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ML022210537 +
10 CFR 50 Appendix A +, 10 CFR 50 +, 10 CFR 50 Appendix J +, 10 CFR 50 Appendix B +, 10 CFR 54 +, 10 CFR 50.12 +, 10 CFR 50.44 +, 10 CFR 50.49 +, 10 CFR 50.61 +, 10 CFR 50.65 +, 10 CFR 50 Appendix G +, 10 CFR 50 Appendix H +, 10 CFR 54.3 +, 10 CFR 54.22, Contents of Application--Technical Specifications +, 10 CFR 50.55a +, 10 CFR 54.4#a +, 10 CFR 50.49#e +, 10 CFR 50.49#f +, 10 CFR 54.3#a6 +, 10 CFR 54.21#d +, 10 CFR 54.21#c1 +, 10 CFR 54.21#c1i +, 10 CFR 54.21#c1ii +, 10 CFR 54.21#c1iii +, 10 CFR 54.21#c +, 10 CFR 50.55a#b2ixB +, 10 CFR 50.55a#b2ix +, 10 CFR 50.55a#b2viiiB +, 10 CFR 54.21#c11i +...
NRC Generic Letter 88-14, Instrument Air Supply System Problems Affecting Safety-Related Equipment +, NRC Generic Letter 88-05, Boric Acid Corrosion of Carbon Steel Reactor Pressure Boundary Components in PWR plants +, NRC Generic Letter 89-13, Service Water System Problems Affecting Safety-Related Equipment +, NRC Generic Letter 97-01, Degradation of Control Rod Drive Mechanism Nozzle and Other Vessel Closure Head Penetrations +, NRC Generic Letter 98-04, Potential for Degradation of the Emergency Core Cooling System and the Containment Spray System After a Loss-of-Coolant Accident Because of Construction and Protective Coating Deficiencies and Foreign Material in Containment + and NRC Generic Letter 89-10, Safety-Related Motor-Operated Valve Testing and Surveillance +
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ML022210537 +, ML022210537 +, ML022210537 +, ML022210537 +, ML022210537 +, ML022210537 +, ML022210537 +, ML022210537 +, ML022210537 +, ML022210537 +, ML022210537 + and ML022210537 +
July 30, 2002 +
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21:20:10, 16 January 2025 +
NRC Bulletin 01-01 +, NRC Bulletin 80-11 +, NRC Bulletin 88-09 +, NRC Bulletin 87-01 +, NRC Bulletin 88-11 +, NRC Bulletin 88-08 +, NRC Bulletin 96-02, Movement of Heavy Loads Over Spent Fuel, Over Fuel in the Reactor Core, or over Safety-Related Equipment + and NRC Bulletin 79-13, Cracking in Feedwater System Piping +
NUREG/CR-5704 +, NUREG/CR-6260 +, NUREG/CR-6583 +, NUREG/CR-5643 +, 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-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-1339, Summarizes Resolution of GI 29 Bolting Degradation or Failure in Nuclear Power Plants +, NUREG-0744, Notice of Issuance & Availability of NUREG-0744, Resolution of Reactor Vessel Matls Toughness Safety Issue. Final Rept Will Provide Resoultion of Unresolved Safety Issue A-11 +, NUREG-1800, Proposed Staff Guidance on Aging Management of Fire Protection Systems for License Renewal + and NUREG-1801, Proprosed Revision of Chapters II & III of Generic Aging Lessons (Gall) Report on Aging Management of Concrete Elements +
193 +
Request +
July 30, 2002 +
Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Auxiliary Feedwater +, Reactor Pressure Vessel +, Residual Heat Removal +, Reactor Water Cleanup +, Main Steam Line +, Control Rod +, Main Steam +, Containment Spray + and Extraction steam +
R. E. Ginna Nuclear Power Plant Application for Renewed Operating License, Volume 2, Section 4.0, Page 4-1 - Appendix D, Page D-1 +
Boric Acid +, Non-Destructive Examination +, Fire Barrier +, Stroke time +, Weld Overlay +, Coatings +, VT-2 +, Zebra Mussel +, Incorporated by reference +, High Energy Line Break +, Aging Management +, Flow Accelerated Corrosion +, Feedwater Heater +, Microbiologically influenced corrosion +, Stress corrosion cracking +, Eddy Current Testing +, Moisture barrier +, Hemyc +, License Renewal +, Earthquake +, Control of Heavy Loads +, Biofouling +, Fire Protection Program +, Flow Induced Vibration +, Core Exit Thermocouple +, Thermal fatigue + and Leak-Before-Break +
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