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Boron +, Iron +, Copper +, Nitrogen +, Carbon +, Sodium +, Lead +, Lithium +, Aluminum +, Silicon +, Calcium +, Titanium +, Zinc +  and Tin +

10 CFR 50 Appendix A +, 10 CFR 50.46 +, 10 CFR 50.59 +, 10 CFR 50.7 +, 10 CFR 50.65 +, 10 CFR 50.54#f +  and 10 CFR 50.71#e +

L-08-036, Supplemental Response to GL-04-002, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors +, L-08-054, Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors - Request for Extension of Completion Date for Corrective Actions +, L-06-020, Revised Commitment Dates Relevant to Firstenergy Nuclear Operating Company Correspondence to the NRC, L-06-020, Dated April 3, 2006 +, L-07-519 +, L-98-21 +, L-07-51 +, L-05-146, Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors. +, L-05-034, Response to GL-04-002, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors. +, L-08-035, Supplemental Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized - Water Reactors +, L 519 +, L-087035 +, L-98-217, Forwards 120-day Response to NRC GL 98-04, Potential for Degradation of ECCS & CSS After LOCA Because of Construction & Protective Coating Deficiencies & Foreign Matl in Containment +  and SECY-06-0078, Approval of Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors Extension Request +

05000334  +, 05000412  +, 00334  +  and 00412  +

Sena P +  and FirstEnergy +

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 +

ML080660597 +, ML080660597 +, ML080660597 +, ML080660597 +, ML080660597 +, ML080660597 +, ML080660597 +, ML080660597 +, ML080660597 +, ML080660597 +, ML080660597 +, ML080660597 +, ML080660597 +, ML080660597 +, ML080660597 +, ML080660597 +, ML080660597 +, ML080660597 +, ML080660597 +, ML080660597 +, ML080660597 +, ML080660597 +, ML080660597 +, ML080660597 +, ML080660597 +, ML080660597 +, ML080660597 +, ML080660597 +, ML080660597 +, ML080660597 +...

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 8.101852e-5 d (0.00194 hours, 1.157407e-5 weeks, 2.6635e-6 months)  +

NRC Inspection Manual 4665 +  and NRC Inspection Manual 4666 +

L-08-036, Supplemental Response to GL-04-002, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors +, L-08-054, Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors - Request for Extension of Completion Date for Corrective Actions +, L-06-020, Revised Commitment Dates Relevant to Firstenergy Nuclear Operating Company Correspondence to the NRC, L-06-020, Dated April 3, 2006 +, L-07-519 +, L-98-21 +, L-07-51 +, L-05-146, Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors. +, L-05-034, Response to GL-04-002, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors. +, L-08-035, Supplemental Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized - Water Reactors +, L 519 +, L-087035 +  and L-98-217, Forwards 120-day Response to NRC GL 98-04, Potential for Degradation of ECCS & CSS After LOCA Because of Construction & Protective Coating Deficiencies & Foreign Matl in Containment +

ML060240146 +, ML061380273 +, L-05-140, Response to a Request for Additional Information (RAI Dtd August 2, 2005) in Support of License Amendment Request Nos. 302 and 173, Extended Power Uprate +  and L-08-035, Supplemental Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized - Water Reactors +

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-6772 +, NUREG/CR-2982 +, NUREG/CR-6877 +  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.. +

CH +, TOP +, CP-10 +  and CH-R-6A +

TAC:MC4665 +  and TAC:MB9554 +

0E-05 +, 1OE-05 +, 2BVS-60 +, 2BVS-634 +, 2BVS-939A +, 2DAS-LE222 +, 2BVS-1 +, 31f2-1 +, 31f4-2 +, 31f4-3 +, 1L-08-035 +, 1IRH-A-1 +, 2DAS-LE200 +, 2DAS-LS200 +, 2DAS-LS210 +  and 07-07-281 +

Beaver Valley +  and NPF-73 +

Illinois +, Washington +, Virginia +  and New Mexico +

Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Primary containment +, Reactor Pressure Vessel +, Residual Heat Removal +, Emergency Core Cooling System +, Main Steam Line +, Main Steam +  and Containment Spray +

Document Control Desk +  and Office of Nuclear Reactor Regulation +

Safe Shutdown +, Boric Acid +, Loop seal +, Mission time +, Safe Shutdown Earthquake +, Coatings +, Operating Basis Earthquake +, High Energy Line Break +, Foreign Material Exclusion +, Exemption Request +, Earthquake +, Commercial Grade +  and Scaffolding +

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

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