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TEXT-SAFETY REPORT  and COMMISSION PAPER

Atomic Energy Act of 1954 +  and National Environmental Policy Act of 1969 +

Carbon +, Hydrogen +, Lead +  and Tin +

10 CFR 50 +, 10 CFR 50.59 +, 10 CFR 52 +, 10 CFR 2 +, 10 CFR 51 +, 10 CFR 2.206 +, 10 CFR 50.34 +, 10 CFR 50.62 +, 10 CFR 50.90 +, 10 CFR 50.109 +, 10 CFR 52.47 +, 10 CFR 52.55 +, 10 CFR 52.79 +, 10 CFR 52.99 +, 10 CFR 2.715 +, 10 CFR 2.760a +, 10 CFR 2.780#a +, 10 CFR 2.715a +, 10 CFR 52.54 +, 10 CFR 52.97 +, 10 CFR 50.34#f2vii +, 10 CFR 50.34#f +, 10 CFR 50.34#a1 +, 10 CFR 50.34#a1iiD +, 10 CFR 50.34#50 +, 10 CFR 50.34#f2iv +, 10 CFR 50.34#f2xxviii +, 10 CFR 50.34#f1i +, 10 CFR 50.62#c1 +, 10 CFR 52.47#a +...

SECY-90-377 +, SECY-96-077 +, SECY-92-381 +, COMSECY-98-025 +, SECY-98-267 +, SECY-99-101 +  and NRC 18 +

63 FR 41872 +, 62 FR 25800 +, 61 FR 65157 +, 61 FR 65158 +, 61 FR 65160 +  and 63 FR 48772 +

Travers W +  and NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO) +

GDC 17, Electric power systems +  and GDC 19, Control room +

ML20206F707 +, ML20206F707 +, ML20206F707 +, ML20206F707 +, ML20206F707 +, ML20206F707 +, ML20206F707 +, ML20206F707 +  and ML20206F707 +

NUREG/BR-0058 +, NUREG/BR-0184 +, NUREG/CR-5562 +, NUREG/CR-5567 +, NUREG-1462, Notification of 921209 Meeting w/ABB-C-E in Rockville,Md to Discuss Status of Closure of Open Items in Draft SER for Sys 80+ (NUREG-1462).Meeting Agenda Encl +, NUREG-1503, Supplement 2, Final Safety Evaluation Report Related to the Certification of the Advanced Boiling Water Reactor Design +, NUREG-1150, Weekly Info Rept for Wk Ending 890922 +, NUREG-1465, Provides Commission W/Results & Findings of Evaluation of Impact of Implementing Revised Source Term Described in NUREG-1465, Accident Source Terms for Light-Water Npps, for Operating Reactors +, NUREG-1512, Provides Advisory Committee on Reactor Safeguards with Attached Suppl to AP600 FSER for Consideration.Suppl FSER Documents Staff Review of Changes to AP600 Design Documentation Since Issuance of FSER NUREG-1512 +, NUREG-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting +  and NUREG-0775, Responds to .Earlier Ltrs Commenting on Des Were Responded to in FES,NUREG-0775.Status of Proceedings Re Permanent Disposal of High Level Waste Discussed +

CP +  and ESP +

SECY-90-377 +, SECY-96-077 +, SECY-92-381 +, SECY-98-267 +  and SECY-99-101 +

Washington +  and Maryland +

Steam Generator +, Reactor Coolant System +, Feedwater +, Secondary containment +, Auxiliary Feedwater +, Reactor Pressure Vessel +, Residual Heat Removal +, Decay Heat Removal +, Containment Spray +  and Emergency Feedwater System +

Anticipated operational occurrence +, Probabilistic Risk Assessment +, Squib +, Incorporated by reference +, B.5.b +, Exemption Request +, Earthquake +, Backfit +  and Control Room Habitability +