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ASME Section III +  and ASME Section IX +

Boron +, Cobalt +, Uranium +, Copper +, Nitrogen +, Carbon +, Xenon +, Zirconium +, Lead +, Helium +, Aluminum +, Chromium +, Hafnium +  and Tungsten +

RS-22-048, 2 to Updated Safety Analysis Report, B 2.0 Safety Limits (Sls) +  and L 25 +

ML22111A202 +, ML22111A202 +, ML22111A202 +, ML22111A202 +, ML22111A202 +, ML22111A202 +, ML22111A202 +, ML22111A202 +, ML22111A202 +  and ML22111A202 +

2.314815e-4 d (0.00556 hours, 3.306878e-5 weeks, 7.61e-6 months)  +, 6.944444e-5 d (0.00167 hours, 9.920635e-6 weeks, 2.283e-6 months)  +  and 0.0579 d (1.389 hours, 0.00827 weeks, 0.0019 months)  +

Cobalt-60 +  and Co-60 +

General Electric +  and Honeywell +

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-0619, Informs That Staff Finds PP&L 980330 Request for Relief from Requirements of Section 4.3 of NUREG-0619,exams of Feedwater Nozzle Bore & Inner Radius for Another Operating Cycle to Be Acceptable +, NUREG-0771, Transcript of 810521 Public Meeting Re Briefing on SECY-81- 240,draft NUREG-0771 & 0772 Re Accident Source Term Assumptions,In Washington,Dc.Pp 1-67.Meeting Outline & Viewgraphs Encl +  and NUREG-0630, 09-09-80 Cladding Swelling and Rupture Models for LOCA Analysis - NUREG-0630 +

TP +  and CH +

Regulatory Guide 1.70 +, Regulatory Guide 1.190 +, Regulatory Guide 1.31 +, Regulatory Guide 1.44 +, Regulatory Guide 1.34 +, Regulatory Guide 1.71 +  and Regulatory Guide 1.37, Quality Assurance Requirements for Cleaning of Fluid Systems and Associated Components of Water-Cooled Nuclear Power Plants +

NEDE-33284P +, NEDE-33284 +, NEDE-21354 +, NEDE-24284 +, NEDE-31758P +, NEDC-33505P +  and NEDO-24284 +

1P-A +  and 1C11-C300 +

California +  and Pennsylvania +

Reactor Coolant System +, Feedwater +, Reactor Protection System +, Reactor Recirculation Pump +, Reactor Pressure Vessel +, Core Spray +, Standby Liquid Control +, Emergency Core Cooling System +, Main Steam Line +, Control rod blade +, Main Condenser +  and Control Rod +

Shutdown Margin +, Anticipated operational occurrence +, Hydrostatic +, Nondestructive Examination +, Finite Element Analysis +, Surveillance Frequency Control Program +, Feedwater Heater +, Scram Discharge Volume +, Stress corrosion cracking +, Fuel cladding +, Power change +, Coast down +, Accident Tolerant Fuel +, Power Uprate +, GNF3 +, Water rod +  and Basic Component +