Browse wiki

CORRESPONDENCE-LETTERS  and INCOMING CORRESPONDENCE

10 CFR 50 Appendix A +, 10 CFR 50 +, 10 CFR 50.109 +, 10 CFR 50.54 +  and 10 CFR 50.54#f +

SECY 93-118 +  and SECY-94-128 +

STATE OF +, Tosch K +  and NEW JERSEY +

NRC Generic Letter 82-33, Supplement 1 to NUREG-0737 - Emergency Response Capability +, NRC Generic Letter 87-02, Verification of Seismic Adequacy of Mechanical and Electrical Equipment in Operating Reactors (USI A-46) +, NRC Generic Letter 92-04, Resolution of the Issues Related to Reactor Vessel Water Level Instrumention in BWRs Pursuant to 10 CFR 50.54(f) +, NRC Generic Letter 93-04, Rod Control System Failure and Withdrawal of Rod Control Cluster Assemblies, 10 CFR 50.54(f) +, NRC Generic Letter 94-03, Intergranular Stress Corrosion Cracking of Core Shrouds in Boiling Water Reactors +, 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 +

ML20091R699 +, ML20091R699 +, ML20091R699 +, ML20091R699 +, ML20091R699 +, ML20091R699 +, ML20091R699 +, ML20091R699 +, ML20091R699 +, ML20091R699 +, ML20091R699 +, ML20091R699 +, ML20091R699 +, ML20091R699 +, ML20091R699 +  and ML20091R699 +

NRC Bulletin 93-03 +, NRC Bulletin 93-02 +, NRC Bulletin 88-08 +, NRC Bulletin 90-01 +  and NRC Bulletin 85-03 +

NUREG-1435, Forwards Suppl 2 to NUREG-1435 Containing Most Recent Assessment of Licensee Actions & Committments Re TMI Action Plan Requirements.W/O Encl +, 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-0510, Responds to 790614 Questions Re Status & Future of Nuclear Power in Mi.Nrc Has Summarized Historical & Economic Data Requested.Forwards NUREG-0510.Cover Sheet Only Encl +  and NUREG-0660, 04-17-80 NUREG-0660 NRC Action Plans Developed as a Result of the TMI-2 Accident, Draft 3 +

SECY 93-118 +  and SECY-94-128 +

New Jersey +  and Washington +

Steam Generator +, Reactor Coolant System +, Feedwater +, Core Spray +, Emergency Core Cooling System +, Control Rod +  and Containment Spray +

NRC (Affiliation Not Assigned) +  and Mckee P +

Reactor Vessel Water Level +, Fire Barrier +, Probabilistic Risk Assessment +, Stress corrosion cracking +, Earthquake +  and Backfit +