1CAN031703, Steam Generator Tube Inspection Report - 1R26
NL-17-134, Radiation Monitor R-26 Inoperable
JAFP-17-0103, Pressure and Temperature Limits Report, Rev. 1 (40 Effective Full-Power Years)
NL-16-103, Steam Generator Tube Inspection Report -Spring 2016 Refueling Outage (2R22)
NL-16-083, Post Accident Monitoring (PAM) Report for an Inoperable Containment Area Radiation Monitor (R-26) High Range, Indian Point Unit Number 3
L-PI-16-030, Transmittal of 2015 180-Day Steam Generator Tube Inspection Report
BSEP 18-0021, Response to Request for Additional Information Regarding Request for License Amendment Regarding Core Flow Operating Range Expansion (CAC Nos. MF8864 and MF8865). Without Proprietary Enclosure
NL-15-118, Post Accident Monitoring (PAM) Report for an Inoperable Reactor Vessel Level Indication System (RVLIS) Train B, Indian Point Unit 3
AEP-NRC-2015-01, Steam Generator Tube Inspection Report
NL-13-1773, Application for Amendment to Technical Specifications Regarding Relocation of Pressure and Temperature (P-T) Curves to the Pressure and Temperature Limits Report (PTLR) Consistent with TSTF-419-A (NL-13-1773)
NRC 2015-0004, LAR 266 to Revise Technical Specifications to Adopt TSTF-51 0, Revision 2, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection, Using the Consolidated Line Item Improvement Process
NL-15-001, Response to Request for Additional Information (RAI) for the Steam Generator Examination Program Results 2014 Refueling Outage (2R21)
NL-14-113, Steam Generator Examination Program Results 2014 Refueling Outage (2R21)
CNS-14-035, Submittal of Post Accident Monitoring (PAM) Report
PNP 2014-009, 40-Year Containment Tendon Surveillance Report
NL-13-166, Report on Inoperable Gross Failed Fuel Detector
NL-13-148, Report on Inoperable Main Steam Line Radiation Monitor
1CAN101306, Unit 1, Steam Generator Tube Inspection Report - 1R24
L-PI-13-052, 2012 180-Day Steam Generator Tube Inspection Report
NL-13-082, Report on Inoperable Core Exit Thermocouple
SBK-L-13030, LAR 13-02 - Application to Revise Technical Specifications to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection, Using the Consolidated Line Item Improvement Process
L-PI-12-107, 2012 180-Day Steam Generator Tube Inspection Report
L-2012-231, Supplement to License Amendment Request No. 221: Application to Revise Technical Specifications to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample.
L-12-271, License Amendment Request to Modify Technical Specification 3.1.3, Moderator Temperature Coefficient Measurement (Mtc), to Provide an Exemption Under Certain Conditions
L-PI-12-054, Application to Revise Technical Specifications Associated with Steam Generator Replacement and Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection
NL-12-060, Submittal of Report on Inoperable Gross Failed Fuel Detector
NL-12-024, Technical Specification 5.6.7 -. IP2 Steam Generator Tube Inspection Report - Spring 2012 Refueling Outage
1CAN031203, Unit 1, Steam Generator Tube Inspection Report - 1R23
NL-11-103, Report on Inoperable Main Steam Line Radiation Monitor
NL-11-016, Revised Report on Inoperable Main Steam Line Radiation Monitor
NL-11-009, Report on Inoperable Main Steam Line Radiation Monitor
NL-18-063, Submission of IP2 Steam Generator Examination Program Results for the 2018 (2R23) Refueling Outage in Accordance with Technical Specification 5.6.7
NL-14-001, Indian Point, Unit 2 - Proposed License Amendment for Alternate Repair Criteria for Steam Generator Tube Inspection and Repair
1CAN111002, Response to Request for Additional Information Regarding the 2010 Steam Generator Tube Inspections
TSTF-10-17, Response to NRC Comments and Submittal of Revision 2 of TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection
TSTF-10-08, Response to Request for Additional Information and Revision to TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection
NL-09-148, Report on Inoperable Post Accident Monitoring Instrument Neutron Source Range
NL-09-108, Submittal of Report on Inoperable Core Exit Thermocouples
NL-09-085, Report on Inoperable Auxiliary Feedwater Flow Monitor
PLA-6519, Submittal of Special Report - Reactor Vessel Water Level Extended Range Channel Inoperable for More than Thirty Days
NL-09-055, Report on Inoperable Post Accident Monitoring Instrumentation Gross Failed Fuel Detector, Radiation Monitors R63A/B
L-PI-09-021, 2008 Unit 2 180-Day Steam Generator Tube Inspection Report
1CAN030907, Steam Generator Tube Inspection Report - 1R21
TSTF-09-08, Transmittal of TSTF-510, Revision 0, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection
NL-08-166, Technical Specification 5.6.7 - Steam Generator Tube Inspection Report - Spring 2008 Refueling Outage
JAFP-08-0098, Supplement to the Application for Amendment to Technical Specifications Regarding Relocation of Pressure and Temperature (P-T) Curves to the Pressure and Temperature Limits Report (PTLR) Consistent.
L-PI-08-036, Day Steam Generator Tube Inspection Report
NL-08-055, Report on Inoperable Post Accident Monitoring Instrumentation for Position Indication for Containment Isolation Valves CA-PCV-1229 and CA-PCV-1230
1CAN110701, Steam Generator Tube Inspection Report
L-PI-06-102, Unit 2 Steam Generator Inspection Results - 15 Day Report
L-HU-06-026, Supplement to Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity
1CAN060601, Steam Generator Tubing Inspection Report
PNP 2018-057, 45-Year Containment Tendon Surveillance Summary Report
NLS2019022, Application for Technical Specifications Improvement to Eliminate Requirements for Hydrogen/Oxygen Monitors (TSTF-447, Rev. 1)
ET 12-0006, Application to Revise Technical Specifications to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection, Using the Consolidated Line Item Improvement Process
1CAN080401, Arkansas, Unit 1 - Once Through Steam Generator Inservice Inspection Report
WO 04-0035, Application for Technical Specification Improvement to Eliminate Requirements to Provide Monthly Operating Reports and Occupational Radiation Exposure Reports Using the Consolidated Line Item Improvement Process
BSEP 04-0015, Supplement to Request for License Amendments Regarding Core Flow Operating Range Expansion
L-PI-03-089, License Amendment Request (LAR) Dated 10/31/03, Changes to Technical Specifications to Implement NEI 97-06, Steam Generator Program Guidelines, and Inspection Requirements Associated with Unit 1 Replacement Steam Generators
NG-03-0123, Technical Specification Change Request (TSCR-059): Adoption of Generic Letter 96-03: 'Relocation of Pressure Temperature Limit Curves & Low Temperature Overpressure Protection System Limits.'
NRC-02-0010, Special Report of Inoperable Main Steam Line Isolation Valve Position Indication
TSTF-20-04, Technical Specifications Task Force - Transmittal of TSTF-577, Revision 0, Revised Frequencies for Steam Generator Tube Inspections
CNL-20-053, Application to Revise Watts Bar Nuclear Plant, Unit 1, Technical Specifications for Steam Generator Tube Inspection Frequency & to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies & Tube Sample Selection, (WBN-39
NUREG-1431, Forwards Request for Addl Info Re Amend to TS Sections 5.0 & 3.8,proposed by Util on 961213,per Improved TS in NUREG-1431
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
RA-20-0363, Post Accident Monitoring Report 369-2020-01
BW990042, Forwards Braidwood Station,Unit 1 Post Accident Monitoring Rept for Reactor Vessel Level Indication Sys (Rvlis),Due to Facility Train B RVLIS Being Restored to Operable Status After 7-day Completion Time,Per TS 3.3.3 & 5.6.7
L-PI-22-040, Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections
RA-22-0280, Supplement to License Amendment Request to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-577, Revised Frequencies for Steam Generator Tube Inspections
RS-22-123, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator
L-PI-22-047, Resubmittal of Prairie Island Nuclear Generating Plant (PINGP) 2018 Unit 1 180-Day Steam Generator Tube Inspection Report
L-PI-23-001, Day Steam Generator Tube Inspection Report
AEP-NRC-2020-78, License Amendment Request Regarding a Change to the Steam Generator (SG) Program to Allow for a One-Time Deferral of SG Inspections
RS-23-050, Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube.
NRC-14-0061, Post Accident Monitoring Report Regarding Inoperable Instrumentation
L-PI-10-099, Unit 2 180-Day Steam Generator Tube Inspection Report
L-PI-03-094, 2003 Steam Generator Inspection Results, 15-Day Report
NRC-24-0041, Technical Specification (TS) 5.6.7 - Post Accident Monitoring Report
1CAN080902, Response to Request for Information Regarding Steam Generator Tube Integrity During Break in Upper Hot Leg Piping
1CAN090401, Arkansas, Unit 1 - License Amendment Request Proposed Technical Specification Change for Revision to ANO-1 Steam Generator Tube Inservice Inspection Program
NL-13-145, Proposed License Amendment to Adopt TSTF-510, Revision 2, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection Indian Point Unit Nuclear Generating Unit Nos. 2 and 3
NRC-12-0065, Post Accident Monitoring Report
NL-12-024, Indian Point Unit 2, Technical Specification 5.6.7 - IP2 Steam Generator Tube Inspection Report - Spring 2012 Refueling Outage
3F0697-10, TS Change Request 210 to License DPR-72,supporting Operation W/Hardware Changes Primarily Involving Efw,Hpi,Emergency Feedwater Initiation & Control Sys & Edgs,As Well as Associated Licensing & Design Bases Changes
BSEP 04-0098, Request for License Amendments Deletion of Hydrogen and Oxygen Analyzer Requirements Consolidated Line Item Improvement Process (TSTF-447, Revision 1)
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
RS-22-086, R. E. Ginna Nuclear Power Plant - Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam.
BSEP 17-0093, Response to Request for Additional Information Regarding Request for License Amendment Regarding Core Flow Operating Range Expansion
NOC-AE-140031, Application to Revise Technical Specifications to Adopt TSTF-510-A, Revision 2, Revision to Steam Generator Program Inspection Frequencies & Tube Sample Selection, Using the Consolidated Line Item Improvement Process
CNS-14-026, Exigent License Amendment Request (LAR) to Revise Technical Specification (TS) 3.3.4, Remote Shutdown System
05000341/LER-2012-004, Regarding Operation or Condition Prohibited by Technical Specification 3.3.3.1
1CAN102104, Steam Generator Tube Inspection Report - 1R29
PNP 2025-005, 50-Year Containment Tendon Surveillance Inspection Summary Report
RA-21-0076, Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections
L-PI-22-003, Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections
NRC-24-0057, Update to NRC 24-0041: Technical Specification (TS) 5.6.7 – Post Accident Monitoring Report
PNP 2025-030, Correction to 50-Year Containment Tendon Surveillance Inspection Summary Report Supplement
DCL-04-123, License Amendment Request 04-06 Removal of Technical Specifications 5.6.1, Occupational Radiation Exposure Report, and 5.6.4, Monthly Operating Reports
ULNRC-05074, Application for Technical Specification Improvement to Eliminate Requirements to Provide Monthly Operating Reports and Occupational Radiation Exposure Reports Using the Consolidated Line Item Improvement Process
TSTF-24-03, Correction of TSTF-591, Revision 0, Revise the Risk Informed Completion Time (RICT) Program
TSTF-20-07, TSTF Response to NRC Questions on TSTF-577, Revision 0, Revised Frequencies for Steam Generator Tube Inspections, and Submittal of Revision 1
JAFP-08-0034, Application for Amendment to Technical Specifications Regarding Relocation of Pressure and Temperature (P-T) Curves to the Pressure and Temperature Limits Report (PTLR) Consistent with TSTF-419-A