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ML16203A374 +
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WM 16-0008, Wolf Creek Generating Station, Redacted Version of Revision 29 to Updated Safety Analysis Report, Chapter 5.0 - Reactor Coolant System and Connected Systems +, WM 16-0008, Wolf Creek Generating Station, Redacted Version of Revision 29 to Updated Safety Analysis Report, Chapter 5.0 - Reactor Coolant System and Connected Systems +, WM 16-0008, Wolf Creek Generating Station, Redacted Version of Revision 29 to Updated Safety Analysis Report, Chapter 5.0 - Reactor Coolant System and Connected Systems +, WM 16-0008, Wolf Creek Generating Station, Redacted Version of Revision 29 to Updated Safety Analysis Report, Chapter 5.0 - Reactor Coolant System and Connected Systems +, WM 16-0008, Wolf Creek Generating Station, Redacted Version of Revision 29 to Updated Safety Analysis Report, Chapter 5.0 - Reactor Coolant System and Connected Systems +, WM 16-0008, Wolf Creek Generating Station, Redacted Version of Revision 29 to Updated Safety Analysis Report, Chapter 5.0 - Reactor Coolant System and Connected Systems +, WM 16-0008, Wolf Creek Generating Station, Redacted Version of Revision 29 to Updated Safety Analysis Report, Chapter 5.0 - Reactor Coolant System and Connected Systems +, WM 16-0008, Wolf Creek Generating Station, Redacted Version of Revision 29 to Updated Safety Analysis Report, Chapter 5.0 - Reactor Coolant System and Connected Systems +, WM 16-0008, Wolf Creek Generating Station, Redacted Version of Revision 29 to Updated Safety Analysis Report, Chapter 5.0 - Reactor Coolant System and Connected Systems + and WM 16-0008, Wolf Creek Generating Station, Redacted Version of Revision 29 to Updated Safety Analysis Report, Chapter 5.0 - Reactor Coolant System and Connected Systems +
6.944444e-5 d (0.00167 hours, 9.920635e-6 weeks, 2.283e-6 months) +, 1.157407e-5 d (2.777778e-4 hours, 1.653439e-6 weeks, 3.805e-7 months) +, 0.00194 d (0.0467 hours, 2.777778e-4 weeks, 6.3924e-5 months) +, 2.893519e-4 d (0.00694 hours, 4.133598e-5 weeks, 9.5125e-6 months) +, 4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months) +, 1.041667e-4 d (0.0025 hours, 1.488095e-5 weeks, 3.4245e-6 months) +, 2.314815e-4 d (0.00556 hours, 3.306878e-5 weeks, 7.61e-6 months) + and 3.703704e-4 d (0.00889 hours, 5.291005e-5 weeks, 1.2176e-5 months) +
May 31, 2016 +
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11:36:25, 8 July 2018 +
NUREG/CR-2907, Responds to 851105 Request for Info Re Radwaste & Containment Spray Sys.Nrc Methodology for Estimating Radwaste Generation Delineated in Encl NUREG-0017.USA Experience Summarized in Encl NUREG/CR-2907.W/o Encls +, NUREG/CR-6582, Forwards,For Review & Comments,Draft Rept, Assessment of Pressurized Water Reactor Primary System Leaks, NUREG/CR-6582,to Meet Planned Issuance Schedule.Comments Requested to Be Submitted by 980130 + and NUREG-1801, Proprosed Revision of Chapters II & III of Generic Aging Lessons (Gall) Report on Aging Management of Concrete Elements +
224 +
Request +
Regulatory Guide 1.147 +, Regulatory Guide 1.45 +, Regulatory Guide 1.65 +, Regulatory Guide 1.99 +, Regulatory Guide 1.14 +, Regulatory Guide 1.31 +, Regulatory Guide 1.83 +, Regulatory Guide 1.44 +, Regulatory Guide 1.85 +, Regulatory Guide 1.150 + and Regulatory Guide 1.37, Quality Assurance Requirements for Cleaning of Fluid Systems and Associated Components of Water-Cooled Nuclear Power Plants +
May 31, 2016 +
Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Reactor Protection System +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Auxiliary Feedwater +, Reactor Core Isolation Cooling +, Shutdown Cooling +, Reactor Pressure Vessel +, Residual Heat Removal +, Reactor Water Cleanup +, Emergency Core Cooling System +, Main Steam Line +, Safety Relief Valve +, Main Condenser +, Control Rod + and Main Steam +
Wolf Creek Generating Station, Redacted Version of Revision 29 to Updated Safety Analysis Report, Chapter 5.0 - Reactor Coolant System and Connected Systems +
Boric Acid +, Loop seal +, Stroke time +, Safe Shutdown Earthquake +, Weld Overlay +, Hydrostatic +, Operating Basis Earthquake +, Nondestructive Examination +, Incorporated by reference +, Feedwater Heater +, Stress corrosion cracking +, Loss of Offsite Power +, Eddy Current Testing +, License Renewal +, Fuel cladding +, Liquid penetrant +, Pressure Boundary Leakage +, Dissimilar Metal Weld +, Scaffolding +, Power change +, Unidentified leakage +, Overspeed +, Water hammer +, Leak-Before-Break + and Pressure Temperature Limits Report +
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