05000296/LER-2014-003, Regarding Primary Containment Isolation Valve Inoperable for Longer than Allowed by Technical Specifications
05000461/LER-2016-003, Regarding Bypassing Both Divisions of Reactor Water Cleanup Leak Detection System Is a Reportable Loss of Safety Function
05000461/LER-2010-004, For Clinton Power Station, Unit 1, Regarding OPDRV Requirements Not Met During Control Rod Drive Mechanism Replacements
05000410/LER-2002-002, Reactor Water Cleanup System Differential Flow Isolation Signal Inoperable
05000331/LER-2013-005, Condition Prohibited by Technical Specifications - Main Steam Line Steam Leak Detection
L-17-042, Request for Licensing Action to Revise the Technical Specifications
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
RS-16-228, License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition
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
NMP2L2616, Supplemental Response to Request for Additional Information by NRR to Support Review of Relocation of Secondary Containment Bypass Leakage Paths Table from Technical Specifications to the Technical Requirements Manual
NMP2L2611, Response to Request for Additional Information by NRR to Support Review of Relocation of Secondary Containment Bypass Leakage Paths Table from Technical Specifications to the Technical Requirements Manual
BSEP 11-0108, Response to Integrated Inspection Report Nos.: 05000325/2011004 and 05000324/2011004
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
GO2-15-173, Supplement to Response to Second Request for Additional Information on License Amendment Request for Adoption of Technical Specification Task Force (TSTF)-425, Revision 3
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
NMP2L2576, License Amendment Request - Relocation of Secondary Containment Bypass Leakage Paths Table from Technical Specifications to the Technical Requirements Manual
CNL-14-166, Application to Revise Technical Specifications 3.3.6.1, Table 3.3.6.1-1, Function 5.g and Bases (BFN-TS-479)
JAFP-15-0017, J.A. Fitzpatrick - Response to Regulatory Issue Summary 2014-13
NLS2014035, License Amendment Request to Eliminate Requirements for Post Accident Sampling System for Boiling Water Reactors Using the Consolidated Line Item Improvement Process
RS-14-006, Updated Safety Analysis Report, Revision 16, CPS Operational Requirements Manual
PLA-6990, Proposed Amendment No. 314, Change to Allow Only One Manual Trip System to Be Operable for the RHR Shutdown Cooling System in Modes 4 and 5 for Units 1 & 2, Technical Specification 3.3.6.1
RS-13-009, Operational Requirements Manual (Orm) 2013
PLA-6915, Proposed Amendment No. 312 to Unit 1, and Proposed Amendment No. 284 to Unit 2 Low Pressure Safety Limit and Reference Changes
GNRO-2012/00096, License Amendment Request for Implementing a 24-Month Fuel Cycle, Grand Gulf Nuclear Station, Unit 1
RBG-47229, Supplemental Information Concerning License Amendment Submittals
L-12-064, Request for an Amendment to Revise Technical Specification 3.10.1. Inservice Leak and Hydrostatic Testing Operation, Using the Consolidated Line Item Improvement Process
RBG-47207, Response to Request for Information, Changes to Technical Specification 3.3.6.1, Primary Containment and Drywell Isolation Instrumentation
RBG-47157, License Amendment Request, Changes to Technical Specification 3.3.6.1, Primary Containment and Drywell Isolation Instrumentation
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
NL-18-0206, Supplement to Application to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control
TSTF-14-17, Technical Specification Task Force - Response to NRC Request for Additional Information Regarding TSTF-454, Revision, Extend PCIV Completion Times (NEDC-33046) and Submittal of TSTF-454, Revision 3
L-MT-18-032, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, and Supplement (EPID: L-2017-LLA-0360
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 2 of 6
NL-11-1812, Edwin I. Hatch, Unit 1 - Technical Requirements Manual
RS-11-100, Dresden, Units 2 and 3, Updated Final Safety Analysis Report (Ufsar), Revision 9, Technical Specification Bases
RS-10-208, Additional Information Supporting the Request for License Amendment Regarding Shutdown Cooling System Isolation Instrumentation
RS-10-152, Additional Information Supporting the Request for License Amendment Regarding Shutdown Cooling System Isolation Instrumentation
RS-10-018, Request for License Amendment Regarding Shutdown Cooling System Isolation Instrumentation
BSEP 09-0019, Application to Revise Technical Specifications Regarding Primary Containment Isolation Instrumentation in Accordance with TSTF-306, Revision 2
RS-09-105, Withdrawal of Request for Amendment to Technical Specifications Section 3.3.6.1, Primary Containment and Drywell Isolation Instrumentation, to Eliminate Requirements for Main Steam Line Isolation on High Turbine Building Temperature
JAFP-09-0086, Application for Amendment for James A. FitzPatrick Nuclear Power Plant to Modify the Technical Specifications Requirements for Testing of the Shutdown Cooling System Isolation, Reactor Pressure - High Function
RS-09-078, Response to Request for Additional Information Related to Technical Specification 3.3.6.1, Primary Containment and Drywell Isolation Instrumentation
RS-09-077, Request for Processing an Amendment to Technical Specifications Section 3.3.6.1, Primary Containment and Drywell Isolation Instrumentation, to Eliminate Requirements for Main Steam Line Isolation on High Turbine Building
RS-09-079, Request for Amendment to Technical Specifications Section 3.3.6.1, Primary Containment and Drywell Isolation Instrumentation, to Eliminate Requirements for Main Steam Line Isolation on High Turbine Building Temperature
GO2-09-072, Revised Implementation Date for License Amendment Request for Proposed Changes to Technical Specification 3.3.6.1; Change Group 1 Primary Containment Isolation Valves Reactor Water Level Isolation Signal from Level 2 to Level 1
GO2-09-051, Initial License Written Examination Documentation
SVP-09-001, CFR 50.59 / 10 CFR 72.48 Summary of Completed Changes, Tests, and Experiments Report
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
GO2-08-122, Supplement to Adoption of Approved Generic Technical Specification Changes Associated with Containment Isolation Valves
BSEP 08-0009, Additional Information in Support of Request for License Amendments Regarding Linear Heat Generation Rate and Core Operating Limits Report References for Areva Fuel
GO2-18-102, Response to Supplemental Information Needed for Acceptance of Requested Licensing Action Re-Renewed Facility Operating License and Technical Specification Clean-Up
TSTF-05-15, TSTF-454, Revision 1, Extend PCIV Completion Times (NEDC-33046)
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
SVP-07-001, CFR 50.59/10 CFR 72.48 Summary Report for January 2004 to December 31, 2006
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
GNRO-2006/00031, Technical Requirements Manual Update to the NRC for Period Dated May 15, 2006
RS-06-003, Request for a License Amendment to Revise Allowable Values for Reactor Core Isolation Cooling Temperature Based Leak Detection
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
L-17-241, Acceptance for Review of Application Concerning Revision to Technical Specification 3.3.6.1 (CAC No. MG0150) (L-17-241)
NRC-2017-0238, Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: January 2, 2018
NRC-2011-0040, Sholly Report for Fr Publication on February 22, 2011
RS-05-008, Additional Information Supporting Main Steam Line Flow - High Instrumentation Amendment Request
SVP-05-001, Summary Report of Changes, Tests, and Experiments Completed
RS-03-199, Request for License Amendment Related to Revision of Instrument Channel Trip Setpoint Allowable Values
RS-04-140, Additional Standby Liquid Control System Information Supporting the Request for License Amendment Related to Application of Alternative Source Term
RS-04-062, Technical Specifications Changes Related to Main Steam Line Flow-High Isolation Instrumentation
RS-04-043, Request for Technical Specification Changes to Eliminate Selected Response Time Testing Requirements
GNRO-2003/00072, Revised License Amendment Request Regarding Shutdown Cooling System Isolation Instrumentation
GNRO-2003/00075, Response to Request for Additional Information Shutdown Cooling System Isolation Instrumentation
GNRO-2003/00032, Amendment Request Modification of Technical Specification 3.3.6.1 Re Shutdown Cooling System Isolation Instrumentation
GNRO-2003/00025, License Amendment Request, Proposed Changes to Primary Containment and Drywell Isolation Instrumentation Requirements, Ldc 2003-033
RS-03-036, Request for TS Surveillance Requirement 3.6.1.3.8 Change Related to Excess Flow Check Valve Testing
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
BSEP 02-0114, Submittal of Technical Specification Bases Changes Revisions 24 & 25
NRC-02-0036, Proposed Technical Specification Change (License Amendment) - Response Time Testing
RS-02-047, Supplemental Information Supporting a License Amendment Request to Revise Plant System Requirements During Fuel Handling Based on Alternative Source Term
RBG-45901, License Amendment Request Regarding Deletion of Turbine Building High Temperature Inputs to Main Steam Line Isolation Logic, Technical Specification Table 3.3.6.1-1 Functions 1f., 1g
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
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
U-602959, Provides Response to Violations Noted in Insp Rept 50-461/97-25.Corrective Actions:Issued Night Order on 980109 Emphasizing Requirement to Review Applicable TS Bases for Other Required Actions
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
U-603112, Requests Withdrawal of Application for Amend of Operating License NPF-62,submitted Via Util Ltrs & 960722
NMP2L2794, Supplemental Information to Support Review of Nine Mile Point Nuclear Station, Unit 2, License Amendment Request to Adopt TSTF-582, Revision 0
JAFP-22-0008, Response to Request for Supplemental Information by the Office of Nuclear Reactor Regulation to Support Review of a License Amendment Request to Eliminate Selected Response Time Testing for Reactor Protection System and Primary
RS-21-006, Application to Incorporate Licensing Topical Report NEDE-33885P-A, Revision 1, GNF CRDA Application Methodology
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
BSEP-94-0413, Application for Amends to Licenses DPR-62 & DPR-71,proposing Ts,Increasing Instrument Surveillance Test Intervals & Allowable out-of-service Times
RS-22-092, Nine and Quad Cities - Application to Revise Primary Containment Isolation Instrumentation Technical Specifications in Accordance with TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration
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
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
GO2-23-107, Application to Revise Technical Specifications to Adopt TSTS-584, Eliminate Automatic RWCU System Isolation on SLC Initiation
RBG-46842, Unit 1, Revisions to the Technical Requirements Manual and the Technical Specification Bases
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
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
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
RS-03-060, Request for License Amendment Related to Application of Alternative Source Term
05000440/LER-2024-002, Reactor Water Clean Up Leak Detection Loss of Safety Function
05000388/LER-2021-005-01, Condition Prohibited by Technical Specification Due to Setpoint Drift Attributed to Age Related Degradation
05000388/LER-2021-005, Condition Prohibited by Technical Specification Due to Setpoint Drift
05000461/LER-2020-003, Reactor Core Isolation Cooling System Card Fuse Failure Results in a Condition Prohibited by Technical Specifications and That Could Have Prevented Fulfillment of a Safetv Function Needed to Control
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
GO2-10-051, License Amendment Request to Change Technical Specifications Relating to Traversing In-Core Probe Containment Isolation Valve Instrumentation
JAFP-11-0046, 2011 Updated Final Safety Analysis Report, Technical Specification Bases and Technical Requirements Manual Changes Transmittal
05000440/LER-1996-007, :on 960821,missed Surveillance Occurred.Caused by Weakness in Design Mod Process.Revised Design Mod Process to Provide Detailed Requirements
05000458/LER-1995-008-02, :on 951024,Div II RCIC Sys Isolated Due to Spurious Trip Caused by Faulty Temp Switch for RCIC Isolation Main Steam Tunnel Ventilation.Compliance W/Ts 3.3.6.1 & 3.5.3 Immediately Established
05000324/LER-1983-015-03, /03L-0:on 830123,reactor Recirculation Pump 2A Tripped.Caused by ATWS Reactor Pressure Instrument 2-B21-PS-NO45C Actuation Below Tech Spec Limit.Instrument Replaced
05000416/LER-1995-001, :on 950106,discovered That 25% Grace Period for I&C Quarterly Surveillance 06-IC-1C51-Q-0001 Attachment IV Missed by Four Days.Ts 4.0.3 Initiated & Surveillance Successfully Performed
05000324/LER-1983-030-03, /03L-0:on 830314,both Recirculation Pumps Tripped. Caused by Slight Disturbance in Common Ref Leg.Trip Signal Reset
05000324/LER-1982-125-03, /03L-0:on 821024,during steady-state Plant Operation,Reactor Recirculation Pump 2A Tripped W/Receipt of ATWS High Reactor Pressure/Low Level Trip Annunciator.Caused by Setpoint Drift.Instrument Calibr & Returned to Svc
05000366/LER-1990-013-03, :on 901220,three Valves Found Misaligned in Offgas post-treatment Radiation Monitoring Sys.Cause Inconclusive.Valve Lineups Verified,Standing Order Issued & Appropriate Procedures Revised
05000324/LER-1982-119-03, /03L-0:on 821007,reactor Recirculation Pump 2A Tripped When Test Signal Applied to Atws/Rpt Instrument 2-B21-LT-N024A-1.Caused by Failure of Periodic Test to Provide for Shutting N024A-1 Instrument Manifold Valves
RS-20-115, Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements
HL-1480, Responds to NRC Re Violations Noted in Insp Rept 50-366/90-26.Corrective Actions:Offgas Sample Flow Restored to Radiation Monitors & Health Physics Standing Order Issued to Require Foreman to Document Acceptability of Lineups
NRC-22-0023, Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements
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
05000461/LER-2019-003, Reactor Water Cleanup System Differential Flow Instrumentation Inoperable
JAFP-24-0053, License Amendment Request to Eliminate Remaining Main Steam Line Radiation Monitor Initiated Isolation Functions
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
TSTF-19-08, Draft of Traveler TSTF-582, Revision 0, RPV WIC Enhancements
05000278/LER-2018-002-01, Reactor Coolant System Pressure Boundary Leakage Resulting in Technical Specification Required Shutdown
05000341/LER-2018-004, Re Inoperability of Reactor Water Cleanup System Isolation Differential Flow-High Function
GO2-96-172, Submits Comments on Draft SE of Proposed Improved Tech Specs
GO2-99-145, Application for Amend to License NPF-21,revising TS 3.4.9, RHR Shutdown Cooling Sys - Hot Shutdown
GO2-99-181, Application for Amend to License NPF-21,revising TS 3.3.6.1, Table 3.3.6.1-1, Primary Containment Isolation Instrumentation. Footnote (D) Is Removed Since Both Inboard & Outboard Trip Sys Are Now Functional in All Modes
GO2-99-148, Forwards Estimate of Number of Licensing Action Requests Planned for Submittal in Future,As Requested in Administrative Ltr 99-02.Twenty-nine Submittals Scheduled for Fy 2000 & Four for Fy 2001
NRC-17-0067, Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control
05000260/LER-2017-002, Regarding Inoperable Primary Containment Isolation Valve Resulting in Condition Prohibited by Technical Specifications
GO2-17-015, Energy Northwest - Transmittal of Response to Request for Additional Information, Columbia MUR LAR: Electrical Instrument and Controls Branch (Eicb) and Reactor Systems Branch (Srxb)
05000341/LER-2016-012, Regarding Unanalyzed Condition for Control Rod Drop Accident at Low Reactor Power
NLS2016046, Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal and Clarify Surveillance Requirement Usage Rule Application to Section 5.5 Testing
05000461/LER-2015-005, Regarding Containment Ventilation Radiation Monitors Inoperable During Operations with the Potential for Draining the Reactor Vessel Activities
05000249/LER-2015-001, Regarding Main Steam Line Flow Switches Found Outside Tech Spec Allowed Value
CNL-15-187, Response to NRC Request for Additional Information (RAI) Regarding Application to Revise Technical Specifications (TS) 3.3.6.1, Table 3.3.6.1-1 to Require Standby Liquid Control (SLC) System Instrumentation in
05000259/LER-2015-002, Regarding High Pressure Coolant Injection System Inoperable Due to Slow Containment Isolation Valve Closing Time
05000397/LER-2015-005, Regarding Reactor Pressure Vessel Level Indication Switch Failures
05000296/LER-2015-003, Regarding Traversing Incore Probe Operation Caused Inoperability of Primary Containment Isolation Valves for Longer than Allowed by Technical Specifications
05000461/LER-2015-001, Regarding Division 1 and Division 2 Reactor Water Cleanup System High Differential Flow Instruments Become Incapable of Performing Their Safety Function
05000259/LER-2014-004, Regarding Main Steam Isolation Valves Leaking in Excess of Technical Specification Requirements
GO2-22-096, Supplement to License Amendment Request to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b
05000331/LER-2013-004, Regarding Condition Prohibited by Technical Specifications - Main Steam Line Steam Leak Detection
05000260/LER-2013-002, Regarding High Pressure Coolant Injection System Declared Inoperable Due to an Unqualified Electrical Splice
05000341/LER-2013-002, Regarding Reactor Core Isolation Cooling Isolation Instrumentation Misconfigured Wiring
RS-17-029, Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control
05000410/LER-2013-001, Regarding Reactor Core Isolation Cooling System Isolation Due to a Temperature Switch Unit Failure
05000259/LER-2012-010, Re Browns Ferry, Unit 1 Primary Containment Isolation Valve Inoperable for Longer than Allowed by the Technical Specifications
05000333/LER-2012-006, Loss of Safety Function for RHR Shutdown Cooling Isolation Function Due to Reference Leg Leakage During Maintenance
05000265/LER-2012-004, Regarding Drywell Radiation Monitor Failed Downscale
05000260/LER-2012-004, Regarding High Pressure Coolant Injection System Rendered Inoperable Due to an Inadvertent Actuation of Primary Containment Isolation System
05000410/LER-2012-002, Regarding Loss of Isolation Function on RHR Shutdown Cooling Suction Line Due to Breaker Trip
RS-10-165, Follow-up Information Supporting Request for License Amendment Regarding Shutdown Cooling System Isolation Instrumentation
05000296/LER-2012-002, Regarding Main Steam Isolation Valve Leakage in Excess of Technical Specification Requirements
NLS2018053, Transmittal of 10 CFR 50.59(d)(2) and 10 CFR 72.48(d)(2) Summary Report
RBG-47211, Response to Request for Information Changes to Technical Specification 3.3.6.1, Primary Containment and Drywell Isolation Instrumentation
TSTF-12-01, Transmittal of TSTF-454, Revision 2, Extend PCIV Completion Times (NEDC-33046)
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-2010-002, Regarding Failure to Meet the Requirements of Technical Specifications Limiting Condition for Operation Due to Inoperable Primary Containment Isolation Instrumentation
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
05000263/LER-2009-003, Main Steam Line B Flow Isolation Instrumentation Inoperable Due to Leaking Equalizing Manifold Valve
05000341/LER-2008-004, Relay Locking Straps Not Fully Engaged
05000440/LER-2006-006, Re Primary Containment Airlock Door Inoperability Results in Operation Prohibited by Technical Specifications
NRC-06-0001, Revision to License Amendment Request to Revise Technical Specification 3.3.6.1, Primary Containment Isolation Instrumentation
L-91-004, Additional Information Supporting the Request for License Amendment Related to 24-Month Fuel Cycle
NRC-05-0016, Revision to License Amendment Request to Revise Technical Specifications 3.3.6.1 Primary Containment Isolation Instrumentation
NRC-04-0006, Proposed License Amendment to Revise Technical Specification 3.3.6.1, Primary Containment Isolation Instrumentation
05000249/LER-2003-001, Regarding Drywell Radiation Monitor Detector Not Fully Inserted
05000296/LER-2002-001, Re Failure to Meet Technical Specification Requirements for Inoperable Primary Containment Isolation Instrumentation Due to Removal of Incorrect Temperature Switches
NUREG-1433, Part 1- Edwin I. Hatch, Units 1 & 2, License Amendments, Replace Current Technical Specification & Associated Bases
05000278/LER-2018-002, Reactor Coolant System Pressure Boundary Leakage Resulting in Technical Specification Required Shutdown
05000298/LER-2015-004, Regarding Isolation of Shutdown Cooling Results in a Loss of Safety Function
RS-23-081, Request for License Amendment to Revise Technical Specifications Related to Reactor Water Cleanup Isolation Instrumentation
NRC-06-0044, Response to Request for Additional Information for Revision to License Amendment Request to Revise Technical Specification 3.3.6.1, Primary Containment Isolation Instrumentation
RS-20-136, Response to Request for Additional Information Re License Amendment Requests for Amendments to Renewed Facility OL to Adopt 10CFR50.69 & to Adopt TSTF-505, Rev. 2 (EPID L-2020-LLA-0017 and EPID-L-2020-LLA-0018)
RS-05-104, Revised Technical Specification Pages for License Amendment Related to Revision of Instrument Channel Trip Setpoint Allowable Values
GNRO-2003/00058, Supplement to Amendment Request, Proposed Changes to Primary Containment and Drywell Isolation Instrumentation Requirements
RS-19-054, Application to Revise Technical Specifications Following Adoption of TSTF-542, Reactor Pressure Vessel Water Inventory Control
05000296/LER-2016-003, Regarding Main Steam Isolation Valve Leaking in Excess of Technical Specification Requirements
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
PLA-7108, Response to NRCs Request for Additional Information Regarding Request to Change Technical Specification 3.3.6.1
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
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
NL-21-0634, Request to Eliminate Automatic Main Steam Line Isolation on High Turbine Building Area Temperature
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
05000263/LER-2023-003, Condition Prohibited by Technical Specifications Due to Inoperable Main Steam Line Low Pressure Isolation Switch
PLA-8144, Proposed Amendment to Licenses NPF-14 and NPF-22: Revised Reactor Vessel Water Level 3 and Level 8 Allowable Value PLA-8144
PLA-8164, Modification to Technical Specification 2.6.1.3 Main Steam Line Isolation System Leakage Rate Surveillance Requirements
JAFP-21-0093, Propose Change to Eliminate Selected Response Time Testing for Reactor Protection System and Primary Containment Isolation Instrumentation
NL-23-0928, Application to Revise Technical Specifications to Adopt TSTF-584, Eliminate Automatic RWCU System Isolation on SLC Initiation
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
BSEP-97-0443, Suppl to Application for Amends to Licenses DPR-71 & DPR-62, Converting Current TS to Improved Ts,As Contained in Rev 1 of NUREG-1433.Rev a to Improved TS & Revised Responses to 970808 & 970911 RAIs Also Encl
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
GO2-96-132, Requests Amend to Ts,Revising Rev a, Including Changes in Vol 7.Proposed Rev Does Not Change Conclusion of Nhsc or Environ Assessment Provided in Rev a
05000461/LER-1996-007, :on 960529,discovered Inoperable Leak Detection Instruments.Caused by Personnel Error.Personnel Briefed Re Event & Labelled Both Reactor Water Cleanup Sys HX Rooms Ceiling Plugs
05000325/LER-1982-122-03, /03L-0:on 821030 & 1104,1A Pump Tripped.On 821101 & 04,1B Pump Tripped.Tripping Concurrent W/Receipt of ATWS High Reactor Pressure/Low Level Trip Annunciation. Caused by Actuation of ATWS Due to Electrical Shorting
RBG-46211, Proposed Upgraded Emergency Action Levels (Eals) Using NEI 99-01, Revision 4 Methodology - LAR 2003-027
CNL-14-148, Response to Request for Additional Information Draft Two-Unit Offsite Dose Calculation Manual, Revision B
L-09-218, Submittal of Technical Specification Bases, Revision 7
JAFP-25-0033, Response to NRC Request for Additional Information for License Amendment Request to Eliminate Remaining Main Steam Line Radiation Monitor Initiated Isolation Functions
RS-25-129, Response to Request for Additional Information Related to License Amendment Request for Clinton Power Station to Approve a Methodology for Testing MSIV Closure RPS Response Time
RS-25-132, Supplement to Clinton Response to Request for Additional Information Related to Response Time Testing License Amendment Request
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