Browse wiki

Boron +, Copper +, Carbon +, Oxygen +, Sodium +, Hydrogen +, Lead +, Lithium +, Aluminum +, Silicon +, Calcium +, Gold +  and Zinc +

10 CFR 50.46 +, 10 CFR 50 +, 10 CFR 50.59 +, 10 CFR 50.65 +  and 10 CFR 50.54#f +

L-2005-181 +, L-2005-145 +, L-2007-194 +, L-2008-138, Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors. +, L-2008-033, Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors. +, L-2007-155, Request for Extension of Completion Date of the Generic Letter 2004-02 Actions +, L-2006-169 +, L-2003-201, NRC Bulletin 2003-01 Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized Water Reactors +, L-98-272, Comment on Draft Reg Guide DG-4005, Preparation of Suppl Environ Repts for Applications to Renew Nuclear Power Plant Operating Licenses +  and L-2005-034, Cycle 15 Core Operating Limits Report +

05000250  +  and 00250  +

ML073110389 +, ML073520891 +, ML071060091 +, ML0726007425 +, ML063460258 +, ML073320176 +, ML080710429 +, ML050670429 +, ML052490339 +, ML052080038 +, ML073450338 +, ML073610401 +, ML060860257 +, ML060370438 +, ML080090147 +  and ML051520202 +

Jefferson W +  and NextEra Energy +

GDC 38 +, GDC 41 +  and GDC 35 +

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 +

ML081960386 +, ML081960386 +, ML081960386 +, ML081960386 +, ML081960386 +, ML081960386 +, ML081960386 +, ML081960386 +, ML081960386 +, ML081960386 +, ML081960386 +, ML081960386 +, ML081960386 +, ML081960386 +, ML081960386 +, ML081960386 +, ML081960386 +, ML081960386 +, ML081960386 +, ML081960386 +, ML081960386 +, ML081960386 +, ML081960386 +, ML081960386 +, ML081960386 +, ML081960386 +  and ML081960386 +

2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +, 1.157407e-4 d (0.00278 hours, 1.653439e-5 weeks, 3.805e-6 months)  +, 5.555556e-4 d (0.0133 hours, 7.936508e-5 weeks, 1.8264e-5 months)  +, 0.00833 d (0.2 hours, 0.00119 weeks, 2.7396e-4 months)  +  and 1.157407e-5 d (2.777778e-4 hours, 1.653439e-6 weeks, 3.805e-7 months)  +

L-2005-181 +, L-2005-145 +, L-2007-194 +, L-2008-138, Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors. +, L-2008-033, Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors. +, L-2007-155, Request for Extension of Completion Date of the Generic Letter 2004-02 Actions +, L-2006-169 +, L-2003-201, NRC Bulletin 2003-01 Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized Water Reactors +, L-98-272, Comment on Draft Reg Guide DG-4005, Preparation of Suppl Environ Repts for Applications to Renew Nuclear Power Plant Operating Licenses +  and L-2005-034, Cycle 15 Core Operating Limits Report +

General Electric +  and Westinghouse +

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/CR-6808 +, NUREG/CR-6916 +, NUREG/CR-6913 +, NUREG-1861 +, 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.. +

AOP +, Emergency Operating Procedure +  and TP-3 +

Regulatory Guide 1.82 +  and Regulatory Guide 1.1 +

Maryland +  and Florida +

Steam Generator +, Reactor Coolant System +, Feedwater +, Primary containment +, Shutdown Cooling +, Residual Heat Removal +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam +  and Containment Spray +

Document Control Desk +  and Office of Nuclear Reactor Regulation +

Boric Acid +, Ultimate heat sink +, Mission time +, Coatings +, Earthquake +, Fuel cladding +  and Scaffolding +

WCAP-16406-P +, WCAP-16793 +, WCAP-16793-NP +, WCAP-16530-NP +, WCAP-16530 +  and WCAP-16785-NP +

WCAP-16406-P +, WCAP-16793 +, WCAP-16793-NP +, WCAP-16530-NP +, WCAP-16530 +  and WCAP-16785-NP +