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RA-18-0090, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors
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JPN-92-024, Responds to Requesting That Util Review FitzPatrick IPE to Assess Accuracy of IPEs Underlying Evaluations & Conclusions & Reconcile W/Findings of Det
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B14476, Forwards Response to NRC 930326 Telcon Request for Addl Info Re Individual Plant Exam,Per GL 88-20.Info Submitted to Enable NRC to Review Util 930331 Individual Plant Exam Results
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0CAN118906, Responds to 890829 Request for Proposed Program for Completion of Generic Ltr 88-20 Re Individual Plant Exam (IPE) for Severe Accident Vulnerabilities.Util Intends to Submit Results of Both Units by End of 1991
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BECO-89-159, Responds to Generic Ltr 88-20,Suppl 1,describing Plan for Completing Individual Plant Exam for Severe Accident Vulnerabilities.Performance of Level 1 PRA Based on Current Plant Design & Operation Intended
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NUREG-2225, Basis for the Treatment of Potential Common-Cause Failure in the Significance Determination Process
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Volcanic Eruption.Events Initiated by Internal Fires Will Be Evaluated by Level 1 PRA
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CR-2300 & Focused or Modified Only to Extent That NRC Concerns Addressed
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L-84-133, Application for Amend to License NPF-16,revising Tech Specs to Extend Subgroup Test Interval from 6 to 18 Months
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L-85-406, Forwards Addl Info Re 840522 Application for Amend to License NPF-16,increasing Esfas/Auxiliary Feedwater Actuating Sys Actuation Logic Surveillance Interval from 6 Months to 18 Months
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ML14314A421
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NL-14-043, Entergy Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima
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ML16237A379
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ML13066A433
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TXX-1208, License Amendment Request (LAR) 12-004, Revision to Technical Specification 3.8.1, Ac Sources - Operating, for Two, 14-Day Completion Times for Offsite Circuits
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RS-17-123, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors
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ML18152B374
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RS-10-015, Request for Amendment to Technical Specification 3.1.7, Standby Liquid Control (SLC) System
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NOC-AE-060019, Proposed Amendment to Technical Specification 6.8.3.j for One-Time Extension of Integrated Leakage Rate Test Interval to 20 Years
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SBK-L-05197, License Amendment Request 05-06 Application for Amendment to Technical Specification 6.15 for a Six Month Extension to the Containment Integrated Leak Rate Test Interval
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ML051050123
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RS-05-001, Request for a License Amendment to Extend the Completion Times Related to Technical Specifications Associated with Residual Heat Removal Service Water, Diesel Generator Cooling Water and the Opposite Unit Division 2 Diesel
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NG-02-0237, Response to Request for Additional Information (RAI) for Technical Specification Change Request TSCR-048 - One-Time On-Line Safety-Related Battery Replacement
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ML17335A167
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LR-N04-0036, Correction PSEG Letter LR-N04-0036, Risk-Informed Inservice Inspection Submittal
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RS-02-164, Request for Amendment to Technical Specification 5.5.13, Primary Containment Leakage Rate Testing Program
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ML21138A781
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L-MT-20-036, Response to Request for Additional Information Related to License Amendment Request to Implement Technical Specification Task Force Traveler TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times
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LR-N25-0005, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors
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DCL-24-111, License Amendment Request 24-05 Revision to Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times – RITSTF Initiative 4b for TS 3.3.1 and 3.3.2
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W3F1-2020-0047, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, System, and Components (Sscs) for Nuclear Power Reactors
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SBK-L-21098, Supplement to License Amendment Request 21-01, Revise 120-Volt AC Vital Instrument Panel Requirements
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BECO-91-155, Describes Program Plan for Completing Individual Plant Exam of External Events for Severe Accident Vulnerabilities,Per Suppl 4 to Generic Ltr 88-20.Exam Will Include Seismic Events,Internal Fires,High Winds & External Floods
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CP-202300270, (CPNPP) - Response to Request for Supplemental Information for License Amendment Request to Adopt 10 CFR 50.59, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors
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L-2025-041, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors
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NUREG/CR-5176, Updated Board Notification 89-01 Re Lll NUREG/CR-5176, Seismic Failure & Cask Drop Analyses of Spent Fuel Pools at Two Representative Nuclear Power Plants
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