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Boron +, Iodine +, Copper +, Carbon +, Oxygen +, Sodium +, Hydrogen +, Lead +, Aluminum +, Calcium +, Zinc +  and Tin +

10 CFR 50.54#f +  and 10 CFR 3.4 +

L-98-277, Forwards Initial Response to NRC GL 98-04, Potential for Degradation of ECCS & CSS After LOCA Because of Construction & Protective Coating Deficiencies & Foreign Matl in Containment +, L-2009-179, Updated Supplemental Response to NRC Generic Letter (GL) 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors +, L-2009-180, Responses to NRCs Request for Additional Information on Generic Letter 2004-02 Supplemental Responses, Dated 02/27/2008 and 06/30/2008 +, L-2008-235, Request for Extension of the Completion Date of the St. Lucie Unit 1 NRC Generic Letter 2004-02 Actions +, L-2005-181 +, L-2008-137, 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-2008-037, Annual Report of Reactor Coolant Specific Activity Limits +, L-2008-030, 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 +  and L-2003-201, NRC Bulletin 2003-01 Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized Water Reactors +

05000335  +  and 00335  +

ML042360586 +, ML073520891 +, ML081840513 +, ML080650560 +, L-2008-235, Request for Extension of the Completion Date of the St. Lucie Unit 1 NRC Generic Letter 2004-02 Actions +  and ML082610690 +

Johnston G +  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 +

ML092170370 +, ML092170370 +, ML092170370 +, ML092170370 +, ML092170370 +, ML092170370 +, ML092170370 +, ML092170370 +, ML092170370 +, ML092170370 +, ML092170370 +, ML092170370 +, ML092170370 +, ML092170370 +, ML092170370 +  and ML092170370 +

6.944444e-5 d (0.00167 hours, 9.920635e-6 weeks, 2.283e-6 months)  +, 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)  +, 1.157407e-5 d (2.777778e-4 hours, 1.653439e-6 weeks, 3.805e-7 months)  +  and 0.00833 d (0.2 hours, 0.00119 weeks, 2.7396e-4 months)  +

NRC Inspection Manual 4710 +  and NRC Inspection Manual 471 +

L-98-277, Forwards Initial Response to NRC GL 98-04, Potential for Degradation of ECCS & CSS After LOCA Because of Construction & Protective Coating Deficiencies & Foreign Matl in Containment +, L-2009-179, Updated Supplemental Response to NRC Generic Letter (GL) 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors +, L-2009-180, Responses to NRCs Request for Additional Information on Generic Letter 2004-02 Supplemental Responses, Dated 02/27/2008 and 06/30/2008 +, L-2008-235, Request for Extension of the Completion Date of the St. Lucie Unit 1 NRC Generic Letter 2004-02 Actions +, L-2005-181 +, L-2008-137, 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-2008-037, Annual Report of Reactor Coolant Specific Activity Limits +, L-2008-030, 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 +  and L-2003-201, NRC Bulletin 2003-01 Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized Water Reactors +

ML082610690 +  and L-2008-235, Request for Extension of the Completion Date of the St. Lucie Unit 1 NRC Generic Letter 2004-02 Actions +

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/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.. +

Emergency Operating Procedure +  and AOP +

Regulatory Guide 1.82 +  and Regulatory Guide 1.1 +

3c-1 +, 3c-2 +, 3f-1 +  and 07-25-151 +

Florida +  and Maryland +

Steam Generator +, Reactor Coolant System +, Feedwater +, Primary containment +, Shutdown Cooling +, Reactor Pressure Vessel +, 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 +, High Energy Line Break +, Earthquake +, Fuel cladding +, Scaffolding +, Leak-Before-Break +  and Restart +

WCAP-16406-P +, WCAP-16793 +, WCAP-16793-NP +, WCAP-16530-NP +, WCAP-16530 +, WCAP-16785-NP +, WCAP-16710-P +  and WCAP-16851-P +

WCAP-16406-P +, WCAP-16793 +, WCAP-16793-NP +, WCAP-16530-NP +, WCAP-16530 +, WCAP-16785-NP +, WCAP-16710-P +  and WCAP-16851-P +