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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
- ML18038A363 +
- Press Release-91-080 NRC Amends Regulations for FITNESS-FOR-DUTY for Licensed Operators, Press Release-91-080 NRC Amends Regulations for FITNESS-FOR-DUTY for Licensed Operators +
- ML003701990 +
- ML18036A296 +
- ML18036A294 +
- ML18096A145 +
- ML18153C675 +
- ML20085E460 +
- ML20082H865 +
- ML20082D405 +
- ML20082D400 +
- ML20082D353 +
- ML20082C451 +
- ML20082C383 +
- ML20082C357 +
- ML20082C185 +
- ML20082C167 +
- ML20082B911 +
- NRC-91-0087, Informs That Facility Currently Does Not Conform to NRC Position on ATWS Alternate Rod Insertion Diversity Requirements.Efforts Underway to Fully Comply by End of Third Refueling Outage +
- ML20082B863 +
- ML20076D408 +
- ML20076C644 +
- ML20076C419 +
- ML20076C373 +
- JPN-91-033, Suppl to 900531 Application for Amend to License DPR-59, Consisting of Suppl a to Holtec Rept HI-89399 Re Expansion of Storage Capacity of Spent Fuel Pool.Analysis Indicates That No rack-to-rack Impacts Would Occur W/Reduced Spacing +
- ML20217C984 +
- 3F0791-08, Forwards Comprehensive Annual Financial Rept,City of Ocala, Fl Fy Ended Sept 1990 & City of Bushenell,Fl General Purpose Financial Statments for Fy Ended Sept 1990 +
- JPN-91-036, Revises Submittal Schedule in 891027 & 901030 Responses to Generic Ltr 88-20 Re Individual Plant Evaluations/Hardened Wetwell Vents.Level II Analysis Will Be Submitted by 910830. Final Position Re Hardened Vents Will Be Sent by 911031 +
- B13884, Forwards Inservice Insp Summary Rept of Millstone Unit 3 Nuclear Power Station,Interval 1,Period 2,Outage 1 +
- U-601859, Forwards Rev 10B to Physical Security Plan for Plant.Rev Withheld (Ref 10CFR73.21(c)(2)) +
- JPN-91-035, Provides Addl Info Re Request for Exemption from 10CFR.50.71(e) to Reschedule Updated FSAR Submittal Date from 910722 to 920122 +
- ELV-02947, Responds to NRC Ltr Re Violations Noted in Insp Repts 50-424/91-10 & 50-425/91-10 on 910520-24.Corrective Actions: Preventive Maintenance Change Request Initiated to Incorporate Fire Pump Gauges & Flow Meters +
- ELV-02943, Responds to NRC Ltr Re Violations Noted in Insp Repts 50-424/91-08 & 50-425/91-08 on 910513-17.Corrective Actions: EOC HVAC Sys Restored Maintaining Positive Pressure During Graded Exercise +
- JSP-458-91, Application for Amend to License NPF-62,changes to Surveillance Requirements, Snubbers, Consistent W/Alternate Schedule for Visual Insp +
- 05000254/LER-1991-010-02, :on 910614,RHR Shutdown Cooling Isolation Valves 1-1001-47 & 50 Isolated While Performing Instrument Functional Test.Caused by Procedural Deficiencies.Calibr & Functional Test Procedure Will Be Revised +
- 05000368/LER-1991-014, :on 910613,four Circuit Breakers in 4160 Volt ESF Switchgear Discovered to Be Routinely Positioned in racked-down Configuration.Caused by Inadequate Licensing Basis Documents.Breakers Moved +
- 05000373/LER-1991-008-03, :on 910613,control Room Ventilation Emergency make-up Train Auto Started on Spurious Trip from Control Room Air Intake Radiation Monitor.Possibly Caused by Random Noise.Logic Modified +
- 05000325/LER-1991-015-01, :on 910612,CRD Hydraulic Control Unit Declared Inoperable.Caused by Simultaneous Inoperability of Two CRD Hydraulic Control Units.Unit Accumulator Recharged W/ Nitrogen & Repaired +
- 05000327/LER-1991-012-01, :on 910612,breach to Control Room Pressurization Boundary Discovered.Caused by Inappropriate Personnel Actions.Work Request Initiated to Seal Breach.W/ +
- 05000354/LER-1990-014, :on 900817,discovered Tech Spec Limit for Ultimate Heat Sink Established Unconservatively High. Caused by Design Calculation Error.Design Change Request Initiated +
- 05000443/LER-1991-007, :on 910615,actuation of Control Room Emergency Air Cleanup & Filtration Subsystems Occurred.Caused by Personnel Error Due to Lack of Attention to Detail.Event Will Be Discuss W/Respective Operating Crews +
- 05000458/LER-1991-002, :on 910216,ESF Actuation Occurred When Reactor Water Sample Containment Isolation Valve.Caused by Failure of Fuse Pressure High.Replacing Fuse & Reopening Reactor Water Sample Valve +
- 05000482/LER-1991-009, :on 910613,discovered That Surveillance Testing for Main Steam Loop 1 Low Point Drain Valve Not Performed at Required Frequency.Caused by Personnel Error.Clearance Order Procedure Revised +
- ML20079D648 +
- ML20085A753 +
- ML20044B464 +
- ML20079D650 +
- ML20029D312 +
- ML20076C869 +
- ML20079D755 +