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ASME Section III +  and ASME Section II +

Boron +, Iodine +, Cesium +, Rubidium +, Copper +, Nitrogen +, Carbon +, Oxygen +, Hydrogen +, Xenon +, Zirconium +, Chloride +, Lead +  and Phosphorus +

10 CFR 100 +, 10 CFR 50 +, 10 CFR 50.63 +, 10 CFR 50.59 +, 10 CFR 50.49 +, 10 CFR 50.65 +, 10 CFR 50 Appendix F +  and 10 CFR 50.48#ci +

Turbine Trip +  and Reactor Trip +

Ameren Missouri +  and Union Electric Co +

GDC 17, Electric power systems +, GDC 2, Design bases for protection against natural phenomena +  and GDC 19, Control room +

ML24149A281 +, ML24149A281 +, ML24149A281 +, ML24149A281 +, ML24149A281 +, ML24149A281 +, ML24149A281 +, ML24149A281 +, ML24149A281 +, ML24149A281 +  and ML24149A281 +

1.157407e-4 d (0.00278 hours, 1.653439e-5 weeks, 3.805e-6 months)  +, 2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +  and 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +

IEEE 384 +, IEEE 344 +  and IEEE 338 +

Westinghouse +  and Limitorque +

NRC Bulletin 79-27 +  and NRC Bulletin 80-06 +

NUREG-0694, Advises That Augmented Natural Circulation Training Should Be Performed.Descriptions of Natural Circulation Tests Should Be Included in Fsar.Detailed Test Procedures Must Be Submitted 60 Days Prior to Scheduled Test Performance +, NUREG-0606, Discusses 336th Meeting of ACRS on 880407-09 Re Proposed Resolution of USI A-47, Safety Implications of Control Sys. Disagrees That NRC Recommendations Constitute Resolution of USI A-47 as Originally Defined +, NUREG-0121, Notifies of 870825 Meeting in Rosemont,Il to Discuss Implementation of Operator Licensing Exam Process within Region Iii.Presentations Will Incorporate Rev 4 of NUREG- 0121, Operator Licensing Examiner Stds. Agenda Encl +, 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-0585, Forwards NUREG-0578, TMI-2 Lessons Learned Task Force Status Report & Short-Term Requirements, & NUREG-0585, TMI-2 Lessons Learned Task Force Final Rept, in Response to .W/O Encl +, NUREG-0830, Advises That Condition 2.c.(3)(a) of License NPF-30 Fulfilled,Based on & 860117 Rept Re Environ Qualification Program for Electrical Equipment.Program Previously Accepted Per NUREG-0830,Section 3.11 +, NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +, NUREG/CR-0660, Forwards Sample Ltr to Applicants,Cp Holders & Licensees of LWRs Transmitting NUREG/CR-0660 Enhancement of Onsite Emergency Diesel Generator Reliability +, NUREG-0577, Forwards Request for Addl Info Re Low Fracture Toughness Since Facility Has Been Classified as Group 1 According to NUREG-0577.Response Should Be Submitted within 30 Days of Receipt of Ltr.Further NRC Evaluation Will Be Required +, NUREG-0609, Forwards Request for Addl Info on Generic Ltr 84-04,Safety Evaluation of Westinghouse Topical Repts Dealing W/ Eliminating of Postulated Pipe Breaks in PWR Primary Main Loops. Response Requested by 840731 +, NUREG-0717, Forwards Suppl 4 to SER (NUREG-0717) Re Operation of Facility +  and NUREG-0630, 09-09-80 Cladding Swelling and Rupture Models for LOCA Analysis - NUREG-0630 +

SP +, CP +  and Emergency Operating Procedure +

Regulatory Guide 1.97 +, Regulatory Guide 1.75 +, Regulatory Guide 1.78 +, Regulatory Guide 1.108 +, Regulatory Guide 1.121 +, Regulatory Guide 1.70 +, Regulatory Guide 1.82 +, Regulatory Guide 1.100 +, Regulatory Guide 1.117 +, Regulatory Guide 1.26 +, Regulatory Guide 1.54 +, Regulatory Guide 1.29 +, Regulatory Guide 1.118 +, Regulatory Guide 1.68 +, Regulatory Guide 1.79 +  and Regulatory Guide 1.80 +

Kansas +, Idaho +  and Oregon +

Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Reactor Protection System +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Auxiliary Feedwater +, Primary containment +, HVAC +, Reactor Pressure Vessel +, Residual Heat Removal +, Control Room Emergency Ventilation +, Fuel Pool Cooling and Cleanup +, Decay Heat Removal +  and Main Steam Line +

TS-3.4.14 +  and TS-5.5.7 +

Hot Short +, Safe Shutdown +, Boric Acid +, Shutdown Margin +, Reactor Vessel Water Level +, Grab sample +, Anticipated operational occurrence +, Tornado Missile +, Hydrostatic +, Coatings +, Emergency Lighting +, High Energy Line Break +, Tornado Missile Protection +, Feedwater Heater +, Loss of Offsite Power +  and Integrated leak rate test +

WCAP-8183 +, WCAP-8236 +, WCAP-8288 +, WCAP-8278 +, WCAP-9283 +, WCAP-10851-P-A +, WCAP-8567 +, WCAP-9401-P-A +, WCAP-9402-A +, WCAP-9292 +, WCAP-8163 +, WCAP-9754 +, WCAP-9842 +  and WCAP-9759 +

WCAP-8183 +, WCAP-8236 +, WCAP-8288 +, WCAP-8278 +, WCAP-9283 +, WCAP-10851-P-A +, WCAP-8567 +, WCAP-9401-P-A +, WCAP-9402-A +, WCAP-9292 +, WCAP-8163 +, WCAP-9754 +, WCAP-9842 +  and WCAP-9759 +