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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
- ML20207F883 + (ML20207F883)
- ML20207F886 + (ML20207F886)
- ML20207F887 + (ML20207F887)
- ML20207F888 + (ML20207F888)
- ML20207F890 + (ML20207F890)
- ML20207F891 + (ML20207F891)
- ML20207F892 + (ML20207F892)
- ML20207F895 + (ML20207F895)
- ML20207F897 + (ML20207F897)
- ML20207F904 + (ML20207F904)
- ML20207F907 + (ML20207F907)
- ML20207F911 + (ML20207F911)
- B12955, Provides NRC W/Plans for Mods Re Degraded Grid Protection for Class 1E Power Sys.Delays Occurred as Result of Identification of Significant Concerns During Review. Requests NRC Initiation of Review of Design + (ML20207F912)
- ML20207F913 + (ML20207F913)
- ML20207F916 + (ML20207F916)
- ML20207F917 + (ML20207F917)
- ML20207F922 + (ML20207F922)
- ML20207F923 + (ML20207F923)
- ML20207F925 + (ML20207F925)
- 1CAN088802, Informs That Util Plans to Perform Section XI Required Exam on Reactor Coolant Pumps (RCP) a & B as Listed.Developments Underway to Use Ultrasonic Test & Other Techniques to Perform Exams of RCPs + (ML20207F927)
- ML20207F930 + (ML20207F930)
- ML20207F935 + (ML20207F935)
- ML20207F936 + (ML20207F936)
- ML20207F937 + (ML20207F937)
- ML20207F938 + (ML20207F938)
- ML20207F940 + (ML20207F940)
- ML20207F941 + (ML20207F941)
- 05000416/LER-1986-022, :on 860619,discovered That Instrument Channel Which Provides Automatic Depressurization Sys Actuation Permissive Signal Not Tested During Mar 1986.Caused by Personnel Error.Package Checks Improved + (ML20207F943)
- ML20207F945 + (ML20207F945)
- ML20207F949 + (ML20207F949)
- ML20207F950 + (ML20207F950)
- ML20207F951 + (ML20207F951)
- ML20207F952 + (ML20207F952)
- ML20207F954 + (ML20207F954)
- 05000271/LER-1986-007, :on 860621,while Performing Type a Containment Leak Rate Test,Leakage in Excess Permitted by Tech Spec Section 4.7.2 Measured.Leak Sources Identified & Repaired. Type a Leak Test Performed Successfully + (ML20207F956)
- ML20207F957 + (ML20207F957)
- ML20207F958 + (ML20207F958)
- ML20207F959 + (ML20207F959)
- ML20207F960 + (ML20207F960)
- NRC-86-3193, Forwards Proprietary Sequoyah Unit 1 Heat Treatment of Steam Generator Inner Radius U-Bend Tubes. Proprietary & Nonproprietary Versions Will Be Submitted within 4 Wks.Rept Withheld (Ref 10CFR2.790) + (ML20207F963)
- ML20207F966 + (ML20207F966)
- ML20207F969 + (ML20207F969)
- ML20207F971 + (ML20207F971)
- ML20207F973 + (ML20207F973)
- ML20207F974 + (ML20207F974)
- ML20207F975 + (ML20207F975)
- ML20207F980 + (ML20207F980)
- ML20207F981 + (ML20207F981)
- ML20207F986 + (ML20207F986)
- ML20207F988 + (ML20207F988)
- ML20207F990 + (ML20207F990)