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Sodium +, Hydrogen +  and Lead +

10 CFR 50.73 +, 10 CFR 50.72 +, 10 CFR 55 +, 10 CFR 26 +, 10 CFR 20 +, 10 CFR 50.46 +, 10 CFR 50.48 +, 10 CFR 50 +, 10 CFR 50.36 +, 10 CFR 30 +, 10 CFR 50.59 +, 10 CFR 72 +, 10 CFR 52 +, 10 CFR 71 +, 10 CFR 2 +, 10 CFR 51 +, 10 CFR 54 +, 10 CFR 60 +, 10 CFR 73 +, 10 CFR 2.802 +, 10 CFR 50.47 +, 10 CFR 50.60 +, 10 CFR 50.65 +, 10 CFR 73.55 +, 10 CFR 140.11 +, 10 CFR 50.54 +, 10 CFR 50.55a +, 10 CFR 50.54#f +, 10 CFR 50.65#a +...

Emergency Preparedness +  and Physical Protection +

SECY-93-087 +, SECY-90-377 +, SECY-92-287 +, SECY-88-147 +, SECY-93-049 +, SECY-93-113 +, SECY-91-273 +, SECY-91-270 +, SECY-96-128 +, SECY-93-270 +, SECY-91-262 +, SECY-91-078 +, SECY-92-413 +, SECY-90-353 +, SECY-87-314 +, SECY-88-57 +, SECY-98-001 +, SECY-88-325 +, SECY 272 +, SECY 129 +  and SECY-93-289 +

Banks M +  and Advisory Committee on Reactor Safeguards +

NRC Generic Letter 91-18, Information to Licensees Regarding Two NRC Inspection Manual Sections on Resolution of Degraded and Nonconforming Conditions and on Operability +, NRC Generic Letter 83-28, Required Actions Based on Generic Implications of Salem ATWS Events +, NRC Generic Letter 95-06, Changes in the Operator Licensing Program +, NRC Generic Letter 88-20, Individual Plant Examination for Severe Accident Vulnerabilities +  and NRC Generic Letter 89-10, Safety-Related Motor-Operated Valve Testing and Surveillance +

ML16211A073 +, ML16211A073 +, ML16211A073 +, ML16211A073 +  and ML16211A073 +

General Electric +  and Westinghouse +

Nureg-1022 +, 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-1206, Comments on NUREG-1206, Analysis of French (Paluel) PWR Design Differences Compared to Current Us PWR Designs, Dtd June 1986.ACRS Recommends Continuation of Program to Study Safety Design Differences Between Us & Foreign Plants +, NUREG-1150, Weekly Info Rept for Wk Ending 890922 +, NUREG-1552, Informs That During 454th Meeting of ACRS on 980708-10, Representatives of NRC Staff Met W/Licensee to Discuss Suppl 1 to NUREG-1552 +, NUREG-1465, Provides Commission W/Results & Findings of Evaluation of Impact of Implementing Revised Source Term Described in NUREG-1465, Accident Source Terms for Light-Water Npps, for Operating Reactors +, NUREG-1225, Submits ACRS Comments on NUREG-1225, Implementation of NRC Policy on Nuclear Power Plant Standardization, Discussed at ACRS 318th Meeting on 861009-11.Rept Should Clarify Scope & Level of Detail of Info Required for Design Certification +, NUREG-0654, Correction to Amendment Nos. 221 and 206 to Authorize Revision of the Emergency Plan Based on NUREG-0654/FEMA-REP-1, Revision 2 +, NUREG-1338, Responds to Ltr to Wd Travers, Re Small,Modular, pebble-bed Reactor Design.Some Background Info & Guidance on Licensing gas-cooled Reactor Designs Can Be Found in NRC Staff repts;NUREG-1226,NUREG-1338 & NUREG-1512 +, NUREG-1200, Summarizes NRC 900706 Discussion W/Officials Involved in Low Level Waste Disposal in PA Re NRC Guidance Documents Including Std Format & Content Guide & Std Review Plan.List of Attendees Also Encl +, NUREG-1021, Revised Effectiveness Review Plan for NUREG-1021 Revision 12 (Public) +, 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 +  and Nureg-0956 +

Regulatory Guide 1.63 +, Regulatory Guide 1.9 +, Regulatory Guide 1.147 +, Regulatory Guide 1.160 +, Regulatory Guide 1.84 +, Regulatory Guide 1.82 +, Regulatory Guide 1.100 +, Regulatory Guide 1.105 +, Regulatory Guide 1.149 +, Regulatory Guide 1.134 +, Regulatory Guide 1.101 +, Regulatory Guide 1.8 +, Regulatory Guide 1.99 +, Regulatory Guide 1.28 +, Regulatory Guide 1.118 +, Regulatory Guide 1.152 +, Regulatory Guide 1.153 +, Regulatory Guide 1.114 +, Regulatory Guide 1.85 +, Regulatory Guide 8.7 +, Regulatory Guide 5.44 +, Regulatory Guide 1.178 +, Regulatory Guide 1.164 +  and Regulatory Guide 5.62, Physical Security Event Notifications, Reports, and Records +

SECY-93-087 +, SECY-90-377 +, SECY-92-287 +, SECY-88-147 +, SECY-93-049 +, SECY-93-113 +, SECY-91-273 +, SECY-91-270 +, SECY-96-128 +, SECY-93-270 +, SECY-91-262 +, SECY-91-078 +, SECY-92-413 +, SECY-90-353 +, SECY-87-314 +, SECY-88-57 +, SECY-98-001 +, SECY-88-325 +, SECY 272 +, SECY 129 +  and SECY-93-289 +

Texas +, Tennessee +  and Arkansas +

Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Emergency Diesel Generator +, Auxiliary Feedwater +, Primary containment +, Emergency Response Data System +, Reactor Pressure Vessel +, Reactor Water Cleanup +, Emergency Core Cooling System +, Decay Heat Removal +  and Containment Spray +

Fitness for Duty +, Fire Barrier +, Probabilistic Risk Assessment +, Nondestructive Examination +, Systematic Assessment of Licensee Performance +, Safeguards Contingency Plan +, License Renewal +, Earthquake +, Commercial Grade +, Chernobyl +, Fire Protection Program +, Backfit +, Siren +, Power Uprate +, Potassium iodide +, Control Room Habitability +  and Leak-Before-Break +

WCAP-10924 +  and WCAP-14572 +

WCAP-10924 +  and WCAP-14572 +