NL-14-046, Response to Request for Additional Information Regarding Containment Integrity Analysis
NL-13-003, Proposed Technical Specification Changes Regarding RWST Temperature and Containment Pressure in Containment Integrity Analysis
PNP 2012-097, Report to NRC of Changes to Technical Specifications Bases
NRC 2011-0021, License Amendment Request 262 Revision to Technical Specification Operating Limits to Include Measurement Uncertainty
NL-16-2280, Vogtle Electric Generating Plant, Units 1 & 2, Updated Final Safety Analysis Report, Bases for Improved Technical Specifications
NL-14-1075, E.I. Hatch, Units 1 and 2 - Technical Specifications. Part 2 of 4
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 2 of 8
NL-14-121, Indian Point, Unit 2, Updated Final Safety Analysis Report (Ufsar), Revision 25, Technical Specification Bases List of Effective Sections
NL-11-1812, Edwin I. Hatch, Unit 1 - Technical Requirements Manual
NL-10-107, Indian Point 2 (IP2) Nuclear Power Plant Amendment Update to the Final Safety Analysis Report (Fsar), Revision 22, Improved Technical Specifications Bases
RS-08-161, Braidwood, Units 1 and 2 - Technical Specification Bases
CNL-19-051, Application to Implement the Full Spectrum LOCA (Fsloca) Methodology for Loss-of-Coolant Accident (LOCA) Analysis and New LOCA-specific Tritium Producing Burnable Absorber Rod Stress Analysis Methodology
RA-19-0308, Clean Technical Specifications Pages Regarding Application to Adopt TSTF-425, Revision 3
PLA-5857, Proposed License Amendment. Numbers 271 for Unit 1 and 239 for Unit 2 for a Change to Technical Specification SR 3.6.4.1.4 and 3.6.4.1.5 Secondary Containment Drawdown Testing
L-14-343, Response to Request for Additional Information Regarding License Amendment Request to Extend Containment Leakage Rate Test Frequency
NL-03-1323, Request to Revise Technical Specifications, DC Sources and TSTF-360, Revision 1
RS-20-010, Application to Revise Technical Specifications 5.6.5, Core Operating Limits Report (COLR)
NRC 2002-0004, License Amendment Request 223 Re Containment Pressure
NSD-NRC-97-5485, Forwards Responses to FSER Open Items on AP600.Summary of Encl Responses Provided in Table 1
NL-06-0756, E. I. Hatch Operating License Revision to Support Use of Potassium Iodide for an Interim Period, Supplemental Information
NMP1L3026, License Amendment Request- Proposed Changes to the Technical Specifications to Address Secondary Containment Personnel Access Door Openings
NL-18-1132, Revision to Technical Specification 3.6.4.1 -Secondary Containment
1CAN031306, License Amendment Request, Adoption of Technical Specification Task Force (TSTF)-431, Revision 3 Change in Technical Specifications End States (BAW-2441)
05000413/LER-1989-013, :on 890412,discovered That Channel Checks for Containment Hydrogen Monitors Inadequate to Verify Standby Readiness of Monitors.Caused by Deficient Vendor Documentation.Hydrogen Monitor Repaired
CP-202200355, Application to Revise Technical Specifications to Apply the Westinghouse Full Spectrum Loss of Coolant Accident Evaluation Model LAR 22-002
L-21-238, License Amendment Request for Addition of Analytical Methodology to the Core Operating Limits Report for a Full Spectrum Loss of Coolant Accident
05000387/LER-2016-012, Regarding Secondary Containment Declared Inoperable Due to Loss of Differential Pressure as a Result of a Solenoid Valve
TSTF-15-07, Transmittal of TSTF-551, Revision 1, Revise Secondary Containment Surveillance Requirements
1CAN121403, License Amendment Request Supplemental ANO-1 Adoption of TSTF-431, Revision 3, Change in Technical Specifications End States (BAW-2441)
TSTF-07-24, TSTF-431, Revision 2, Change in Technical Specifications End States (BAW-2441)
NRC 2007-0052, Technical Specification Bases Change Summary
TSTF-06-26, Submittal of TSTF-431, Revision 1, Change in Technical Specifications End States (BAW-2441)
ET 02-0030, Operating Corporation Revision to Technical Specification 3.6.3, Containment Isolation Valves
DCL-18-100, License Amendment Request 18-02 - License Amendment Request to Revise Technical Specification 5.6.5b1 Core Operating Limits Report (COLR) for Full Spectrum Loss-of-Coolant Accident Methodology
WO 04-0030, Revision to Technical Specification 3.6.3, Containment Isolation Valves
NL-24-0417, License Amendment Request: Shutdown Actions Mode Change Restrictions
CNL-21-010, Correction of Application to Implement the Full Spectrum LOCA (Fsloca) Methodology for Loss-of-Coolant Accident (LOCA) Analysis and New LOCA-specific Tritium Producing Burnable Absorber Rod Stress Analysis Methodology (WBN-TS-19-04) (EPID
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
NL-17-0534, Joseph M. Farley Nuclear Plant, Technical Specifications Bases