RS-17-145, Supplement to Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control
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)
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
NL-13-007, Supplement to Proposed Change to Containment Purge System and Pressure Relief Line Isolation Instrumentation Technical Specifications
GNRO-2012/00132, License Amendment Request for Revision of Technical Specification Allowable Value for Primary Containment and Drywell Isolation Instrumentation Function 3.c RCIC Steam Supply Line Pressure - Low
GNRO-2012/00096, License Amendment Request for Implementing a 24-Month Fuel Cycle, Grand Gulf Nuclear Station, Unit 1
NL-12-002, Proposed Change to Containment Purge System and Pressure Relief Line Isolation Instrumentation Technical Specifications
ULNRC-05654, Proposed Revision to Technical Specification 3.3.6, Containment Purge Isolation Instrumentation, (License Amendment Request LDCN 09-0040)
NG-11-0299, Response to Request for Additional Information Related to an Amendment to Adopt Technical Specifications Task Force Traveler TSTF-425, Revision 3, to Relocate Specific Surveillance Frequencies to a Licensee Controlled Program
RBG-47157, License Amendment Request, Changes to Technical Specification 3.3.6.1, Primary Containment and Drywell Isolation Instrumentation
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 2 of 9
NL-14-121, Indian Point, Unit 2, Updated Final Safety Analysis Report (Ufsar), Revision 25, Technical Specification Bases List of Effective Sections
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
RNP-RA/10-0001, Request for Technical Specification Changes to Section 3.3.2, Engineered Safety Feature, Actuation System (ESFAS) Instrumentation, and Section 3.3.6, Containment Ventilation Isolation Instrumentation
ULNRC-05566, Amplification for Amendment, Revision of Technical Specification 3.3.2 and 3.7.2 and Addition of New Technical Specification 3.7.19 (License Amendment Request OL-1277 Revised)
RS-08-161, Braidwood, Units 1 and 2 - Technical Specification Bases
TSTF-08-10, Transmittal of TSTF-507, Revision 0, CLIIP Traveler to Increase Standardization
GNRO-2013/00062, Supplement to the License Amendment Request for Implementing a 24 Month Fuel Cycle - Addendum
RA-19-0308, Clean Technical Specifications Pages Regarding Application to Adopt TSTF-425, Revision 3
RS-04-062, Technical Specifications Changes Related to Main Steam Line Flow-High Isolation Instrumentation
CPSES-200400149, License Amendment Request (LAR) 03-08 Common Stars License Amendment Implementation of WCAP-14333 and WCAP-15376 RTS and ESFAS Test Times, Completion Times, and Surveillance Test Intervals
ULNRC-04929, Common Stars License Amendment Regarding Implementation of WCAP-14333 and WCAP-15379, RTS and ESFAS Test Times, Completion Times, and Surveillance Test Intervals
ULNRC-04856, Technical Specification Bases, Revision 4
GNRO-2003/00025, License Amendment Request, Proposed Changes to Primary Containment and Drywell Isolation Instrumentation Requirements, Ldc 2003-033
RS-03-038, Request for Amendment to TS for Main Steam Line Low Pressure Isolation Function
JAFP-02-0124, Revision K to Proposed Technical Specification Change (License Amendment) Conversion to Improved Standard Technical Specifications
CNL-21-038, Application to Revise the Measurement Units for the Watts Bar Nuclear Plant, Unit 1 and Unit 2 Technical Specifications for the Containment Vent Isolation Instrumentation and Control Room Emergency Ventilation System Radiation Monitors (W
JAFP-21-0052, Emergency License Amendment Request, One Time Extension of Condition a to TS 3.5.1, TS 3.6.1.9, and TS 3.6.4.1 Completion Time to Support Residual Heat Removal (RHR) Pump Motor Replacement
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
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
3F0595-01, Application for Amend to License DPR-72,revising TSs to Allow Continuous Operation for Up to 24 Month Period
1CAN031306, License Amendment Request, Adoption of Technical Specification Task Force (TSTF)-431, Revision 3 Change in Technical Specifications End States (BAW-2441)
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 4 of 8
05000458/LER-2021-005, Potential Loss of Safety Function Due to Inoperable Reactor Core Isolation Cooling Steam Flow Transmitter
RS-21-078, Response to Request for Additional Information for Application to Revise Technical Specification to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements, and TSTF-583-T, TSTF-582 Diesel
DCL-04-013, License Amendment Request 03-17, Common Stars Amendment, Implementation of WCAP-14333 and WCAP-15376, RTS and ESFAS Test Times, Completion Times, and Surveillance Test Intervals
RNP-RA/02-0118, Response to Request for Additional Information on Technical Specifications Change Re Selective Implementation of Alternative Radiological Source Term
NL-03-2451, Request for Surveillance Test Interval Extensions for Components of the Reactor Protection System
RS-20-115, Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements
CP-201101065, Comanche Peak Units 1 & 2 Final Safety Analysis Report (Fsar), Amendment 104, Technical Specifications Bases
A08949, Responds to Comments Identified in Insp Rept 50-423/90-80 Re EOP at Millstone Unit 3
JAFP-24-0053, License Amendment Request to Eliminate Remaining Main Steam Line Radiation Monitor Initiated Isolation Functions
ND-19-1129, Supplement to the Request for License Amendment Regarding Protection and Safety Monitoring System Surveillance Requirement Reduction Technical Specification .
3F1089-23, Application for Amend to License DPR-72,consisting of Tech Spec Change Request 174 Re Proposed Heatup,Cooldown & Inservice Leak & Hydrostatic Testing Pressure/Temp Limits. Rept Re Low Temp Overpressure Protection Withheld
CP-200801015, Technical Specification Bases for Comanche Peak Steam Electric Station Units 1 & 2
05000296/LER-1999-003-01, :on 990408,declared Plant HPCI Sys Inoperable Due to Loose Wire.Caused by Failure to Properly Tighten Screw at Some Time in Past.Loose Wire Was Tightened
GO2-97-071, Forwards Response to RAI Related to Response Time Testing. W/Related Info
RS-17-029, Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control
RS-10-165, Follow-up Information Supporting Request for License Amendment Regarding Shutdown Cooling System Isolation Instrumentation
RS-12-223, License Amendment Request to Revise Technical Specification 3.3.6, Containment Ventilation Isolation Instrumentation
CP-201300130, Comanche Peak, Units 1 & 2, Technical Specification Bases, Revision 67
ET 08-0041, Revision to Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation
TSTF-07-24, TSTF-431, Revision 2, Change in Technical Specifications End States (BAW-2441)
TSTF-06-26, Submittal of TSTF-431, Revision 1, Change in Technical Specifications End States (BAW-2441)
RS-05-039, Response to Request for Additional Information for License Amendment Related to Revision of Instrument Channel Trip Setpoint Allowable Values
CP-201000212, Technical Specifications Bases for Comanche Peak Steam Electric Station, Units 1 and 2
RS-10-018, Request for License Amendment Regarding Shutdown Cooling System Isolation Instrumentation
L-22-053, Request for an Amendment to Consolidate Fuel Decay Time Technical Specifications in a New Limiting Condition for Operation Titled Decay Time
NL-17-0534, Joseph M. Farley Nuclear Plant, Technical Specifications Bases
TSTF-22-01, Technical Specifications Task Force - Transmittal of TSTF-589, Revision 0, Eliminate Automatic Diesel Generator Start During Shutdown
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