full Scope Application of NUREG-1465 Alternative Source Term Insights
U-603588, Transmittal of Revision 7 to Clinton Power Station Technical Specification Bases
PLA-5542, Proposed Amendment No. 251 to License NPF-14 & Proposed Amendment No. 216 to License NPF-22: Adoption of NRC Approved Generic Changes to Improved Standard Technical Specifications (Intermittent Opening of Isolated Flow Paths & Tip Isolation
GO2-02-135, Revised Request for Amendment on the Alternate Source Term
RS-02-110, Request for Amendment to Technical Specifications Table 3.3.8.1-1, Loss of Power Instrumentation
BSEP 02-0114, Submittal of Technical Specification Bases Changes Revisions 24 & 25
RBG-45950, License Amendment Request Re Removal Operating Mode Restrictions for Performing Emergency Diesel Generator Testing
RBG-45946, Entergy Nuclear- South, River Bend Station, Unit-1, License Amendment LAR 2002-11 Modification of the Technical Specification Surveillance Requirements for the Safety/Relief Valves
BSEP 02-0093, Part 2 of 2 - Brunswick, Units 1 and 2 - Submittal of Technical Specification Bases Changes for Revisions 21 and 22 (Units 1 and 2) and Revision 23 (Unit 1 Only)
RBG-45935, Part B - Revisions 58 -76 to River Bend Station Technical Requirements Manual & Technical Specification Bases
GNRO-2002/00006, License Amendment Request Regarding Removal of Operating Mode Restrictions for Performing High Pressure Core Spray Emergency Diesel Generator Testing
RS-02-018, Supplement to 06/21/2001 License Amendment Request, Surveillance Requirements for Main Steam Line Safety Relief Valves
RS-02-010, Additional Information Supporting Technical Specification Changes to Reactor Pressure Vessel Level Instrumentation Surveillance Frequencies and Allowable Values Requirements
RBG-48033, Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements
L-20-166, Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements
RA-20-0165, Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements
NL-20-0949, License Amendment Request to Revise, Technical Specifications to Adopt TSTF-541, Revision 2
L-MT-21-017, Response to Request for Additional Information (RAI) Related to License Amendment Request to Implement Technical Specifications Task Force Traveler TSTF-505, Revision 2
JAFP-21-0028, Application to Revise Technical Specifications to Adopt TSTF-582, Revision 0, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements
NLS2021018, Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements
NMP2L2780, Application to Revise Technical Specifications to Adopt TSTF-582, Revision 0, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements
NG-97-1597, Forwards Response to Request for Addl Info on Improved Tech Spec Change Re Not Entering LCO Action Statements During Certain Surveillances
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
NG-97-2008, Application for Amend to License DPR-49,revising 961030 Amend Request to Convert TS to Improved Ts.Marked Up Pages for Rev a Showing Changes for Rev B,Encl
JAFP-98-0046, Forwards Revised Amend to DPR-59,revising TS Table 3.2-2 & 4.2-2, Core & Containment Cooling Sys Initiation & Control Instrumentation Operability Requirements. W/Revised TS Pages & Safety Evaluation
JAFP-98-0352, Forwards Addl Info Re Proposed TS Amend Concerning TS Table 3.2-2, Core & Containment Cooling Sys Initiation & Control Instrumentation Operability Requirements. Explanations, Encl
RBG-43339, Responds to NRC Re Violations Noted in Insp Rept 50-458/96-12.Corrective Actions:Restored Transmitter to Svc,Verified Nuclear Boiler Instrumentation line-up & Performed Verification of 2,650 Safety Related Valves
RA-20-0107, Duke Energy Progress, LLC, and Duke Energy Carolinas, LLC, Application to Revise Technical Specifications to Adopt TSTF-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position
PLA-8005, Response to Request for Additional Information Regarding License Amendment to Revise Reactor Steam Dome Pressure - Low Instrumentation Function Allowable Value (PLA-8005)
TSTF-22-07, Transmittal of TSTF-592, Revision 0, Revise Automatic Depressurization System (ADS) Instrumentation Requirements
PLA-8025, Supplement to License Amendment to Revise Reactor Steam Dome Pressure - Low Instrumentation Function Allowable Value
L-20-239, Application to Revise the Technical Specifications to Adopt TSTF-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position
U-602520, Application for Amend to License NPF-62,revising TS 3.3.1.1, RPS Instrumentation & TS 3.3.6.1, Primary Containment Dwl Isolation Instrumentation, to Eliminate Periodic Response Time Testing of Analog Trip Modules
U-602407, Responds to NRC 941228 RAI on Potential Concern Re Requirements for Inoperable ECCS Actuation Instrumentation During Plant Shutdown Conditions,Per Review of Util Request to Implement Improved TS
CNL-22-097, Response to Request for Additional Information and Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide .
RS-23-002, Application to Adopt TSTF-332, ECCS Response Time Testing
CNL-22-037, Application to Revise Technical Specifications to Adopt TSTF-541-A, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position (BFN TS-533)
U-602417, Application for Amend to License NPF-62,changing TS 3.8.2, 3.8.5 & 3.8.8 to Revise Operability Requirements for Div 3 DG & Divs 3 & 4 Batteries,Battery Chargers & Inverters to Apply Only When HPCS Required to Be Operable
NLS2023007, Technical Specification Bases Changes
L-22-221, Supplement to Application to Revise the Technical Specifications to Adopt TSTF-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position
U-602196, Application for Amend to License NPF-62,requesting Changes to TS to Improve & Reformat CPS TS Consistent w/NUREG-1434, Improved BWR-6 TS, Rev 0,Sept 1992
PY-CEI-NRR-2216, Forwards Supplemental Response to NRC Bulletin 96-003, Potential Plugging of ECCS Strainers by Debris in Bwrs. Updated Info to NRC on Several Design Approaches Which Have Been Revised During Final Design Process,Provided
PY-CEI-NRR-2430, Application for Amend to License NPF-58,revising Allowables Values for CST Low Water Level Limits from Greater than or Equal to 59,700 Gallons to Greater than or Equal to 90,300 Gallons
RS-23-123, Emergency License Amendment Request - Increase Technical Specifications Completion Time in TS 3.8.1.B.4 from 7 Days to 30 Days
GO2-23-107, Application to Revise Technical Specifications to Adopt TSTS-584, Eliminate Automatic RWCU System Isolation on SLC Initiation
NLS2024001, Application to Modify the Allowable Value for Cooper Nuclear Station Technical Specifications High Pressure Coolant Injection Pump Discharge Low Flow
NLS2011093, Submittal of Technical Specification Bases Changes
RS-24-032, Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion
NLS2005007, License Amendment Request to Adopt Generic Changes to Standard Technical Specifications
NRC-19-0054, DTE Energy Company - License Amendment Request to Revise Technical Specifications to Change Surveillance Intervals to Accommodate a 24-Month Fuel Cycle
NLS2005051, Response to Request for Additional Information License Amendment Request to Revise the Required Channels Per Trip System for Primary & Secondary Containment Isolation and Control Room Emergency Filter System Instrumentation
GO2-24-051, Application to Revise Technical Specifications to Adopt TSTF-592, Revise Automatic Depressurization System (ADS) Instrumentation Requirements
RBG-48271, Supplement to License Amendment Request to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times – RITSTF Initiative 4b and Application to Adopt 10 CFR 50.69, Risk
NMP2L2789, Response to Request for Additional Information by the Office of Reactor Regulation to Support Review of License Amendment Request to Adopt TSTF-582, Revision 0
GNRO-2010/00042, Technical Specification Bases & Technical Requirements Manual Update
L-08-325, License Amendment Request No. 08-18 to Incorporate Technical Specification Task Force Travelers 479 and 497
NRC-12-0004, Proposed License Amendment to Modify Technical Specification Surveillance Requirements for Safety Relief Valves
NRC-13-0001, License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-423, Revision 1, Technical Specifications End States, NEDC-32988-A, Using the Consolidated Line Item Improvement Process
RA-14-032, Dresden, Units 2 & 3, Attachment 5, Discussion of Revision to the Radiological Emergency Plan Annex, EP-AA-1004, NEI 99-01, Rev. 6, Development of Emergency Action Levels for Non-Passive Reactors, Enclosure 5B and 5C, Dr 3-77 - Dr 3-160
05000373/LER-2023-001, Low Pressure Core Spray Inoperable Due to Minimum Flow Valve Flow Pressure Switch Failure
NLS2002122, 10CFR50.59(d)(2) Summary Report
05000388/LER-2021-001-01, Condition Prohibited by Technical Specifications Due to Drift of Reactor Pressure Switch
05000341/LER-2021-003, High Pressure Coolant Injection Inoperable Due to Contact Oxidation
05000298/LER-2021-003, Re Failure of High Pressure Coolant Injection Flow Indicating Switch Results in Condition Prohibited by Technical Specifications
05000388/LER-2020-002-01, Condition Prohibited by Technical Specifications Due to Drift of Reactor Pressure Switch Caused by Lack of Requirements for Acclimation of the Instrument to the Operating Environment
05000387/LER-2017-010-02, Condition Prohibited by Technical Specifications Due to Drift of Reactor Pressure Switches
05000387/LER-2018-005-02, (SSES) Unit 1 Re Condition Prohibited by Technical Specifications Due to Drift of Reactor Pressure Switches
PLA-7901, Condition Prohibited by Technical Specifications Due to Drift of Reactor Pressure Switch
GO2-12-104, Response to Request for Additional Information for License Amendment Request to Make Administrative and Editorial Changes to Technical Specifications and the Operating License
A06214, Proposed Tech Specs,Providing Limiting Conditions for Operation Per Generic Ltr 83-37
BSEP-99-0042, Provides Response to RAI Re Itss,As Contained in Rev 1 of NUREG-1433, Std Tech Specs General Electric Plants,BWR/4, Proposing Lengthening AOTs for Balance of Plant & Emergency Electrical Buses to 7 Days
GO2-20-095, Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements
05000325/LER-1999-004-01, On 990325,drywell Pressure Instrumentation Sensing Line Deficiency,Was Determined.Caused by Incorrect Design & Installation of Instrument Sensing Lines.Associated Sensing Lines Were Purged.With
05000277/LER-1997-008-02, :on 740705,logic Sys Functional Testing Did Not Contain All Required Testing Per TS Surveillance Requirements.Caused by Test Procedures Not Containing Required Testing.Untested Contacts Tested & Proved Operable
JAFP-11-0046, 2011 Updated Final Safety Analysis Report, Technical Specification Bases and Technical Requirements Manual Changes Transmittal
05000458/LER-1996-008, :on 960214,mispositioned Drywell Pressure Transmitter Isolation Valve Caused Condition Prohibited by Ts.Restored & Verified Position of Other SR Instrumentation Valves
RBG-47169, Unit 1, Revisions to the Technical Requirements Manual and the Technical Specification Bases
PY-CEI-NRR-1694, Suppls 920629 LAR for PNPP Unit 1 for License NPF-58, Increasing Surveillance Test Intervals & AOT for Instrumentation
NRC-22-0023, Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements
05000388/LER-1917-010, Regarding Condition Prohibited by Technical Specifications Due to Drift of Reactor Pressure Switches
05000387/LER-2018-005-01, Condition Prohibited by Technical Specifications Due to Drift of Reactor Pressure Switches
RS-08-045, LaSalle, Units 1 and 2, Technical Requirements Manual
RS-02-174, Co., Llc. (EGC) Application for Amendment to Licenses DPR-19, DPR-25, DPR-29 & DPR-30, Related to Application of Alternative Source Term, Attachments a - E-1
L-MT-20-018, License Amendment Request: Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements
CNL-24-049, Brows Ferry Nuclear Plant, Units 1, 2 and 3 - License Amendment Request for Adoption of TSTF-576 to Revise Safety/Relief Valve Requirements
RS-24-019, Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Completion Times TSTF
NRC-23-0063, Inservice Testing Program for Pumps and Valves - Part 12: IST Program Pump Basis Revision 1
CNL-19-064, Response to NRC Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt Technical Specifications Task Force (TSTF)-542, Reactor Pressure Vessel Water.
TSTF-19-08, Draft of Traveler TSTF-582, Revision 0, RPV WIC Enhancements
05000387/LER-2018-005, Condition Prohibited by Technical Specifications Due to Drift of Reactor Pressure Switches
05000296/LER-2018-003, Misadjusted Switch Results in Condition Prohibited by Technical Specifications
RS-03-087, Request for Amendment to Technical Specifications Surveillance Requirements for the Main Steam Line Relief Valves and Relief Request RV-30D
GO2-97-228, Provides Amended Response to Violations Noted in Insp Rept 50-397/96-11.Corrective Actions:Portions of RCIC Sys Required to Support Reactor Vessel Inventory Makeup Will Be Reclassified as safety-related & Seismic Category I
GO2-99-143, Application for Amend to License NPF-21,revising TS Table 3.3.5.1-1, ECCS Instrumentation Items 1.a,2.a,4.a & 5.a
NRC-17-0067, Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control
05000341/LER-2017-002, Regarding High Water Level Indications at Low Reactor Pressures Causes Some Functions of High Pressure Coolant Injection System and Reactor Core Isolation Cooling System to Be Inoperable
CNL-16-126, Response to NRC Request for Additional Information Related to License Amendment Request for Adding New Specifications to Technical Specification 3.3.8.3 (BFN-TS-486)
05000296/LER-2016-002, Regarding Improperly Installed Switch Results in Condition Prohibited by Technical Specifications
05000331/LER-2015-006, Regarding HPCI and RCIC Condensate Storage Tank Suction Transfer Inoperable
CNL-15-073, Application to Modify the Technical Specifications by Adding New Specification TS 3.3.8.3, Emergency Core Cooling System Preferred Pump Logic, Common Accident Signal (CAS) Logic, and Unit Priority Re-Trip Logic, and
05000296/LER-2015-002, Regarding Switch Failure Rendered Automatic Startup of Some Emergency Core Cooling System Pumps Inoperable Longer than Allowed by Technical Specifications
GO2-22-096, Supplement to License Amendment Request to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b
05000259/LER-2013-004, Brown Ferry, Unit 1, Regarding High Pressure Coolant Injection System Declared Inoperable Due to Exceeding the Allotted Time Frame for Instrument Inoperability
NRC-11-0049, License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration
05000260/LER-2011-001, For Browns Ferry Nuclear Plant, Unit 2 Regarding Core Spray Relay Found in Incorrect Position
GO2-10-052, License Amendment Request for Proposed Changes to Technical Specification 3.3.6.1; Add Channel Check Surveillance Requirement to Primary Containment Isolation Instrumentation Main Steam Line Isolation - Reactor Vessel
GNRO-2007/00068, To Amendment Request Changes to the Condensate Storage Tank Level-Low Setpoints
RS-07-118, Application for Technical Specification Change TSTF-423, Risk Informed Modification to Selected Required Action End States for BWR Plants, Using the Consolidated Line Item Improvement Process
05000397/LER-2007-001, Regarding Automatic Depressurization System Logic Signal Instrument Inadvertently Disabled
RS-06-154, Request for Amendment to Technical Specifications Section 5.5.7, Inservice Testing Program
TSTF-06-20, TSTF-495, Revision 0, Bases Change to Address GE Part 21 SC05-03
05000388/LER-2006-001, Re Tech Specs Not Met for Inoperable ADS Pressure Switches
RS-07-074, Application for Technical Specification Change TSTF-423, Risk Informed Modification to Selected Required Action End States for BWR Plants, Using the Consolidated Line Item Improvement Process
05000237/LER-2003-004, Regarding HPCI System Inoperable Due to Leaking Gland Seal Leak Off Pump Check and Regulating Valves
NUREG-1433, Part 1- Edwin I. Hatch, Units 1 & 2, License Amendments, Replace Current Technical Specification & Associated Bases
JAFP-02-0146, Updated Markup and Retyped Technical Specification Pages for Proposed License Amendment for a Limited Scope Application of the Alternate Source Term Guidelines in NUREG-1465 Related to the Re-Evaluation of the Fuel Handling.
RS-07-117, Application for Technical Specification Change TSTF-423, Risk Informed Modification to Selected Required Action End States for BWR Plants, Using the Consolidated Line Item Improvement Process
05000298/LER-2024-003, High Pressure Coolant Injection Steam Leak Causes Condition That Could Have Prevented Fulfillment of a Safety Function and a Condition Prohibited by Technical Specifications
NMP1L3545, Supplemental Information Letter to Adopt TSTF-505, Provide Risk- Informed Extended Completion Times - RITSTF Initiative 4b, Revision 2 and 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems .
RS-05-104, Revised Technical Specification Pages for License Amendment Related to Revision of Instrument Channel Trip Setpoint Allowable Values
RS-03-053, Additional Information Supporting the Request for License Amendment Related to Application of Alternatives Source Term
RS-07-044, Amergen Energy Company, LLC, Request for Amendment to Technical Specifications Section for the Inservice Testing Program
JAFP-09-0132, Application for Amendment to Modify the Technical Specifications Requirements for Testing of Safety/Relief Valves
JAFP-22-2020, Supplemental Information No. 1 for James A. FitzPatrick Nuclear Power Plant to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b. and 10CFR 50.69, Risk-Info
RS-22-056, Constellation Radiological Emergency Plan Addendum Revision
CNL-23-018, – Request for Amendment Regarding Technical Specification Surveillance Requirements 3.4.3.2 and 3.5.1.11 Regarding Safety Relief Valves (BFN TS-540)
L-MT-16-031, Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing, and to Request an Alternative to the ASME Code
NMP2L2745, Request for Additional Information for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-505, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b, Revision 2
RS-22-069, Constellation Nuclear Radiological Emergency Plan Addendum Revision. Includes EP-AA-1006, Addendum 3, Revision 10, Emergency Action Levels for Quad Cities Station
GO2-25-011, License Amendment Request for Change to Tehnical Specification TSTF-65-A, Revision 1, Use of Generic Titles for Utility Positions
05000298/LER-2024-003-01, High Pressure Coolant Injection Steam Leak Causes Condition That Could Have Prevented Fulfillment of a Safety Function and a Condition Prohibited by Technical Specifications
TSTF-21-03, TSTF Response to NRC Questions on TSTF-576, Revision 0, Revise Safety/Relief Valve Requirements and Submittal of Revision 1
NRC-21-0001, License Amendment Request to Revise Technical Specifications to Remove Obsolete Information, Make Minor Corrections, and Make Miscellaneous Editorial Changes
CNL-21-008, Application to Revise Technical Specifications to Adopt TSTF-582, RPV WIC Enhancements (BFN TS-532)
L-MT-20-036, Response to Request for Additional Information Related to License Amendment Request to Implement Technical Specification Task Force Traveler TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times
CNL-25-039, Response to Request for Additional Information Regarding License Amendment Request to Adopt TSTF-576
JAFP-19-0083, License Amendment Request - Proposed Change to the Technical Specifications to Revise the Allowable Value for Reactor Water Cleanup (RWCU) System Primary Containment Isolation
BSEP 18-0013, Supplement to Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control
LR-N25-0015, License Amendment Request (LAR) - Hope Creek Technical Specification Conversion to NUREG-1433, Revision 5, Supplement 2
NRC-25-0015, Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times – RITSTF Initiative 4b, TSTF-439, Revision 2
TSTF-19-10, Transmittal of Errata Changes to TSTF-541, Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position
PLA-7950, Revise Reactor Steam Dome Pressure - Low Instrumentation Function Allowable Value (PLA-7950)
JAFP-21-0089, Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position
05000388/LER-2021-001, Condition Prohibited by Technical Specifications Due to Drift of Reactor Pressure Switch
05000298/LER-2024-005, High Pressure Coolant Injection Pressure Switch Installation Causes Condition That Could Have Prevented Fulfillment of a Safety Function and a Condition Prohibited B Technical
PLA-8144, Proposed Amendment to Licenses NPF-14 and NPF-22: Revised Reactor Vessel Water Level 3 and Level 8 Allowable Value PLA-8144
NLS2004007, License Amendment Request - One-Time Extension of Surveillance Requirements
NL-20-0785, Southern Nuclear Operating Co - Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements
NRC-16-0034, Fermi, Unit 2, Submittal of Revision 20 Updated Final Safety Analysis Report, 10CFR50.59 and 10CFR72.48 Evaluation Summary Reports, Commitment Management Report & Revisions to Technical Requirements Manual & Technical Specifications Base
GO2-23-006, License Amendment Request to Clean-Up Operating License and Appendix a Technical Specifications
L-09-218, Submittal of Technical Specification Bases, Revision 7
PLA-7979, Supplement to License Amendment to Revise Reactor Steam Dome Pressure Low Instrumentation Function Allowable Value
LR-N24-0029, Enclosure 1: Contents of the Hope Creek Improved Technical Specifications (ITS) Submittal
TSTF-23-08, TSTF-592, Revision 2, Revise Automatic Depressurization System (ADS) Instrumentation Requirements Correction
TSTF-23-07, TSTF Response to NRC Request for Additional Information on TSTF-592, Revision 1, Revise Automatic Depressurization System (ADS) Instrumentation Requirements
TSTF-23-06, TSTF Response to NRC Request for Additional Information on TSTF-576, Revision 2, Revise Safety/Relief Valve Requirements
TSTF-23-02, TSTF Response to Request for Additional Information on TSTF-592,Revise Automatic Depressurization System (ADS) Instrumentation Requirements and Submission of Revision 1
TSTF-23-04, Technical Specifications Taskforce Transmittal of TSTF-576, Revision 2, Revise Safety/Relief Valve Requirements
TSTF-22-03, Transmittal of TSTF-584, Revision 0, Eliminate Automatic RWCU System Isolation on SLC Initiation
PLA-8189, Supplement to License Amendment Requesting Revision to Technical Specifications for Reactor Vessel Water Level 3 and Level 8 Allowable Values - PLA-8189
JAFP-25-0046, License Amendment Request - Proposed Change to the Technical Specifications to Revise the Allowable Value for Reactor Water Cleanup (RWCU) System Primary Containment Isolation