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ML19179A135 +
10 CFR 50 Appendix R +, 10 CFR 20 +, 10 CFR 50.48 +, 10 CFR 100 +, 10 CFR 50 +, 10 CFR 51 +, 10 CFR 50.69 +, 10 CFR 50.90 +, 10 CFR 51.22 +, 10 CFR 73.21 +, 10 CFR 50.46a#b +, 10 CFR 50 Appendix B Criterion VI +, 10 CFR 50.69#e +, 10 CFR 50.69#c1 +, 10 CFR 50.69#b +, 10 CFR 50.69#c1iv +, 10 CFR 50.69#c +, 10 CFR 50.69#c1ii +, 10 CFR 50.69#d2i +, 10 CFR 50.54#f +, 10 CFR 50.54#p +, 10 CFR 50.69#a +, 10 CFR 50.49#iv +, 10 CFR 50.69#i +, 10 CFR 50.69#c2 +, 10 CFR 50.69#f +, 10 CFR 5#b +, 10 CFR 73.55#51 +, 10 CFR 50.55a#vi +, 10 CFR 51.22#b +...
Regulatory Guide 1.200 +, Regulatory Guide 1.174 +, ML090930246 +, ML063550238 +, ML090970525 +, ML17079A427 +, ML17086A431 +, ML14365A203 +, ML061090627 +, ML052910035 +, ML12215A425 +, CNL-17-010, Submittal of Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors (SQN-TS-17-06) +, ML17062A466 +, ML17031A269 +, ML19179A135 +, ML19015A419 +, ML152388460 +, ML091310111 +, CNL-19-002, Response to Request for Additional Information Regarding Application to Modify Sequoyah Nuclear Plant Units 1 and 2, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, + and L-88-020, GL-88-020, Supplement 4, Individual Plant Examinations of External Events for Severe Accident Vulnerabilities - 10 CFR 50.54(f) +
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September 18, 2019 +
IR 05000327/2017001 +, CNL-17-010, Submittal of Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors (SQN-TS-17-06) + and CNL-19-002, Response to Request for Additional Information Regarding Application to Modify Sequoyah Nuclear Plant Units 1 and 2, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, +
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06:37:30, 5 January 2025 +
NUMARC 91-06 + and NUMARC 96-01 +
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-1407, Forwards Staff Evaluation of Millstone Unit 3,individual Plant Exam of External Events Submitted on 911223 Re Response to GL 88-20 .Util Capable of Identifying Severe Accidents & Vulnerabilites & Met GL 88-20,Suppl 4 + and NUREG-1232, Forwards Safety Evaluation Accepting Improvement Plan for Emergency Diesel Generators Transient Voltage Response.Mods Remain Scheduled by TVA for Completions Prior to Restart of Unit 1,Cycle 4 Refueling Outage +
55 +
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Approval +
September 18, 2019 +
Issuance of Amendment Nos. 346 and 340, Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors +
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