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ML20197A396 +
GDC 57 +, GDC 15 +, GDC 10 +, GDC 55 +, GDC 14 +, GDC 31 +, GDC 23 +, GDC 29 +, GDC 2, Design bases for protection against natural phenomena +, GDC 4, Environmental and dynamic effects design bases +, GDC 1, Quality standards and records + and GDC 26, Reactivity control system redundancy and capability +
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ML20197A396 +, ML20197A396 +, ML20197A396 +, ML20197A396 +, ML20197A396 +, ML20197A396 +, ML20197A396 +, ML20197A396 + and ML20197A396 +
June 19, 2020 +
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20:29:57, 10 December 2024 +
NUREG/CR-1677 +, NUREG/CR-1980 +, NUREG-0484, Forwards SER Suppl Info on Applicant 830203 Submittal Re Applicability of Square Root of Sum of Squares Combination of Dynamic Responses.Method Applicable & Complies w/NUREG-0484 +, 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-1339, Summarizes Resolution of GI 29 Bolting Degradation or Failure in Nuclear Power Plants +, NUREG-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting +, NUREG-1367, FRN NUREG 1307 Rev 20 FRN 11/19/24 +, NUREG-1061, Summary of 890217 Meeting W/Util in Rockville,Md Re Resolution of Open Civil/Seismic Issues for Plant.List of Attendees & Slide Presentation Encl +, NUREG-2192, Rev. 1, Standard Review Plan for Review of Subsequent License Renewal Applications for Nuclear Power Plants Final Report + and NUREG-1482, Revision 4, Guidelines for Inservice Testing at Nuclear Power Plants: Inservice Testing of Pumps and Valves and Inservice Examination and Testing of Dynamic Restraints (Snubbers) at Nuclear Power Plants Final Report +
183 +
SP-58 + and SP-58-2009 +
Request +
Regulatory Guide 1.97 +, Regulatory Guide 1.180 +, Regulatory Guide 1.63 +, Regulatory Guide 1.84 +, Regulatory Guide 1.7 +, Regulatory Guide 1.100 +, Regulatory Guide 1.26 +, Regulatory Guide 1.65 +, Regulatory Guide 1.29 +, Regulatory Guide 1.92 +, Regulatory Guide 1.28 +, Regulatory Guide 1.61 +, Regulatory Guide 1.122 +, Regulatory Guide 1.152 +, Regulatory Guide 1.89 +, Regulatory Guide 1.153 +, Regulatory Guide 1.20 +, Regulatory Guide 1.40 +, Regulatory Guide 1.124 +, Regulatory Guide 1.130 +, Regulatory Guide 1.192 +, Regulatory Guide 1.73 +, Regulatory Guide 1.199 +, Regulatory Guide 1.209 +, Regulatory Guide 1.206 +, Regulatory Guide 1.156 +, Regulatory Guide 1.158 +, Regulatory Guide 1.207 + and Regulatory Guide 1.211 +
June 19, 2020 +
Steam Generator +, Reactor Coolant System +, Feedwater +, Reactor Protection System +, Main Steam Isolation Valve +, HVAC +, Reactor Pressure Vessel +, Main Steam Safety Valve +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Safety Relief Valve +, Control Rod + and Main Steam +
Part 02 - Final Safety Analysis Report (Rev. 4.1) - Part 02 - Tier 02 - Chapter 03 - Design of Structures, Systems, Components and Equipment - Sections 03.09 - 03.13 (Rev. 4.1) +
Safe Shutdown +, Boric Acid +, Ultimate heat sink +, Stroke time +, Anticipated operational occurrence +, Safe Shutdown Earthquake +, Post Accident Monitoring +, Hydrostatic +, Operating Basis Earthquake +, Incorporated by reference +, Finite Element Analysis +, High Energy Line Break +, Feedwater Heater +, Stress corrosion cracking +, Excess Flow Check Valve +, Earthquake +, Commercial Grade +, Power-Operated Valves +, Power Operated Valves +, Fuel cladding +, Power change +, Flow Induced Vibration +, Unidentified leakage +, Thermal fatigue +, Water hammer +, Leak-Before-Break +, Leak Before Break +, Seal weld + and AutoPIPE +
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