NG-17-0086, Transmittal of Revision 24 of the DAEC Updated Final Safety Analysis Report and the Current DAEC Technical Specifications Bases
NMP2L2652, License Amendment Request - Revise Surveillance Requirement 3.5.1.2 to Remove Note
L-MT-17-058, Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control
CNL-16-159, Application to Modify Technical Specifications to Extend Surveillance Requirement (SR) Intervals for SRs 3.6.11.2 and 3.6.11.3 (WBN-TS-16-022)
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
NRC-15-0091, License Amendment Request to Revise Technical Specification Section 3.5.1, ECCS - Operating
NRC-15-0090, License Amendment Request to Revise Technical Specifications to Adopt TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process
L-MT-15-048, License Amendment Request: Revise Technical Specifications to Adopt TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process
NL-14-1349, License Amendment Request to Revise Technical Specifications Regarding Generic Letter 2008-01, Managing Gas Accumulation in Accordance with TSTF-523, Revision 2, Using the Consolidated Line Item Improvement..
PLA-7125, Response to Request for Additional Information on Change to Technical Specification Surveillance Requirement 3.5.1.12
PLA-7092, Withdrawal of Relief Requests 1RR07 and 2RR07 for Third Ten-Year Interval Inservice Testing Program Plans for Susquehanna Ses (SSES) Unit 1 and Unit 2, PLA-7092
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
NRC-12-0044, Response to Request for Additional Information Regarding Proposed License Amendment to Modify Technical Specification Surveillance Requirements for Safety Relief Valves
NRC-12-0015, Submittal of Revised Relief Request No. PRR-002 for the Inservice Testing Program Third 10-Year Interval
L-MT-12-004, License Amendment Request: Revise Technical Specification Requirements for Testing the Main Steam Safety/Relief Valves
L-MT-11-018, Response to Request for Additional Information Related to Generic Letter 2008-01
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
L-2018-054, Turkey Point, Units 3 and 4 - 2017 Annual Radioactive Effluent Release Report
NL-16-109, Indian Point 2 Technical Requirements Manual
RS-11-100, Dresden, Units 2 and 3, Updated Final Safety Analysis Report (Ufsar), Revision 9, Technical Specification Bases
JAFP-10-0039, Response to Request for Additional Information Application for Amendment to Modify the Technical Specifications Requirements for Testing of Safety/Relief Valves
NRC-10-0003, Proposed License Amendment to Revise the Core Spray Flow Requirement of Technical Specification Surveillance Tests SR 3.5.1.8 and SR 3.5.2.6
JAFP-09-0131, Application for Amendment to Modify Technical Specifications Section 5.5.7, Inservice Testing Program, to Reference the Current Code of Record
RS-09-153, Response to Request for Additional Information Regarding Generic Letter 2008-01
RS-09-149, Response to Request for Additional Information Regarding Generic Letter 2008-01
JAFP-09-0087, Application for Amendment to Modify the Technical Specifications Requirements for Testing of Safety/Relief Valves
BVY 08-084, Technical Specifications Proposed Change No. 273, Supplement 5, Response to Request for Additional Information
RS-08-131, General Company, LLC and Amergen Energy Company, LLC, Nine-Month Response to Generic Letter 2008-01
L-MT-08-063, Nine-Month Response to NRC Generic Letter 2008-01, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems.
NLS2007036, Technical Specification Bases Changes
L-MT-07-014, License Amendment Request to Revise Technical Specification Surveillance Requirement 3.5.1.3 to Correct the Alternate Nitrogen System Pressure
BSEP 06-0129, Request for License Amendments Regarding Linear Heat Generation Rate and Core Operating Limits Report References for Areva Np Fuel
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
NRC-2014-0132, FRN: Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations: Publication Date: June 6, 2014
RA-19-0015, Request for License Amendment: Surveillance Requirements for Safety Relief Valves
TSTF-19-05, Transmittal of TSTF-541, Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position
RS-05-007, Request for Amendment to Technical Specifications Associated with Isolation Condenser System Heat Removal Capability Surveillance
TSTF-19-09, Technical Specifications Task Force - Transmittal of TSTF-576, Revision 0, Revise Safety/Relief Valve Requirements
RS-04-106, Additional Information Regarding Request for Amendment to Technical Specifications Surveillance Requirements for the Main Steam Line Relief Valves and Associated Relief Requests
NL-04-0981, Transmittal of Quarterly Update for Hatch, Units 1 and 2 Technical Specifications Bases
RS-04-005, Request for Amendment to Technical Specifications Surveillance Requirements for the Main Steam Line Valves and Associated Relief Requests
RS-03-157, Additional Information Regarding Inservice Testing Program Relief Requests
RS-03-100, Additional Information Supporting the Request for Amendment to Technical Specifications Surveillance Requirements for the Main Steam Line Relief Valves and Relief Request RV-30E
RS-03-090, Request for Amendment to Technical Specifications Surveillance Requirements for the Main Steam Relief Valves and Relief Request RV-30E
NL-20-0949, License Amendment Request to Revise, Technical Specifications to Adopt TSTF-541, Revision 2
NLS2021018, Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements
JAFP-20-0083, Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule
NG-97-1597, Forwards Response to Request for Addl Info on Improved Tech Spec Change Re Not Entering LCO Action Statements During Certain Surveillances
NRC-96-0117, Provides 180-day Response for NRC Bulletin 96-003, Potential Plugging of Emergency Core Cooling Suction Strainers by Debris in Bwrs,
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
ST-HL-AE-5571, Submits Suppl Info Re STP Proposed Improved TS
HL-5276, Application for Amends to Licenses DPR-57 & NPF-5,which Provides an Alternate Method of Testing S/Rvs During Shutdown Conditions Rather than During Unit Startup as Is Currently Done
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)
NLS2023007, Technical Specification Bases Changes
NL-16-0091, License Amendment Request to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application
NRC-19-0054, DTE Energy Company - License Amendment Request to Revise Technical Specifications to Change Surveillance Intervals to Accommodate a 24-Month Fuel Cycle
NL-11-0162, Submittal of Revision to Relief Request RR-V-4 Fourth 10-Year Interval Inservice Testing Program
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
05000265/LER-2022-001, Electromatic Relief Valve 3B Did Not Actuate Due to Incorrectly Oriented Plunger Well Plastic Guides
05000333/LER-2021-002, Automatic High Pressure Coolant Injection (HPCI) System Function Prevented by Control Circuit Relay Failure
JAFP-11-0046, 2011 Updated Final Safety Analysis Report, Technical Specification Bases and Technical Requirements Manual Changes Transmittal
AECM-90-0089, Forwards Draft Tech Specs for Power Distribution Limits,Rcs, ECCS & Plant Sys as Part of Util Involvement W/Bwr Owners Group as BWR-6 Lead Plant
CP-201101065, Comanche Peak Units 1 & 2 Final Safety Analysis Report (Fsar), Amendment 104, Technical Specifications Bases
TSTF-19-12, TSTF Comments on Draft Safety Evaluations for Traveler TSTF-541, Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position
NRC-23-0063, Inservice Testing Program for Pumps and Valves - Part 12: IST Program Pump Basis Revision 1
CP-200801015, Technical Specification Bases for Comanche Peak Steam Electric Station Units 1 & 2
TSTF-19-08, Draft of Traveler TSTF-582, Revision 0, RPV WIC Enhancements
RS-03-087, Request for Amendment to Technical Specifications Surveillance Requirements for the Main Steam Line Relief Valves and Relief Request RV-30D
GO2-97-057, Application for Amend to License NPF-21,modifying Response Time Testing Surveillance Requirements for RPS Instrumentation,Primary Containment Isolation Actuation Instrumentation & ECCS Actuation Instrumentation
BSEP 16-0087, License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-423, Revision 1, Technical Specifications End States, NEDC-32988-A
CNL-16-164, Application to Modify Technical Specifications to Extend Surveillance Requirement Intervals for AC Sources (WBN-TS-16-024)
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
RBG-47605, Application for Technical Specification Changes for Technical Specification Task Force (TSTF) Improved Standard Technical Specification Change Traveler, TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation
05000341/LER-2015-002, Regarding Loss of Both Divisions of the Residual Heat Removal Low Pressure Coolant Injection Functions Due to 480 Volt Swing Bus Inoperable
RS-17-029, Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control
05000260/LER-2012-003, Regarding 480V Reactor Motor Operated Valve Board 2E Failed to Manually Transfer to Alternate Power
CP-201300130, Comanche Peak, Units 1 & 2, Technical Specification Bases, Revision 67
05000387/LER-2009-001, Regarding High Pressure Coolant Injection System Inoperable Due to Turbine Stop Valve Failure
HL-6261, Third 10-Year Interval Inservice Testing Program, Revision to Existing Relief Request RR-V-11
NUREG-1433, Part 1- Edwin I. Hatch, Units 1 & 2, License Amendments, Replace Current Technical Specification & Associated Bases
CP-201000212, Technical Specifications Bases for Comanche Peak Steam Electric Station, Units 1 and 2
GO2-17-028, License Amendment Request for Change to Technical Specification 3.5.1, ECCS-Operating
JAFP-09-0132, Application for Amendment to Modify the Technical Specifications Requirements for Testing of Safety/Relief Valves
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
CNL-25-008, Application to Modify Sequoyah Nuclear Plant, Unit 2 Technical Specifications to Extend Surveillance Requirement (SR) Intervals for SRs 3.6.12.2 and 3.6.12.3 (SQN-TS-24-006)
TSTF-21-03, TSTF Response to NRC Questions on TSTF-576, Revision 0, Revise Safety/Relief Valve Requirements and Submittal of Revision 1
LR-N25-0015, License Amendment Request (LAR) - Hope Creek Technical Specification Conversion to NUREG-1433, Revision 5, Supplement 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
NRC-98-0146, Submits Required 30-day Rept Confirming Completion of Requested Actions Contained in NRC Bulletin 96-003, Potential Plugging of ECCS Suction Strainers by Debris in Bwrs
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
NLS2004007, License Amendment Request - One-Time Extension of Surveillance Requirements
BSEP-98-0090, Provides Comments on Draft SE Re Conversion to Improved Tech Specs.Encl 2 Provides Draft SE pages,marked-up to Reflect Comments as Well as Addl Editorial Comments
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
NRC-99-0050, Forwards Rev 7 to ITS Submittal of 980403,to Provide Remaining Responses to NRC RAIs Re ITS Sections 3.5 & 3.8. Revision Instructions Included
TSTF-23-06, TSTF Response to NRC Request for Additional Information on TSTF-576, Revision 2, Revise Safety/Relief Valve Requirements
TSTF-23-04, Technical Specifications Taskforce Transmittal of TSTF-576, Revision 2, Revise Safety/Relief Valve Requirements
L-09-141, Application to Permit Operation with ASTRUM Best-Estimate Large Break Loss of Coolant Accident (LOCA) Methodology
NL-24-0064, Units 1 & 2 and Hatch Nuclear Plant - Units 1 & 2 License Amendment Request to Revise Technical Specification 1.1 and Add Online Monitoring Program to Technical Specification 5.5