Browse wiki

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

Boron +, Iron +, Oxygen +, Hydrogen +  and Lead +

P.4(t) +  and P.6(l) +

00352  +, 00353  +, 05000352  +  and 05000353  +

NRC Generic Letter 82-33, Supplement 1 to NUREG-0737 - Emergency Response Capability +, NRC Generic Letter 83-28, Required Actions Based on Generic Implications of Salem ATWS Events +, NRC Generic Letter 84-23, Reactor Vessel Water Level Instrumentation in BWRs +  and NRC Generic Letter 84-11, Inspections of BWR Stainless Steel Piping +

ML20129E791 +, ML20129E791 +, ML20129E791 +, ML20129E791 +, ML20129E791 +, ML20129E791 +, ML20129E791 +, ML20129E791 +, ML20129E791 +, ML20129E791 +, ML20129E791 +, ML20129E791 +, ML20129E791 +, ML20129E791 +, ML20129E791 +, ML20129E791 +, ML20129E791 +, ML20129E791 +, ML20129E791 +, ML20129E791 +, ML20129E791 +, ML20129E791 +, ML20129E791 +, ML20129E791 +, ML20129E791 +, ML20129E791 +  and ML20129E791 +

ML20073L519 +, ML20100F652 +, ML20099L300 +, ML20094R639 +, ML20094L561 +, ML20113C785 +, 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 +  and 05000352/LER-1984-005-02, :on 841109,noncoincident Full Scram Signal Occurred.Caused by Failed Metal Bond Securing Inductor L507 to Mounting Bracket.Panel Feeder Breakers 1BY160 Replaced +

NUREG/CR-3028, Forwards NUREG/CR-3028, Review of Limerick Generating Station PRA & Vols 1 & 2 to NUREG/CR-0027, Proceedings of Intl Meeting on Thermal Nuclear Reactor Safety. Advises That NUREG/CR-3300 Not Published.W/O Encls +, NUREG-0612, Safety Evaluation Supporting Util Request to Delete Three Commitments in Response to NUREG-0612 Re Heavy Load Control on 5-ton Electric Monorail Hoist W/Integral Trolley & 4-ton Monorail Chain Hoist W/Geared Trolley +, 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-0588, Responds to 870709 Request for NRR Assistance in Determining Adequacy of Two Test Repts Re Acceptance Criteria of NUREG-0588,Category I.Qualification of Kulka Terminal Blocks Demonstrated & Not Used in Instrumentation Circuits +, NUREG-1068, Responds to Constituent Inquiry Re Nuclear Reactor Containment Sys Designed by G.E.Probability of Severe Reactor Accidents Quite Low.Third Party Liability Insurance Provided Under Price-Anderson Legislation.W/O Stated Encls +, NUREG/CR-3493 +  and NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +

AM +  and RT-11-00449 +

Regulatory Guide 1.97 +, Regulatory Guide 1.45 +  and Regulatory Guide 1.46 +

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

Reactor Coolant System +, Feedwater +, Secondary containment +, Reactor Protection System +, Primary containment +, Main Turbine +, Safety Parameter Display System +, Reactor Pressure Vessel +, Core Spray +, Residual Heat Removal +, Standby Liquid Control +, Intermediate Range Monitor +, Remote shutdown +, Spray Pond +  and Main Steam +

Safe Shutdown +, Boric Acid +, High winds +, Ultimate heat sink +, Probabilistic Risk Assessment +, Squib +, High Energy Line Break +, Process Control Program +, Main Steam Line Radiation Monitor +, Earthquake +, Control of Heavy Loads +, Fuel cladding +, Through-Wall Leakage +  and Thermal fatigue +