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This page provides a simple browsing interface for finding entities described by a property and a named value. Other available search interfaces include the page property search, and the ask query builder.

List of results

• ML022490148  + (Use of Protected Telecommunications for Transmission of Safeguards Information)
• ML022140233  + (Use of Protected Telecommunications for Transmission of Safeguards Information)
• PLA-5464, Use of Protected Telecommunications for Transmission of Safeguards Information  + (Use of Protected Telecommunications for Transmission of Safeguards Information)
• ML020990117  + (Use of Protected Telecommunications for Transmission of Safeguards Information)
• ML020870476  + (Use of Protected Telecommunications for Transmission of Safeguards Information)
• ML021210490  + (Use of Protected Telecommunications for Transmission of Safeguards Information (Tac Nos. MB4882, MB4883, MB4884))
• Information Notice 2025-04, Use of Quality Assurance Alternatives During Exigent Conditions  + (Use of Quality Assurance Alternatives During Exigent Conditions)
• ML19253D077  + (Use of Reconnaissance Level Info for Environ Assessment)
• ML17338A561  + (Use of Revised Reactor Coolant pressure-temp Limits Should Continue Until Final Resolution Re Use of Atypical Weld Wire Is Completed)
• RIS 2000-07, Use of Risk Informed Decision Making in License Amendment Reviews  + (Use of Risk Informed Decision Making in License Amendment Reviews)
• ML20350B444  + (Use of Risk Insights Under 50.59 for NEI 96-07 Public Meeting Summary 120120)
• ML20304A625  + (Use of Risk Insights Under 50.59 for NEI 96-07 Public Meeting Summary 10082020)
• PMNS20200583, Use of Risk Insights in Support of 10 CFR 50.59 Evaluations  + (Use of Risk Insights in Support of 10 CFR 50.59 Evaluations)
• PMNS20200881, Use of Risk Insights in Support of 10 CFR 50.59 Evaluations  + (Use of Risk Insights in Support of 10 CFR 50.59 Evaluations)
• PMNS20201125, Use of Risk Insights in Support of 10 CFR 50.59 Evaluations  + (Use of Risk Insights in Support of 10 CFR 50.59 Evaluations)
• PMNS20201339, Use of Risk Insights in Support of 10 CFR 50.59 Evaluations  + (Use of Risk Insights in Support of 10 CFR 50.59 Evaluations)
• ML103620079  + (Use of Risk Measures in Design and Licensing of Future Reactors)
• DCL-20-108, Use of Risk-Informed Evaluation Methodology to Address Open Phase Condition  + (Use of Risk-Informed Evaluation Methodology to Address Open Phase Condition)
• ML102640144  + (Use of Risk-Informed Inservice Inspection Program for Class 1 and 2 Piping for the Fifth 10 Year Inservice Inspection Interval - R.E. Ginna Nuclear Power Plant)
• Information Notice 2002-07, Use of Sodium Hypochlorite for Cleaning Diesel Fuel Oil Supply Tanks  + (Use of Sodium Hypochlorite for Cleaning Diesel Fuel Oil Supply Tanks)
• ML19340D604  + (Use of Stds in Selecting Sites for Nuclear Power Plants)
• ML20133H212  + (Use of Steady-State Critical Heat Flux Correlations for Transient Analysis in Pwrs)
• ML060250067  + (Use of Subsequent Editions and Addenda of the ASME OM Code)
• 05000255/FIN-2010004-06  + (Use of TLDs May Not Be Consistent With the Methods Used by the NVLAP Accreditation Process)
• 05000305/FIN-2011005-07  + (Use of TLDs may not be consistent with the Methods Used by the NVLAP Accreditation Process)

• RIS 2008-14, Use of TORMIS Computer Code for Assessment of Tornado Missile Protection  + (Use of TORMIS Computer Code for Assessment of Tornado Missile Protection)

• TSTF-484  + (Use of TS 3.10.1 for SCRAM Time Testing Activities)
• 05000285/LER-2013-006, Use of Teflon in LPSI and CS Pump Mechanical Seals  + (Use of Teflon in LPSI and CS Pump Mechanical Seals)
• W3F1-2005-0066, Use of Temporary Alternate Emergency Operations Facility  + (Use of Temporary Alternate Emergency Operations Facility)
• ML20086R261  + (Use of Thickness Reduction to Estimate Values of K)
• ML19275A503  + (Use of Time Series Analysis in Nuclear Reactor Safety Applications)
• 05000454/FIN-2011005-03  + (Use of Tlds May Not Be Consistent with the Methods Used by the NVLAP Accreditation Process)
• 05000440/FIN-2016007-02  + (Use of Unapproved Standard for Site Flooding Modifications and Analysis)
• 05000346/FIN-2013010-02  + (Use of Unqualified Procedure for Ultrasonic Examination of Shield Building Rebar)
• ML050670474  + (Use of Updated Version of PGP Encryption Software for Electronic Transmission of Safeguards Information)
• AEP-NRC-2008-25, Use of Weld Inlays as an Alternative Repair Technique for Reactor Vessel Safe End-to-Primary Nozzle Alloy 82/182 Welds  + (Use of Weld Inlays as an Alternative Repair Technique for Reactor Vessel Safe End-to-Primary Nozzle Alloy 82/182 Welds)
• ML071720528  + (Use of Weld Overlays (TAC Nos. MD3903/3904))
• ML070040490  + (Use of Weld Overlays as an Alternative Repair Technique)
• ML17304A943  + (Use of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI, for Inservice Inspection Activities)
• ML18142B126  + (Use of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI, for Inservice Inspection Activities)
• ML19136A216  + (Use of a Provision in a Later Edition of the ASME Code)
• 05000458/FIN-2010004-03  + (Use of a decommissioning funding mechanism that did not meet the requirements of 10 CFR 50.75(e)(1)(v))
• 05000219/FIN-2015008-01  + (Use of an Analytical Method to Determine the Core Operating Limits Without Prior NRC Approval)
• 05000373/FIN-2015009-01  + (Use of an Analytical Method to Determine the Core Operating Limits without Prior NRC Approva)
• 05000482/FIN-2008004-02  + (Use of hammer to reduce accumulator check valve leakage)
• ML081200001  + (Use of the 1995 ASME Code and Perform Flaw Evaluation of the Recirculation Inlet Nozzle-to-Safe End Weld Indication)
• NG-07-0933, Use of the Provisions of Appendix Viii, Article VIII-4000, in the Evaluation of Changes in Maximum Cable Length for In-Service Inspection Examination Equipment  + (Use of the Provisions of Appendix Viii, Article VIII-4000, in the Evaluation of Changes in Maximum Cable Length for In-Service Inspection Examination Equipment)
• NUREG/CR-6859, Use of the University of Marylands Letter Report, Thermal-hydraulic Uncertainty Analysis in Pressurized Thermal Shock Risk Assessment, as a Reference in Our NUREG/CR-6859, PRA Procedures and Uncertainty for PTS Analysis  + (Use of the University of Marylands Letter Report, Thermal-hydraulic Uncertainty Analysis in Pressurized Thermal Shock Risk Assessment, as a Reference in Our NUREG/CR-6859, PRA Procedures and Uncertainty for PTS Analysis)
• 05000482/FIN-2007002-02  + (Use of wrench on manual service water valve handwheel)
• ML20245L263  + (Used Molded Case Circuit Breakers Installed in Safety- Related Applications, Safety Evaluation 252)
• ML20245L289  + (Used Molded Case Circuit Breakers Installed in Safety- Related Applications, Addendum 1 to Safety Evaluation 252)