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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

• JPN-96-011, Forwards Application for Amend to License & Proposed TS, Supporting Adoption of Primary Containment Lrt Requirements of Option B to 10CFR50,App J at Plant & Clarifies Numerical Value of Allowable Containment Lrt as 1.5% Per Day  + (ML20101H657)
• ML20101H658  + (ML20101H658)
• ML20101H667  + (ML20101H667)
• U-601997, Rev 11 to Revised Inservice Testing Program for Cps  + (ML20101H669)
• ML20101H674  + (ML20101H674)
• 05000373/LER-1992-007-06, :on 920531,spurious auto-start of Control Room Ventilation Emergency Makeup Train Occurred Due to High Radiation Spike.Detectors Taken Apart,Cleaned & Inspected & Chart Recorders Connected  + (ML20101H690)
• 05000254/LER-1987-016, :on 870912,determined That Measured Combined Leakage Rate from All Penetrations & Valves Exceeded TS Limit of 293.75 Scfh.Caused by Rust on Valves & Valve Stuck Open.Gates Valves Will Be Replaced  + (ML20101H715)
• ML20101H725  + (ML20101H725)
• ML20101H731  + (ML20101H731)
• ML20101H732  + (ML20101H732)
• 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  + (ML20101H756)
• ML20101H759  + (ML20101H759)
• ML20101H763  + (ML20101H763)
• ML20101H769  + (ML20101H769)
• ML20101H782  + (ML20101H782)
• ML20101H784  + (ML20101H784)
• ML20101H791  + (ML20101H791)
• ML20101H795  + (ML20101H795)
• ML20101H801  + (ML20101H801)
• ML20101H804  + (ML20101H804)
• 1CAN069203, Forwards Arkansas Nuclear One,Unit 1 Reactor Containment Bldg Integrated Leakage Rate Test Rept, for Apr 1992  + (ML20101H813)
• 05000336/LER-1996-007, :on 960220,discovered RCS C/D Rate Exceeded TS Limit.Caused by Use of Wrong Temp Sensor.Plant Operating Procedures,Heatup/C/D Monitoring Computer Program & Operator Training Involving These Events Revised  + (ML20101H819)
• ML20101H820  + (ML20101H820)
• 05000249/LER-1984-021-04, :on 840307,reactor Scrammed During Surveillance Testing.Caused by Bad Jumper Wire.Jumper Discarded & Personnel Reinstructed on Using Jumper Wire Const for Surveillance Test  + (ML20101H826)
• 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  + (ML20101H827)

• ML20101H830  + (ML20101H830)

• 05000249/LER-1984-022-04, :on 840317,reactor Scrammed While Adjusting Mode Switch in Attempt to Clear Rod Block.Caused by Operator Error When Mode Switch Inadvertently Moved to Shutdown Position.Operator Counseled  + (ML20101H841)
• ML20101H852  + (ML20101H852)
• ML20101H867  + (ML20101H867)
• ML20101H872  + (ML20101H872)
• ST-HL-AE-5323, Forwards ANI to Maelu Policy 96-201,NEIL-III Policy UX95-075 & NEIL-III Policy UX95-075,per 10CFR50.54(w)(2)  + (ML20101H881)
• ML20101H893  + (ML20101H893)
• ML20101H895  + (ML20101H895)
• L-84-149, Responds to NRC Re Violations Noted in Insp Repts 50-250/84-11 & 50-251/84-11.Corrective Actions:Personnel Counseled Re Valve Clearance Procedure & Initial Air Aerosol Mixing Uniformity Test Procedures Developed  + (ML20101H897)
• ML20101H905  + (ML20101H905)
• ST-HL-AE-5321, Forwards Revised STP Electric Generating Station Operations QA Plan, Incorporating Methodology for Implementation of STP Graded QA Program.Draft Procedures Also Encl  + (ML20101H918)
• ML20101H929  + (ML20101H929)
• ML20101H930  + (ML20101H930)
• ML20101H931  + (ML20101H931)
• ML20101H945  + (ML20101H945)
• ML20101H955  + (ML20101H955)
• ML20101H960  + (ML20101H960)
• PY-CEI-NRR-1515, Provides Update to Info Previously Submitted in Response to GL 88-01 Re Addition to & Reclassification of Welds & Identifying Changes in Examination Schedules.Summary of Changes to Table 2 Re Weld Insp Schedules Encl  + (ML20101H966)
• ML20101H971  + (ML20101H971)
• ML20101H977  + (ML20101H977)
• ML20101H983  + (ML20101H983)
• B15604, Submits Changes to & Errors in ECCS Evaluation Model/ Applications of Model for Unit 2  + (ML20101H991)
• NSD-NRC-96-4673, Forwards Response to NRC RAI 440.515 (Rev 1) Re Notrump Computer Code  + (ML20101H993)
• ML20101H996  + (ML20101H996)
• ULNRC-03352, Responds to NRC 960307 RAI Re Temp of SFP After Full Core Offload Assuming Both Trains of Sfpc Area in Operation,In Ref to 950906 Request for Rev to TS Sections 5.3.1 & 5.6.1.1 & Figure 3.9-1 Re SFP Storage  + (ML20101H998)
• 05000336/LER-1996-008, :on 960222,concluded That Condition of Wire Mesh Screen Encl Over Two Containment Recirculation Suction Pipes Outside Design Basis.Caused by Const/Installation Error.Screen Encl Being Replaced  + (ML20101J003)