LR-N17-0087, 2016 Annual Radioactive Effluent Release Report
BSEP 16-0020, Request for Notice of Enforcement Discretion (Noed), Limiting Condition for Operation (LCO) 3.0.3, Per Technical Specification 3.8.1, AC Sources - Operating
RNP-RA/15-0006, Response (120-Day) to Request for Additional Information Associated with License Amendment to Adopt National Fire Protection Association (NFPA) Standard 805
LR-N14-0084, Offsite Dose Calculation Manual, Revision 27
LR-N13-0093, 2012 Annual Radioactive Effluent Release Report, for the Period of January 1, 2012, to December 31, 2012
LR-N17-0088, Hope Creek Generating Station Updated Final Safety Analysis Report, Rev. 22, Chapter 11, Radioactive Waste Management
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
LR-N12-0121, Salem and Hope Creek - 2011 Annual Radioactive Effluent Release Report
ULNRC-05743, Offsite Dose Calculation Manual Revision 17
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
ULNRC-05621, 2008 Annual Radioactive Effluent Release Report
LR-N09-0099, Hope Creek, and Salem, Units 1 and 2, 2008 Annual Radioactive Effluent Release Report, Cover Through Page 180
LR-N19-0042, 2018 Annual Radioactive Effluent Release Report (ARERR)
BVY 05-067, NRC GL-03-001 Control Room Habitability - Final Response
LR-N04-0117, Stations, Radioactive Effluent Release Report
DCL-03-060, License Amendment Request 03-06, Revision to Technical Specification 3.8.1, AC Sources - Operating
ULNRC-04840, Annual Radioactive Effluent Release Report
LR-N20-0025, 2019 Annual Radioactive Effluent Release Report (Rerr)
2CAN109801, Forwards Addl Info in Support of risk-informed Inservice Insp Pilot Application Submitted in Licensee 970930 & s.Pilot Plant Application Is to Be Used as Alternative, Per 10CFR50.55(a)(3)(i),to Certain ASME Requirements
NSD-NRC-97-5151, Forwards W Responses to NRC RAI Re AP600 Level 1 PRA
BVY-98-114, Provides Response to Request for Addl Info Re Implementation of ASME Code N560 at Plant
B11361, Informs That Error Identified in Attachment II to 841009 Discussion of 840510 Review Meeting Re Fire Related Core Melt Frequency Number.Error Corrected in Encl Revised Attachment II
ET-NRC-93-3872, Forwards Responses to NRC Requests for Addl Info on AP600 from Ltrs of 930126 & 0312.Listing of NRC Requests for Addl Info Responded to Ltr Contained in Attachment a
05000528/LER-1989-008-02, :on 890714,internal Audit Revealed Cooling Tower Sludge Contained Low Level Amounts of Radioactivity. Caused by Lack of Sludge Sampling Before Landfill Disposal. Approval to Dispose of Sludge Requested
05000315/LER-2015-001, Regarding Plant Shutdown Required by Technical Specifications
LR-N15-0078, Annual Radioactive Effluent Release Report
LR-N08-0096, 2007 Radioactive Effluent Release Report for January 1, 2007 to December 31, 2007