Browse wiki

TEXT-SAFETY REPORT, NUREG REPORTS  and SAFETY EVALUATION REPORT--FACILITY

IWB-2500 +, IWB-2600 +, IWC-2100 +, IWC-2520 +, IWC-2600 +  and IWA-2232 +

ASME Section XI +, ASME Section III +  and ASME Section V +

Nitrogen +  and Lead +

10 CFR 50 +, 10 CFR 50.59 +, 10 CFR 61 +, 10 CFR 50.44 +, 10 CFR 550.47#b12 +, 10 CFR 50.55a +, 10 CFR 50.55a#g +, 10 CFR 50.55a#a3 +, 10 CFR 50.55a#b +, 10 CFR 50.55a#g2 +, 10 CFR 50.55#a +  and 10 CFR 50.44#c3 +

00352  +, 00353  +, 05000352  +  and 05000353  +

NRC Generic Letter 82-33, Supplement 1 to NUREG-0737 - Emergency Response Capability +  and NRC Generic Letter 83-28, Required Actions Based on Generic Implications of Salem ATWS Events +

ML20132F732 +, ML20132F732 +, ML20132F732 +, ML20132F732 +, ML20132F732 +, ML20132F732 +, ML20132F732 +, ML20132F732 +, ML20132F732 +, ML20132F732 +, ML20132F732 +, ML20132F732 +, ML20132F732 +, ML20132F732 +, ML20132F732 +, ML20132F732 +, ML20132F732 +, ML20132F732 +, ML20132F732 +, ML20132F732 +, ML20132F732 +, ML20132F732 +, ML20132F732 +, ML20132F732 +, ML20132F732 +, ML20132F732 +, ML20132F732 +, ML20132F732 +, ML20132F732 +, ML20132F732 +...

05000352/LER-1984-006, Forwards LER 84-006-00 Re Automatic Isolation of Main Control Room Ventilation Sys on 841113.Event Occurred Prior to Initial Criticality +, ML20100L041 +, ML20100G324 +, ML20100D198 +, ML20100C528 +, ML20099M307 +, 05000352/LER-1984-015, :on 841126,prior to Initial Criticality, Outboard RHR Shutdown Cooling Valves Received Isolation Signal Due to Surveillance Testing.Caused by Procedural Deficiency.Shutdown Cooling Mode Restored +, 05000352/LER-1985-056, :on 850529,primary Containment Instrument Gas Sys Isolation Valves Isolated to Closed Position.Caused by Loose Connections in Panel.Connections Tightened to Prevent Further Inadvertent Isolations +, 05000352/LER-1985-032, :on 850314,fire Damper in Reactor Encl Found Held Open W/Wire During Cold Shutdown.Caused by Personnel Error.Damper Closed,Fusible Link Replaced,Damper Returned to Svc & Memo Issued +, 05000352/LER-1985-028, :on 850301,determined That Internal Seals for Hot Gas & Smoke Protection Not Present in Conduits 1BI647,1CL048 & 1DL046.Hourly Fire Watch Established. Internal Conduit Seals Installed +, 05000352/LER-1985-023, :on 850205,reactor Encl Equipment Compartment B Exhaust Fan Failed,Resulting in Low Air Flow Rate & Low Differential Pressure.Caused by Loose Pneumatic Fitting on Fan.Fitting Tightened +  and 05000352/LER-1985-015, :on 850118,sprinkler Sys for Cable Spreading Room Inoperable W/O Continuous Fire Watch.Caused by Inadequate Procedure for Hydrostatic Testing & Personnel Error.Procedure Issued & Personnel Counseled +

NUREG-0801, Forwards Comments on Program Plan for Detailed Control Room Design Review (Dcrdr).Program Plan Addresses All Required Elements of DCRDR.In-progress Audit Not Planned +, NUREG-0991, Advises That Rev 1 to Plant Preservice Insp Program for Reactor Coolant Pressure Boundary & for ASME Code Class 2 & 3 Sys & Components Acceptable & in Compliance W/ 10CFR50.55a(g)(2).Evaluation Included in NUREG-0991,Suppl 7 +, NUREG-991 +, NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +  and NUREG-0660, 04-17-80 NUREG-0660 NRC Action Plans Developed as a Result of the TMI-2 Accident, Draft 3 +

Limerick +  and NPF-27 +

Pennsylvania +, Maryland +, Washington +  and New York +

Steam Generator +, Reactor Coolant System +, Service water +, Reactor Protection System +, Reactor Recirculation Pump +, Safety Parameter Display System +, Core Spray +  and Remote shutdown +

Safe Shutdown +, Hydrostatic +, Nondestructive Examination +, Emergency Lighting +  and Overexposure +