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ANSI 18.1 +, ANSI N42.18-2004 +, ANSI/ANS 18.1-1999 +, ANSI/ANS 55.4-1993 +, ANSI/ANS 40.37-2009 +, ANSI N42.18 - 2004 +, ANSI/ANS-55.4 +, ANSI/ANS-40.37-2009 +, ANSI/ANS-55.1-1992 +  and ANSI/ANS-40.37 +

ASME Section III +, ASME Section IX +, ASME Section II +  and ASME Section VIII +

Boron +, Iodine +, Cesium +, Rubidium +, Gadolinium +, Krypton +, Nitrogen +, Carbon +, Oxygen +, Hydrogen +, Xenon +, Lithium +, Argon +  and Antimony +

10 CFR 20 +, 10 CFR 50 +, 10 CFR 20 Appendix B +, 10 CFR 71 +, 10 CFR 61 +, 10 CFR 2.390 +, 10 CFR 20.1201 +, 10 CFR 20.1202 +, 10 CFR 20.1301 +, 10 CFR 20.1302 +, 10 CFR 20.1406 +, 10 CFR 20.2006 +, 10 CFR 20.2007 +, 10 CFR 20.2108 +, 10 CFR 20 Appendix G +, 10 CFR 50.65 +, 10 CFR 50 Appendix I +, 10 CFR 61.55 +, 10 CFR 61.56 +, 10 CFR 71 Appendix A +, 10 CFR 50.36a +, 10 CFR 50.34a +, 10 CFR 50.34#a +, 10 CFR 50.34#f2xvii +, 10 CFR 50.34#f2xxvii +, 10 CFR 20.1101#b +  and 10 CFR 20.1301#e +

Drawing 11.2-36 +, Drawing 11.2-37 +, Drawing 11.2-38 +, Drawing 11.2-39 +, Drawing 11.2-40 +, Drawing 11.2-41 +, Drawing 11.2-42 +, Drawing 11.2-43 +, Drawing 11.2-44 +, Drawing 11.2-45 +, Drawing 11.3-27 +, Drawing 11.3-28 +  and Drawing 11.4-23 +

Bergman T +  and NuScale +

GDC 61 +, GDC 60 +, GDC 64 +, GDC 63 +, GDC 2, Design bases for protection against natural phenomena +  and GDC 3, Fire protection +

ML20197A405 +, ML20197A405 +, ML20197A405 +, ML20197A405 +, ML20197A405 +, ML20197A405 +, ML20197A405 +, ML20197A405 +  and ML20197A405 +

Tritium +, Cs-137 +, U-235 +, Kr-85 +, I-131 +, N-16 +, Nitrogen-16 +, C-14 +, Carbon-14 +  and H-3 +

NEI 08-08 +  and NEI 97-06, Steam Generator Conditioning Monitoring Report +

NUREG-1301, Amends 188 & 70 to Licenses DPR-66 & NPF-73,respectively, Revising App a TSs by Relocating Requirements of RETS & Solid Radwaste TSs from App a TSs to ODCM or to PCP in Accordance W/Gl 89-01 & NRC Rept NUREG-1301 +, 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 +  and NUREG-0133, Safety Evaluation Accepting Licensee Rev 3 to ODCM for Plant Through Temporary Change 4.Rev Meets Criteria of NUREG-0133 & Other Guidance. Guidance +

Regulatory Guide 1.97 +, Regulatory Guide 1.45 +, Regulatory Guide 1.143 +, Regulatory Guide 1.21 +, Regulatory Guide 1.109 +, Regulatory Guide 8.8 +, Regulatory Guide 8.10 +, Regulatory Guide 1.54 +, Regulatory Guide 4.21 +, Regulatory Guide 1.140 +, Regulatory Guide 1.112 +  and Regulatory Guide 1.110 +

1E-6 +, 1E-8 +, 1E-5 +, 1E-4 +, 1E-7 +, 1E-9 +, 3E-7 +, 4E-5 +, 5E-8 +, 1E-2 +, 3E-10 +, 07-07-09A +, 07-07-10A +  and 0A-BPD-TNK-000 +

Washington +  and New York +

Steam Generator +, Reactor Coolant System +, Feedwater +, Main Turbine +, Emergency Response Data System +, HVAC +, Reactor Building Ventilation +, Circulating Water System +, Emergency Core Cooling System +, Main Steam Line +, Safety Relief Valve +, Main Condenser +, Main Steam +  and Turbine Gland Sealing System +

Safe Shutdown +, Boric Acid +, Packing leak +, Grab sample +, Offsite Dose Calculation Manual +, Anticipated operational occurrence +, Process Control Program +, Fuel cladding +, Pressure Boundary Leakage +  and Control Room Habitability +