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10 CFR 2.309 +, 10 CFR 51.22 +, 10 CFR 2.302#g +, 10 CFR 50.91#a +, 10 CFR 2.309#c1i +, 10 CFR 2.315#c +, 10 CFR 51.22#b +  and 10 CFR 50.92#c +

05000171  +, 05000219  +, 05000220  +, 05000244  +, 05000249  +, 05000254  +, 05000265  +, 05000266  +, 05000269  +, 05000270  +, 05000272  +, 05000277  +, 05000287  +, 05000289  +, 05000301  +, 05000311  +, 05000317  +, 05000318  +, 05000320  +, 05000324  +, 05000325  +, 05000336  +, 05000338  +, 05000339  +, 05000348  +, 05000352  +, 05000353  +, 05000364  +, 05000369  +, 05000370  +...

ML12326A805 +, ML100620847 +, ML15153A282 +, ML15141A058 +, ML15167A456 +, ML15090A584 +, ML15128A352 +, ML15198A147 +, ML15175A438 +, ML15161A380 +, ML15181A179 +, ML15187A326 +, RIS 2003-18, Use of Nuclear Energy Institute (NEI) 99-01, Methodology for Development of Emergency Action Levels, Revision 4, Dated January 2003 +, ML15191A175 +, ML15195A201 +, ML15180A334 +, ML15187A011 +, ML15187A186 +, ML15161A121 +, ML15159A602 +, ML15159A617 +, ML15159A632 +, ML15170A055 +, ML15187A127 +, ML15174A227 +, ML15133A144 +, ML15153A230 +, ML15176A703 +, ML15131A445 +, ML15187A424 +...

72 FR 49139 +, 79 FR 2700 +, 80 FR 30100 +, 79 FR 61661 +, 80 FR 27197 +, 79 FR 77044 +, 80 FR 45559 +, 79 FR 64227 +, 79 FR 70212 +, 80 FR 30099 +, 80 FR 41095 +, 80 FR 41097 +, 80 FR 22224 +, 79 FR 67201 +, 80 FR 11475 +, 79 FR 55511 +, 80 FR 25719 +, 79 FR 42548 +, 79 FR 73110 +, 79 FR 67203 +, 79 FR 73111 +, 80 FR 13912 +, 80 FR 11492 +, 79 FR 61663 +  and 80 FR 17105 +

Division of Operating Reactor Licensing +  and Lund A +

ML15218A625 +, ML15218A625 +, ML15218A625 +, ML15218A625 +, ML15218A625 +, ML15218A625 +, ML15218A625 +, ML15218A625 +, ML15218A625 +, ML15218A625 +, ML15218A625 +, ML15218A625 +, ML15218A625 +, ML15218A625 +, ML15218A625 +, ML15218A625 +, ML15218A625 +, ML15218A625 +, ML15218A625 +  and ML15218A625 +

NEI 99-01, SNC Slides - SNC Fleet - Pre-Submittal Meeting - LAR for EAL Scheme Change to NEI 99-01 Rev 7 +  and NEI 94-01, License Amendment Request Supplement Pursuant to 10 CFR 50.90: Adoption of NEI 94-01, Revision 2-A, and Extension of Primary Containment Integrated Leakage Rate Test Interval to Fifteen (15) Years +

Louise Lund +, Carol Gallagher +, Cindy Bladey +, Shana Helton +  and Sandra Figueroa +

ML15218A625 +  and ML15218A625 +

SR-3.8.1.2 +  and SR-4.7.1.2.1 +

Millstone +, Calvert Cliffs +, Dresden +, Peach Bottom +, Salem +, Oconee +, Mcguire +, Nine Mile Point +, Catawba +, Harris +, Wolf Creek +, Point Beach +, Oyster Creek +, Byron +, Braidwood +, Susquehanna +, Summer +, Brunswick +, Limerick +, North Anna +, River Bend +, Ginna +, Vogtle +, Waterford +, Farley +, Clinton +, South Texas +, Comanche Peak +, Quad Cities +, McGuire +...

Hatch +, Calvert Cliffs +, Peach Bottom +, Salem +, Oconee +, Nine Mile Point +, Oyster Creek +, Byron +, Braidwood +, Brunswick +, Limerick +, North Anna +, Turkey Point +, Ginna +, Vogtle +, Farley +, Clinton +, Quad Cities +, NPF-68 +, LaSalle +, NPF-66 +, DPR-2 +, DPR-19 +, DPR-25 +, DPR-24 +, NPF-42 +, NPF-93 +  and NPF-94 +

Texas +, Pennsylvania +, Connecticut +, Kansas +, Georgia +, Illinois +, Maryland +, North Carolina +, Washington +, Alabama +, Virginia +, New Jersey +, South Carolina +, New York +, Wisconsin +, Florida +  and Louisiana +

Steam Generator +, Reactor Coolant System +, Reactor Protection System +, Emergency Diesel Generator +, Primary Containment Isolation System +, Auxiliary Feedwater +, Reactor Core Isolation Cooling +, Residual Heat Removal +, Automatic Depressurization System +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +  and Containment Spray +

TS-3.0.3 +, TS-3.4.3 +, TS-3.4.10 +, TS-4.0.5 +, TS-6.8.4.i +, TS-6.0 +, TS-6.9.1 +, TS-3.7.18 +, TS-6.8.3.j +  and TS-3.8.3.j +

TSTF-426 +, TSTF-523 +  and TSTF-510 +

Cyber Security +, Incorporated by reference +, Integrated leak rate test +, Exemption Request +  and Gas accumulation +