5E-2D4
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creation date: 2025-12-08T16:36:19-05:00
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5E-4
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05000352/FIN-2016001-02
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IR 05000352/2016001
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IR 05000286/2015010
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Regulatory Guide 3.73
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IR 05000220/2008007
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IR 05000352/2002004
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LR-N17-0087, 2016 Annual Radioactive Effluent Release Report
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LR-N16-0232, Response to Prelim White Finding in Integrated Inspection Report 05000354/2016003
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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
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ML101970547
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LR-N18-0021, Supplemental Information to License Amendment Request for Implementation of WCAP-14333 and WCAP-15376, Reactor Trip System Instrumentation and Engineered Safety Feature Actuation System Instrumentation Test Times and Completion Times
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ML15132A064
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LR-N15-0078, Annual Radioactive Effluent Release Report
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NL-15-030, Revised 10 C.F.R. 50.59 Safety Evaluation and Supporting Analyses Prepared in Response to the Algonquin Incremental Market Natural Gas Project
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NL-14-106, 10 C.F.R. 50.59 Safety Evaluation and Supporting Analyses Prepared in Response to the Algonquin Incremental Market Natural Gas Project Indian Point Nuclear Generating Unit Nos. 2 & 3
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NRC 2014-0054, Response (90 Day) to Request for Additional Information License Amendment Request Associated with NFPA 805
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ML14160B113
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LR-N14-0084, Offsite Dose Calculation Manual, Revision 27
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ML14010A306
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ML12340A450
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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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NRC 2013-0021, Request for Approval of Risk-Informed/Safety Based Inservice Inspection Alternative for Class 1 and 2 Piping in Accordance with 10 CFR 50.55a(a)(3)(i)
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NG-13-0102, 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 Generating Plants
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ML12361A019
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ULNRC-05908, Responses to Requests for Additional Information (RAI) for Severe Accident Mitigation Alternatives
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ML071580314
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ML12171A320
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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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ML12011A165
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SBK-L-11197, Request for Alternative to Use ASME Code Case N-716 to Implement Risk-Informed Inservice Inspection Program
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ML022200382
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ML092660616
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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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ML020430357
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NRC 2018-0018, License Amendment Request 288, Request to Extend Containment Leakage Rate Test Frequency
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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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L-2016-198, Turkey Point, Units 3 & 4, Updated Final Safety Analysis Report, List of Effective Pages
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L-2016-198, Turkey Point, Units 3 & 4, Updated Final Safety Analysis Report, Chapter 5, Structures
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DCL-15-027, Diablo Canyon Power Plant Er Changes Reflected in the Environmental Report Update Amendment 2. Part 5 of 9
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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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NL-14-106, 10CFR50.59 Safety Evaluation and Supporting Analyses Prepared in Response to the Algonquin Incremental Market Natural Gas Project, Indian Point Nuclear Generating Station, Unit Nos. 2 & 3
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ML18180A326
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NG-17-0235, Duane Arnold Energy Center, Calc No. NEE-323-CALC-005, Revised Gaseous Radiological EALs Per NEI 99-01 Rev. 06
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LR-N12-0121, Salem and Hope Creek - 2011 Annual Radioactive Effluent Release Report
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ML101730384
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10-0108, H. B. Robinson,Response to Request for Additional Information Regarding Changes to Technical Specification Section 3.3.2, Engineered Safety Feature Actuation System Instrumentation, and Section 3.3.6, Containment Ventilation Isolation
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label: RNP-RA/10-0108, H. B. Robinson,Response to Request for Additional Information Regarding Changes to Technical Specification Section 3.3.2, Engineered Safety Feature Actuation System Instrumentation, and Section 3.3.6, Containment Ventilation Isolation
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L-2010-212, Turkey Point, Units 3 & 4, Updated Final Safety Analysis Report - Unit 4 Cycle 24 Update, Chapter 5, Structures
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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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RNP-RA/10-0019, Supplemental Information for Request for Technical Specifications Change Regarding Steam Generator Alternate Repair Criteria
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