NL-15-1898, Enclosure 3: Hatch EAL Calculations - License Amendment Request for Changes to EAL Schemes to Adopt NEI 99-01 Rev. 6 and to Modify Radiation Monitors at Farley Nuclear Plant. Part 2 of 3
RS-08-045, LaSalle, Units 1 and 2, Updated Final Safety Analysis Report (Ufsar), Revision 17, Appendix a Through Appendix N
RS-08-045, LaSalle, Units 1 and 2, Updated Final Safety Analysis Report (Ufsar), Revision 17, Table of Contents Through List of Effective Pages
IA-80-586, Study Re Potential of Licensed Sites to Cause Significant Radiation Exposure to Surrounding Populations in Event of Severe Accident
L-88-366, Changes,Tests & Experiments Made W/O Prior Commission Approval for Jul 1987 - June 1988
AECM-84-0438, Semiannual Radioactive Effluent Release Rept, Jan-June 1984
PY-CEI-NRR-1415, Monthly Operating Rept for Oct 1991 for Perry Nuclear Plant Unit 1
05000352/LER-1989-014, :on 890216,isolation of Refuel Floor Secondary Containment & Initiation of Standby Gas Treatment Sys,Esf Occurred.Caused by Boiler Malfunction.Auxiliary Operator at Auxiliary Boiler Encl Restored Three Boilers
05000298/LER-1986-026, :on 861011,cracks Discovered in Fire Dome Area of 12 Cylinder Heads on Emergency Diesel Generator DG-2. Cause Attributed to Cylinder Head Design.New Cylinder Heads Received & All Cracked Heads Replaced
05000424/LER-1987-045, :on 870702,centrifugal Charging Pumps Removed from Svc.Caused by Personnel Error.Personnel Responsible for Writing,Reviewing & Approving Clearance Associated W/Closure of Incorrect Valves Counseled
05000289/LER-1986-013, :on 861107,failure Declared on as-found Reactor Bldg Integrated Leak Rate Test.Caused by Leakage from Bldg Purge Exhaust Valve Interspace.Second Test Performed & Resultant as-left Bldg Leak Rate Acceptable
05000366/LER-1986-020-01, :on 860924,primary Containment Penetrations Failed Local Leak Rate Tests.Full Description of Causes & Corrective Actions Will Be Provided
05000529/LER-1986-041-01, :on 860701,unidentified Leakage Greater than 1 Gpm Detected in Rcs.Caused by Seal Leakage Due to Strainer Flushing Techniques Previously Employed.Flushing Procedure Modified
05000482/LER-1985-065, :on 850905,main Turbine Trip Caused Reactor Trip,Feedwater Isolation,Auxiliary Feedwater Actuation,Steam Generator Blowdown & Sample Isolation.Caused by Faulty Control Pump Discharge Relief Valve
05000445/LER-1992-009, :on 920508,reactor Tripped.Caused by Personnel Error During Testing.Appropriate Level of Positive Discipline Program Implemented for Individuals Involved & Cabinet Locking Scheme Modified
05000298/LER-1991-008, :on 910826,valve RHR-MO-M057 Exceeded TS Closure Time During Surveillance Testing.On 910917,valve Not Deactivated During Period of Inoperability.Caused by Personnel Failure.Personnel Counseled
05000461/LER-1990-009, :on 900427,discovered That Moving Filter Paper in Leak Detection Sys Drywell Air Particulate Sample Panel Not Collecting on take-up Reel.Caused by Loose Set Screw on Gear Train.Set Screw Tightened
05000424/LER-1989-019-01, :on 891206,discovered That Tech Specs Violated Due to Foreman Approving Measurements of Cell Recorded as 2.10 V on 891122.Caused by Personnel Error & Inadequate Procedure.Foreman Counseled
05000348/LER-1989-008-03, :on 891113,containment Integrity Not Maintained for Approx 30 S.Caused by Personnel in That Inner Door Was Left Blocked Open.Personnel Counseled & Interim Administrative Controls Established
GO2-84-465, Semiannual Effluent Rept,Jan-June 1984
L-82-542, Forwards Addl Info Re Small Feedwater Line Break Analysis. Info Needed to Close Confirmatory Issue Addressed in Section 15.10.2 of SER
BYRON 2017-0038, 2016 Annual Radiological Environmental Operating Report
05000482/LER-1986-068, :on 861220,steam Generator D Water Level Reached lo-lo Setpoint,Initiating Stated Events,Including Reactor Trip & Main Feedwater Isolation.Caused by Steam Generator Level Sensitivity
05000339/LER-1984-002-03, :on 840505,reactor Tripped Manually After Receiving Automatic Turbine Trip Signal & Loss of Normal Feedwater.Caused by High Water Level in Feedwater Heater 5B. Module Recalibr & Channel Returned to Svc