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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

• ML20115F368  + (Ampacity Derating for Std Fire Wrap Configurations)
• ML20138H294  + (Ampacity Derating of Cables Due to Thermo-Lag - MP-1)
• ML20045D712  + (Ampacity Study Tabulations for 10CFR50 App R Cable Wrapping)
• ML17334A559  + (Ampacity Test for Power Cables)
• ML17333A822  + (Ampacity Test for Power Cables in Randomly-Filled Trays)
• ML20128G986  + (Ampacity of Power Cable Wrapped W/330-660 Installed as Free Air Drop)
• ML050660384  + (Ampdb Report Database Files)
• 05000416/LER-1983-111-03, Amphenol Type Signal Cable Connector in Control Room Panel Disconnected.Caused by Personnel Error.Changes to Administrative Controls Governing Maint Activites Implemented  + (Amphenol Type Signal Cable Connector in Control Room Panel Disconnected.Caused by Personnel Error.Changes to Administrative Controls Governing Maint Activites Implemented)
• ULNRC-05566, Amplification for Amendment, Revision of Technical Specification 3.3.2 and 3.7.2 and Addition of New Technical Specification 3.7.19 (License Amendment Request OL-1277 Revised)  + (Amplification for Amendment, Revision of Technical Specification 3.3.2 and 3.7.2 and Addition of New Technical Specification 3.7.19 (License Amendment Request OL-1277 Revised))
• ML20053B583  + (Amplified Response Spectra for Seismic Category I Structures,Vols 1-3)
• 05000346/LER-1983-016-03, Amplifier of Startup Level Transmitter LT-SP9A3 for Steam Generator 1-2 Failed. Caused by Component Failure within Amplifier.Amplifier Replaced  + (Amplifier of Startup Level Transmitter LT-SP9A3 for Steam Generator 1-2 Failed. Caused by Component Failure within Amplifier.Amplifier Replaced)
• ML20078Q163  + (Amplifies 830204 Statement Re Criteria for Reportability,Per Telcon Request.E Blake in Possession of All Info Re Investigation of Incident.E Blake Statement Encl)
• GO2-83-996, Amplifies 830916 Response to NRC Re Violations Noted in IE Insp Rept 50-397/83-38.Corrective Actions: Discrepancies from Design Requirements Evaluated.Structural Members Adequate for All Loads  + (Amplifies 830916 Response to NRC Re Violations Noted in IE Insp Rept 50-397/83-38.Corrective Actions: Discrepancies from Design Requirements Evaluated.Structural Members Adequate for All Loads)
• ML20137P489  + (Amplifies Contention That alarm-only Mod Adequately Ensures That NUREG-0737,Item II.K.3.19 Recirculation Loop Interlock Functional Requirements Satisfied.Concurrence Requested)
• ML19317G322  + (Amplifies Corrective Action Taken Re RO-77-37 & Describes Intensive Program Set Up to Assure Steam Driven Emergency Feedwater Pump'S Automatic Start on Main Steam Supply)
• ML19317G321  + (Amplifies Corrective Action Taken Re RO-77-37 & Describes Intensive Program Set Up to Assure Steam Driven Emergency Feedwater Pumps Automatic Start on Main Steam Supply)
• ML20028B924  + (Amplifies Justifications Provided in 820721 Application for Amend of CPPR-148 & CPPR-149 to Extend Const Completion Dates.Reduced Demand,Increased Regulations & High Interest Rates Delayed Need for Capacity Supplied by Facilities)
• ML20126C611  + (Amplifies Previous Comments Re Pipe Cracking,Operation of Core Spray Sys & Discussions W/Tmi Water Chemist. Investigating Possibility That Boron Is Related to Pipe Cracking in PWR Fuel Storage Pool Piping Sys)
• ML20005H101  + (Amplifies Response Made in 850515 Licensee Ltr to Concerns Addressed in NRC .Corrective Action Response for Audit QAL-82-0223 Conducted at I-T-E Siemens Allis Found Adequate)
• ML19312E702  + (Amplifies Response to IE Bulletin 80-04 Contained in ,Stating That TMI-I Containment Design Pressure Was 60 Psig.Reiterates That Containment Design Pressure Is 55 Psig. Initial Response Accurate When Assuming 55 Psig Pressure)
• ML20030A582  + (Amplifies Util 740701 Analysis of Postulated Cask Drop Accident,Including Proposed Design & Procedural Mods. Discusses Util 620503 Amend 10,support Features & Cask Routing)
• ENS 48549  + (Amsac Actuated at Lower than Expected Turbine Inlet Pressure)
• ML23171A913  + (Amse, Section XI, Fifth 10 Year Inspection Interval, Inservice Inspection, System Pressure Test, Containment Inspection, and Repair and Replacement Programs, Owner’S Activity Report)
• ML20086T305  + (Amswer to New Contentions Proposed by Friends of the Earth on Onsite Storage of Unirradiated Fuel & Transmittal of Related Correspondence.Proposed Late Contentions Should Be Denied.Certificate of Svc Encl)
• ML21103A032  + (Amz PSA 2021 NRC 390 Signed)

• ML030640288  + (An 08-2002 Draft Operating Exam)

• ML082320824  + (An 2 - Generic Letter 2008-01, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems, Proposed Alternative Course of Action (TAC Nos MD7866 & MD7867))
• RS-16-134, An 2 and Byron, Units 1 and 2 - Appeal of Imposition of Backfit Regarding Compliance with 10 CFR Section 50.34 (B), General Design Criteria (GDC) 15, GDC 21, GDC 29, and Licensing Basis  + (An 2 and Byron, Units 1 and 2 - Appeal of Imposition of Backfit Regarding Compliance with 10 CFR Section 50.34 (B), General Design Criteria (GDC) 15, GDC 21, GDC 29, and Licensing Basis)
• ML031820245  + (An 2, Response to NRC Questions Re License Amendment Request 02-03, Spent Fuel Cask Handling)
• ML17157B366  + (An 2, Submittal of Revised Updated Safety Analysis Report, Revision 23)
• ML030640314  + (An 8-2002 Draft Written Exam)
• ML030640309  + (An 8-2002 Draft Written Exam Comments)
• ML19322A093  + (An Advanced Thermohydraulic Simulation Code for Transients in LMFBRs(SSC-L Code). Describes Physical Models for Various Processes Encountered in Preaccident & Transient Simulation of Thermohydraulic Transients in LMFBR)
• ML20002E401  + (An Advanced Thermohydraulic Simulation Code for POOL-TYPE Lmfbrs (SSC-P Code))
• ML13184A139  + (An Aerial Radiological Survey of the Seabrook Nuclear Station and Surrounding Area - July 1988)
• ML20088A674  + (An Age Structured Stochastic Recruitment Model for Assessment Power Plant Impact)
• ML20236K860  + (An Aging Assessment of Relays and Circuit Breakers and System Interactions)
• ML20238A375  + (An Aging Failure Survey of Light Water Reactor Safety Systems and Components)
• ML20154H700  + (An Aging Failure Survey of Light Water Reactor Safety Systems and Components)
• ML20071P460  + (An Analysis of Boiling Water Nuclear Reactor Stability Margin)
• ML20077F415  + (An Analysis of Core Meltdown Accidents in CE Sys 80+ Plant Using Melcor,)
• ML19282B888  + (An Analysis of Crack Growth Potential in 42-Inch A516 Grade 70 PWR Piping)
• ML20073K875  + (An Analysis of DENSITY-WAVE Oscillations in Ventilated Channels)
• ML20010B563  + (An Analysis of Evacuation Time Estimates Around 52 Nuclear Power Plant Sites)
• ML20010B566  + (An Analysis of Evacuation Time Estimates Around 52 Nuclear Power Plant Sites)
• ML20004C723  + (An Analysis of Evacuation Time Estimates Around 52 Nuclear Power Plant Sites)
• ML20207H314  + (An Analysis of Excursions at Selected in Situ Uranium Mines in Wyoming and Texas)
• ML20044G973  + (An Analysis of Ki Prophylaxis for General Public in Event of Nuclear Accident)
• ML20141D937  + (An Analysis of LOW-LEVEL Wastes:Review of Hazardous Waste Regulations and Identification of Radioactive Mixed Wastes. Final Report)
• ML20009H336  + (An Analysis of Licensee Event Reports Related to Nuclear Generating Station Onsite Electrical Sys Malfunctions 1976-1978)
• ML20071L497  + (An Analysis of Operational Experience During LOW Power and Shutdown and a Plan for Addressing Human Reliability Assessment Issues)