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Meeting Briefing Package/Handouts, Standard Review Plan  and Standard Review Plan Update

ASME Section I +, ASME Section IV +, ASME Section II +  and ASME Section VI +

Hydrogen +  and Lead +

10 CFR 50 +, 10 CFR 50 Appendix B +, 10 CFR 52 +, 10 CFR 50.44 +, 10 CFR 50.69 +, 10 CFR 51.45 +, 10 CFR 51.55 +, 10 CFR 51.52 +, 10 CFR 50.69#b2 +, 10 CFR 50.34#f +, 10 CFR 50.34#a +, 10 CFR 50.34#b +, 10 CFR 50.34#b4 +, 10 CFR 50.34#a14 +, 10 CFR 50.34#b13 +, 10 CFR 50.34#a4 +, 10 CFR 50.34#a1i +, 10 CFR 50.34#a3ii +, 10 CFR 50.34#a3iii +, 10 CFR 50.34#a3i +, 10 CFR 50.34#f2xxv +, 10 CFR 50.34#f1i +, 10 CFR 50.36#c2iiD +, 10 CFR 50.34#a1ii +, 10 CFR 50.34#f2ix +, 10 CFR 52.47#a1 +, 10 CFR 52.47#a8 +, 10 CFR 52.47#a2 +, 10 CFR 52.47#b2 +, 10 CFR 52.47#a23 +...

Emergency Preparedness +, Initiating Events +  and Mitigating Systems +

SECY-93-087 +, SECY-90-016 +, SECY-96-128 +, SECY-97-044 +  and NRC-2009-0196 +

Regulatory Guide 1.200 +, Regulatory Guide 1.174 +, Regulatory Guide 1.7 +, ML003708056 +, ML003707849 +, ML003708021 +, ML003707885 +, ML15089A068 +, ML103470210 +, ML100491233 +, ML080570048 +, ML093200703 +, ML003708224 +, ML003708192 +, ML003708316 +, ML003708232 +, ML071700652 +  and ML081430087 +

60 FR 42622 +, 51 FR 28044 +, 52 FR 34884 +, 50 FR 32138 +, 50 FR 32128 +, 59 FR 35461 +, 72 FR 49365 +, 72 FR 49387 +, 72 FR 49380 +, 72 FR 49443 +  and 72 FR 49388 +

NRC Generic Letter 88-17, Loss of Decay Heat Removal +  and NRC Generic Letter 89-01, Implementation of Programmatic and Procedural Controls for Radiological Effluent Technical Specifications +

ML22041A527 +, ML22041A527 +, ML22041A527 +, ML22041A527 +, ML22041A527 +, ML22041A527 +, ML22041A527 +  and ML22041A527 +

DC/COL-ISG-20 +, DC/COL-ISG-020 +, DC/COL-ISG-003 +  and DC/COL-ISG-024 +

Information Notice 91-41 +  and Information Notice 88-36 +

NUREG-1793 +, NUREG-1855, Summary of 7/18/19 Public Meeting with Nuclear Energy Institute to Discuss Application of NUREG-1855, Guidance on the Treatment of Uncertainties Associated with PRAs in Risk-Informed Decision Making +, 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-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/CR-4461, Requests Assistance in Achieving Mod of Reg Guide 1.76 Re Tornado Design Criteria,Based on NRC Recommendation in NUREG/CR-4461 & Initial Response to EPRI Declining to Adopt ANSI/ANS-2.3-1980 Std +, NUREG-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting +  and NUREG/CR-6850, To Propose an Alternative Methodology to Distribute Transient Ignition Frequencies (Bins 3, 5, 6, 7, 11, 24, 25, 31, 36, 37) That Contains a More Structured Approach to Accounting for Influence Factor Variations within a Pau +

RAP +  and CP +

Regulatory Guide 1.200 +, Regulatory Guide 1.174 +, Regulatory Guide 1.70 +, Regulatory Guide 1.7 +, Regulatory Guide 1.216 +, Regulatory Guide 1.206 +, Regulatory Guide 1.178 +  and Regulatory Guide 1.221 +

SECY-93-087 +, SECY-90-016 +, SECY-96-128 +  and SECY-97-044 +

Washington +  and New York +

Steam Generator +, Reactor Coolant System +, Residual Heat Removal +  and Decay Heat Removal +

Safe Shutdown +, High winds +, Ultimate heat sink +, Mission time +, Offsite Dose Calculation Manual +, Fire Barrier +, Probabilistic Risk Assessment +, Squib +, Process Control Program +  and Earthquake +