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ML022210409 +
10 CFR 50 Appendix R +, 10 CFR 50.48 +, 10 CFR 100 +, 10 CFR 50 +, 10 CFR 50.63 +, 10 CFR 30 +, 10 CFR 50.2 +, 10 CFR 25 +, 10 CFR 51 +, 10 CFR 54 +, 10 CFR 50.12 +, 10 CFR 50.37 +, 10 CFR 50.49 +, 10 CFR 50.61 +, 10 CFR 50.62 +, 10 CFR 54.3 +, 10 CFR 54.4 +, 10 CFR 54.17 +, 10 CFR 54.19 +, 10 CFR 54.22, Contents of Application--Technical Specifications +, 10 CFR 54.23, Contents of Application--Environmental Information +, 10 CFR 100.11 +, 10 CFR 140.92 Appendix B +, 10 CFR 50.55a +, 10 CFR 54.4#a +, 10 CFR 54.4#a2 +, 10 CFR 54.4#a3 +, 10 CFR 54.4#a1 +, 10 CFR 50.49#b1 +, 10 CFR 50.67#b2 +...
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July 30, 2002 +
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21:20:22, 16 January 2025 +
NUREG-41 +, 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-0821, Forwards Safety Evaluations of SEP Topics,Vols I-III,per App E of NUREG-0821, Integrated Plant Safety Assessment Rept for Re Ginna Nuclear Power Plant +, NUREG-1800, Proposed Staff Guidance on Aging Management of Fire Protection Systems for License Renewal +, NUREG-1801, Proprosed Revision of Chapters II & III of Generic Aging Lessons (Gall) Report on Aging Management of Concrete Elements +, 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 + and NUREG-1437, Supp. 17, Second Renewal, Generic Environmental Impact Statement for License Renewal of Nuclear Plants Supplement 17, Second Renewal Regarding Subsequent License Renewal for Dresden Nuclear Power Station, Units 2 and 3 Final Rep +
197 +
Request +
7DB9-10000 + and 7N92-1 +
July 30, 2002 +
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 +, Circulating Water System +, Main Steam Safety Valve +, Emergency Core Cooling System +, Decay Heat Removal +, Control Rod +, Main Steam + and Containment Spray +
R. E. Ginna Nuclear Power Plant Application for Renewed Operating License, Volume 1, Table of Contents - Section 2.0, Table 2.3.3.9 +
Safe Shutdown +, Unanalyzed Condition +, Boric Acid +, Shutdown Margin +, Ultimate heat sink +, Non-Destructive Examination +, Fire Barrier +, Safe Shutdown Earthquake +, Post Accident Monitoring +, Internal Flooding +, Coatings +, Incorporated by reference +, High Energy Line Break +, Aging Management +, Foreign Material Exclusion +, Intergranular Stress Corrosion Cracking +, Stress corrosion cracking +, Loss of Offsite Power +, License Renewal +, Earthquake +, Fire Protection Program +, Core Exit Thermocouple +, Spent fuel rack + and Leak-Before-Break +
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