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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
- ML18030A376 +
- ML17317A390 +
- ML17289A663 +
- ML17289A654 +
- Press Release-92-096, Informing That Nuclear Regulatory Commission Has Received Four letter-type Reports from Its Independent Advisory Committee +
- ML17306A814 +
- ML20101P597 +
- ML20101P537 +
- ML20101P531 +
- ML20101P524 +
- ML20101N833 +
- ML20101M361 +
- ML20101M330 +
- ML20101M219 +
- ML20101M204 +
- ML20101K579 +
- ML20101J787 +
- ML20101J231 +
- ML20101H830 +
- ML20101H638 +
- ML20101H529 +
- ML20101H305 +
- ML20101H234 +
- ML20099K289 +
- ML20099A308 +
- ML20116M194 +
- ML20126J160 +
- ML20126C715 +
- ML20126C645 +
- ML20125C232 +
- ML20125C230 +
- ML20125B730 +
- ML20261K539 +
- TAC:M83522 +
- ELV-03648, Forwards Response to Rev 1 to Generic Ltr 92-01 Re Reactor Vessel Structural Integrity.Heat Number of Each Beltline Plate Located on C-E Matl Certification Repts Maintained by Westinghouse +
- 1CAN069203, Forwards Arkansas Nuclear One,Unit 1 Reactor Containment Bldg Integrated Leakage Rate Test Rept, for Apr 1992 +
- 3F0692-19, Forwards Suppl 2 to BAW-2127, Pressurizer Surge Line Thermal Stratification for B&W 177-FA Nuclear Plants,Summary Rept Fatigue Stress Analysis of Surge Line Elbows, to Address Util Actions to Comply W/Bulletin +
- 3F0692-21, Advises That Util Response to Generic Ltr 92-01 Documented in BAW-2166 +
- 3F0692-22, Advises That Util Completed Installation of Auxiliary Feedwater Pump FWP-7 Associated W/Resolution of GSI-124. Functional Testing Identified Excessive Vibration in Motor. Pump Will Be Available for Emergency Use +
- ELV-03825, Rev 1 to Special Rept 2-92-1,reclassifying 920205 DG Failure from Valid to Nonvalid.Area Exists within Kvar Range in Which Voltage Regulator Will Not Function Due to Power Transformers.Operation of Generator in Range Limited +
- ML20134E814 +
- 05000382/LER-1991-009, :on 910521,discovered That Safety Injection Tank 1A & 1B Inoperable Due to Relief Valve Malfunction. Precaution Will Be Added to NOCP-207,cautioning Scaffolders to Exercise Caution in Safety Injection Area +
- 05000265/LER-1992-002, :on 920103,determined That TS 3.7.A.2.a.2 Limit of 293.75 Scfh Exceeded.Cause Not Determined.Feedwater Checkvalve 2-220-62A Repaired +
- 05000265/LER-1992-003, :on 900205,determined That Measured Leakage Rate of 528.6 Standard Cubic Feet Per Hr Exceeded TS for All Valves.Caused by Excessive Leakage of HPCI Steam Exhaust Check Valve.Valve Replaced +
- ML20101K066 +
- ML20101K072 +
- ML20101K109 +
- 05000412/LER-1992-008, :on 920526,closing Springs on Quench Spray Pump a Breaker Found Discharged from 920423-0526.Caused by Failed Breaker Control Device.Breaker Replaced W/Spare & Sample of 4 Kv Breakers Will Be Inspected +
- 05000424/LER-1992-005-03, :on 920604,containment Isolation Occurred Due to Inadvertent Grounding of Radiation Monitor Power Panel. Caused by Personnel Error.Personnel Will Receive Review of Event & Training Re Proper Use of Jumpers +
- ML20155F856 +