LR-N17-0087, 2016 Annual Radioactive Effluent Release Report
LR-N15-0078, Annual Radioactive Effluent Release Report
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
NG-12-0177, Response to Request for Additional Information, License Amendment Request to Adopt National Fire Protection Association Standard 805, Performance-Based Standard for Fire Protection for Light Water Reactor Generational Plants
NL-10-2355, Request for Approval of Risk-Informed/Safety Based Inservice Inspection Alternative for Class 1 and 2 Piping FNP-ISI-AL T-12, Version 2.0
LR-N17-0088, Redacted - Hope Creek Generating Station Updated Final Safety Analysis Report, Rev. 22, Appendices 15A - 15D
LR-N17-0088, Hope Creek Generating Station Updated Final Safety Analysis Report, Rev. 22, List of Current Pages and Master Table of Contents
LR-N17-0088, Hope Creek Generating Station Updated Final Safety Analysis Report, Rev. 22, Chapter 11, Radioactive Waste Management
LR-N17-0088, Hope Creek Generating Station Updated Final Safety Analysis Report, Rev. 22, Chapter 3, Design of Structures, Components, Equipment and Systems, Appendices 3A Through 3I
NL-16-2280, Vogtle Electric Generating Plant, Units 1 & 2, Updated Final Safety Analysis Report, Figures 3D-137 Through 4.3-41
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
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
2CAN011005, Supplement to Request for Alternative Implementation of a Risk-Informed Inservice Inspection Program Based on ASME Code Case N-716
L-MT-10-003, Mellla+ Risk Assessment, Attachment 6 of L-MT-10-003
2CAN011001, Request for Alternative - Implementation of a Risk-Informed Inservice Inspection Program Based on ASME Code Case N-716
LR-N09-0099, Hope Creek, and Salem, Units 1 and 2, 2008 Annual Radioactive Effluent Release Report, Cover Through Page 180
LR-N08-0096, 2007 Radioactive Effluent Release Report for January 1, 2007 to December 31, 2007
NL-06-2550, Request to Implement an Alternative Source Term Radtrad Input Files
LR-N19-0042, 2018 Annual Radioactive Effluent Release Report (ARERR)
LR-N04-0117, Stations, Radioactive Effluent Release Report
L-PI-03-052, Annual Radioactive Effluent Report & Offsite Dose Calculation Manual. Attachment 4 Pages 77 - 211
L-03-072, Annual Radioactive Release Report for 2002, Table of Contents Through Attachment E
CPSES-200300262, Supplemental Information for Consideration During Significance Determination Process Review of Apparent Violation 50-445/02-09-01
E910-02-046, Decommissioning Environmental Report, Revision 2
LR-N20-0025, 2019 Annual Radioactive Effluent Release Report (Rerr)
IA-85-199, Forwards Draft Rev of Policy Statement on Severe Reactor Accidents Re Future Designs & Existing Plants & Draft NUREG-1070,incorporating Policy Statement Rev,As Followup to Response to Commission Questions Per SECY-84-370
B12002, Forwards Probabilistic risk-based Fire Analysis of internally-initiated Events.Fire Analysis Documented as Chapter 6 of Probabilistic Safety Study.W/Nine Oversize Encls
BVY-97-137, Forwards Response to 971009 RAI Re Plans for Implementing ASME Code Case N560 at Vermont Yankee Nuclear Power Station
HL-4672, Responds to GL 94-03 Re IGSCC of Core Shrouds in Bwrs.Ge Evaluation of Indications in Plant Hatch Unit-2 Core Shroud Welds H1,H2,H3 & H4 & Proprietary Info Re Unit Shroud Restraint Sys Encl.Proprietary Info Withheld
W3P85-1466, Semiannual Radioactive Effluent Release Rept for 850304-0630
A08845, Responds to NRC Backfit Analyses of Hardened Wetwell Vent, Contained in .Benefit of Installing Hardened Wetwell Vent to Satisfy Basic Design Objective of Preventing core-melt Event Not Sufficient for Immediate Decision
05000320/LER-1982-003-03, /03L-0:on 820111,during Weekly Scheduled Preventive Maint,Pump NR-P-1B Failed to Start.Caused by Loose Fuse Clip in Control Power Switchgear.Clip Repaired
L-2018-118, Response to Sixth Request for Additional Information Regarding License Amendment Request 236, Revision to the Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 1, Provide Risk-Informed
RAIO-0518-60098, LLC - Response to NRC Request for Additional Information No. 397 (Erai No. 9238) on the NuScale Design Certification Application
L-2018-001, Supplement to Response to Fourth Request for Additional Information Regarding License Amendment Request 236, Revision to the Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 1, Provide
GO2-94-215, Requests Enforcement Discretion from TS 3.6.3.a,for 14 Days Starting on 940915 to Allow Time to Process TS Amend Under Emergency Conditions
L-87-147, Application for Amend to License NPF-16,revising Tech Spec 3/4 7.10, Snubbers, to Delete Snubber Listings,Per Generic Ltr 84-13.Evaluation of NSHC Encl.Fee Paid
RA-02-008, Transmittal of Special Report, Transuranic and Other Hard to Detect Radionuclides in Maine Yankee Sample Media
RS-21-014, License Amendment Request for One-Time Extension of the Containment Type a Integrated Leakage Rate Test Frequency