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Lead +, Aluminum +, Silicon +  and Zinc +

10 CFR 50.46 +, 10 CFR 50.59 +, 10 CFR 2.390 +, 10 CFR 50.65 +, 10 CFR 50.65#a4 +, 10 CFR 9.17#a4 +  and 10 CFR 2.390#b4 +

NL-05-1633 +, NL-06-0279 +, NL-06-0753 +, NL-06-2055 +, NL-06-2686 +, NL-07-0090 +, NL-07-2367 +, NL-08-0670, Supplemental Response to NRC Generic Letter 2004-02 +, NL-07-1777, Supplemental Response to NRC Generic Letter 2004-02 +, NL-07-1969, Generic Letter 2004-02 Response Extension Request +, NL-06-1483, Response to NRC RAI on SNC Request for Extension for Completing Corrective Actions for GL 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors +, NL-06-1275, Request for Extension for Completing Corrective Actions for Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors +, NL-05-1264, Vogtle Electric Generating Plant, September 2005 Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors. +, NL-05-1207, Vogtle Electric Generating Plant, Response to a Request for Additional Information on NRC Bulletin 03-001, Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized Water Reactors - Revision 1 +, NL-05-0290, Response to GL-04-002 Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors. +, NL-04-2013, Response to a Request for Additional Information on NRC Bulletin 2003-01, Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized Water Reactors +, NL-03-1514, 60 Day Response to NRC Bulletin 2003-01 Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized Water Reactors for Joseph M. Farley Nuclear Plant & Vogtle Electric Generating Plant +, ND-3929 +  and ND-3923 +

05000424  +, 05000425  +, 00424  +, 00425  +, 00348  +  and 00364  +

EC-552 +  and EC-1905 +

David Jones +  and Southern Nuclear +

NRC Generic Letter 04-02 +  and NRC Generic Letter 97-04, Assurance of Sufficient Net Positive Suction Head for Emergency Core Cooling and Containment Heat Removal Pumps +

ML081640617 +, ML081640617 +, ML081640617 +, ML081640617 +, ML081640617 +, ML081640617 +, ML081640617 +, ML081640617 +, ML081640617 +, ML081640617 +, ML081640617 +, ML081640617 +, ML081640617 +, ML081640617 +, ML081640617 +, ML081640617 +, ML081640617 +, ML081640617 +, ML081640617 +, ML081640617 +, ML081640617 +, ML081640617 +, ML081640617 +, ML081640617 +, ML081640617 +, ML081640617 +, ML081640617 +, ML081640617 +, ML081640617 +, ML081640617 +...

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

ML073380100 +, ML032240030 +, ML060870274 +, ML061730462 +, ML072010369 +, ML073520145 +, ML073440044 +, ML073190577 +, ML072760379 +, ML063490324 +, ML062380003 +  and ML043240168 +

General Electric +  and Westinghouse +

ND-3929 +  and ND-3923 +

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 +

NL-05-1633 +, NL-06-0279 +, NL-06-0753 +, NL-06-2055 +, NL-06-2686 +, NL-07-0090 +, NL-07-2367 +, NL-08-0670, Supplemental Response to NRC Generic Letter 2004-02 +, NL-07-1777, Supplemental Response to NRC Generic Letter 2004-02 +, NL-07-1969, Generic Letter 2004-02 Response Extension Request +, NL-06-1483, Response to NRC RAI on SNC Request for Extension for Completing Corrective Actions for GL 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors +, NL-06-1275, Request for Extension for Completing Corrective Actions for Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors +, NL-05-1264, Vogtle Electric Generating Plant, September 2005 Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors. +, NL-05-1207, Vogtle Electric Generating Plant, Response to a Request for Additional Information on NRC Bulletin 03-001, Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized Water Reactors - Revision 1 +, NL-05-0290, Response to GL-04-002 Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors. +, NL-04-2013, Response to a Request for Additional Information on NRC Bulletin 2003-01, Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized Water Reactors +  and NL-03-1514, 60 Day Response to NRC Bulletin 2003-01 Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized Water Reactors for Joseph M. Farley Nuclear Plant & Vogtle Electric Generating Plant +

NUREG/CR-6773 +, NUREG/CR-3616 +, NUREG/CR-6808 +, NUREG/CR-6772 +, NUREG/CR-2791 +, NUREG/CR-6762 +, NUREG/CR-6916 +, 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 +, NUREG-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting +  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.. +

SR-3.5.4.2 +  and SR-3.5.4 +

Washington +  and Georgia +

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

TS-3.3.2 +  and TS-3.5.4 +

Document Control Desk +  and Office of Nuclear Reactor Regulation +

Safe Shutdown +, Mission time +, Fire Barrier +, Safe Shutdown Earthquake +, Coatings +, Operating Basis Earthquake +, Temporary Modification +, High Energy Line Break +, Foreign Material Exclusion +, Affidavit +, Manual Operator Action +  and Leak-Before-Break +

WCAP-16568-P +, WCAP-16406-P +, WCAP-16793 +, WCAP-16793-NP +, WCAP-16530-NP +, WCAP-16530 +  and WCAP-16710-P +

WCAP-16568-P +, WCAP-16406-P +, WCAP-16793 +, WCAP-16793-NP +, WCAP-16530-NP +, WCAP-16530 +  and WCAP-16710-P +