Browse wiki

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

Hydrogen +, Chlorine +  and Lead +

10 CFR 50 Appendix R +, 10 CFR 50.72 +, 10 CFR 50 Appendix A +  and 10 CFR 50 +

NRC-03-81 +  and U-0633 +

00461  +  and 05000461  +

NRC Generic Letter 81-27, Privacy and Proprietary Material in Emergency Plans +, NRC Generic Letter 81-07, Control of Heavy Loads +, NRC Generic Letter 81-01, Qualification of Inspection, Examination, Testing and Audit Personnel +, NRC Generic Letter 82-33, Supplement 1 to NUREG-0737 - Emergency Response Capability +, NRC Generic Letter 83-42, Clarification to GL 81-07 Regarding Response to NUREG-0612, "Control of Heavy Loads at Nuclear Power Plants" +, NRC Generic Letter 83-41, Fast Cold Starts of Diesel Generators +, NRC Generic Letter 83-38, NUREG-0965, "NRC Inventory of Dams" +, NRC Generic Letter 83-35, Clarification of TMI Action Plan Item II.K.3.31 +, NRC Generic Letter 83-32, NRC Staff Recommendations Regarding Operator Action for Reactor Trip and ATWS +, NRC Generic Letter 83-28, Required Actions Based on Generic Implications of Salem ATWS Events +, NRC Generic Letter 84-03, Availability of NUREG-0933, "A Prioritization of Generic Safety Issues" +, NRC Generic Letter 84-02, Notice of Meeting Regarding Facility Staffing +, NRC Generic Letter 84-01, NRC Use Of The Terms "Important To Safety" and "Safety Related" +  and NRC Generic Letter 82-43 +

ML20140C120 +, ML20140C120 +, ML20140C120 +, ML20140C120 +, ML20140C120 +, ML20140C120 +, ML20140C120 +, ML20140C120 +, ML20140C120 +, ML20140C120 +, ML20140C120 +, ML20140C120 +, ML20140C120 +, ML20140C120 +, ML20140C120 +, ML20140C120 +, ML20140C120 +, ML20140C120 +, ML20140C120 +, ML20140C120 +, ML20140C120 +, ML20140C120 +, ML20140C120 +, ML20140C120 +, ML20140C120 +, ML20140C120 +, ML20140C120 +, ML20140C120 +, ML20140C120 +, ML20140C120 +...

ML20010H747 +, ML20052D694 +, ML20063F381 +, ML20069B718 +, ML20086L045 +, ML20083F597 +, ML20077N459 +, ML20076K838 +, ML20073P435 +, ML20072T976 +, ML20070H793 +, ML20004G109 +  and ML20053B512 +

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

NUREG-0965, Forwards marked-up Copy of Section 3.2 of NUREG-0965, NRC Inventory of Dams, & Corrected Pages for App C & App E +, NUREG-0731, Summary of 860314 Meeting W/Util in Bethesda,Md Re Qualifications of Radiation Protection Manager as Compared to Qualifications Outlined in 1975 Rev 1 to Reg Guide 1.8, Personnel Selection & Training. Viewgraphs 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-0798, Advises That NRC Review of Sys Leakage Reduction Test Results Cannot Be Completed Until Final Test Procedures & Acceptance Criteria Upon Which Sys Test Results Based Submitted & Reviewed +, NUREG-0612, Safety Evaluation Supporting Util Request to Delete Three Commitments in Response to NUREG-0612 Re Heavy Load Control on 5-ton Electric Monorail Hoist W/Integral Trolley & 4-ton Monorail Chain Hoist W/Geared Trolley +, NUREG-0313, Safety Evaluation Supporting Amend 133 to License DPR-59 +, 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 +, NUREG-0881, Safety Evaluation Accepting Licensee Submittals & Addl Info on Environ Qualification & Design for Instrumentation,Per Reg Guide 1.97 +, NUREG/CR-1582, Forwards Aug 1980 NUREG/CR-1582,Vols 2 & 3, Seismic Hazard Analysis,Solicitation of Expert Opinion, Prepared by Tera Corp.W/O Encl +, NUREG-0793, Requests Assistance in Expediting Printing of Facility SER (NUREG-0793) +, NUREG-0011, Notice of Availability of SER (NUREG-0011) +  and NUREG-1050, Forwards Regulatory Analysis of Generic Safety Issue 61, Safety/Relief Valve Discharge Line Break within Mark I or II Wetwell Airspace. Based on Results Discussed in NUREG/CR-4594,risk Lower than Previously Estimated +

Regulatory Guide 1.97 +, Regulatory Guide 1.60 +  and Regulatory Guide 1.133 +

Tennessee +, Illinois +, Maryland +, Washington +  and New York +

Feedwater +, Secondary containment +, Service water +, Reactor Core Isolation Cooling +, Shutdown Cooling +, Safety Parameter Display System +, HVAC +, High Pressure Core Spray +, Residual Heat Removal +, Automatic Depressurization System +, Circulating Water System +, Remote shutdown +, Emergency Core Cooling System +, Decay Heat Removal +, Control Rod +  and Low Pressure Coolant Injection +

Safe Shutdown +, Reactor Vessel Water Level +, Ultimate heat sink +, Fire Barrier +, Safe Shutdown Earthquake +, Probabilistic Risk Assessment +, Nondestructive Examination +, Emergency Lighting +, Earthquake +, Control of Heavy Loads +, Fire Protection Program +, Early Warning Fire Detection +  and Control Room Habitability +