GO2-17-027, Supplement to License Amendment Request to Modify Technical Specification Surveillance Requirement (SR) 3.4.3.1 and (SR) 3.4.4.1 Safety/Relief Valves Setpoint Lower Tolerance
GO2-17-124, Final Technical Specification Markup and Clean Pages for Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3
ONS-2016-071, Duke Energy Carolinas, LLC - Oconee Nuclear Station, Docket Numbers 50-269, 50-270, and 50-287 - Technical Specification (TS) Bases Change
GO2-16-086, Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3
GO2-16-079, Erratum for License Amendment Request to Modify Technical Specification Surveillance Requirement (SR) 3.4.3.1 and SR 3.4.4.1 Safety/Relief Valves (Srvs) Setpoint Lower Tolerance
GO2-16-046, License Amendment Request to Modify Technical Specification Surveillance Requirement (SR) 3.4.3.1 and SR 3.4.4.1 Safety/Relief Valves (Srvs) Setpoint Lower Tolerance
PLA-7441, Supplemental Information on Technical Specification Changes to Adopt Traveler TSTF-425
U-604396, Transmittal of Revision 19 to the Clinton Power Station Technical Specification Bases
GO2-15-173, Supplement to Response to Second Request for Additional Information on License Amendment Request for Adoption of Technical Specification Task Force (TSTF)-425, Revision 3
GO2-15-108, Provides Affected Technical Specification Pages Supporting License Amendment Request for Adoption of Technical Specification Task Force (TSTF) Traveler TSTF-423, Revision 1, Using the Consolidated Line Item Improvement Process
ONS-2015-047, License Amendment Request (LAR) to Add High Flux Trip for 3 Reactor Coolant Pump Operation, License Amendment Request No. 2014-05
GNRO-2014/00058, Letter GNRO-2012/00146, Technical Requirements Manual and Technical Specification Bases Update (ML12361A330)
GNRO-2012/00096, License Amendment Request for Implementing a 24-Month Fuel Cycle, Grand Gulf Nuclear Station, Unit 1
NG-12-0034, Supplemental Information to an Application to Adopt Technical Specifications Task Force Traveler TSTF-425, Revision 3, to Relocate Specific Surveillance Frequencies to a Licensee Controlled Program
BSEP 11-0068, License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF-514, Revision 3, Revise BWR Operability Requirements and Actions for RCS Leakage Instrumentation
PLA-6695, Amend. Request No. 308 to License NPF-14 & Amend. Request No. 279 to License NPF-22: Adoption of Technical Specification Task Force Traveler TSTF-514, Rev. 3, Revise BWR Operability Requirements & Actions RCS Leakage Instrumentation
RS-18-023, License Amendment Request to Revise the Technical Specifications (TS) Surveillance Requirement (SR) 3.4.4.1 to Revise the Lower Setpoint Tolerances for Safety/Relief Valves (S/Rvs)
NL-16-2280, Vogtle Electric Generating Plant, Units 1 & 2, Updated Final Safety Analysis Report, Bases for Improved Technical Specifications
NL-14-121, Indian Point, Unit 2, Updated Final Safety Analysis Report (Ufsar), Revision 25, Technical Specification Bases List of Effective Sections
NRC-12-0067, Fermi 2, Submittal of Revision 18 to the Updated Final Safety Analysis Report, 10 CFR 50.59 Evaluation Summary Report, Commitment Management Report and Revision to the Technical Requirements Manual and the Technical Specifications Bases
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
TSTF-11-13, Transmittal of TSTF-534, Revision 0, Clarify Application of Pressure Boundary Leakage Definition
RS-11-100, Dresden, Units 2 and 3, Updated Final Safety Analysis Report (Ufsar), Revision 9, Technical Specification Bases
U-603987, Transmittal of Revision 13 to Technical Specification Bases
TSTF-10-14, Submittal of TSTF-513, Revision 3 and TSTF-514, Revision 2
NLS2010029, Technical Specifications Bases Changes
RBG-46925, License Amendment Request, Technical Specification Change to Revise ASME Code Reference for Inservice Test Requirements
TSTF-09-03, Transmittal of TSTF-513, Revision 1, Revise PWR Operability Requirements and Actions for RCS Leakage Instrumentation and TSTF-514, Revision 0, Revise BWR Operability Requirements and Actions for RCS Leakage Instrumentation
RS-08-161, Braidwood, Units 1 and 2 - Technical Specification Bases
NLS2008001, License Application Amendment Request for Technical Specification Change Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process and Related
GNRO-2018/00039, Report of Technical Specification Bases Changes
05000260/LER-1998-004-03, :on 981202,SR Intent Was Not Adequately Implemented.Caused by Procedural Inadequacy.Revised Procedures to Provide Proper SR Implementation.With
U-603781, Transmittal of Revision 10 to the Clinton Power Station Technical Specifications Bases
JAFP-02-0098, Part 7 of 7, James A. FitzPatrick Nuclear Power Plant - Revision J to Proposed Technical Specification Change (License Amendment) Conversion to Improved Standard Technical Specifications, Bases
RA-19-0308, Clean Technical Specifications Pages Regarding Application to Adopt TSTF-425, Revision 3
BSEP 05-0109, Submittal of Technical Specification Bases Revisions
BSEP 05-0082, Submittal of Technical Specification Bases Changes
JAFP-05-0084, Application for Technical Specifications (TS) Change Regarding Mode Change Limitations (TSTF-359) Using the Consolidated Line Item Improvement Process (CLIIP)
TSTF-19-09, Technical Specifications Task Force - Transmittal of TSTF-576, Revision 0, Revise Safety/Relief Valve Requirements
NRC-04-0005, Application for Technical Specification Change Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process
RBG-46179, Revisions to the Technical Requirements Manual and the Technical Specification Bases
U-603588, Transmittal of Revision 7 to Clinton Power Station Technical Specification Bases
RBG-45946, Entergy Nuclear- South, River Bend Station, Unit-1, License Amendment LAR 2002-11 Modification of the Technical Specification Surveillance Requirements for the Safety/Relief Valves
RBG-45935, Part B - Revisions 58 -76 to River Bend Station Technical Requirements Manual & Technical Specification Bases
RS-02-018, Supplement to 06/21/2001 License Amendment Request, Surveillance Requirements for Main Steam Line Safety Relief Valves
NLS2021015, (CNS) - Technical Specification Bases Changes
RBG-45077, Application for Amend to License NPF-47 to Change TS to Extend Operation of RBS from Current Licensed Power Level of 2894 Mwt to Uprated Power Level 3039 Mwt.Encl Proprietary GE Rept NEDC-32778P Withheld
RS-22-046, Relief Requests Associated with the Sixth Inservice Inspection Interval
RS-22-030, Submittal of Relief Request Associated with the Sixth Inservice Inspection Interval
NLS2022005, Application to Revise Technical Specifications to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements
CNL-22-039, Application to Revise Technical Specifications to Adopt TSTF-554-A, Revision 1, Revise Reactor Coolant Leakage Requirements (BFN TS-537) (SQN-21-05) (WBN-TS-21-04)
RS-22-101, Response to Request for Additional Information Related to Relief Request I6R-01 Associated with the Sixth Inservice Inspection Interval
RS-22-096, Response to Request for Additional Information Related to Relief Request I6R-01 Associated with the Sixth Inservice Inspection Interval
PLA-8062, Supplement to Relief Request 4RR-10 Relief from Code Seal Weld Requirement for Valve 252F007B, PLA-8062
PLA-8061, Relief Request 4RR-10 Relief from Code Seal Weld Requirement for Valve 25F007B, PLA-8061
NLS2017032, 10 CFR 50.55a Request Number RI-21, Revision 1
NRC-19-0054, DTE Energy Company - License Amendment Request to Revise Technical Specifications to Change Surveillance Intervals to Accommodate a 24-Month Fuel Cycle
NL-24-0026, Application to Revise Technical Specifications Surveillance Requirements to Increase Safety/Relief Valves Setpoint
RS-03-194, Fourth Interval Inservice Inspection Program Plan
GNRO-2010/00042, Technical Specification Bases & Technical Requirements Manual Update
L-MT-24-025, Application to Revise Technical Specifications to Adopt TSTF-554, Revise Reactor Coolant Leakage Requirements
1CAN102202, Application to Remove Technical Specification Condition Allowing Two Reactor Coolant Pump Operation
TSTF-19-11, TSTF Response to NRC Questions on TSTF-554, Revise Reactor Coolant Leakage Requirements
RBG-47169, Unit 1, Revisions to the Technical Requirements Manual and the Technical Specification Bases
AECM-90-0089, Forwards Draft Tech Specs for Power Distribution Limits,Rcs, ECCS & Plant Sys as Part of Util Involvement W/Bwr Owners Group as BWR-6 Lead Plant
RA-22-0091, Application to Revise Technical Specifications to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements
CP-200801015, Technical Specification Bases for Comanche Peak Steam Electric Station Units 1 & 2
NLS2019011, License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF-514, Revision 3, Revise BWR Operability Requirements and Actions for RCS Leakage Instrumentation
05000373/LER-2018-003, Regarding Two Main Steam Safety Relief Valves Failed Inservice Lift Inspection Pressure Test
05000374/LER-2017-004, Regarding Two Main Steam Safety Relief Valves Failed Inservice Lift Inspection Pressure Test
05000374/LER-2015-002, Regarding Two Main Steam Safety Relief Valves Failed Inservice Inspection Pressure Test
ASLBP 12-923-01-LA-BD01, Transcript of 12/05/2012 Pre-hearing Conference Regarding San Onofre Units 2 and 3
NRC-11-0013, License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF-514, Revision 3, Revise BWR Operability Requirements and Actions for RCS Leakage Instrumentation
RS-24-106, Request RV-04, Proposed Alternative to Modify Reactor Pressure Vessel Safety Relief Valve Testing Sampling Requirements Per Inservice Test Program
TSTF-10-24, Submittal of TSTF-514, Revision 3, Revise BWR Operability Requirements and Actions for RCS Leakage Instrumentation
RS-10-025, Supplemental Information Concerning Request for License Amendments to Revise Technical Specifications 3.4.5, RCS Leakage Detection Instrumentation
TSTF-09-18, Response to June 11, 2009 Request for Additional Information Regarding TSTF-514, Revision 0, Revise BWR Operability Requirements and Actions for RCS Leakage Instrumentation
RS-06-154, Request for Amendment to Technical Specifications Section 5.5.7, Inservice Testing Program
RS-09-104, Request for License Amendment to Revise Technical Specification 3.4.5, RCS Leakage Detection Instrumentation, to Allow Alternate Method of Verifying Drywell Leakage
RS-07-074, Application for Technical Specification Change TSTF-423, Risk Informed Modification to Selected Required Action End States for BWR Plants, Using the Consolidated Line Item Improvement Process
NUREG-1433, Part 1- Edwin I. Hatch, Units 1 & 2, License Amendments, Replace Current Technical Specification & Associated Bases
RS-09-042, Request for Amendment to Technical Specifications Section 5.5.6, Inservice Testing Program to Incorporate Previously NRC-Approved Generic TS Changes
RAIO-0917-56153, LLC Response to NRC Request for Additional Information No. 156 (Erai No. 9031) on the NuScale Design Certification Application
3F0506-05, 2005 Technical Specifications Bases Control Program
CP-201000212, Technical Specifications Bases for Comanche Peak Steam Electric Station, Units 1 and 2
05000373/LER-2018-003-01, For LaSalle County Station, Unit 1, Two Main Steam Safety Relief Valves Failed Inservice Lift Inspection Pressure Test
RS-21-063, Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements
TSTF-21-03, TSTF Response to NRC Questions on TSTF-576, Revision 0, Revise Safety/Relief Valve Requirements and Submittal of Revision 1
NL-16-109, Indian Point 2 Improved Technical Specifications Bases
PLA-5764, Proposed License Amendment Numbers 267 for Unit 1 and 232 for Unit 2 Mode Change Limitations Using the Consolidated Line Item Improvement (CLIIP) Process PLA-5764
JAFP-21-0089, Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position
NRC-16-0034, Fermi, Unit 2, Submittal of Revision 20 Updated Final Safety Analysis Report, 10CFR50.59 and 10CFR72.48 Evaluation Summary Reports, Commitment Management Report & Revisions to Technical Requirements Manual & Technical Specifications Base
NL-17-0534, Joseph M. Farley Nuclear Plant, Technical Specifications Bases
LR-N24-0030, License Amendment Request to Revise Technical Specification Lift Settings for Reactor Coolant System Safety/Relief Valves
TSTF-23-06, TSTF Response to NRC Request for Additional Information on TSTF-576, Revision 2, Revise Safety/Relief Valve Requirements
TSTF-23-04, Technical Specifications Taskforce Transmittal of TSTF-576, Revision 2, Revise Safety/Relief Valve Requirements