05000416/LER-2015-003, Regarding Technical Specification Surveillance on Primary Containment Isolation Valves
NRC-17-0056, Supplemental Information Regarding License Amendment Request to Revise Technical Specifications to Adopt TSTF-545, Revision 3
RS-16-228, License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition
L-PI-16-054, Pressure and Temperature Limits Report, Revision 5
GO2-16-086, Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3
RIS 2012-10, NRC Staff Position on Applying Surveillance Requirements (SR) SR 3.0.2 and 3.0.3 to Administrative Controls Program Tests
2CAN111702, License Amendment Request - Updating the Reactor Coolant System Pressure-Temperature Limits
PNP 2015-089, Inservice Inspection Master Program Fifth 10-Year Interval
GNRO-2015/00076, Supplemental Letter to Application to Revise the Technical Specifications to Remove the Inservice Testing Program and to Clarify SR Usage Rule Application to Section 5.5 Testing to Provide Relief Request in Format Requested by Nrc
NG-15-0315, Technical Specification 5.6.6 Post Accident Monitoring (PAM) Report, October 2015
NG-15-0284, License Amendment Request (TSCR-1 30) for Amendment to Technical Specifications Section 5.5.6 for the Inservice Testing Program
JAFP-15-0098, License Amendment Request to Revise Technical Specifications Section 5.5.6 for Extension of Type a and Type C Leak Rate Test Frequencies
L-PI-15-034, Pressure and Temperature Limits Report (PTLR) Revision 4
GO2-15-055, Submittal of Fourth 10-Year Inservice Testing (IST) Program Plan
RBG-47553, Response to Request for Additional Information on License Amendment Request 2013-13
BYRON 2015-0026, Response to Request for Additional Information Regarding Pressure and Temperature Limits Reports
GO2-14-049, Relief Request for the Columbia Generating Station Fourth Ten-Year Interval Inservice Testing Program
PLA-7120, Revised Proposed Relief Requests for the Fourth Ten-Year Inservice Testing Interval for Susquehanna Units 1 and 2, PLA-7120
NG-13-0401, Relief Request for Hardship or Unusual Difficulty Without Compensating Increase in Level of Quality or Safety
NRC-13-0058, Submittal of Inservice Testing Program Relief, Request PVRR-001, for the Third Ten-Year Interval
PLA-7055, Proposed Relief Requests for the Fourth Ten-Year Inservice Testing Interval
1CAN081302, Response to Request for Additional Information, Adoption of Technical Specification Task Force (TSTF)-500, Revision 2, DC Electrical Rewrite - Update to TSTF-360
RBG-47350, License Amendment Request, Changes to Technical Specification 2.1.1, Reactor Core SLs
RS-12-149, Response to Request for Additional Information Regarding Relief Requests Associated with the Fifth Inservice Testing Interval
NL-11-087, Proposed License Amendment Regarding Travelers - TSTF-479-A and TSTF-497-A
NLS2011026, License Amendment Request for Administrative Revisions to Technical Specifications and to Remove an Expired One-Time Exception to the Five-Year Test Frequency for a Single Safety Valve
NL-17-067, Browns Ferry, Units 1, 2, and 3 - Administrative Changes to Proposed Revised Technical Specification Pages Related to Application to Revise Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing, to Request an A
NL-16-109, Indian Point 2 Technical Requirements Manual
ULNRC-06166, Callaway, Unit 1, Submittal of Revision 32 of Callaway Pump and Valve Inservice Testing Program
RS-12-221, Byron, Units 1 and 2, Updated Final Safety Analysis Report, Revision 14, Technical Requirements Manual
NL-10-107, Indian Point 2 (IP2) Nuclear Power Plant Amendment Update to the Final Safety Analysis Report (Fsar), Revision 22, Technical Requirements Manual
WO 10-0010, Updated Safety Analysis Report, Revision 23
RBG-46925, License Amendment Request, Technical Specification Change to Revise ASME Code Reference for Inservice Test Requirements
RS-09-042, Request for Amendment to Technical Specifications Section 5.5.6, Inservice Testing Program to Incorporate Previously NRC-Approved Generic TS Changes
RS-08-118, Additional Information Supporting Request to Revise Containment Tendon Surveillance Program
TSTF-08-10, Transmittal of TSTF-507, Revision 0, CLIIP Traveler to Increase Standardization
RS-08-036, License Amendment Request to Revise Containment Tendon Surveillance Program
NRC 2016-0034, Point Beach Nuclear Plant, Units 1 and 2, Periodic Update of the Final Safety Analysis Report (Fsar), Chapter 15 - Aging Management Programs and Time Limited Aging Analysis
GO2-07-156, Supplement to License Amendment Request for Proposed Changes to Technical Specifications: Miscellaneous Administrative Changes Including Adoption of Approved TSTF Travelers 284, 479, and 485
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
NLS2007048, License Amendment Request for a One-Time Exception to the Five-Year Test Frequency for a Single Safety Valve
BSEP-07-0064, Request for License Amendments, Technical Specification 5.5.12, Primary Containment Leakage Rate Testing Program
GNRO-2007/00021, Technical Specification Bases, Technical Requirements Manual and Core Operating Limits Updates to the NRC for Period Dated April 7, 2007
NL-07-028, Inservice Testing Program Summary for 4th Interval, Revision 0
PLA-6020, Proposed Amendment No. 287 and Proposed Amendment No. 255: Revision to Technical Specifications 5.5.6 & 5.5.12
NL-06-1458, Response to Request for Additional Information Regarding Technical Specification Review Request, Containment Tendon Surveillance Program
NLS2006044, Revision to License Amendment Request to Update the American Society of Mechanical Engineers Code Referenced in Technical Specification Section 5.5.6, Inservice Testing Program
NL-06-0266, Request for Technical Specification Amendment Re Containment Tendon Surveillance Program
NLS2006013, License Amendment Request to Update the American Society of Mechanical Engineers Code Referenced in TS Section 5.5.6, Inservice Testing Program
NL-06-0076, Request for Additional Information RR-58, Proposed Alternative to IWL-2421 (B) Requirements and Containment Tendon Surveillance Program
GNRO-2018/00055, Response to Request for Additional Information for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a .
NRC-2016-0202, Biweekly FRN - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: September 27, 2016
NRC-2016-0071, FRN - Withdrawal of Amendment Request to Revise Technical Specification 5.5.6 for Extension of Type a and Type C Leak Rate Test Frequencies
NRC-2011-0290, Biweekly Report - Applications and Amendments to Facility Operating Licenses Involving No Significant Hazards Considerations: Fr Publication Date December 27, 2011
NG-19-0077, Technical Specification 5.6.6 Post Accident Monitoring (PAM) Report
PNP 2019-034, Response to Request for Additional Information Regarding License Amendment Request Resubmittal to Adopt TSTF-425, Revision 3, Relocate Surveillance Frequencies to Licensee Control- Risk Informed Technical Specification.
L-PI-19-038, Submittal of Revised Pressure and Temperature Limits Report
NL-05-0328, Request for Technical Specification Amendment Containment Tendon Surveillance Program
NL-05-0285, ASME Section XI Request for Alternative Numbers RR-57, Proposed Alternative to IWL-2421(a) Requirements, and RR-58, Proposed Alternative to IWL-2421 (B) Requirements
PLA-5840, Proposed Amendment: Revision to Technical Specification 5.5.6., PLA-5840
ND-19-1142, Request for License Amendment and Exemption: Automatic Depressurization System (ADS) and Core Makeup Tank (Cmt) Design Parameters (LAR-19-009)
ND-18-1005, Request for License Amendment: Technical Specification Changes for Physics Tests Exceptions and Nomenclature (LAR-18-020)
ND-18-0537, Request for License Amendment: Engineered Safety Feature Safeguards Actuation Technical Specifications Applicability Changes (LAR-18-011)
ND-18-0067, Request for License Amendment: Fuel Management Related Technical Specifications (LAR-18-005)
2CAN120401, License Amendment Request Proposed Technical Specification Changes Revising Containment Building Structural Integrity Requirements
NRC 2004-0103, License Amendment Request 243 Application for Technical Specification Improvement to Extend the Inspection Interval for Reactor Coolant Pump Flywheels Using the Consolidated Line Item Improvement Process
NLS2004111, Response to Request for Additional Information Regarding One Time Extension of Diesel Generator Allowed Outage Time
PLA-5739, Proposed Amendment Nos. 264 and 229, Respectively Regarding Resolution of URI 2001-04-03 Standby Liquid Control/Atws
ULNRC-04923, License Application for Revision to Technical Specification 5.5.6, Containment Tendon Surveillance Program, and Technical Specification 5.5.16, Containment Leakage Rate Testing Program
RS-03-157, Additional Information Regarding Inservice Testing Program Relief Requests
JAFP-03-0108, Proposed License Amendment to Provide a One-time Integrated Leak Rate Test (ILRT) Interval Extension
NRC-02-0040, Proposed License Amendment for a One-Time Deferral of the Primary Containment Integrated Leak Rate Test
RNP-RA/02-0067, Request for Technical Specifications Change, Full Implementation of Alternative Radiological Source Term
ND-20-0668, Request for License Amendment for Vacuum Relief Valve Technical Specification Changes (LAR-20-005)
ND-20-1005, Supplement to Request for License Amendment: Vacuum Relief Valve Technical Specification Changes (LAR-20-005S1)
ND-20-0122, Request for License Amendment: Main Control Room Emergency Habitability System (Ves) Pressure Regulating Valve and Source Range Neutron Flux Doubling Surveillance Changes, and Other Miscellaneous.
RBG-43650, Forwards Response to Violations Noted in Insp Rept 50-458/96-15.Corrective Actions:Programs Being Revised to Reflect Strong Mgt Expection of Zero Preventable Plant Errors
CNL-22-024, American Society of Mechanical Engineers Operation and Maintenance Code, Request for Alternative RV-02
CNL-22-062, Response to Request for Additional Information Regarding American Society of Mechanical Engineers Operation and Maintenance Code, Request for Alternative RV-02
CNL-22-085, Response to Request for Additional Information Regarding Sequoyah Nuclear Plant (Sqn), Units 1 and 2 and Watts Bar Nuclear Plant (Wbn), Units 1 and 2, American Society of Mechanical Engineers Operation and Maintenance Code, Request for Al
RBG-43077, Submits Response to Violations Noted in Insp Rept 50-458/96-04.Corrective Actions:Insps of Instrument Performed for Each Transmitter Found Without Required Plug
L-23-171, CFR 50.55a Request Number VR-9. Revision 0, Feedwater Check Valve Exercising Test Frequency
L-2024-090, Revised Steam Generator Tube Inspection Reports
WO 20-0029, License Amendment Request to Revise Specification 5.5.16 for Permanent Extension of Type a and Type C Leak Rate Test Frequencies
L-24-066, Response to Request for Additional Information Regarding 10 CFR 50.55a Request Number VR-9, Feedwater Check Valve Exercising Test Frequency
NL-15-0217, Response to Request for Additional Information Regarding Multiple Technical Specifications Changes
NL-09-1410, VEGP-ISI-RR-01, Version 1.0, Relief Request in Accordance with 10 CFR 50.55a(g)(5)(iii)
DCL-03-101, Response to NRC Request for Additional Information Regarding License Amendment Request 02-04, Revision of TS 5.6.6 - Reactor Coolant System Pressure & Temperature Limits Report
ND-20-0464, Request for License Amendment: Technical Specification 3.3.13 for Main Control Room Emergency Habitability System (Ves) Instrumentation Applicability Change and Include Undervoltage Actuation
ND-19-0644, Request for License Amendment: Spent Fuel Pool Boron Concentration Applicability and Actions (LAR-19-012)
L-PI-04-112, Application for Technical Specification Improvement to Extend the Inspection Interval for Reactor Coolant Pump Flywheels Using the Consolidated Line Item Improvement Process
L-2024-044, Revised Steam Generator Tube Inspection Reports
PY-CEI-NRR-2352, Suppl to 980909 LAR to License NPF-58,improving Licensing & Design Basis for Isolation of Feedwater Penetrations, Including Sensitivity Study Performed to Examine Radiological Significance of Leakage Through FW Sys Cvs
L-08-325, License Amendment Request No. 08-18 to Incorporate Technical Specification Task Force Travelers 479 and 497
AEP-NRC-2016-29, Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3 and to Request an Alternative to the ASME Code
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
ND-20-0725, Revision to License Amendment Request: Technical Specification 3.3.13 for Main Control Room Emergency Habitability System (Ves) Instrumentation Applicability Change and Include Undervoltage Actuation
JAFP-16-0129, License Amendment Request to Revise Technical Specifications Section 5.5.6 for Extension of Type a and Type C Leak Rate Test Frequencies
CNRO-2007-00042, Entergy Operations, Inc. - Relief Requests for 10 Year Updates to the 120 Month Inservice Testing Intervals
PY-CEI-NRR-2299, Supplemental Application for Amend to License NPF-58, Revising MSL Leakage Requirements & Eliminating Msli Valve Leakage Control Sys.Proprietary & non-proprietary Rev 1 to Calculation Psat 08401T.03,encl.Proprietary Info Withheld
JAFP-18-0078, Fifth Ten-Year Interval Inservice Testing Program Plan
05000397/LER-1997-009, :on 970717,discovered Error in Recently Performed Inservice Testing procedure,OSP-TIP/IST-R701. Caused by Procedure Inadequacy.Plant Procedure OSP/TIP/IST-R701 Will Be Changed
GO2-97-156, Application for Amend to License NPF-21,modifying Inservice Testing Requirements Specified in TS 5.5.6 for Inboard Primary Containment Isolation Valve on Transvering in-core Probe (TIP) Sys Nitrogen Purge Line
GO2-97-155, Requests Enforcement Discretion from Required Actions Associated W/Ts Action 3.6.1.3.A Which Requires That Penetration Flow Path W/Inoperable Primary Containment Isolation Valve Be Isolated
CNL-17-067, Administrative Changes to Proposed Revised Technical Specification Pages Related to Application to Revise Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing, to Request an Alternative
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
NLS2016046, Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal and Clarify Surveillance Requirement Usage Rule Application to Section 5.5 Testing
JAFP-16-0042, Withdrawal of License Amendment Request to Revise Technical Specifications Section 5.5.6 for Extension of Type a and Type C Leak Rate Test Frequencies
GNRO-2015/00068, Supplemental Letter to GNRO-2015-00037: Application to Revise the Technical Specifications to Remove the Inservice Testing Program and to Clarify SR Usage Rule Application to Section 5.5 Testing to Provide Relief Request in Format
BW150018, Response to Request for Additional Information (RAI) Regarding Pressure and Temperature Limits Reports (Ptlrs)
1CAN011304, License Amendment Request - Adoption of Technical Specification Task Force (TSTF)-500, Revision 2 DC Electrical Rewrite - Update to TSTF-360
L-13-040, License Amendment Request for Proposed Revision of Technical Specification (TS) 3.4.17, Steam Generator (SG) Tube Integrity; TS 3.7.18, Steam Generator Level; TS 5.5.8, Steam Generator Program; and TS 5.6.6
GO2-17-009, License Amendment Request - Revise Technical Specification 5.5.12 for Permanent Extension of Type a Test and Type C Leak Rate Test Frequencies
RS-12-155, Submittal of Relief Requests Associated with the Fifth Inservice Testing Interval
05000333/LER-2010-004, Regarding Main Steam Isolation Valve Leak Rate Exceeds Authorized Limit
05000416/LER-2009-001, Re Containment Isolation Valves Placed in Service After Maintenance Without Administrative Controls Due to Human Performance Error
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
GNRO-2007/00068, To Amendment Request Changes to the Condensate Storage Tank Level-Low Setpoints
NRC 2005-0074, Final Update Information Regarding the Point Beach Nuclear Plant License Renewal Application
TSTF-05-07, Submittal and Request for Fee Waiver for Review of TSTF-343, Revision 1, Containment Structural Integrity
WO 03-0051, Revision to Technical Specification (TS) 5.5.6, Containment Tendon Surveillance Program, and TS 5.5.16, Containment Leakage Rate Testing Program
L-2024-060, 10 CFR 50.59(d)(2) Evaluation and 10 CFR 50.71(e)(2) Technical Specification Bases Summaries Report
NUREG-1433, Part 1- Edwin I. Hatch, Units 1 & 2, License Amendments, Replace Current Technical Specification & Associated Bases
GNRO-2015/00087, Supplemental Letter to Application to Revise the Technical Specifications to Remove the Inservice Testing Program and to Clarify SR Usage Rule Application to Section 5.5 Testing to Provide Relief Request in Format Requested by
RS-07-044, Amergen Energy Company, LLC, Request for Amendment to Technical Specifications Section for the Inservice Testing Program
JAFP-16-0170, Response to Request for Additional Information (RAI) Regarding License Amendment Request to Revise Technical Specifications Section 5.5.6 for Extension of Type a and Type C Leak Rate Test Frequencies - Supplement 1
L-MT-16-031, Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing, and to Request an Alternative to the ASME Code
CNL-25-033, Revision to Sequoyah Nuclear Plant, Units 1 and 2 American Society of Mechanical Engineers Operation and Maintenance Code, Request for Alternative RV-02
RS-12-026, Submittal of Relief Requests Associated with the Fifth Inservice Testing Interval
NL-15-0784, Submittal of the Inservice Testing Program Relief Requests and Alternatives for Pumps and Valves - Fifth Ten-Year Interval
BSEP 16-0110, Request for Alternatives in Support of the Fifth 10-Year Inservice Testing (IST) Program
NL-14-121, Indian Point, Unit 2, Updated Final Safety Analysis Report (Ufsar), Revision 25, Technical Requirements Manual
L-2025-169, U4R35 Steam Generator Tube Inspection Report