GNRO-2013/00033, Offsite Dose Calculation Manual, Revs. 38 & 39, Page 2.0-31 Through End
RS-12-221, Byron, Units 1 and 2, Updated Final Safety Analysis Report, Revision 14, Technical Requirements Manual
PLA-6480, One-Time Extension to Technical Specification 3.8.1 Allowable Completion Time for Offsite AC Circuits, PLA-6480
1CAN088602, Forwards Info in Response to Requests in Generic Ltr 86-05 Concerning plant-specific Data Not Covered by B&W Owners Group & Other submittals.NUREG-0737,Item II.K.3.5 Re Automatic Trip of Reactor Coolant Pumps Addressed
1CAN109607, Monthly Operating Rept for Sept 1996 for Arkansas Nuclear One Unit 1
RS-22-014, Application to Adopt TSTF-246, RTS Instrumentation, 3.3.1 Condition F Completion Time
05000388/LER-1986-001-01, :on 860121,during Startup,Reactor Scrammed When Vessel Water Level Dropped to Plus 13 Inches.Caused by Operator Failing to Notice Turbine Bypass Valves Opened. Procedures Revised.Alarms Will Be Installed
05000320/LER-1988-011, :on 880807,control Room Personnel Failed to Recognize Requirements to Enter Action Statement.Caused by Misunderstanding of Requirements of Tech Spec 3.8.1.1. Event Discussed W/Operators
05000313/LER-1996-007-02, :on 960912,automatic Reactor Trip & Emergency Feedwater Sys Actuation Occurred When Two RCP Motors de-energized.Caused by Defective Fuse in Electrical Bus Undervoltage Circuit.Fuse Replaced
05000416/LER-1992-006, :on 920428,operators Received Alarm,Indicating Actuation of RPS Via Channel G of APRM Sys.On 920427, Excessive Undervessel Leakage Occurred.Caused by Electrical Short.Uncoupling Tool Removed from Svc
05000362/LER-1984-022-01, :on 840601,failure in Turbine Control Sys Caused High Pressure Turbine Stop Valves to Close,Resulting in Loss of Load Reactor Trip.Cause Undetermined.Module Replaced
05000341/LER-1993-006, :on 930304,determined That Test Procedures Used to Perform Channel Functional Tests of RPS & Electrical Protection Assemblies Incorrect,Due to Defective Procedure. Procedures Will Be Revised by 930730
RS-11-136, Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specifications (TS) 3.3.1
RS-11-019, Units 1 & 2 - License Amendment Request to Revise Technical Specifications 3.3.1, Reactor Trip System Instrumentation, & TS 3.3.2, Engineered Safety Feature Actuation System Instrumentation, to Reflect Installation of Bypass
ELV-00840, Semiannual Rept Plant Radioactive Effluent Releases Jan-June 1989
AEP-NRC-2024-86, Unit 2 - Decommissioning Funding Plan for Independent Spent Fuel Storage Installation
RS-25-016, License Amendment Request to Adopt TSTF-286, TSTF-471, TSTF-571-T