IP 71111.21M, Design Bases Assurance Inspection
LR-N17-0087, 2016 Annual Radioactive Effluent Release Report
NL-17-047, Submittal of 2016 Annual Radioactive Effluent Release Report
GO2-16-119, License Amendment Request for One-Time 7 Day Extension of Completion Time for TS Condition 3.5.1.A, 3.6.1.5.A, and 3.6.2.3.A
NL-16-1390, License Amendment Request to Revise Technical Specification Section 5.5.12 for Permanent Extension of Type a and Type C Leak Rate Test Frequencies, Correction to Attachment 3
PLA-4192, Provides Initial Response to GL 94-03, IGSCC of Core Shrouds in Bwrs. Remaining Info Re Insp Plans,Repair Plans & Insp Results Will Be Submitted to NRC Per Schedules Noted in GL
NL-15-048, 2014 Annual Radioactive Effluent Release Report
LR-N15-0078, Annual Radioactive Effluent Release Report
RS-14-314, Requests for Relief for Alternate Examination Frequency Under ASME Code Case N-729-1 for Reactor Vessel Head Penetration Welds in Accordance with 10 CFR 50.55a(a)(3)(i)
LR-N14-0084, Offsite Dose Calculation Manual, Revision 27
NL-14-039, Annual Radioactive Effluent Release Report
LR-N13-0093, 2012 Annual Radioactive Effluent Release Report, for the Period of January 1, 2012, to December 31, 2012
NL-11-039, 2010 Annual Radioactive Effluent Release Report
LR-N17-0088, Hope Creek Generating Station Updated Final Safety Analysis Report, Rev. 22, Chapter 11, Radioactive Waste Management
L-2016-198, Turkey Point, Units 3 & 4, Updated Final Safety Analysis Report, List of Effective Pages
L-2016-198, Turkey Point, Units 3 & 4, Updated Final Safety Analysis Report, Chapter 5, Structures
LR-N14-0084, Salem, Units 1 and 2, Offsite Dose Calculation Manual, Revision 27
LR-N14-0084, Hope Creek and Salem, Units 1 and 2, 2013 Annual Radioactive Effluent Release Report
NG-17-0235, Duane Arnold Energy Center, Calc No. NEE-323-CALC-005, Revised Gaseous Radiological EALs Per NEI 99-01 Rev. 06
NG-17-0235, Duane Arnold Energy Center, Calc No. NEE-323-CALC-005, Revised Gaseous Radiological EALs Per NEI 99-01 Rev. 6
NL-12-020, Indian Point Unit Nos. 1, 2 & 3 - 2011 Annual Radioactive Effluent Release Report
LR-N12-0121, Salem and Hope Creek - 2011 Annual Radioactive Effluent Release Report
NL-11-068, Indian Point, Units 1, 2 and 3 - 2010 Annual Radioactive Effluent Release Report, Revision 1
L-2010-212, Turkey Point, Units 3 & 4, Updated Final Safety Analysis Report - Unit 4 Cycle 24 Update, Chapter 5, Structures
RS-10-108, Additional Information Supporting Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program
LR-N10-0140, Hope Creek - Attachment 1, Offsite Dose Calculation Manual Revision, 23
LR-N10-0140, Salem - Attachment 1, Offsite Dose Calculation Manual, Revision 23
LR-N10-0140, Salem - Attachment 1, Offsite Dose Calculation Manual, Revision 22
NL-10-045, Indian Point Units 1, 2 & 3 - 2009 Annual Radioactive Effluent Release Report
RS-09-121, License Amendment Request for a One-Time Extension of the Essential Service Water Train Completion Time
LR-N09-0099, Hope Creek, and Salem, Units 1 and 2, 2008 Annual Radioactive Effluent Release Report, Cover Through Page 180
NL-09-045, Indian Point, Units 1, 2, & 3, 2008 Annual Radioactive Effluent Release Report
NL-08-068, Indian Point, Units 1, 2 and 3 - 2007 Annual Radioactive Effluent Release Report
LR-N08-0096, 2007 Radioactive Effluent Release Report for January 1, 2007 to December 31, 2007
NL-07-050, Units, 1, 2 and 3 - 2006 Annual Radioactive Effluent Release Report
NRC 2006-0040, License Amendment Request 246 - Deletion of Core Alterations
NL-06-045, Annual Radioactive Effluent Release Report
LR-N19-0042, 2018 Annual Radioactive Effluent Release Report (ARERR)
NRC 2005-0063, To Request for Exigent Review of Heavy Load Analysis
NRC 2005-0055, Units I and 2, Request for Review of Heavy Load Analysis
DCL-04-105, Response to July 8, 2004, NRC Request for Additional Information Re License Amendment Request 04-01, Revised Steam Generator Voltage-based Repair Criteria Probability of Detection Method
LR-N04-0117, Stations, Radioactive Effluent Release Report
RA-03-147, Request for Exemption from NRC Certificate of Compliance No. 1015, Amendment 2, Technical Specification B3.4.3.6
NRC 2003-0090, Submittal of Additional Information Concerning Auxiliary Feedwater Orifice Regulatory Conference
RS-02-179, Request for Technical Specification Change Extension of Completion Time for Instrument Bus Inverters
GNRO-2002/00007, License Amendment Request Emergency Diesel Generator Extended Allowed Out-of-Service Time (AOT) - TS 3.8.1, AC Sources--Operating, Ldc 2001-192
LR-N20-0025, 2019 Annual Radioactive Effluent Release Report (Rerr)
B12105, Forwards Isap 1.03, Containment Penetration Evaluations, to Facilitate NRC Review of Project Analysis.Public Safety Impact Scores Considered Preliminary
BVY-98-114, Provides Response to Request for Addl Info Re Implementation of ASME Code N560 at Plant
0CAN129603, Submits Proposed TS Change Request Re Control Room Ventilation Sys
RBG-48271, Supplement to License Amendment Request to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times – RITSTF Initiative 4b and Application to Adopt 10 CFR 50.69, Risk
LIC-93-0301, Phase I Rept on IPEEE for FCS Re Tornado,Flooding, Transportation & Nearby Facilities Accidents & Others
L-82-221, Forwards Addl Info Re NUREG-0737,Item II.B.1, RCS Vents, in Response to NRC 820224 Request.One Oversize Drawing Encl. Aperture Card Is Available in PDR
L-99-209, Forwards Rev 16 of Updated Fsar.Info Accurately Reflects Plant Changes Made Since Previous Submittal.Rev Incorporates Changes Completed Between 971015 & 990408.Summary of Accuracy Review Changes & Instructions,Included
05000397/LER-1993-031, :on 931109,engineering Evaluation Determined That MCR HVAC Sys Will Not Maintain CR Temp.Caused by Inadequate Design Margin in Original Design.Per Written to Document Potential Analysis Concerns
GO2-81-561, Forwards Responses to Hydrologic Engineering Section Safety Questions 371.015,371.016,371.017 & 371.018 Contained in NRC .Other Responses Will Be Submitted by 820115.Ten Oversize Drawings Encl.Aperture Cards Are in PDR
RS-10-172, Additional Information Supporting the Request for Amendment to Technical Specification 3.1.7, Standby Liquid Control (SLC) System
CPSES-200701127, Response to Request for Additional Information Related to License Amendment Request (LAR) 06-009, Revision to Technical Specification (TS) 3.8.1, AC Sources - Operating, Extension of Completion Times
BVY 03-116, To Psat 3019CF.QA.09, Alternative Source Term Impact on NUREG-0737 Equipment Qualification, Vital Area Access, and Areas of Continuous Occupancy
RA-02-008, Transmittal of Special Report, Transuranic and Other Hard to Detect Radionuclides in Maine Yankee Sample Media