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CP-201400324, Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(0 Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident
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L-PI-14-028, PINGP 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 Fukushima Dai-ichi Accident
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L-PI-13-102, License Amendment Request (LAR) to Revise Staff Augmentation Times in the Prairie Island Nuclear Generating Plant (PINGP) Emergency Plan
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2CAN111301, Response to Request for Additional Information, Adoption of National Fire Protection Association Standard NFPA-805
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RS-13-131, First Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)
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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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LR-N17-0088, Hope Creek Generating Station Updated Final Safety Analysis Report, Rev. 22, Chapter 11, Radioactive Waste Management
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NL-15-1898, Enclosure 3: Hatch EAL Calculations - License Amendment Request for Changes to EAL Schemes to Adopt NEI 99-01 Rev. 6 and to Modify Radiation Monitors at Farley Nuclear Plant. Part 1 of 3
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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. 6
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ML21194A307
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ML21130A214
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ML20309A731
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ML20246G438
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BVY-98-114, Provides Response to Request for Addl Info Re Implementation of ASME Code N560 at Plant
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ML22070A159
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ML20189A102
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L-2022-038, Emergency Response Data System (Eros) Changes
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AECM-88-0174, Semiannual Radioactive Effluent Release Rept,Jan-June 1988
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BECO-85-180, Provides Info to Close Remaining Open Issues Re NUREG-0737, Item I.D.2 Concerning Spds.Complete List of Radiation Monitors Which Will Be Used in SPDS for Monitoring Radioactivity Control Safety Provided
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ML20140G488
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ST-HL-AE-4248, Forwards Changes to Emergency Response Data Sys (ERDS) Data Point Library (Dpl),Per 10CFR50 & NUREG-1394,rev 1
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Nrc Contractor
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label: B14323, Forwards Dpl for Millstone Unit 1,2,3 & Haddam Neck Plant. Dpl Lists Data Points That Will Be Transmitted for Erds. Update to ERDS Will Incorporate Changes Identified During Sys Testing Performed W/Nrc Contractor
page: https://kanterella.com/B14323-2C_Forwards_Dpl_for_Millstone_Unit_1-2C2-2C3_-26_Haddam_Neck_Plant._Dpl_Lists_Data_Points_That_Will_Be_Transmitted_for_Erds._Update_to_ERDS_Will_Incorporate_Changes_Ident…
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ET-NRC-92-3789, Forwards Westinghouse Response to NRC 920923,1001,09 & 28 Requests for Addl Info on AP600
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ML20252A251
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ML20114E142
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L-06-221, Rev 0 to in Situ Operational Testing of HPCS Svc Water Pump for Grand Gulf Nuclear Power Station
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ML20106E901
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ST-HL-AE-4028, Forwards ERDS Data Point Library,Rev a for Conformance W/ NUREG-1394 & ERDS Communications Description & Questionnaire
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IR 05000277/2022003
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ML22095A177
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ML23076A044
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NUREG/CR-2907 Volume 26, Radioactive Effluents from Nuclear Power Plant - Annual Report 2020
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ML22122A092
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3F0407-12, License Amendment Request 295, Revision 0, Extension of Allowed Outage Time to Seven Days and Elimination of Second Completion Times Limiting Time
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3F0105-02, License Amendment Request 289, Revision 0 Revised Improved Technical Specifications 3.5.2, Emergency Core Cooling Systems - Operating, 3.6.6, Reactor Building Spray & Containment Cooling Systems, 3.7.8, Decay Heat Closed Cycle.
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ML24199A151
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NUREG/CR-2907 Volume 27, Radioactive Effluents from Nuclear Power Plants: Annual Report 2021
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IR 05000282/2024010
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ML23304A474
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05000318/LER-2023-001-01, Condition Prohibited by Technical Specifications Due to Inoperable Nuclear Instrumentation at Very Low Power
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LER-1996-035, :on 961018,requirement for Post Accident Iodine Sampling Inadvertently Removed from Procedure.Caused by Inadequate Control of Licensing Commitment.Procedure 9-304-1 Was Corrected
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label: 05000309/LER-1996-035, :on 961018,requirement for Post Accident Iodine Sampling Inadvertently Removed from Procedure.Caused by Inadequate Control of Licensing Commitment.Procedure 9-304-1 Was Corrected
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IR 05000387/2024012
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ML24135A321
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JAFP-23-0064, Emergency Plan Document Revision
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IR 05000317/1979011
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ML19210D818
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IR 05000317/1979007
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ML19206A791
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RAIO-0518-60098, LLC - Response to NRC Request for Additional Information No. 397 (Erai No. 9238) on the NuScale Design Certification Application
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ML18117A027
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GO2-84-465, Semiannual Effluent Rept,Jan-June 1984
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GO2-90-144, Washington Nuclear Plant 2 Semiannual Effluent Release Rept,Jan-June 1990
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L-94-220, Forwards Response to Addl Info Re Proposed License Amends on Flood Protection
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ML16047A342
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NUREG/CR-2907 Volume 19, Radioactive Effluents from Nuclear Power Plants - Annual Report 2013
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ML16230A385
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IR 05000206/1988020
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IR 05000206/1988018
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ML13196A428
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ML13311A426
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L-PI-12-007, Response to Requests for Additional Information for License Amendment Request to Add Diesel Fuel Oil License Bases and Revise Technical Specifications 3.7.8, Cooling Water System & 3.8.3, Diesel Fuel Oil
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IR 05000280/2009301
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L-09-143, License Amendment Request to Exclude Source Range Neutron Flux Instrument Channel Preamplifier from Channel Calibration Requirements of Technical Specification 3.3.9, Source Range Neutron Flux, & TS 3.9.2, Nuclear Instrumentation
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ML090360056
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ML100700507
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RNP-RA/05-0048, Response to NCR Request for Additional Information Regarding Proposed Technical Specifications Changes to Section 3.3
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IR 05000281/2002301
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Regulatory Guide 3.34
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