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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
- ML20101K971 + (ML20101K971)
- 0CAN079201, Forwards Rev 0 to A-MECH-ER-005, Response to NRC Generic Ltr 92-01 for Arkansas Nuclear One - Unit 2, Prepared by C-E + (ML20101K983)
- ML20101K986 + (ML20101K986)
- ML20101K990 + (ML20101K990)
- ML20101K994 + (ML20101K994)
- ML20101L000 + (ML20101L000)
- ML20101L010 + (ML20101L010)
- ML20101L027 + (ML20101L027)
- ML20101L032 + (ML20101L032)
- ML20101L040 + (ML20101L040)
- ML20101L043 + (ML20101L043)
- ML20101L060 + (ML20101L060)
- ML20101L063 + (ML20101L063)
- ML20101L071 + (ML20101L071)
- ML20101L076 + (ML20101L076)
- ML20101L078 + (ML20101L078)
- ML20101L079 + (ML20101L079)
- ML20101L080 + (ML20101L080)
- CP-202000269, Supplement to Inservice Inspection (ISI) Program Relief Request + (ML20101L082)
- ML20101L089 + (ML20101L089)
- ML20101L092 + (ML20101L092)
- ML20101L096 + (ML20101L096)
- ML20101L098 + (ML20101L098)
- ML20101L104 + (ML20101L104)
- ML20101L107 + (ML20101L107)
- 05000285/LER-1992-020, :on 920601,determined That Operators Failed to Obtain Appropriate Grab Samples During Radiation Monitor Inoperability.Caused by Procedural Inadequacies.Procedure Upgraded & Personnel Trained Re Monitors + (ML20101L120)
- ML20101L126 + (ML20101L126)
- ST-HL-AE-1153, Revised Final Deficiency Rept Re Rejectable Indications in Welds in Essential Cws.Initially Reported on 800312. Evaluation of Reexam Data Concluded Replacement Unnecessary for 12 Inaccessible Welds + (ML20101L127)
- ML20101L131 + (ML20101L131)
- ML20101L135 + (ML20101L135)
- 05000331/LER-1984-042, :on 841123,reactor Scram Occurred as Result of Loss of Nonvital Buses.Caused by Transformer Trip from Spurious Fire Protection Deluge Sys Activation.Deluge Sys Modified + (ML20101L141)
- ML20101L151 + (ML20101L151)
- ML20101L157 + (ML20101L157)
- ML20101L161 + (ML20101L161)
- ML20101L163 + (ML20101L163)
- ML20101L167 + (ML20101L167)
- ML20101L175 + (ML20101L175)
- ML20101L178 + (ML20101L178)
- BECO-92-070, Forwards Response to Rev 1 to Generic Ltr 92-01 Re Reactor Vessel Structural Integrity,Consisting of NRC-approved Insp Program Governed by Procedures & Encl TS + (ML20101L181)
- ML20101L185 + (ML20101L185)
- ML20101L186 + (ML20101L186)
- 05000369/LER-1992-007, :on 920506,ESF Actuation Occurred While Control Room Personnel Performing Wet Layup Evolution on SG 1D. Caused by Defective Procedure & Inappropriate Personnel Action.Procedure Revised + (ML20101L189)
- HL-2280, Suppls Containing Commitments to Comply W/Generic Ltr 89-10 Re safety-related motor-operated Valve Testing & Surveillance,Per Findings in Insp Repts 50-321/92-04 & 50-366/92-04.Exceptions for in Situ Testing Discussed + (ML20101L192)
- ML20101L193 + (ML20101L193)
- ML20101L199 + (ML20101L199)
- ML20101L205 + (ML20101L205)
- ML20101L211 + (ML20101L211)
- ELV-03871, Provides Info Describing Deviations from Approved Fire Protection Program Resulting from Plant Review in Response to NRC Bulletin 92-001,per 920626 Conversation W/Nrc. Transient Combustibles Limited Inside Containment + (ML20101L213)
- ML20101L229 + (ML20101L229)
- PY-CEI-NRR-1500, Forwards Response to Rev 1 to Generic Ltr 92-01, Reactor Vessel Structural Integrity. Util Utilized Assistance of GE to Performed Technical Analysis to Predict Effects of Neutron Irradiation on Reactor Vessel Matls + (ML20101L250)
- ML20101L251 + (ML20101L251)