Browse wiki

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

Nitrogen +, Sodium +, Hydrogen +  and Lead +

10 CFR 50.48 +, 10 CFR 100 +, 10 CFR 50 +, 10 CFR 50.49 +, 10 CFR 50.54 +, 10 CFR 50.48#c4 +  and 10 CFR 50.44#c3iii +

00244  +  and 05000244  +

Turbine Trip +  and Reactor Trip +

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 84-04, Safety Evaluation of Westinghouse Topical Reports Dealing with Elimination of Postulated Pipe Breaks in PWR Primary Main Loops (Generic Letter 84-04) +  and NRC Generic Letter 84-01, NRC Use Of The Terms "Important To Safety" and "Safety Related" +

ML17254B012 +, ML17254B012 +, ML17254B012 +, ML17254B012 +, ML17254B012 +, ML17254B012 +, ML17254B012 +, ML17254B012 +, ML17254B012 +, ML17254B012 +, ML17254B012 +, ML17254B012 +, ML17254B012 +, ML17254B012 +, ML17254B012 +, ML17254B012 +, ML17254B012 +, ML17254B012 +, ML17254B012 +, ML17254B012 +, ML17254B012 +, ML17254B012 +, ML17254B012 +, ML17254B012 +, ML17254B012 +, ML17254B012 +, ML17254B012 +, ML17254B012 +, ML17254B012 +, ML17254B012 +...

ML17309A336 +, ML17309A307 +, ML17309A110 +, ML17258B162 +, ML17258A899 +, ML17258A417 +, ML17255A758 +, ML17255A741 +, ML17255A740 +, ML17255A714 +, ML17255A603 +, ML17255A598 +, ML17255A572 +, ML17255A514 +, ML17255A387 +, ML17254A931 +, ML17254A793 +, ML20087L342 +, ML20082F776 +, ML20072N589 +, 05000244/LER-1984-005, :on 840514,RHR Suction Valve MOV-700 Failed to Stroke to Open Position When Actuated from Control Room. Caused by Packing Gland Flange Shifting Out of Vertical Position.Valve Stroked Manually +, ML17255A622 +, ML17255A697 +, ML17255A812 +, ML17255A581 +, ML17255A801 +, ML17254A775 +, ML17255A432 +  and ML17258A498 +

NRC Bulletin 79-14 +, NRC Bulletin 83-07 +  and NRC Bulletin 79-02, Pipe Support Base Plate Designs Using Concrete Expansion Anchor Bolts +

NUREG-0944, Notice of Availability of SER for full-term OL (NUREG-0944) +, NUREG-0623 +, 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-944 +, NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +, NUREG-0909, Forwards NRC Rept on 820125 Steam Generator Tube Rupture, Re Ginna Nuclear Power Plant, (NUREG-0909).W/o Encl +, NUREG-0821, Forwards Safety Evaluations of SEP Topics,Vols I-III,per App E of NUREG-0821, Integrated Plant Safety Assessment Rept for Re Ginna Nuclear Power Plant +, NUREG-0609, Forwards Request for Addl Info on Generic Ltr 84-04,Safety Evaluation of Westinghouse Topical Repts Dealing W/ Eliminating of Postulated Pipe Breaks in PWR Primary Main Loops. Response Requested by 840731 +  and NUREG-0660, 04-17-80 NUREG-0660 NRC Action Plans Developed as a Result of the TMI-2 Accident, Draft 3 +

Texas +, Washington +  and New York +

Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Emergency Diesel Generator +, Auxiliary Feedwater +, Residual Heat Removal +, Emergency Core Cooling System +  and Main Steam +

Safe Shutdown +, Boric Acid +, Tornado Missile +, Systematic Assessment of Licensee Performance +, Exemption Request +, Earthquake +, Control of Heavy Loads +, Pressure Boundary Leakage +  and Control Room Habitability +

WCAP-9804 +, WCAP-10019 +  and WCAP-10054 +

WCAP-9804 +, WCAP-10019 +  and WCAP-10054 +