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TEXT-SAFETY REPORT  and GENERAL EXTERNAL TECHNICAL REPORTS

ANSI N45.2-1977 +, ANSI N45.2.6 +, ANSI N45.2 +, ANSI N45.2.2 +, ANSI N45.2.8 +, ANSI N45.2.12 +, ANSI N45.2.9 +, ANSI N45.2.4 +, ANSI N45.2.10 +, ANSI N45.2.13 +, ANSI N45.2.23 +, ANSI N45.2.14 +  and ANSI N45.2.22 +

Copper +, Sodium +, Chloride +, Lead +  and Lithium +

2CAN088412 +, 2CAN038607, Forwards Revised Schedule for Completion of Inadequate Core Cooling Sys Milestones (NUREG-0737,Item II.F.2). Qualification Program for in-containment Cabling & Connectors for Core Exit Thermocouples Currently Underway +, 2CAN118303, Forwards Responses to SER Re Inadequate Core Cooling (NUREG-0737,Item II.F.2) Outstanding Questions.Updated Schedule for Fourth Refueling Outage Will Be Provided by 840601 +, 2CAN098306, Forwards Responses to NRC 830809 Questions Re 830415 & 0504 Submittals Concerning Proposed Inadequate Core Cooling Instrumentation Sys.Complete Responses to Certain Questions Will Require Addl Progress in Design & Confirmatory Testing +  and 2CAN048306, Provides Info Re Inadequate Core Cooling Instrumentation Sys,Per NRC 821210 Order for License Mod.Approach Based on Radcal Gamma Thermometer.Concept Presented at 830331 Meeting W/Nrc +

05000368  +  and 00368  +

ML20155F678 +, ML20155F678 +, ML20155F678 +, ML20155F678 +, ML20155F678 +, ML20155F678 +, ML20155F678 +, ML20155F678 +, ML20155F678 +, ML20155F678 +, ML20155F678 +, ML20155F678 +, ML20155F678 +, ML20155F678 +, ML20155F678 +, ML20155F678 +, ML20155F678 +, ML20155F678 +, ML20155F678 +, ML20155F678 +, ML20155F678 +, ML20155F678 +, ML20155F678 +, ML20155F678 +, ML20155F678 +, ML20155F678 +, ML20155F678 +, ML20155F678 +  and ML20155F678 +

IEEE 384 +, IEEE 383 +, IEEE 344 +, IEEE 323 +, IEEE 323-1974 +, IEEE 344-1975 +  and IEEE 384-1981 +

1CAN038604, Forwards Revised Schedule for Completion of Inadequate Core Cooling Sys Milestones (NUREG-0737,Item II.F.2).Two Changes to 830826 Conceptual Design Implemented Based on Further Evaluations & 821210, Order for Mod of License +, 0CAN038502, Forwards Proprietary & Nonproprietary Rev 1 to R-84-011-NP & R-84-011-P, Summary Rept,Phase I of Arkansas Power & Light Inadequate Core Cooling Monitoring Sys Program Test Series. Proprietary Rept Withheld (Ref 10CFR2.790) +, 2CAN088414, Responds to 840727 Request for Addl Info Re IAEA Safeguards Implementation.Review of Draft Implementation Plans Expected to Be Complete by 840930.Encl Withheld +, 0CAN088301, Responds to NRC Re Violations Noted in IE Insp Repts 50-313/83-14 & 50-368/83-14.Corrective Actions:Plant Operating Procedure 1015.01 Revised to Clarify Methods for Locking T-handled Valves +, 0CAN088314, Program Plan for Inadequate Core Cooling Sys - Unit 1: Reactor Vessel Monitoring Sys/Hot Leg Monitoring Sys;Unit 2:Reactor Vessel Monitoring Sys +, 05000368/LER-1983-037-03, /03L-0:on 830816,during Mode 1 Operation, Degradations in Fire Doors 257 & 270 Observed.Caused by Relocation of Signs & Security Equipment Installation & Mods.Degradations Repaired +, 0CAN058301, Forwards Responses to NRC 830406 Request for Addl Info Re Use of Radcal Gamma Thermometer (Rgt) for Inadequate Core Cooling Instrumentation.Rgt Consists of Sheathed Thermocouples,Heater Rod,Core Tube & Jacket Tube +, 05000313/LER-1989-047, :on 891219,RCS Temp Increased Above 250 F W/ Oxygen Concentration Greater than Tech Specs Limit.Caused by Inadequate Procedural Guidance.Plant Startup Procedure Revised to Require Chemistry Dept Signoff +  and ML20033D848 +

Regulatory Guide 1.97 +, Regulatory Guide 1.75 +, Regulatory Guide 1.63 +, Regulatory Guide 1.100 +, Regulatory Guide 1.26 +  and Regulatory Guide 1.89 +

Alabama +  and Arkansas +

Steam Generator +, Reactor Coolant System +, Safety Parameter Display System +  and Reactor Pressure Vessel +

Boric Acid +, Coatings +  and Core Exit Thermocouple +