CNS-15-054, Submittal of Technical Specification Bases Changes 5.5.14
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
NL-12-0471, Supplemental Information Regarding the Inter-Unit Spent Fuel Transfer License Amendment Request (TAC Nos. ME1671, ME1672, and L24299)
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
NL-11-130, Response to Request for Additional Information Regarding the Inter-Unit Spent Fuel Transfer License Amendment Request (TAC Nos. ME1671, ME1672, and L24299)
NL-16-2280, Vogtle Electric Generating Plant, Units 1 & 2, Updated Final Safety Analysis Report, Bases for Improved Technical Specifications
NL-15-144, Indian Point, Units 2 and 3 - License Amendment Request - Conditional Exemption from End-of-Life (Eol) Moderator Temperature Coefficient (Mtc) Measurement
NL-14-121, Indian Point, Unit 2, Updated Final Safety Analysis Report (Ufsar), Revision 25, Technical Specification Bases List of Effective Sections
RS-12-221, Byron, Units 1 and 2, Updated Final Safety Analysis Report, Revision 14, Technical Specifications Bases
RS-12-221, Braidwood, Units 1 and 2, Updated Final Safety Analysis Report, Revision 14, 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
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
GO2-10-116, Supplemental Information in Support of License Amendment Request Regarding Control Rod Operability and Control Rod Scram Accumulators
NLS2010029, Technical Specifications Bases Changes
ULNRC-05682, Application for Amendment, Revision of Technical Specification 3.3.9
RBG-47006, Revisions to the Technical Requirements Manual and the Technical Specification Bases
GO2-10-024, License Amendment Request to Change Technical Specifications Relating to Control Rod Operability and Control Rod Scram Accumulators
ULNRC-05655, Application for Amendment to Facility Operating License, Revision of Technical Specification 3.3.9
NLS2009034, Application for Technical Specification Change Regarding Revision of Control Rod Notch Surveillance Test Frequency and Clarification of a Frequency Example Using the Consolidated Line Item Improvement Process
L-09-031, Application for Technical Specification Change Regarding Revision of Control Rod Application for Technical Specification Change Regarding Revision of Control
GO2-09-011, License Amendment Request to Revise Control Rod Notch Testing Frequency Using the Consolidated Line Item Improvement Process (CLIIP) for TSTF-475
RS-08-161, Braidwood, Units 1 and 2 - Technical Specification Bases
GNRO-2009/00008, Technical Specification Bases Update to the NRC for Period Dated January 23, 2009
NLS2008091, Technical Specification Bases Changes for Time Period from 03/15/2007 Through 09/04/2008
RBG-46690, License Amendment Request, Application for Technical Specification Changes Using the Consolidated Line Item Improvement Process (CLIIP)
PLA-6330, Proposed Amendment Nos. 300 and 270: Request for Adoption of TSTF-475, Rev. 1, Control Rod Notch Testing Frequency and SRM Insert Control Rod Action, Using the Consolidated Line Item Improvement Process (CLIIP)
BSEP 08-0082, Request for License Amendment - Adoption of TSTF-475, Revision 1 - Revision of Control Rod Notch Surveillance Test Frequency and a Clarification of a Frequency Example Using the Consolidated Line Item Improvement Process
GNRO-2008/00014, License Amendment Request, Application to Technical Specification Changes Using the Consolidated Line Item Improvement Process - TSTF-475 Control Rod Notch Testing
RA-08-047, Application for Technical Specification Change Regarding Revision of Control Rod Notch Surveillance Test Frequency, Clarification of SRM Insert Control Rod Action and Clarification of a Frequency Example Using the Consolidation Line Item I
L-MT-08-012, License Amendment Request: Application for Technical Specification Change Regarding Revision of Control Rod Notch Surveillance Test Frequency and a Clarification of a Frequency Example Using the Consolidated Line Item Improvement Process
JAFP-08-0011, License Amendment Request Application for Technical Specification Changes Using the Consolidated Line- Item Improvement Process (CLIIP)
NRC-08-0001, Application for Technical Specification Change Regarding Revision of Control Rod Notch Surveillance Test Frequency and a Clarification of a Frequency Example Using the Consolidated Line Item Improvement Process
TSTF-07-19, Response to NRC Request for Additional Information (RAI) Regarding TSTF-475, Revision 0, Control Rod Notch Testing Frequency and SRM Insert Control Rod Action, Dated February 28, 2007
TSTF-07-06, Response to NRC Request for Additional Information Regarding TSTF-486, Revision 0, Revise Mtc Surveillance for Startup Test Activity Reduction (STAR) Program (WCAP-16011), Dated November 20, 2006 and Submittal of Revision 1
RAIO-0319-64994, LLC Supplemental Response to NRC Request for Additional Information No. 512 (Erai No. 9634) on the NuScale Design Certification Application
ULNRC-04721, Technical Specification Bases Revision 3
BSEP 02-0114, Submittal of Technical Specification Bases Changes Revisions 24 & 25
RBG-45935, Part B - Revisions 58 -76 to River Bend Station Technical Requirements Manual & Technical Specification Bases
NOC-AE-20003774, License Amendment Request to Revise Technical Specification Surveillance Requirement (SR) 4.1.1.3 A. and B. and Specification 6.9.1.6 B
RS-21-006, Application to Incorporate Licensing Topical Report NEDE-33885P-A, Revision 1, GNF CRDA Application Methodology
NL-23-0611, Core Operating Limits Report, Cycle 11 Version 1
PLA-8054, Proposed Amendment to Licenses NPF-14 and NPF-22: Remove Control Rod Operability Separation Criteria and Replace Reference to Banked Position Withdrawal Sequence with the Analyzed Rod Position Sequence
NL-14-0115, Units 1 & 2 & Vogtle Electric Generating Plant - Units 1 and 2 - License Amendment Request to Revise Technical Specification Surveillance Requirement 3.1.3.2 and Specification 5.6.5
NL-24-0408, Unit 3, Core Operating Limits Report, Cycle 2, Version 1
B16834, Application for Amend to License DPR-65,correcting Various TS Compliance Issues,Including Modifying Definition of Azimuthal Power Tilt,Changing Wording of SR 4.1.1.1.2 & Changing Applicability of TS 3.1.3.4
HBL-10-004, License Amendment Request 10-01 Deletion of Technical Specification 3.1.3, Fuel Storage Pool Liner Water Level, & TS 1.0, Use & Application, 3.0, Limiting Condition for Operation Applicability, 3.0, Surveillance Requirement
HBL-10-005, To the Defueled Safety Analysis Report, Revision 26 to the Quality Assurance Plan, and Revision 3 to the Technical Specifications Bases
TSTF-07-18, TSTF-486, Revision 2, Revise Mtc Surveillance for Startup Test Activity Reduction (STAR) Program (WCAP-16011)
SVPLTR 07-0005, Request for Enforcement Discretion Technical Specification 3.1.7, Standby Liquid Control (SLC) System
TSTF-04-07, TSTF-475, Revision 0, Control Rod Notch Testing Frequency and SRM Insert Control Rod Action
NUREG-1433, Part 1- Edwin I. Hatch, Units 1 & 2, License Amendments, Replace Current Technical Specification & Associated Bases
RAIO-0917-56153, LLC Response to NRC Request for Additional Information No. 156 (Erai No. 9031) on the NuScale Design Certification Application
NL-16-109, Indian Point 2 Improved Technical Specifications Bases
L-21-007, License Amendment Request 21-02 - Proposed Revisions to Humboldt Bay Independent Spent Fuel Storage Installation - Special Nuclear Materials License Number 2514 and Technical Specifications
NL-25-0125, Core Operating Limits Report, Cycle 1, Version 2
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
NL-25-0378, Core Operating Limits Report, Cycle 2