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creation date: 2025-12-09T19:02:55-05:00
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1E-9
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05000530/LER-2015-004, Condition Prohibited by Technical Specifications 3.0.4 and 3.7.2 Due to an Inoperable Main Steam Isolation Valve
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IR 05000333/2004005
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IR 05000416/2014003
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IR 05000247/2012009
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IR 05000382/2012004
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05000382/FIN-2012004-03
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IR 05000373/2003003
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RS-17-051, Request for License Amendment to Revise Technical Specifications Section 5.5.12 for Permanent Extension of Type a and Type C Leak Rate Test Frequencies
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L-MT-17-016, Risk-Informed Request for Exemption from 10 CFR 50, Appendix R, III.G.2 Requirements for Multiple Spurious Operations of Drywell Spray Motor-Operated Valves
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CNL-17-071, Seismic Probabilistic Risk Assessment, Response to NRC Request for Information Pursuant to 10CFR50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident
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GO2-16-119, License Amendment Request for One-Time 7 Day Extension of Completion Time for TS Condition 3.5.1.A, 3.6.1.5.A, and 3.6.2.3.A
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L-MT-13-062, Response to an Apparent Violation in NRC Inspection Report 05000263/2013008 (EA-13-096)
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L-15-150, Response to Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805
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PLA-7193, Request to Continue Use of a Risk-Informed Inservice Inspection Alternative in a Proposed Relief Request No. 4RR-01 to the Fourth 10-Year Inservice Inspection Program
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NG-13-0182, 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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W3F1-2012-0064, Response to Request for Additional Information Regarding Adoption of National Fire Protection Association Standard NFPA 805 License Amendment Request
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ULNRC-05908, Responses to Requests for Additional Information (RAI) for Severe Accident Mitigation Alternatives
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ML11355A192
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L-11-150, Offsite Dose Calculation Manual, Rev. 24
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SBK-L-11001, Response to Request for Additional Information, NextEra Energy License Renewal Application
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NRC Generic Letter 1984-04
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ML17334B233
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IR 05000397/1996018
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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, Chapter 7, Instrument and Control
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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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TMI-10-021, Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (Adoption of TSTF-425, Revision 3)
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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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ULNRC-05621, 2008 Annual Radioactive Effluent Release Report
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ML081700650
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NUREG/CR-2907 Volume 16, Radioactive Effluents from Nuclear Power Plants - Annual Report 2010
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NRC-07-0034, Response to Request for Additional Information Regarding License Amendment Request for Extension of Completion Time for an Inoperable Emergency Diesel Generator
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CNRO-2007-00022, Request for Alternative GG-ISI-002, Response to Requests for Additional Information
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PLA-6154, Response to SAMA Request for Additional Information
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NRC-06-0040, Proposed License Amendment Request to Extend the Completion Time for Technical Specification 3.8.1 for an Inoperable Emergency Diesel Generator
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3F0506-05, 2005 Technical Specifications Bases Control Program
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NUREG/CR-2907 Volume 20, Radioactive Effluents from Nuclear Power Plants - Annual Report 2014
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