NLS2014035, License Amendment Request to Eliminate Requirements for Post Accident Sampling System for Boiling Water Reactors Using the Consolidated Line Item Improvement Process
L-14-135, Offsite Dose Calculation Model, Revision 27
AEP-NRC-2013-25, Annual Radioactive Effluent Release Report
L-12-152, Offsite Dose Calculation Manual, Revision 26
L-2011-189, License Amendment Request No. 211, Technical Specification Changes Regarding Section 5.0 Design Features
NL-16-109, Indian Point 2 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
L-2011-032, Turkey Point, Units 3 and 4 - Supplement 1 to Fuel Storage Criticality Analysis
NG-03-0355, Ctr Technical Specification Change Request, Eliminate Requirements for Post Accident Sampling System Using Consolidated Line Item Improvement Process
GNRO-2003/00019, Application for Technical Specification Improvement to Eliminate Requirements for Post Accident Sampling Stations for Boiling Water Reactors Using the Consolidated Line Item Improvement Process (CLIIP)
RBG-46090, License Amendment Request Application for Technical Specification Improvements to Eliminate Requirements for Post Accident Sampling Stations for Boiling Water Reactors Using the Consolidated Line Item Improvement (CLIIP)
PLA-5603, Application for Technical Specification Improvement to Eliminate Requirements for Post Accident Sampling Stations for Boiling Water Reactors Using the Consolidated Line Item Improvement Process
JAFP-03-0034, Proposed License Amendment to Eliminate the Requirements for the Post Accident Sampling System (PASS) Using the Consolidated Line Item Improvement Process
GO2-02-174, License Amendment Request to Eliminate Requirements for Post Accident Sampling System (PASS)
NRC-02-0025, Application for Technical Specification Improvement to Eliminate Requirements for Post Accident Sampling Systems Using the Consolidated Line Item Improvement Process
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-44415, Responds to Violations Noted in Insp Rept 50-458/97-19. Corrective Actions:Removed Subject Extension Cord,Issued Rev 3 to Procedure ADM-0073,notified Potential User of Extension Cords of Revs to ADM-0073 & Performed Walkdown of Plant
VPN-067-99, Forwards Proposed Rev 23 to PGE-8010, Trojan Nuclear QAP, in Response to NRC 990708 RAI Re Relocation of TS ACs to Qap.Revised QAP Will Be Made Effective Concurrently with Implementation of License Change Application Lca 245
NSD-NRC-98-5541, Provides Westinghouse Responses to FSER Open Items on AP600. Summary of Encl Responses Provided in Table 1.NRC Should Review Encls & Inform Westinghouse of Status to Be Designated in NRC Status Column of Oits
NL-23-0136, License Amendment Request: More Restrictive Action for Technical Specification 3.1.9 (LAR-23-006)
BSEP 02-0159, Application for Technical Specification Change Regarding Elimination of Post Accident Sampling System Requirements
L-11-150, Offsite Dose Calculation Manual, Rev. 24
NL-05-137, Proposed Changes to Indian Point 2 and 3 Technical Specifications: Adoption of TSTF-258, TSTF-308, and Related Administrative Control Changes Based on NUREG-1431
ND-19-1129, Supplement to the Request for License Amendment Regarding Protection and Safety Monitoring System Surveillance Requirement Reduction Technical Specification .
AEP-NRC-2018-35, Annual Radioactive Effluent Release Report - Off-Site Dose Calculation Manual
L-16-030, Request for an Amendment to Revise Technical Specification 5.5.3, Radioactive Effluents Controls Program
AEP-NRC-2010-38, Annual Radioactive Effluent Release Report, January 1, 2009, Through December 31, 2009
L-96-003, License Amendment Request: Adoption of GL 96-03, Relocation of the Pressure Temperature Limit Curves and Low Temperature Overpressure Protection System Limits and TSTF-419-A, Rev. 0, Revise PTLR Definition
NRC-21-0001, License Amendment Request to Revise Technical Specifications to Remove Obsolete Information, Make Minor Corrections, and Make Miscellaneous Editorial Changes
AEP-NRC-2021-27, Annual Radioactive Effluent Release Report
PMNS20250980, Meeting with Tennessee Valley Authority to Discuss a Proposed License Amendment Request for Sequoyah Nuclear Plant, Units 1 and 2
TSTF-23-04, Technical Specifications Taskforce Transmittal of TSTF-576, Revision 2, Revise Safety/Relief Valve Requirements
NL-14-121, Indian Point, Unit 2, Updated Final Safety Analysis Report (Ufsar), Revision 25, Technical Requirements Manual