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INTERNAL OR EXTERNAL MEMORANDUM  and MEMORANDUMS-CORRESPONDENCE

Nitrogen +, Carbon +, Oxygen +, Hydrogen +  and Lead +

10 CFR 100 +, 10 CFR 50 +, 10 CFR 50.54#f +  and 10 CFR 50#54 +

Barrier Integrity +  and Initiating Events +

SECY-97-234 +, SECY-97 234 +, SECY 97-234 +  and SECY-97132 +

Turbine Trip +  and Reactor Trip +

NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO) +  and Callan L +

ML20202H679 +, ML20202H679 +, ML20202H679 +, ML20202H679 +, ML20202H679 +, ML20202H679 +, ML20202H679 +, ML20202H679 +, ML20202H679 +, ML20202H679 +, ML20202H679 +, ML20202H679 +  and ML20202H679 +

2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +, 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +, 8.333333e-4 d (0.02 hours, 1.190476e-4 weeks, 2.7396e-5 months)  +  and 3.472222e-5 d (8.333333e-4 hours, 4.960317e-6 weeks, 1.1415e-6 months)  +

Westinghouse +  and Mercoid +

NUREG/CR-4550 +, NUREG/CR-4840 +, NUREG/CR-4772 +, NUREG/CR-4527 +, NUREG/CR-2300 +, NUREG/CR-5789 +, NUREG/CR-4566 +, NUREG/CR-5420 +, NUREG-140 +, NUREG/CR-0096 +, NUREG/CR-50 +, NUREG/CR-00988 +, NUREG/CR-8143 +, NUREG-1150, Weekly Info Rept for Wk Ending 890922 +, NUREG-1407, Forwards Staff Evaluation of Millstone Unit 3,individual Plant Exam of External Events Submitted on 911223 Re Response to GL 88-20 .Util Capable of Identifying Severe Accidents & Vulnerabilites & Met GL 88-20,Suppl 4 +, NUREG/CR-0098, Forwards SEP Position Re Consideration of Inelastic Response Using NUREG/CR-0098 Ductility Factor Approach,Providing Addl Guidance Regarding Application of Ductility Methodology +, NUREG/CR-5088, Discusses Proposed Actions Re SECY-89-170, Fire Risk Scoping Study:Summary of Results & Proposed Staff Actions, (NUREG/CR-5088).Need for Addl Research Will Be Considered Following Final Definition of fire-related Parts +, NUREG/CR-1278, Official Exhibit - NRC098-00-BD01 - NUREG/CR-1278, Handbook of Human Reliability Analysis with Emphasis on Nuclear Power Plant Applications - Final Report +  and NUREG-1050, Forwards Regulatory Analysis of Generic Safety Issue 61, Safety/Relief Valve Discharge Line Break within Mark I or II Wetwell Airspace. Based on Results Discussed in NUREG/CR-4594,risk Lower than Previously Estimated +

AOP +, SP +  and CP +

SECY-97-234 +, SECY-97 234 +, SECY 97-234 +  and SECY-97132 +

Texas +, Maryland +, Washington +, Florida +, Nebraska +, New Hampshire +  and Maine +

Steam Generator +, Reactor Coolant System +, Feedwater +, Secondary containment +, Service water +, Reactor Protection System +, Main Steam Isolation Valve +, Auxiliary Feedwater +, Main Transformer +, HVAC +, High Pressure Core Spray +, Residual Heat Removal +, Remote shutdown +, Residual Heat Removal Service Water +, Decay Heat Removal +, Main Steam Line +, Safety Relief Valve +, Control Rod +, Auxiliary Feed Water +, Main Steam +  and Containment Spray +

NRC COMMISSION (OCM) +, Shirley Ann Jackson +, The Chairman +, Diaz N +, Mcgaffigan E +  and Dicus G +

Hot Short +, Safe Shutdown +, High winds +, Mission time +, Fire Barrier +, Tornado Missile +, Safe Shutdown Earthquake +, Probabilistic Risk Assessment +, Design basis earthquake +, Loss of Offsite Power +, Severe Accident Management Guideline +, Earthquake +  and Fire Protection Program +