3E-2D4
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creation date: 2025-12-12T02:42:26-05:00
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3E-4
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IR 05000269/2003011
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IR 05000397/2002005
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IR 05000341/2012004
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Regulatory Guide 8.36
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ML17130A970
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LR-N17-0087, 2016 Annual Radioactive Effluent Release Report
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LR-N15-0078, Annual Radioactive Effluent Release Report
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LR-N14-0084, Offsite Dose Calculation Manual, Revision 27
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LR-N13-0093, 2012 Annual Radioactive Effluent Release Report, for the Period of January 1, 2012, to December 31, 2012
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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
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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
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LR-N17-0088, Redacted - Hope Creek Generating Station Updated Final Safety Analysis Report, Rev. 22, Appendices 15A - 15D
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LR-N17-0088, Hope Creek Generating Station Updated Final Safety Analysis Report, Rev. 22, List of Current Pages and Master Table of Contents
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LR-N17-0088, Hope Creek Generating Station Updated Final Safety Analysis Report, Rev. 22, Chapter 11, Radioactive Waste Management
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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
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NL-16-2280, Vogtle Electric Generating Plant, Units 1 & 2, Updated Final Safety Analysis Report, Figures 3D-137 Through 4.3-41
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LR-N14-0084, Salem, Units 1 and 2, Offsite Dose Calculation Manual, Revision 27
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LR-N14-0084, Hope Creek and Salem, Units 1 and 2, 2013 Annual Radioactive Effluent Release Report
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LR-N12-0121, Salem and Hope Creek - 2011 Annual Radioactive Effluent Release Report
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LR-N10-0140, Hope Creek - Attachment 1, Offsite Dose Calculation Manual Revision, 23
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LR-N10-0140, Salem - Attachment 1, Offsite Dose Calculation Manual, Revision 23
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LR-N10-0140, Salem - Attachment 1, Offsite Dose Calculation Manual, Revision 22
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2CAN011005, Supplement to Request for Alternative Implementation of a Risk-Informed Inservice Inspection Program Based on ASME Code Case N-716
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L-MT-10-003, Mellla+ Risk Assessment, Attachment 6 of L-MT-10-003
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2CAN011001, Request for Alternative - Implementation of a Risk-Informed Inservice Inspection Program Based on ASME Code Case N-716
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LR-N09-0099, Hope Creek, and Salem, Units 1 and 2, 2008 Annual Radioactive Effluent Release Report, Cover Through Page 180
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LR-N08-0096, 2007 Radioactive Effluent Release Report for January 1, 2007 to December 31, 2007
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NL-06-2550, Request to Implement an Alternative Source Term Radtrad Input Files
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LR-N19-0042, 2018 Annual Radioactive Effluent Release Report (ARERR)
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BVY-97-137, Forwards Response to 971009 RAI Re Plans for Implementing ASME Code Case N560 at Vermont Yankee Nuclear Power Station
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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
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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
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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
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RS-21-014, License Amendment Request for One-Time Extension of the Containment Type a Integrated Leakage Rate Test Frequency
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