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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

• ML20113C875  + (ML20113C875)
• ML20113C905  + (ML20113C905)
• ML20113C909  + (ML20113C909)
• ML20113C913  + (ML20113C913)
• ML20113C915  + (ML20113C915)
• ML20113C916  + (ML20113C916)
• ML20113C918  + (ML20113C918)
• 05000322/LER-1985-009, :on 850305,reactor Water Cleanup Sys Inadvertently Isolated.Caused by Contact of Two Leads During post-work Logic Circuit Testing on Steam Leak Detection Sys. Testing Resumed & Completed W/O Incident  + (ML20113C920)
• ML20113C922  + (ML20113C922)
• ML20113C923  + (ML20113C923)
• ML20113C929  + (ML20113C929)
• ML20113C931  + (ML20113C931)
• ML20113C934  + (ML20113C934)
• ML20113C936  + (ML20113C936)
• A04718, Forwards Response to Request for Addl Info Re Item 4 of IE Bulletin 79-02 Concerning Verification of Design Requirement for Concrete Anchor Bolts from Insp Rept 50-336/85-01,per 850222 Commitment  + (ML20113C949)
• ML20113C951  + (ML20113C951)
• ML20113C956  + (ML20113C956)
• ML20113C959  + (ML20113C959)
• ML20113C963  + (ML20113C963)
• ML20113C966  + (ML20113C966)
• ML20113C969  + (ML20113C969)
• ML20113C971  + (ML20113C971)
• ML20113C989  + (ML20113C989)
• ML20113C990  + (ML20113C990)
• ML20113D001  + (ML20113D001)

• PY-CEI-NRR-0223, Forwards Rev 4 to 80A4425, Preservice Insp Program Plan: RCIC, 80A4426, ...:Feedwater Sys & 80A4423,...:LPCS Sys. Revs Replace Preservice Insp Program Plans Submitted w/841214 Ltr  + (ML20113D005)

• ML20113D010  + (ML20113D010)
• ML20113D013  + (ML20113D013)
• ML20113D019  + (ML20113D019)
• ML20113D022  + (ML20113D022)
• ML20113D031  + (ML20113D031)
• 05000281/LER-1984-021-02, :on 841216,w/unit at Approx 20% Power & Ramping Down for Secondary Sys Repair,Unit Tripped When Breakers for Main Feed Pump B Opened.Caused by Invalid Low Flow Condition.Trip Circuitry Tested  + (ML20113D037)
• 05000317/LER-1984-016, :on 841215,during Performance of Surveillance Test STP-0-67,HPSI Sys Injection Leg Flows Outside Tech Spec Requirement.Caused by Improperly Set Limit Switches.Switches Adjusted  + (ML20113D059)
• ML20113D072  + (ML20113D072)
• TXX-4220, Forwards Table Providing Description of 840713 Amend 50 to FSAR  + (ML20113D093)
• ML20113D096  + (ML20113D096)
• TXX-4443, Forwards Estimates for Future Operator Licensing Exams in Response to Generic Ltr 85-04  + (ML20113D104)
• U-602601, Responds to NRC 960523 RAI Re GL 95-07, Pressure Locking & Thermal Binding of SR Power Operated Gate Valves  + (ML20113D113)
• 05000346/LER-1984-012, :on 840821,Kaowool Packing Around Conduit Going Into Bottom of Reactor Protection Sys Channel 2 Cabinet Fell Out.Addl Kaowool Immediately Stuffed in Penetration  + (ML20113D114)
• RBG-43006, Monthly Operating Rept for May 1996 for River Bend Station Unit 1  + (ML20113D116)
• ML20113D119  + (ML20113D119)
• ML20113D122  + (ML20113D122)
• 05000440/LER-1996-005, :on 960530,automatic Reactor Scram Occurred. Caused by Auxiliary Transformer Failure.Replaced Failed Auxiliary & Load Center Transformers  + (ML20113D124)
• 0CAN069601, Application for Amends to Licenses DPR-51 & NPF-6,allowing Reactor Containment Bldg Equipment Hatch Doors to Remain Open During Fuel Handling & Core Alterations  + (ML20113D127)
• ML20113D132  + (ML20113D132)
• ML20113D135  + (ML20113D135)
• 3F0385-14, Documents Results of Assessment of Impact of Capacity Re IE Bulletin 79-02 Wej-it Concrete Anchors Installed on Large Bore safety-related Piping Sys.Followup to Outstanding Issues Identified in Insp Rept 50-302/84-32 Provided  + (ML20113D138)
• 05000366/LER-1984-033, :on 841213,determination Made That Personnel Failed to Submit LERs Re 840930 & 1117 Reactor Scrams,Per Deficiency Control Sys Procedure HNP-444.Personnel Counseled to Complete Deficiencies in Timely Manner  + (ML20113D139)
• ML20113D140  + (ML20113D140)
• ML20113D141  + (ML20113D141)
• 05000348/LER-1996-002-01, :on 960529,TS Surveillance Requirements Not Met & common-cause Failure Identified.Caused by Personnel Error. Revised Surveillance Test Procedures & Modified Underfrequency Reactor Trip Circuits  + (ML20113D143)