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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
- CY-97-017, Forwards Supplemental Response to Submitted in Response to Confirmatory Action Ltr + (ML20137C889)
- 05000352/LER-1985-095, :on 851208,full Reactor Scram Occurred Due to High Neutron Flux.Caused by Loose Wires in Recirculation Pump B Motor Generator Control Circuit.Connection Screws & Circuit Tested + (ML20137C890)
- ML20137C894 + (ML20137C894)
- 05000458/LER-1985-016, :on 851024,ESF Isolation of Shutdown Cooling Suction Valve Occurred.Caused by Jumper Slipping Off Terminal & Blowing Fuse During Surveillance Test.Fuse Replaced.Banana Plugs Installed + (ML20137C895)
- ML20137C897 + (ML20137C897)
- ML20137C900 + (ML20137C900)
- ML20137C903 + (ML20137C903)
- ML20137C907 + (ML20137C907)
- ML20137C908 + (ML20137C908)
- ML20137C911 + (ML20137C911)
- ML20137C913 + (ML20137C913)
- 05000382/LER-1985-053, :on 851212,discovered That Portion of Core Protection Calculator Tech Spec Functional Test Not Performed for Several Intervals.Caused by Procedural Change Eliminating Requirement.Procedure Changed + (ML20137C916)
- ST-HL-AE-1572, Forwards Response to Draft SER Item 61F Re Proportional Integral Derivitive Controller mod,NUREG-0737,II.K.3.9. Requests That NRC Consider Item closed.Marked-up FSAR Page Will Be Included in Future FSAR Amend + (ML20137C918)
- ML20137C920 + (ML20137C920)
- ML20137C922 + (ML20137C922)
- ML20137C924 + (ML20137C924)
- 05000458/LER-1985-018, :on 851021,RHR Sys Loop a Isolation Occurred. Caused by Technician Mistakenly Connecting Lead to Wrong Relay & Then Misinterpreting Relay Drawings.Isolation Reset. Test Jacks Added to Terminals + (ML20137C925)
- ML20137C927 + (ML20137C927)
- 05000483/LER-1985-053, :on 851209,discovered That Penetration 98 (P-98) Not Included in Surveillance Procedure Used to Satisfy Tech Spec 3/4.6.1.1.Caused by Personnel error.P-38 Verified Closed.Procedure Will Be Revised + (ML20137C930)
- 05000220/LER-1985-025, :on 851215,reactor Power Reduction Initiated Due to Inability to Monitor Specified Core Thermal Parameters.Caused by Plant Process Computer Failure. Reactor Power Restored + (ML20137C935)
- 05000318/LER-1985-012-01, :on 851212,during Mode 1,reactor Tripped on Low Steam Generator Water Due to Loss of Steam Generator Feed Pump 21.Caused by Defective High Signal Selector.Selector Replaced + (ML20137C939)
- ML20137C941 + (ML20137C941)
- 05000528/LER-1985-087, :on 851209,discovered That Response Time for Loss of Power Relays Did Not Meet Acceptance Criteria.Unit Entered Mode 3 on 851128 W/O Meeting Action Statement + (ML20137C942)
- 05000458/LER-1985-017, :on 851025,ESF Isolation of Shutdown Cooling Section Valve Occurred.Caused by Inadvertent Grounding of Recorder Lead During Attempt to Attach to Relay Terminal. Fuse Replaced.Procedure STP-204-0602 Revised + (ML20137C943)
- ML20137C945 + (ML20137C945)
- ML20137C946 + (ML20137C946)
- ML20137C949 + (ML20137C949)
- ML20137C952 + (ML20137C952)
- ML20137C954 + (ML20137C954)
- ML20137C956 + (ML20137C956)
- 05000312/LER-1984-016, :on 840425,RCS Pump Seal Return Line Isolation Valve Exceeded Tech Spec Stroke Time Limit.Caused by Weaknesses in Documentation & Surveillances of Equipment. Valve Restroked.Surveillance Procedure Revised + (ML20137C957)
- ML20137C959 + (ML20137C959)
- ML20137C960 + (ML20137C960)
- ML20137C961 + (ML20137C961)
- NPL-97-0090, Responds to GL 96-05, Periodic Verification of Design-Basis Capability of SR Movs + (ML20137C963)
- ML20137C966 + (ML20137C966)
- ML20137C967 + (ML20137C967)
- ML20137C971 + (ML20137C971)
- ML20137C974 + (ML20137C974)
- ML20137C975 + (ML20137C975)
- IA-85-450, Responds to FOIA Request for Mailing List for IE Info Notices Issued by Div of Emergency Preparedness & Engineering Response.Mailing Labels Encl.Labels W/ Individual Names Deleted,Per 850716 Telcon.W/O Encls + (ML20137C975)
- ML20137C978 + (ML20137C978)
- 05000281/LER-1985-011-02, :on 851023,emergency Diesel Generator (EDG) Automatically Started.Caused by Inadequate Design Change Test Procedure.Control of EDG 2 Transferred to Main Control Room Panel & Diesel Shut Down + (ML20137C982)
- ML20137C983 + (ML20137C983)
- ML20137C984 + (ML20137C984)
- ML20137C987 + (ML20137C987)
- B16327, Monthly Operating Rept for Feb 1997 for Millstone Nuclear Power Station Unit 3 + (ML20137C990)
- ML20137C992 + (ML20137C992)
- NPL-97-0104, Forwards Documentation for Review to Support Restart Issues Identified on Unit 2 Startup Commitment List + (ML20137C994)
- 05000316/LER-1985-041-01, :on 851211,at 81% Reactor Thermal Power,High Alarm Received on Upper Containment Normal Range Area Monitor,Train B After Instrument Failed Low.Investigation Into Cause Continuing + (ML20137C998)
- ML20137D005 + (ML20137D005)