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TEXT-SAFETY REPORT, NUREG REPORTS  and NRC TECHNICAL REPORT

ASME Section XI +  and ASME Section III +

Copper +, Nitrogen +, Lead +  and Tin +

10 CFR 50 +, 10 CFR 50.36 +, 10 CFR 50.61 +  and 10 CFR 0748 +

Mitigating Systems +  and Initiating Events +

00275  +, 00313  +, 00302  +, 00346  +, 00269  +, 00270  +, 00287  +, 00312  +, 00289  +, 00368  +, 00317  +, 00318  +, 00285  +, 00309  +, 00336  +, 00255  +, 00528  +, 00529  +, 00361  +, 00363  +, 00335  +, 00382  +, 00334  +, 00463  +, 00414  +, 00316  +, 00323  +, 00348  +, 00364  +, 00213  +...

NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES) +  and Throm E +

GDC 15 +  and GDC 31 +

ML20055E089 +, ML20055E089 +, ML20055E089 +, ML20055E089 +, ML20055E089 +, ML20055E089 +  and ML20055E089 +

9.259259e-5 d (0.00222 hours, 1.322751e-5 weeks, 3.044e-6 months)  +, 5.787037e-5 d (0.00139 hours, 8.267196e-6 weeks, 1.9025e-6 months)  +, 0.0208 d (0.5 hours, 0.00298 weeks, 6.849e-4 months)  +, 0.0255 d (0.611 hours, 0.00364 weeks, 8.371e-4 months)  +, 4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months)  +, 2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +, 0.01 d (0.241 hours, 0.00143 weeks, 3.298935e-4 months)  +, 0.00896 d (0.215 hours, 0.00128 weeks, 2.94507e-4 months)  +, 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +, 1.62037e-4 d (0.00389 hours, 2.314815e-5 weeks, 5.327e-6 months)  +, 1.388889e-4 d (0.00333 hours, 1.984127e-5 weeks, 4.566e-6 months)  +, 1.157407e-5 d (2.777778e-4 hours, 1.653439e-6 weeks, 3.805e-7 months)  +, 5.555556e-4 d (0.0133 hours, 7.936508e-5 weeks, 1.8264e-5 months)  +  and 6.944444e-5 d (0.00167 hours, 9.920635e-6 weeks, 2.283e-6 months)  +

NUREG/BR-0058 +, NUREG-13 +, NUREG/CR-4551 +, NUREG-1326 +, NUREG/CR-4999 +, NUREG/CR-3568 +, NUREG/CR-4627 +, NUREG/CR-2723 +, NUREG-52029 +, NUREG/CR-2326 +, NUREG/CR-4486 +, NUREG/CR-4692 +, NUREG/CR-5186 +, NUREG/CR-5015 +, NUREG/CR-4483 +, NUREG/CR-4568 +, NUREG/CR-2789 +, NUREG/CR-2239, Forwards Slides/Handout Used at 821110 Presentation of NUREG/CR-2239 Re Sandia Siting or Consequences Study. Transcript of Meeting in PDR Did Not Include Slides +, NUREG-1109, Recommends That Final Station Blackout Rule,As Contained in Encl Fr Notice & Reg Guide,Providing Method Acceptable to Comply W/Rule,Be Issued in Order to Implement Final Resolution of USI A-44 +, NUREG/CR-4267 +, NUREG-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting +, NUREG-52101 +, NUREG/CR-4614 +, NUREG-0748, Summarizes Operating Reactors Licensing Actions Summary Revisions to non-computer Originated Pages for NUREG-0748 +, NUREG-0020, Responds to Encl Re Spent Fuel Storage Capacity at Plant.Spent Fuel Pool at Plant Has Sufficient Space to Accommodate Addl Fuel Storage Racks of Current Design +, NUREG-0348, Responds to Re Rural & Urban Characteristics of Proposed & Existing Nuclear Power Plants.Data Re Plant Site Characteristics & Current Licensing Status Contained in NUREG-0348 & NUREG-0380 +, NUREG-0371, Forwards NUREG-0371,NUREG-0471 & NUREG-0600.W/o Encl +  and NUREG-0224, Safety Evaluation Accepting Adequacy of Low Temp Overpressure Mitigating Sys Per Multi-Plant Action Item B-04,NUREG-0224 & GDC 15 & 31 +

ES +, SP +, RT +, TOP +  and ES.1 +

Regulatory Guide 1.26 +, Regulatory Guide 1.99 +  and Regulatory Guide 1.153 +

7x10-7 +, 7x10-6per +, 74xio-6 +  and 7et-pressur +

Maryland +, Washington +, New York +, Arkansas +  and Maine +

Steam Generator +, Reactor Coolant System +, Shutdown Cooling +, Reactor Pressure Vessel +, Residual Heat Removal +, Emergency Core Cooling System +, Decay Heat Removal +, Safety Relief Valve +  and Main Condenser +

Boric Acid +, Anticipated operational occurrence +, Hydrostatic +, Probabilistic Risk Assessment +  and Loss of Offsite Power +