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ML19298B485 +
10 CFR 50 Appendix J +, 10 CFR 50 Appendix B +, 10 CFR 50.49 +, 10 CFR 50.65 +, 10 CFR 50 Appendix C +, 10 CFR 50 Appendix G +, 10 CFR 50 Appendix H +, 10 CFR 54.21 +, 10 CFR 50.55a +, 10 CFR 54.4#a2 +, 10 CFR 54.4#a1 +, 10 CFR 54.4#b +, 10 CFR 50.49#f +, 10 CFR 54.37#b +, 10 CFR 54.21#c1iii +, 10 CFR 54.21#c +, 10 CFR 50.55a#g4 +, 10 CFR 50.55a#g6iiC +, 10 CFR 50.55#a + and 10 CFR 50.71#e +
NRC Generic Letter 88-14, Instrument Air Supply System Problems Affecting Safety-Related Equipment +, NRC Generic Letter 88-01, NRC Position on Intergranular Stress Corrosion Cracking (IGSCC) in BWR Austenitic Stainless Steel Piping +, NRC Generic Letter 89-13, Service Water System Problems Affecting Safety-Related Equipment +, NRC Generic Letter 89-08, Erosion/Corrosion-Induced Pipe Wall Thinning +, NRC Generic Letter 98-05, Boiling Water Reactor Licensees Use of the BWRVIP-05 Report to Request Relief from Augmented Examination Requirements on Reactor Pressure Vessel Circumferential Shell Welds + and NRC Generic Letter 89-10, Safety-Related Motor-Operated Valve Testing and Surveillance +
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ML19298B485 +, ML19298B485 +, ML19298B485 +, ML19298B485 +, ML19298B485 +, ML19298B485 +, ML19298B485 +, ML19298B485 + and ML19298B485 +
October 4, 2019 +
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11:46:40, 2 January 2025 +
NUREG/CR-5704 +, NUREG/CR-6260 +, NUREG-1475 +, NUREG/CR-6583 +, NUREG/CR-5999, Forwards Updated Fatigue Design Curves for Austenitic Stainless Steels in LWR Environments.Design Curves Being Provided in Advance of Future Update of NUREG/CR-5999 to Facilitate Efforts on Resolution of GSI-190 +, NUREG-0619, Informs That Staff Finds PP&L 980330 Request for Relief from Requirements of Section 4.3 of NUREG-0619,exams of Feedwater Nozzle Bore & Inner Radius for Another Operating Cycle to Be Acceptable +, 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-1339, Summarizes Resolution of GI 29 Bolting Degradation or Failure in Nuclear Power Plants + and NUREG-1557, Technical Info from Industry Repts Addressing License Renewal, Presented at 970817-22 14th Intl Conference on Structural Mechanics in Reactor Technology in Lyon,France +
32 +
Request +
October 4, 2019 +
Feedwater +, Service water +, Primary containment +, Main Transformer +, Reactor Pressure Vessel +, Core Spray +, Reactor Water Cleanup +, Standby Liquid Control +, Intermediate Range Monitor +, Emergency Equipment Cooling Water +, Safety Relief Valve +, Control Rod +, Main Steam + and Low Pressure Coolant Injection +
Ultimate heat sink +, Fire Barrier +, Hydrostatic +, Coatings +, Aging Management +, Intergranular Stress Corrosion Cracking +, Stress corrosion cracking +, Moisture barrier +, License Renewal +, Earthquake +, Maintenance Rule Program +, Control of Heavy Loads +, Biofouling +, Fire Protection Program + and Dissimilar Metal Weld +
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