ST-HL-AE-5654, Forwards Results for Hot,Full Flow Rod Drop Testing in Unit 2 Cycle 6,performed 970501.Core Map,Core Design Data & NRC Bulletin 96-001 Correspondence Table,Encl
NSD-NRC-97-5133, Forwards Formal Transmittal of Correspondence Previously Sent Informally Over Period 970416-0502,including Draft of SSAR Markup for LOOP Issue & Open Item Status
05000454/LER-1985-063, :on 850708,control Rod P-8 Misaligned.Decision to Trip Turbine Caused Reactor Trip Because Permissive P-7 Not Actuated.Reactor & Turbine Power Below 10%.Impulse Pressure Rescaled
05000369/LER-1989-022, :on 890826,reactor Trip Occurred Due to Failed Universal Board in Solid State Protection Sys Cabinet A. Caused by Equipment/Malfunction.Universal Board Replaced
B14458, Forwards Suppl Info to 930330 Application for Amend to License NPF-49 Re Several 18-month SR for Surveillances Listed in Table 1 of Submittal to Be Performed During Fourth Refueling Outage Presently Scheduled to Begin on 930731
05000333/LER-1981-024-03, /03L-0:on 810323,drywell Equipment Drain Sump Pump B Lost Suction & Could Not Effect Sump Pump Out.Cause Unknown.Amend to Tech Spec Submitted
AECM-80-255, Completes Response to IE Bulletin 80-08.Forwards List of Pipe Sizes & Matls,Welds Needing Repair or Replacement & Description of Defects.No Further Action Required
05000155/LER-1980-005-03, /03L-0:on 800301,following Several Intermittent Automatic Test Circuit Alarms,Sensor Channel D of Reactor Depressurizing Sys Removed from Svc.Caused by Setpoint Drift on Transmitter LT-3183.Transmitter Vented & Returned to S