5E-2D05
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creation date: 2025-12-08T16:57:40-05:00
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5E-05
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Regulatory Guide 1.109
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LIC-17-0024, Supplemental Information Needed for Acceptance of Requested Licensing Action Fort Calhoun Station Request for Exemptions from Portions of 10 CFR 50.47 and 10 CFR Part 50, Appendix E (CAC No. MF9067). (Non-Proprietary)(Part 4 of 4)
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BSEP 15-0033, Notification of Full Compliance with Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond Design Basis External Events and Order EA-12-051, Order to Modify Licenses
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NL-14-0343, Seismic Hazard and Screening Report for CEUS Sites
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W3F1-2014-0023, Entergy Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Per 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident, Wa
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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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NRC 2018-0018, License Amendment Request 288, Request to Extend Containment Leakage Rate Test Frequency
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U-603962, Addenda to 2009 Annual Radioactive Effluent Release Report
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NL-10-045, Indian Point Units 1, 2 & 3 - 2009 Annual Radioactive Effluent Release Report
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RS-09-121, License Amendment Request for a One-Time Extension of the Essential Service Water Train Completion Time
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L-PI-08-027, Nuclear Management Company, Inc. 2007 Annual Radioactive Effluent Report and Offsite Dose Calculation Manual
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RS-08-045, LaSalle, Units 1 and 2, Updated Final Safety Analysis Report (Ufsar), Revision 17, Chapter 15.0 - Accident Analyses
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NL-08-068, Indian Point, Units 1, 2 and 3 - 2007 Annual Radioactive Effluent Release Report
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L-08-081, Reply to Request for Additional Information Regarding Severe Accident Mitigation Alternatives License Renewal
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NL-08-009, Indian Point Energy Center - Hydrogeologic Site Investigation Report - Appendix N (Continued) Through End
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NRC 2013-0028, Point Beach Nuclear Plant, Units 1 and 2: License Amendment Request 271 - Transition to 10 CFR 50.48(c) - NFPA 805, Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants, 2001 Edition. Part 2
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CPSES-200700130, License Amendment Request (LAR) 06-009, Revision to Technical Specification (TS) 3.8.1, AC Sources - Operating, Extension of Completion Times for Diesel Generators
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LIC-19-0001, License Amendment Request (LAR) 19-01: Independent Spent Fuel Storage Installation (ISFSI) Emergency Plan and Emergency Action Level Scheme
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JAFP-02-0051, Semi-Annual Radioactive Effluent Release Report for July 1, 2001 Through December 31, 2001
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NOC-AE-04001743, 2004 Evaluated Emergency Preparedness Exercise Scenario. Introduction Through Frisker Swipe CPM
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RS-03-065, Units 1 & 2, Request for License Amendment for One-Time Extension of Essential Service Water Train Completion Time
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RS-03-004, Response to Request for Additional Information Supporting a Relief Request for Alternative Testing of Containment Sump Suction Valves 1/2S18811A/B
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RS-02-179, Request for Technical Specification Change Extension of Completion Time for Instrument Bus Inverters
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E910-02-018, Annual Radioactive Effluent Releases Report
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WO 02-0019, Annual Radioactive Effluent Release Report - Report 25
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IR 05000254/1989019
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BSEP-95-0344, Forwards Corrected Effluent & Waste Disposal Annual Rept for 1993 Suppl Info. Info Will Be Published in NUREG/CR-2907
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RBG-37649, Addendum Semiannual Radioactive Effluent Release Rept for 920101 Through 920630
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SNRC-2185, Summarizes Results from Revised Exposure Pathway Analysis Using Corrected Dcf for External Exposure for Cs-137.Rev 1 to Analysis of Bulk Matl Reconcentration Potential & Possible Exposure Pathways Encl
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RBG-48220, Submittal of 2022 Annual Radioactive Effluent Release Report
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3F0884-19, Effluent & Waste Disposal Semiannual Rept,Jan-June 1984
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IR 05000010/1977026
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ML20149K344
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IR 05000155/1977018
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IR 05000155/1978003
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IR 05000346/1981006
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IR 05000254/1980021
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IR 05000295/1980022
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IR 05000266/1980013
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IR 05000282/1979032
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IR 05000155/1978011
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IR 05000266/1979015
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ML19296A528
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IR 05000409/1979021
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PLA-2993, Semiannual Effluent & Waste Disposal Rept,Jul-Dec 1987. W/
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PLA-3433, Semiannual Effluent & Waste Disposal Rept for Jan-June 1990 for Susquehanna Steam Electric Station
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PLA-3739, Semiannual Radioactive Effluent Release Rept for Jul-Dec 1991
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Low Steam Generator Water Level in Steam Generator a Caused Reactor Trip.Caused by Broken Valve Stem FCV-3-478 Due to Improper Load Distribution.Stems Replaced
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IR 05000315/1980022
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IR 05000315/1991021
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IR 05000315/1978039
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IR 05000315/1987030
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IR 05000315/1978032
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PLA-3529, Semiannual Radioactive Effluent Release Rept for Jul-Dec 1990
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IR 05000315/1978026
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IR 05000237/1988019
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L-80-351, Forwards Comments on Suppl Info to Draft Effluent & Waste Disposal Semiannual Rept for 1978 Encl in
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L-93-021, ERS-ATL-93-021, Rev. 4, Process Alarm Setpoints for Liquid Effluent Monitors
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ML19101A184
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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
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A00000, CRC Depletion Calculations for the Rodded Assemblies in Batches 10 and 11 of Crystal River Unit 3
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W3F1-2003-0079, 6 to EP-002-050, Offsite Dose Assessment (Manual)
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NUREG-0218, Letter Requesting Comments and Suggested Changes and an Enclosed Draft Copy of Data with Respect to Nine Mile Point Unit 1
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