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Sodium +, Lead +, Silicon +  and Zinc +

10 CFR 50 Appendix A +, 10 CFR 50.46 +  and 10 CFR 50.54#f +

TXX-05162 +, TXX-05047 +  and TXX-05 162 +

05000445  +, 05000446  +, 00445  +  and 00446  +

Blevins M +, TXU Power +  and Madden F +

GDC 35 +  and GDC 4, Environmental and dynamic effects design bases +

NRC Generic Letter 04-02 +  and NRC Generic Letter 98-04, Potential for Degradation of the Emergency Core Cooling System and the Containment Spray System After a Loss-of-Coolant Accident Because of Construction and Protective Coating Deficiencies and Foreign Material in Containment +

ML052550052 +, ML052550052 +, ML052550052 +, ML052550052 +, ML052550052 +, ML052550052 +, ML052550052 +, ML052550052 +, ML052550052 +, ML052550052 +, ML052550052 +, ML052550052 +, ML052550052 +, ML052550052 +, ML052550052 +, ML052550052 +, ML052550052 +, ML052550052 +, ML052550052 +, ML052550052 +, ML052550052 +, ML052550052 +, ML052550052 +, ML052550052 +, ML052550052 +, ML052550052 +, ML052550052 +, ML052550052 +  and ML052550052 +

2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +, 5.787037e-5 d (0.00139 hours, 8.267196e-6 weeks, 1.9025e-6 months)  +  and 3.472222e-5 d (8.333333e-4 hours, 4.960317e-6 weeks, 1.1415e-6 months)  +

Westinghouse +  and General Electric +

NEI 04-07, Response to Request No. 2 in NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors. +  and NEI 02-01 +

NUREG-6224 +, NUREG-0797, Summary of Meeting on 890905 in Rockville,Md to Discuss Ground Motion Estimates for Criner Tectonic Structure of Southern Oklahoma Aulacongen in Wichita Tectonic Province, Per Section 2.5.2 of Fsar.Viewgraphs Encl +, NUREG/CR-6369, Forwards Second Transmittal of NUREG/CR-6369, Drywell Debris Transport Study, & Suppls . Pages 2-12,3-8 & C-19 of Incoming Submittal Not Included +  and NUREG/CR-6224, Requests That Encl Documents Be Available Through NRC PDR & Central Files.Documents Provided Background or Ref Info for Resolution of BWR Strainer Blockage Issue,As Ref by Draft NUREG/CR-6224, Parametric Study of Potential for Bwr.. +

TAC:MC4676 +  and TAC:MC4776 +

Washington +  and Texas +

Steam Generator +, Reactor Coolant System +, Feedwater +, Emergency Core Cooling System +, Main Steam Line +, Main Steam +  and Containment Spray +

TS-3.6.7 +  and TS-3.5.6 +

TXX-05162 +, TXX-05047 +  and TXX-05 162 +

Document Control Desk +  and Office of Nuclear Reactor Regulation +

Mission time +, Fire Barrier +, Coatings +, High Energy Line Break +, Hemyc +, Exemption Request +, Scaffolding +  and Backfit +