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TEXT-SAFETY REPORT  and SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES

Nitrogen +, Oxygen +, Hydrogen +, Zirconium +, Lead +  and Tin +

10 CFR 50.46 +, 10 CFR 50 +, 10 CFR 50.44 +, 10 CFR 50.44#c3viB +, 10 CFR 50.44#c3ivA +  and 10 CFR 50.44#c3ivB +

ML20058N394 +, ML20058N394 +, ML20058N394 +, ML20058N394 +, ML20058N394 +, ML20058N394 +, ML20058N394 +, ML20058N394 +, ML20058N394 +, ML20058N394 +, ML20058N394 +, ML20058N394 +, ML20058N394 +, ML20058N394 +, ML20058N394 +, ML20058N394 +, ML20058N394 +, ML20058N394 +, ML20058N394 +, ML20058N394 +, ML20058N394 +, ML20058N394 +, ML20058N394 +, ML20058N394 +, ML20058N394 +  and ML20058N394 +

8.101852e-5 d (0.00194 hours, 1.157407e-5 weeks, 2.6635e-6 months)  +  and 6.944444e-5 d (0.00167 hours, 9.920635e-6 weeks, 2.283e-6 months)  +

ML20138A369 +, ML20203J811 +, AECM-87-0042, Responds to 870115 SALP Repts 50-416/86-35 & 50-417/86-05 for May 1985 - Oct 1986.Comments Re Plant Operations, Radiological Controls,Maint,Fire Protection,Security, Licensing Activities & Quality Programs +, AECM-88-0065, Forwards NIS-1-00006, Inservice Insp Summary Rept for Grand Gulf Nuclear Station Unit 1, for Period Ending Second Refueling Outage +, AECM-86-0061, Informs That List of Drywell & Containment Mechanical Penetration Barriers,Including Isolation Valves, Appurtenances & Potential Release Paths,Issued for Use on 860219 +, AECM-86-0098, Forwards Monthly Operating Rept for Mar 1986.Corrected Cumulative Forced Outage Rate Listed in Feb 1986 Rept Is 11.1 +  and AECM-84-0066, Advises That Containment,Liner & Penetrations Capable of Withstanding 5 Psid Negative Internal Pressure Due to Hydrogen Combustion,Per NRC Request +

NUREG/CR-5079 +, NUREG/CR-4866 +, NUREG-0979, Forwards Sser 5,(NUREG-0979).W/o Encl +, NUREG-0887, Forwards Approved Changes to Tech Specs for Full Power License,Per 860618,0718 & 30 Requests.Certification That Changes Consistent W/Fsar,Ser & as-built Plant Requested by 860908 +, NUREG-0853, Forwards Suppl 6 to NUREG-0853, SER Re Operation of Clinton Power Station,Unit 1 +, NUREG-0989, Safety Evaluation Supporting Proposed Turbine Maint Program. Proposal Satisfies Licensee Commitment Prescribed in Sser 5. Commitment Acceptable Resolution of Turbine Maint Issue +, NUREG-1150, Weekly Info Rept for Wk Ending 890922 +, 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/CP-1659 +, NUREG/CR-1659, Forwards Reactor Safety Study Methodology Applications Program Rept for plant,NUREG/CR-1659.Safety Evaluation Based on Rept & Other Info to Be Prepared by Nrc.Util Views Requested.W/O Encl +, NUREG-0831, Forwards Suppl 1 to SER (NUREG-0831) Prepared in Connection W/Application for Ols.W/O Encl +  and NUREG-0011, Notice of Availability of SER (NUREG-0011) +

3D-day +  and 3D-Complex +

Mississippi +  and Rhode Island +

Emergency Diesel Generator +, Reactor Core Isolation Cooling +, Primary containment +, Reactor Pressure Vessel +, High Pressure Core Spray +, Core Spray +, Reactor Water Cleanup +, Shield Building +, Automatic Depressurization System +, Emergency Core Cooling System +, Safety Relief Valve +, Control rod blade +, Control Rod +  and Containment Spray +

Safe Shutdown +, Probabilistic Risk Assessment +, Coatings +, Loss of Offsite Power +, Fuel cladding +  and Scaffolding +