L-17-042, Request for Licensing Action to Revise the Technical Specifications
NL-16-103, Steam Generator Tube Inspection Report -Spring 2016 Refueling Outage (2R22)
NL-16-0292, Response to Request for Additional Information on Revision to Secondary Containment Drawdown Time Technical Specifications Amendment Request
GO2-16-047, License Amendment Request to Revise Technical Specifications to Adopt TSTF-522, Revision 0
PNP 2017-067, Submittal of Changes to Palisades Nuclear Plant Technical Specifications Bases
GNRO-2015/00060, Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt Technical Specification Task Force (TSTF) TSTF-522, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours
PNP 2015-024, Requests Relief of Proposed Alternatives for the Fifth 10-Year Inservice Test Interval
AEP-NRC-2015-01, Steam Generator Tube Inspection Report
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)
NL-14-045, Correction to Entergy Letter NL-14-045, Indian Point Unit Number 2
RS-14-084, Responses to NRC Requests for Additional Information, Set 10, Dated February 26, 2014 Related to the License Renewal Application
RBG-47404, Unit 1, License Amendment Request 2013-17, Revision of the Ventilation Filter Testing Program and Associated Surveillance Requirements
SBK-L-12235, License Amendment Request 12-06, Application for Technical Specification Improvement to Extend the Inspection Interval for Reactor Coolant Pump Flywheels Using the Consolidated Line Item Improvement Process
NRC-12-0071, Application to Revise Technical Specifications to Adopt TSTF-522, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month, Using the Consolidated Line Item Improvement Process
GNRO-2012/00096, License Amendment Request for Implementing a 24-Month Fuel Cycle, Grand Gulf Nuclear Station, Unit 1
DCL-12-081, License Amendment Request 12-02 James M. Welsch Station Director 10 CFR 50.90 Revision to Technical Specification 5.5.7. Reactor Coolant Pump Flywheel Inspection Program (TSTF-421)
AEP-NRC-2012-38, Response to Request for Information, 10 CFR 50.46 Report for Emergency Core Cooling System Model Change or Error Associated with Thermal Conductivity Degradation
NLS2012039, Supplement to License Amendment Request for Implementing a 24-Month Fuel Cycle and Adoption of TSTF-493, Revision 4, Option a
NL-11-0007, Units 1 & 2 - Application for Technical Specification Improvement to Extend Inspection Interval for Reactor Coolant Pump Flywheels Using Consolidated Line Item Improvement Process
NL-11-087, Proposed License Amendment Regarding Travelers - TSTF-479-A and TSTF-497-A
NL-11-018, Response to Request for Additional Information on IP2 Steam Generator Inspection Report
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-16-109, Indian Point 2 Technical Requirements Manual
NL-14-121, Indian Point, Unit 2, Updated Final Safety Analysis Report (Ufsar), Revision 25, Technical Specification Bases List of Effective Sections
NL-14-001, Indian Point, Unit 2 - Proposed License Amendment for Alternate Repair Criteria for Steam Generator Tube Inspection and Repair
DCL-12-006, Diablo Canyon - Inservice Inspection Program Plan, Third 10-Year Inspection Interval, Revision 1, Page 201 Through Drawing No. 102028, Sheet 38
NL-10-107, Indian Point 2 (IP2) Nuclear Power Plant Amendment Update to the Final Safety Analysis Report (Fsar), Revision 22, Technical Requirements Manual
RS-11-100, Dresden, Units 2 and 3, Updated Final Safety Analysis Report (Ufsar), Revision 9, Chapter 6.0, Engineered Safety Features
JAFP-10-0019, Submittal of Corrected Proposed Technical Specifications Mark-Up Page and Final Typed Format with Change Bars
NL-09-1510, Vogtle Electric Generation Plant, Unit 2 - 3rd Interval VOGTLE-2 ISI Plan, Version 3.0
NL-09-1510, Vogtle Electric Generation Plant, Unit 1 - Third 10-Year Interval ISI Plan, Version 3.0
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-16-205, Relief Requests Associated with the Fourth Interval Inservice Testing Program
RBG-46754, Revision to License Amendment Request, Application for Technical Specification (TS) Change Regarding Ventilation Filter Testing Program (Vftp), TS 5.5.7, Control Room Fresh Air System (Crfas) Heater Wattage
BSEP 07-0081, Request for License Amendments to Revise Technical Specification 5.5.6, Inservice Testing Program, to Adopt Technical Specification Task Force (TSTF) Standard Technical Specification Change Traveler TSTF-479, Revision 0
L-PI-07-048, License Amendment Request (LAR) Incorporating Technical Specification Task Force (TSTF) Industry Travelers TSTF-479, TSTF-485, and TSTF-497
RBG-46669, License Amendment Request, Application for Technical Specification (TS) Change Regarding Ventilation Filter Testing Program (Vftp), TS 5.5.7, Control Room Fresh Air System (Crfas) Heater Wattage
NRC-2006-0032, License Amendment Request 242, Supplement 2 Technical Specification 5.5, Programs and Manuals
NL-06-008, Proposed Steam Generator Examination Program - 2006 Refueling Outage
NRC 2006-0018, License Amendment Request 242, Supplement 1 Technical Specification 5.5 Programs and Manuals
NRC-2011-0290, Biweekly Report - Applications and Amendments to Facility Operating Licenses Involving No Significant Hazards Considerations: Fr Publication Date December 27, 2011
NRC-2010-0309, FRN: General Notice. Biweekly Notice, Applications and Amendments to Facility Operating Licenses Involving No Significant Hazards Considerations, NRC-2010-0309
CNL-20-010, Application to Revise Sequoyah Nuclear Plant (SQN) Unit 1 Technical Specifications for Steam Generator Tube Inspection Frequency (SQN-TS-20-01)
NRC 2004-0107, License Amendment Request 242 Technical Specification 5.5, Programs and Manuals
CPSES-200401311, License Amendment Request (LAR) 04-01 Revision to Technical Specification (TS) 5.5.7 Extension of the Reactor Coolant Pump Flywheel Inspection Interval
LR-N04-0345, Request for Change to Technical Specifications to Extend the Inspection Interval for Reactor Coolant Pump Flywheels Using the Consolidated Line Item Improvement Process
ULNRC-04975, Application for Technical Specification Improvement to Extend the Inspection Interval for Reactor Coolant Pump Flywheels Using the Consolidated Line Item Improvement Process
WO 04-0001, Application for Technical Specification Improvement to Extend the Inspection Interval for Reactor Coolant Pump Flywheels Using the Consolidated Line Item Improvement Process
NRC-03-0090, 180-Day Response to Generic Letter 2003-01, Control Room Habitability.
NL-03-1556, Inservice Inspection Summary Report
PLA-5519, Proposed Amendment No. 248 to License NPF-14 & Proposed Amendment No. 213 to License NPF-22: Creoass Pressure Drop Limit
GO2-02-173, License Amendment Request - Technical Specification Change to Section 5.0, Administrative Controls
CNL-20-076, Response to Request for Additional Information Re Application to Revise Sequoyah Nuclear Plant (SQN) Unit 1 Technical Specifications for Steam Generator Tube Inspection Frequency (SQN-TS-20-01)
U-603243, Forwards Response to NRC GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal. Util Performing Testing of ESF Ventilation Sys Charcoal Samples Using ASTM D3803- 1989 Methodology as Required by TS 5.5.7
CNL-22-001, Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections (SQN-TS-21-03 and WBN-TS-21-08)
AEP-NRC-2022-42, Unit 2 Updated Steam Generator Tube Inspection Report to Reflect TSTF-577 Reporting Requirements
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
1CAN092301, Supplemental Information - Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4
RA-19-0039, License Amendment Request to Revise Technical Specifications to Adopt Two NRC-Approved Generic Technical Specification Changes
RS-05-111, Additional Information Supporting the Request for License Amendment Related to Application of Alternative Source Term
L-PI-03-007, Bulletin 2002-01, Reactor Pressure Vessel Head Degradation & Reactor Coolant Pressure Boundary Integrity, 60-day Response for Prairie Island Nuclear Generating Plant, Request for Additional Information
L-2010-122, Proposed License Amendment, Application to Delete Structural Integrity Technical Specifications, Update Accident Monitoring Instrumentation Requirements, and Minor Corrections
NRC-2016-0180, Biweekly FRN - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations- Publication Date: August 30, 2016
NRC-19-0054, DTE Energy Company - License Amendment Request to Revise Technical Specifications to Change Surveillance Intervals to Accommodate a 24-Month Fuel Cycle
2CAN012403, Supplemental Information - Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4
NL-18-1132, Revision to Technical Specification 3.6.4.1 -Secondary Containment
RS-03-060, Request for License Amendment Related to Application of Alternative Source Term
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
05000416/LER-2022-002, Loss of Secondary Containment During Standby Gas Treatment System Testing Due to Boundary Leakage
05000458/LER-1998-001-04, :on 980417,flow Rate Through SBGTS Filter Assembly Units Was Found to Be Higher than Design Flow Rate. Cause Analysis Is Currently Being Performed.Detailed Evaluation of Sys Ability to Perform Was Done
NRC-17-0044, License Amendment Request to Revise Technical Specification 5.5.7, Ventilation Filter Testing Program, to Be Consistent with Standard Technical Specifications
JAFP-11-0046, 2011 Updated Final Safety Analysis Report, Technical Specification Bases and Technical Requirements Manual Changes Transmittal
BYRON 2006-0027, Transmittal of Inservice Inspection Program Plan for Third Ten Year Inspection Interval
RS-16-248, Braidwood Nuclear Stations, Revision 16 to Updated Final Safety Analysis Report, Technical Requirements Manual
RS-08-045, LaSalle, Units 1 and 2, Technical Requirements Manual
RS-02-174, Co., Llc. (EGC) Application for Amendment to Licenses DPR-19, DPR-25, DPR-29 & DPR-30, Related to Application of Alternative Source Term, Attachments a - E-1
JAFP-18-0078, Fifth Ten-Year Interval Inservice Testing Program Plan
LD-99-002, Part 21 Rept Re Incorrect Modeling of BWR Lower Plenum Vol in Bison.Defect Applies Only to Reload Fuel Assemblies Currently in Operation at WNP-2.BISON Code Model for WNP-2 Has Been Revised to Correct Error
CNL-16-155, Application to Revise Technical Specifications to Adopt TSTF-545, Rev. 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing, to Request Alternative to the ASME Code, and to
PNP 2016-005, License Amendment Request - Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal and Clarify SR Usage Rule Application to Section 5.5 Testing
RBG-47572, Response to Request for Information - Change to Technical Specification 3.8.1, AC Sources - Operating
L-PI-14-015, 10 CFR 50.55a Requests RR-01, RR-03. RR-05, RR-06 and RR-07 Associated with the Fifth Ten-Year Interval for the Inservice Test Program
BW110084, Inservice Inspection Summary Report
05000458/LER-2010-002, Unit 1, Standby Gas Treatment Filter Inoperable Due to Inadequate Surveillance Test Acceptance Criteria
BW100010, Inservice Inspection Summary Report
L-2009-262, Proposed License Amendment Application to Delete Structural Integrity Technical Specifications, Update Accident Monitoring Instrumentation Requirements, and Minor Corrections
BSEP 07-0136, Revision of Request for License Amendments to Revise Technical Specification 5.5.6, Inservice Testing Program, to Adopt Technical Specification Task Force (TSTF) Standard Technical Specification Change Traveler TSTF-479
ULNRC-05422, Owners Activity Report (Form OAR-1) for Refuel 14
RS-06-154, Request for Amendment to Technical Specifications Section 5.5.7, Inservice Testing Program
NL-03-2418, Application for License Renewal Supplemental Information and Future Action Commitment List
RS-09-042, Request for Amendment to Technical Specifications Section 5.5.6, Inservice Testing Program to Incorporate Previously NRC-Approved Generic TS Changes
GNRO-2014/00057, Letter GNRO-2012/00146, Technical Requirements Manual and Technical Specification Bases Update (ML12361A330)
1CAN050807, Inservice Inspection Plan for the Fourth 10 - Year Interval
05000366/LER-2012-001, 0 for Edwin I. Hatch Nuclear Plant, 2B Standby Gas Treatment Filter Train Found Operating at Higher Flow than Allowed by Technical Specification
L-19-099, License Amendment Request to Modify Technical Specifications 3.4.16, RCS Specific Activity, 3.7.13 Secondary Specific Activity, 5.5.7, Ventilation Filter Testing Program (Vftp), and 5.5.14, Control Room Envelope
NLS2005075, Calculation Nedc 05-031, Review of Alion Calculation ALION-CAL-NPPD-3236-001, Radiological Dose Analysis for a Fuel Handling Accident (FHA) at Cooper Nuclear Station
05000416/LER-2019-006, Failure to Meet Technical Specification 5.5.7 for Division II Standby Gas Charcoal Filter Media Efficiency
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-02-160, Response to Request for Additional Information Regarding Sections 1.0, 2.0, 3.0, 3.1, 3.2, 3.3, 3.4, 3.5, 3.6, 3.7, 3.9, 4.0, & 5.0 of Improved TS
RS-10-052, License Amendment Request for an Extension of the Inspection Interval for Reactor Coolant Pump Flywheels Using the Consolidated Line Item Improvement Process
NL-16-109, Indian Point 2 Improved Technical Specifications Bases
L-20-097, Response to Request for Additional Information and Supplemental Information Regarding License Amendment Request to Modify Technical Specifications 3.4.16, RCS Specific Activity, 3.7.13 Secondary Specific Activity,.
05000458/LER-1998-001, :on 980417,flow Rate Through SGTS Filter Assembly Units Were Found to Be Higher than Design Flow Rate.Caused by Personnel Error.Reviewed & Updated Design & Licensing Basis Documents
RA-20-0252, License Amendment Request to Remove Extraneous Content and Requirements from the Operating License and Technical Specifications
05000254/LER-2022-003, Both Trains of Standby Gas Treatment Inoperable Due to Blockage in the Common Discharge Line
RS-24-101, License Amendment Request for One-Time Extension of Standby Gas Treatment System Technical Specifications Completion Time to Support Piping Repair
NLS2004007, License Amendment Request - One-Time Extension of Surveillance Requirements
L-14-245, Response to Request for Additional Information Regarding Request for Licensing Action on Alternative Accident Source Term Radiological Dose Calculations
NL-14-121, Indian Point, Unit 2, Updated Final Safety Analysis Report (Ufsar), Revision 25, Technical Requirements Manual
NL-16-2280, Vogtle Electric Generating Plant, Units 1 & 2, Updated Final Safety Analysis Report, Chapter 1, Introduction and General Description of Plant