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TEXT-SAFETY REPORT, NUREG REPORTS  and SAFETY EVALUATION REPORT--FACILITY

Hydrogen +  and Chlorine +

10 CFR 50.73 +, 10 CFR 55 +, 10 CFR 50 Appendix A +, 10 CFR 50.46 +, 10 CFR 50 +, 10 CFR 50.36 +, 10 CFR 50.44 +  and 10 CFR 50.55a#g +

00461  +  and 05000461  +

GDC 57 +, GDC 54 +, GDC 61 +  and GDC 64 +

ML20206B236 +, ML20206B236 +, ML20206B236 +, ML20206B236 +, ML20206B236 +, ML20206B236 +, ML20206B236 +, ML20206B236 +, ML20206B236 +, ML20206B236 +, ML20206B236 +, ML20206B236 +, ML20206B236 +, ML20206B236 +, ML20206B236 +, ML20206B236 +, ML20206B236 +, ML20206B236 +, ML20206B236 +, ML20206B236 +, ML20206B236 +, ML20206B236 +, ML20206B236 +, ML20206B236 +, ML20206B236 +, ML20206B236 +, ML20206B236 +, ML20206B236 +, ML20206B236 +, ML20206B236 +...

4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months)  +, 1.388889e-4 d (0.00333 hours, 1.984127e-5 weeks, 4.566e-6 months)  +, 2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +, 1.157407e-5 d (2.777778e-4 hours, 1.653439e-6 weeks, 3.805e-7 months)  +  and 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +

ML20141N816 +, IR 05000461/1986001 +, IA-84-940, Notification of 841218 Meeting W/Hydrogen Control Owners Group in Norwood,Ma,To Review & Inspect Installation of Test Equipment in 1/4 Scale Test Facility +, IR 05000461/1986067 +, ML20212H498 +, IR 05000461/1987007 +, IR 05000461/1987037 +, ML20266D845 +, U-600679, Forwards Clinton Single Loop Operation Analysis. Proposed Tech Spec Changes,Necessary to Implement Operation,Also Encl +, U-600818, Requests 30-day Extension of Submittal Date for Initial Leak Rate Test Results,Per NUREG-0737,TMI Action Item III.D.1.1 & Sser 5.Leakage Data Currently Being Gathered +, ML20210A981 +, ML20209F602 +, U-600881, Confirms Plans Re Power Ascension Test Program,Per 870313 Presentation to NRC +  and ML20199G064 +

Westinghouse +  and General Electric +

NRC Bulletin 79-27 +, NRC Bulletin 80-06 +  and NRC Bulletin 79-02, Pipe Support Base Plate Designs Using Concrete Expansion Anchor Bolts +

NUREG-0853, Forwards Suppl 6 to NUREG-0853, SER Re Operation of Clinton Power Station,Unit 1 +, NUREG-0133, Safety Evaluation Accepting Licensee Rev 3 to ODCM for Plant Through Temporary Change 4.Rev Meets Criteria of NUREG-0133 & Other Guidance. Guidance +, NUREG-0313, Safety Evaluation Supporting Amend 133 to License DPR-59 +, NUREG-0123, Safety Evaluation Supporting Amend 99 to License DPR-6 +, NUREG-853 +, NUREG-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting +, NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +  and NUREG-0660, 04-17-80 NUREG-0660 NRC Action Plans Developed as a Result of the TMI-2 Accident, Draft 3 +

Regulatory Guide 1.97 +, Regulatory Guide 1.7 +  and Regulatory Guide 1.106 +

NEDC-30851P +  and NEDC-30851 +

SR-4.6.2.2 +, SR-4.8.2.1.d +, SR-4.4.3.2.1 +, SR-4.4.1.1 +, SR-4.6.1.7 +, SR-4.4.4.c +, SR-4.6.1.4.c +, SR-4.6.3.1.c +  and SR-4.6.2.6 +

Illinois +, Washington +  and Idaho +

Feedwater +, Secondary containment +, Reactor Protection System +, Main Steam Isolation Valve +, Primary containment +, Safety Parameter Display System +, Reactor Pressure Vessel +, Core Spray +, Residual Heat Removal +, Standby Gas Treatment System +, Shield Building +, Circulating Water System +, Remote shutdown +, Emergency Core Cooling System +, Control Rod +  and Containment Spray +

TS-3.1.2 +, TS-6.2.2 +, TS-1.28 +, TS-6.4.1 +, TS-6.12.2 +, TS-6.12 +, TS-6.7.1.d +, TS-5.1.1 +, TS-6.1.2 +, TS-6.2.1 +, TS-6.2.3.4 +, TS-6.5.1.2 +  and TS-6.12.3 +

Safe Shutdown +, Shutdown Margin +, High Radiation Area +, Ultimate heat sink +, Offsite Dose Calculation Manual +, Feedwater Controller Failure +, Control of Heavy Loads +, Fuel cladding +  and Control Room Habitability +