NL-17-0534, Technical Requirements Manual
NL-16-0630, Resubmittal of Clean-Typed Pages for Multiple Technical Specifications Task Force Traveler Adoption
DCL-16-028, Technical Specifications B.4.17., Steam Generator (SG) Tube Integrity, LTOP Orifice-Key Design Features, and Additional Information
NL-15-094, Proposed Changes to Technical Specifications Regarding Reactor Vessel Heatup and Cooldown Curves and Low Temperature Overpressure Protection System Requirements
NRC 2014-0075, Supplement to License Amendment Request 273 Application for Technical Specification Change Regarding Risk-Informed Justifications for the Relocation of Specific Surveillance Frequency Requirements to Licensee Controlled Prog
ONS-2014-064, Technical Specification (TS) Bases Change
MNS-14-003, License Amendment Request for Technical Specification (TS) 3.4.12, Low Temperature Overpressure Protection (LTOP) System
ULNRC-05975, Revision to TS LCO 3.4.12, Cold Overpressure Mitigation System (Coms), to Clarify No Limitation on Normal Charging Pump Use During Modes 4, 5 and 6 License Amendment Request LDCN 13-0003
PNP 2012-097, Report to NRC of Changes to Technical Specifications Bases
NL-17-0534, Joseph M. Farley Nuclear Plant, Technical Requirements Manual
NL-16-2280, Vogtle Electric Generating Plant, Units 1 & 2, Updated Final Safety Analysis Report, Bases for Improved Technical Specifications
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 7 of 8
NL-15-014, Indian Point, Unit 3 - Proposed Changes to Technical Specifications Regarding Reactor Vessel Heatup and Cooldown Curves and Low Temperature Overpressure Protection System Requirements
NL-14-121, Indian Point, Unit 2, Updated Final Safety Analysis Report (Ufsar), Revision 25, Technical Specification Bases List of Effective Sections
NL-14-121, Indian Point, Unit 2, Amendment Update to the Updated Final Safety Analysis Report (Ufsar), Revision 25
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
L-09-072, License Amendment Request to Incorporate the Use of Alternate Methodologies for Development of Reactor Pressure Vessel Pressure-Temperature Limit Curves and Request for Exemption from Certain Requirements Contained in 10 Cfr
RS-08-161, Braidwood, Units 1 and 2 - Technical Specification Bases
ULNRC-05459, Application for Amendment to Facility Operating License No. NPF-30, Adoption of Industry Travelers TSTF-247-A and TSTF-352-A
1CAN100701, License Amendment Request - Technical Specification Changes Regarding Mode Change Limitations and Associated Bases Using the Consolidated Line Item Improvement Process
1CAN100703, License Amendment Request - Technical Specification Changes and Analyses Relating to Use of Alternate Source Term
NL-18-1299, Technical Requirements Manual
ULNRC-06478, Specifications to Adopt TSTF-545 Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing, (LDCN 18-0021)
RA-19-0308, Clean Technical Specifications Pages Regarding Application to Adopt TSTF-425, Revision 3
ET 14-0034, Application to Revise Technical Specifications to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process
NL-04-0548, Request to Revise Technical Specifications Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process
NL-04-0134, Request to Revise Technical Specifications to Relocate the Cold Overpressure Protection System Arming Temperature
NRC 2003-0033, Technical Specification Bases Revisions
DCL-02-061, Inservice Testing (IST) Program Plan, Revision 18
RBG-45935, Part B - Revisions 58 -76 to River Bend Station Technical Requirements Manual & Technical Specification Bases
L-PI-20-004, License Amendment Request to Revise Technical Specifications (TS) to Remove Note I from Limiting Condition for Operating (LCO) 3.4.12 and LCO 3.4.13
AEP-NRC-2020-01, License Amendment Request Regarding a Change to the Reactor Coolant System Pressure and Temperature Limits and Low Temperature Overpressure Protection (LTOP) System
NL-20-0442, Revisions to Technical Requirements Manual (TRM)
NSD-NRC-96-4833, Forwards Roadmap for Content of AP600 Tech Specs Vs NUREG-1431 & Description of General or Overall Changes Whose Explanations Apply to Multiple TS
NSD-NRC-98-5514, Forwards W Responses to FSER Open Items Re AP600.NRC Should Review Encl & Inform W of Status to Be Designated in NRC Status Column of Oits
NL-23-0020, Emergency License Amendment Request: Technical Specification Limiting Conditions for Operation 3.4.11, 3.4.12, and 3.4.13 Operability Requirements for Automatic Depressurization System Stage 4 Flow Paths Prior to Initial Criticality
3F0307-07, License Amendment Request 264, Revision 2: Application to Modify Improved Technical Specifications Regarding Steam Generator Tube Integrity and Response to Request for Additional Information
3F1206-02, License Amendment Request 264, Revision 1: Application to Modify Improved Technical Specifications Regarding Steam Generator Tube Integrity and Response to Request for Additional Information
ONS-2014-093, Technical Specification (TS) Bases Change
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
DCL-03-178, Response to NRC Request for Additional Information Regarding License Amendment Request 03-07, Revision to Technical Specifications (TS) 3.8.1 AC Sources - Operating & 3.8.4 DC Sources - Operating Surveillance Requirements
ULNRC-03664, Proposed Tech Specs 3/4.4.9 Re Pressure/Temp Limits
CNS-15-098, Technical Specification Bases Changes
NL-24-0259, License Amendment Request to Revise Technical Specification 3.4.14, Reactor Coolant System Pressure Isolation Valve Leakage, Surveillance Requirement 3.4.14.3 Acceptance Criteria and Miscellaneous Obsolete Changes
L-PI-06-097, License Amendment Request (LAR) to Revise Technical Specification (TS) 3.5.3 Operability Requirements for Safety Injection (SI) Subsystem
DCL-02-116, Letter Regards Inservice Testing Program Plan, Revision 19
05000370/LER-1999-002-02, :on 990318,noted Failure to Comply with TS 3.4.12 Requirements Re Two Centifugal Charging Pumps.Caused by Use of Wrong Procedure.Licensee Will Review & Revise Procedures & Operator Training Program as Needed
CPSES-200602341, License Amendment Request (LAR) 06-006, Revision to Technical Specification (TS) 5.5.8, Inservice Testing Program
05000302/LER-1995-018, :on 950922,inadequate ITS Note Allows Delayed Entry Into ITS Lco,Resulting in Violation of Its.Caused by Personnel Error.Its Not Clarified & Pertinent Procedures & Other ITS Notes Reviewed
05000302/LER-1996-016, :on 960430,review Revealed Control Room Emergency Ventilation Sys (CREVS) Not Consistent W/Improved Tech Specs.Caused by Personnel error.In-place Testing Performed & CREVS Trains Declared Operable
05000302/LER-1996-008, :on 960304,discovered That Ambiguous Note Caused Misinterpretation of Improved TS (ITS) SR 3.4.12.1 & Failure to Perform Required Surveillance Prior to Mode Ascension.Its Bases for SR Will Be Revised
DCL-04-002, Inservice Testing (IST) Program Plan, Revision 20
ND-19-1129, Supplement to the Request for License Amendment Regarding Protection and Safety Monitoring System Surveillance Requirement Reduction Technical Specification .
CP-200801015, Technical Specification Bases for Comanche Peak Steam Electric Station Units 1 & 2
DCL-18-105, Submittal of the Fourth Ten-Year Interval Inservice Testing (1ST) Program Plan, Revision 1
CP-201600216, License Amendment Request 16-001, Application to Revise Technical Specifications to Adopt TSF-545, Revision 3, TS Inservice Testing Program Removal and Clarify SR Usage Rule Application to Section 5.5 Testing
WO 12-0066, License Amendment Request to Revise Technical Specification 3.4.12, Low Temperature Overpressure Protection (LTOP) System
CP-201300130, Comanche Peak, Units 1 & 2, Technical Specification Bases, Revision 67
1CAN021004, Response to Request for Additional Information, Application for Technical Specification Improvement to Adopt TSTF-490, Revision 0, Deletion of E Bar Definition and Revision to RCS Specific Activity Tech Spec
1CAN030802, License Amendment Request Application for Technical Specification Improvement to Adopt TSTF-490, Revision 0, Deletion of E Bar Definition and Revision to RCS Specific Activity Tech Spec
3F0506-03, License Amendment Request 264, Revision 0, Application to Modify Improved Technical Specifications Regarding Steam Generator Tube Integrity
DCL-03-142, Response to NRC Request for Additional Information Regarding License Amendment Request 03-06, Revision to Technical Specification 3.8.1, AC Sources - Operating
DCL-05-023, Inservice Testing (IST) Program - Third Ten-Year Interval and IST Relief Requests
ET 06-0001, Revision to Technical Specification 5.5.8, Inservice Testing Program to Adopt Technical Specification Task Force Standard Technical Specification Change Traveler, TSTF-479, Revision 0
3F0506-05, 2005 Technical Specifications Bases Control Program
CP-201000212, Technical Specifications Bases for Comanche Peak Steam Electric Station, Units 1 and 2
AEP-NRC-2021-28, 10 CFR 50.90 License Amendment Request Regarding a Change to the Reactor Coolant System Pressure and Temperature Limits and Low Temperature Overpressure Protection (LTOP) System
NL-16-109, Indian Point 2 Improved Technical Specifications Bases
1CAN092101, License Amendment Request Proposed Technical Specifications 3.4.12 and 3.4.13 Revised Dose Calculations
1CAN122101, Response to Request for Supplemental Information Concerning Licensing Amendment Request to Revise Technical Specification 3.4.12 and 3.4.13
NSD-NRC-98-5561, Forwards W Responses to FSER Open Items on AP600.Summary of Encl Responses,Fser Open Item Number,Associated Oits Number & Status to Be Designated in W Status of Column of Oits, Provided in Table 1
NL-17-0534, Joseph M. Farley Nuclear Plant, Technical Specifications Bases
L-09-225, Supplemental Information Related to a License Amendment Request to Incorporate the Use of Alternate Methodologies for the Development of Reactor Pressure Vessel Pressure-Temperature Limit Curves, and Request for Exemption from