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Letter, Report  and Miscellaneous

Canadian Nuclear Safety Commission +  and Federal Aviation Administration +

Oxygen +, Hydrogen +  and Lead +

10 CFR 50 Appendix A +, 10 CFR 50.46 +, 10 CFR 52 +, 10 CFR 2.335 +, 10 CFR 20.1201 +, 10 CFR 50.44 +, 10 CFR 52.47 +, 10 CFR 100.11 +, 10 CFR 20.1101 +, 10 CFR 52.54 +, 10 CFR 50.34#f2vii +, 10 CFR 50.34#f2viii +, 10 CFR 50.34#f2xxviii +, 10 CFR 50.34#f2xxvi +, 10 CFR 52.47#a2iv +, 10 CFR 20.1201#b +, 10 CFR 50.46#c1 +, 10 CFR 50.44#c3 +  and 10 CFR 50.44#c4 +

Advisory Committee on Reactor Safeguards +  and Committee To Review Generic Requirements +

SECY-98-144 +, SECY-90-377 +, SECY-91-229 +, SECY-18-0099, NuScale Power Exemption Request from 10 CFR Part 50, Appendix a, General Design Criterion 27, Combined Reactivity Control Systems Capability +, NRC-2009-0196 +, RAIO-0518-59925, LLC Response to NRC Request for Additional Information No. 445 (Erai No. 9255) on the NuScale Design Certification Application +, SECY-19-0079, Staff Approach to Evaluate Accident Source Terms for the Nuscale Power Design Certification Application +, NRC-2017-0029 +, SECY-34-302 +, SECY-21-0004, Rulemaking: Proposed Rule: Environmental Assessment: Response to SRM-SECY-21-0004 NuScale Small Modular Reactor Design Certification +, RAIO-0618-60459, LLC Supplemental Response to NRC Request for Additional Information No. 63 (Erai No. 8882) on the NuScale Design Certification Application +, SECY-19-0036, SRM-SECY-19-0036: Application of the Single Failure Criterion to NuScale Power LLCs Inadvertent Actuation Block Valves +, RAIO-0118-58186, LLC Supplemental Response to NRC Request for Additional Information No. 71 (Erai No. 8889) on the NuScale Design Certification Application +, COMSECY-14-0037, Enclosure 3 - Non-Concurrence Process Record for NCP-2014-010 +  and SECY-18-0049, Enclosure 1 -Draft-Management Directive and Handbook 8.4, Management of Backfitting, Issue Finality, and Information Collection +

ML18136A850 +, ML18351A145 +, RAIO-0518-59925, LLC Response to NRC Request for Additional Information No. 445 (Erai No. 9255) on the NuScale Design Certification Application +, ML20029E958 +, ML19149A308 +, ML19204A277 +, ML003699802 +, ML20211M386 +, ML090060320 +, ML20268C271 +, RAIO-0618-60459, LLC Supplemental Response to NRC Request for Additional Information No. 63 (Erai No. 8882) on the NuScale Design Certification Application +  and RAIO-0118-58186, LLC Supplemental Response to NRC Request for Additional Information No. 71 (Erai No. 8889) on the NuScale Design Certification Application +

Bergman T +  and NuScale +

GDC 35 +, GDC 27 +  and GDC 19, Control room +

ML21050A431 +, ML21050A431 +, ML21050A431 +, ML21050A431 +, ML21050A431 +, ML21050A431 +, ML21050A431 +, ML21050A431 +, ML21050A431 +, ML21050A431 +, ML21050A431 +  and ML21050A431 +

0.00509 d (0.122 hours, 7.275132e-4 weeks, 1.6742e-4 months)  +, 9.490741e-4 d (0.0228 hours, 1.35582e-4 weeks, 3.1201e-5 months)  +, 8.333333e-4 d (0.02 hours, 1.190476e-4 weeks, 2.7396e-5 months)  +  and 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +

NRC-2009-0196 +  and NRC-2017-0029 +

NUREG-1736 +, NUREG-1718 +, NUREG-1503, Supplement 2, Final Safety Evaluation Report Related to the Certification of the Advanced Boiling Water Reactor Design +, NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +  and NUREG-0660, 04-17-80 NUREG-0660 NRC Action Plans Developed as a Result of the TMI-2 Accident, Draft 3 +

ESP +  and Emergency Plan +

RAIO-0518-59925, LLC Response to NRC Request for Additional Information No. 445 (Erai No. 9255) on the NuScale Design Certification Application +, RAIO-0618-60459, LLC Supplemental Response to NRC Request for Additional Information No. 63 (Erai No. 8882) on the NuScale Design Certification Application +  and RAIO-0118-58186, LLC Supplemental Response to NRC Request for Additional Information No. 71 (Erai No. 8889) on the NuScale Design Certification Application +

Regulatory Guide 1.183 +, Regulatory Guide 1.7 +, Regulatory Guide 1.232 +  and Regulatory Guide 1.233 +

SECY-98-144 +, SECY-90-377 +, SECY-91-229 +, SECY-18-0099, NuScale Power Exemption Request from 10 CFR Part 50, Appendix a, General Design Criterion 27, Combined Reactivity Control Systems Capability +, SECY-19-0079, Staff Approach to Evaluate Accident Source Terms for the Nuscale Power Design Certification Application +, SECY-34-302 +, SECY-21-0004, Rulemaking: Proposed Rule: Environmental Assessment: Response to SRM-SECY-21-0004 NuScale Small Modular Reactor Design Certification +, SECY-19-0036, SRM-SECY-19-0036: Application of the Single Failure Criterion to NuScale Power LLCs Inadvertent Actuation Block Valves +  and SECY-18-0049, Enclosure 1 -Draft-Management Directive and Handbook 8.4, Management of Backfitting, Issue Finality, and Information Collection +

1x10-6 +, 1x10-7 +, 1x10-4 +, 1x10-5 +, 3E-10 +, 2x10-6 +, 5x10-7 +, 1x10-9 +  and 3x10-10 +

Washington +  and New York +

Steam Generator +  and Decay Heat Removal +

Office of Nuclear Reactor Regulation +  and Document Control Desk +

Probabilistic Risk Assessment +, Design basis earthquake +, Exemption Request +, Earthquake +, Backfit +, Fatality +, Control Room Habitability +  and Pre-application +