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List of results

• BSEP 07-0102, ANP-2661 (Np), Revision 0, Brunswick Nuclear Plant New Fuel Storage Vault Criticality Safety Analysis for ATRIUM-10 Fuel  + (ANP-2661 (Np), Revision 0, Brunswick Nuclear Plant New Fuel Storage Vault Criticality Safety Analysis for ATRIUM-10 Fuel)
• ML092150054  + (ANP-2693(NP), Revision 0, Loss of Forced Reactor Coolant Flow Analysis for Harris Nuclear Plant, Unit 1, Enclosure 4 to Serial: HNP-09-068)
• ML081080338  + (ANP-2695(NP), Rev 0, Enclosure 3, Sequoyah Nuclear Plant Unit 1, Realistic Large Break Loss of Coolant Accident Analysis)
• ML090080385  + (ANP-2789(NP), Revision 0, Atrium Tm 10XM Lead Test Assemblies for LaSalle Unit 2)
• ML090400518  + (ANP-2796(NP), Rev. 0, Zircaloy-BWR Lead Use Channel Program at LaSalle County Generating Station)
• ML093350658  + (ANP-2821(NP), Rev. 0, Browns Ferry Unit 1 Thermal-Hydraulic Design Report for ATRIUM-10 Fuel Assemblies (105% Oltp))
• ML101160154  + (ANP-2821(NP), Revision 0, Browns Ferry Unit 1 Thermal-Hydraulic Design Report for ATRIUM-10 Fuel Assemblies (105% Oltp))
• ML093350101  + (ANP-2834(NP), Revision 0, Calvert Cliffs Nuclear Plant Unit 1 Cycle 21 & Unit 2 Cycle 19 Realistic Large Break LOCA Summary Report, Enclosure 4)
• RS-10-102, ANP-2843Q1NP, Revision 0, LaSalle Unit 2 Nuclear Power Station Spent Fuel Storage Pool Criticality Safety Analysis with Neutron Absorbing Inserts and Without Boraflex - Rais  + (ANP-2843Q1NP, Revision 0, LaSalle Unit 2 Nuclear Power Station Spent Fuel Storage Pool Criticality Safety Analysis with Neutron Absorbing Inserts and Without Boraflex - Rais)
• ML093350659  + (ANP-2859(NP), Rev. 0, Browns Ferry Unit 1 Cycle 9 Fuel Cycle Design (105% Oltp))
• ML101160152  + (ANP-2859(NP), Revision 0, Browns Ferry Unit 1 Cycle 9 Fuel Cycle Design (105% Oltp))
• NL-15-169, ANP-2860NP Revision 2, Supplement 2, Browns Ferry Unit 1 - Summary of Responses to Request for Additional Information, Extension for Use of Atrium 10XM Fuel for Extended Power Uprate.  + (ANP-2860NP Revision 2, Supplement 2, Browns Ferry Unit 1 - Summary of Responses to Request for Additional Information, Extension for Use of Atrium 10XM Fuel for Extended Power Uprate.)
• ML15282A223  + (ANP-2860NP Revision 2, Supplement 2, Browns Ferry Unit 1 - Summary of Responses to Request for Additional Information, Extension for Use of Atrium 10XM Fuel for Extended Power Uprate)
• ML13070A317  + (ANP-2860NP, Revision 2, Browns Ferry Unit 1 - Summary of Response to Request for Additional Information, Supplement 1NP, Revision 0, Extension for Atrium 10XM)
• ML093350653  + (ANP-2863(NP), Rev. 0, Browns Ferry Unit 1 Cycle 9 Reload Safety Analysis for 105% Oltp)
• ML101160155  + (ANP-2863(NP), Revision 1, Browns Ferry Unit 1 Cycle 9 Reload Safety Analysis for 105% Oltp)
• ML093350657  + (ANP-2877NP, Rev. 0, Mechanical Design Report for Browns Ferry Unit 1 Reload BFE1-9 ATRIUM-10 Fuel Assemblies (105% Oltp))
• ML101160164  + (ANP-2877NP, Revision 0, Mechanical Design Report for Browns Ferry Unit 1 Reload BFR1-9 ATRIUM-10 Fuel Assemblies (105% Oltp))
• ML101160197  + (ANP-2903(NP), Rev. 0, St. Lucie Nuclear Plant Unit 1 EPU Cycle Realistic Large Break LOCA Summary Report with Zr-4 Fuel Cladding)
• L-2010-078, ANP-2903(NP), Rev. 0, St. Lucie Nuclear Plant Unit 1 EPU Cycle Realistic Large Break LOCA Summary Report with Zr-4 Fuel Cladding.  + (ANP-2903(NP), Rev. 0, St. Lucie Nuclear Plant Unit 1 EPU Cycle Realistic Large Break LOCA Summary Report with Zr-4 Fuel Cladding.)
• L-2011-206, ANP-2903(NP), Revision 1, St. Lucie Nuclear Plant, Unit 1 - EPU Cycle Realistic Large Break LOCA Summary Report with ZR-4 Fuel Cladding, Attachment 7  + (ANP-2903(NP), Revision 1, St. Lucie Nuclear Plant, Unit 1 - EPU Cycle Realistic Large Break LOCA Summary Report with ZR-4 Fuel Cladding, Attachment 7)
• L-2011-418, ANP-2903Q1(NP), Revision 0, St Lucie Nuclear Plant Unit 1 EPU Cycle Realistic Large Break LOCA Summary Report with Zr-4 Fuel Cladding  + (ANP-2903Q1(NP), Revision 0, St Lucie Nuclear Plant Unit 1 EPU Cycle Realistic Large Break LOCA Summary Report with Zr-4 Fuel Cladding)
• L-2012-072, ANP-2903Q2(NP), Rev 0, St. Lucie, Unit 1 - EPU Cycle Realistic Large Break LOCA Summary Report with Zr-4 Fuel Cladding, Attachment 3  + (ANP-2903Q2(NP), Rev 0, St. Lucie, Unit 1 - EPU Cycle Realistic Large Break LOCA Summary Report with Zr-4 Fuel Cladding, Attachment 3)
• ML101160183  + (ANP-2908(NP), Revision 0, Browns Ferry Units 1, 2, and 3 105% OLTP LOCA Break Spectrum Analysis)
• ML101160496  + (ANP-2915(NP), Rev. 1, Request for Additional Information - Calvert Cliffs Unit 2 Cycle 19 Fuel Rod Thermal Mechanical Inputs)

• BSEP 10-0071, ANP-2920(NP), Revision 0, Brunswick Unit 2 Cycle 20 Fuel Cycle Design  + (ANP-2920(NP), Revision 0, Brunswick Unit 2 Cycle 20 Fuel Cycle Design)

• BSEP 10-0093, ANP-2936(NP), Revision 0, Brunswick, Unit 2, Thermal-Hydraulic Design Report for Atrium Tm 10XM Fuel Assemblies  + (ANP-2936(NP), Revision 0, Brunswick, Unit 2, Thermal-Hydraulic Design Report for Atrium Tm 10XM Fuel Assemblies)
• ML102780679  + (ANP-2941(NP), Revision 0, Brunswick, Units 1 and 2, LOCA Break Spectrum Analysis for Atrium 10XM Fuel)
• BSEP 10-0112, ANP-2943(NP), Revision 0, Brunswick Units 1 and 2, LOCA-ECCS Analysis MAPLHGR Limit for Atrium 10XM Fuel  + (ANP-2943(NP), Revision 0, Brunswick Units 1 and 2, LOCA-ECCS Analysis MAPLHGR Limit for Atrium 10XM Fuel)
• ML103260322  + (ANP-2948NP, Rev. 0, Mechanical Design Report for Brunswick Atrium 10XM Fuel Assemblies, Enclosure 3 to BSEP 10-0126)
• BSEP 10-0118, ANP-2950NP, Revision 0, Atrium 10XM Fuel Rod Thermal and Mechanical Evaluation for Brunswick Unit 2 Cycle 20 Reload BRK2-20  + (ANP-2950NP, Revision 0, Atrium 10XM Fuel Rod Thermal and Mechanical Evaluation for Brunswick Unit 2 Cycle 20 Reload BRK2-20)
• BSEP 10-0126, ANP-2956(NP), Rev. 0, Brunswick Unit 2 Cycle 20 Reload Safety Analysis, Enclosure 6 to BSEP 10-0126  + (ANP-2956(NP), Rev. 0, Brunswick Unit 2 Cycle 20 Reload Safety Analysis, Enclosure 6 to BSEP 10-0126)
• ML11172A064  + (ANP-2970(NP), Rev 0, Sequoyah, Units 1 and 2 Htp Fuel Realistic Large Break LOCA Analysis, Attachment 10)
• ML12118A166  + (ANP-2970Q1(NP), Revision 000, Htp Fuel Realistic Large Break LOCA Analysis, April 2012 (Non-Proprietary Version), Enclosure 2)
• ML12137A298  + (ANP-2970Q2(NP), Rev 0, Sequoyah, Units 1 and 2 Htp Fuel Realistic Large Break LOCA Analysis)
• ML11172A072  + (ANP-2971(NP), Rev 1, Sequoyah Units 1 and 2 Htp Fuel S-RELAP5 Small Break LOCA Analysis, Attachment 9)
• ML11215A091  + (ANP-2975(NP), Revision 0, San Onofre Nuclear Generating Station, Unit 2 and Unit 3 - Realistic Large Break LOCA Report, Enclosure 6)
• BSEP 10-0141, ANP-2978NP, Rev. 0, Areva Responses to RAIs on the Atrium 10XM Compliance Audit and Brunswick Lars  + (ANP-2978NP, Rev. 0, Areva Responses to RAIs on the Atrium 10XM Compliance Audit and Brunswick Lars)
• ML11172A070  + (ANP-2986(NP), Revision 2, Sequoyah Htp Fuel Transition, Attachment 8)
• ML11210B532  + (ANP-2986(NP), Revision 3, Sequoyah Htp Fuel Transition. Attachment 2)
• ML110590055  + (ANP-2988NP, Revision 0, Browns Ferry Nuclear Plant, Unit 1, Areva Fuel Transition Input to TVA for Rais, Enclosure 3)
• ML12100A087  + (ANP-2989(NP), Revision 0, Brunswick, Unit 1, Thermal-Hydraulic Design Report for Atrium 10XM Fuel Assemblies)
• ML11153A049  + (ANP-3000(NP), Rev. 0, St. Lucie Nuclear, Unit 1 - EPU-Information to Support License Amendment Request, Attachment 6)
• L-2011-206, ANP-3000(NP), Rev. 0, St. Lucie Nuclear, Unit 1 - EPU-Information to Support License Amendment Request, Attachment 6  + (ANP-3000(NP), Rev. 0, St. Lucie Nuclear, Unit 1 - EPU-Information to Support License Amendment Request, Attachment 6)
• ML11238A078  + (ANP-3011(NP), Rev. 1, Harris Nuclear Plant Unit 1 Realistic Large Break LOCA Analysis)
• ML12067A180  + (ANP-3011Q1(NP), Revision 000, Harris Nuclear Plant Unit 1 Realistic Large Break LOCA Analysis. Enclosure 4 Response to Request for Additional Information (Non-Proprietary))
• ML16257A407  + (ANP-3013(NP), Revision 0, Brunswick Unit 1 Cycle 19 Fuel Cycle Design Mellla+ Operating Domain)
• ML12215A006  + (ANP-3015(NP), Revision 0, Browns Ferry Units 1, 2, and 3, LOCA Break Spectrum Analysis)
• ML11286A109  + (ANP-3015(NP), Revision 0, Browns Ferry, Units 1, 2 & 3, LOCA Break Spectrum Analysis, Enclosure 6)
• L-2011-311, ANP-3019NP, Revision 0, St. Lucie Unit 1 EPU - Information to Support NRC Review of Steam Generator Tube Rupture, Attachment 2  + (ANP-3019NP, Revision 0, St. Lucie Unit 1 EPU - Information to Support NRC Review of Steam Generator Tube Rupture, Attachment 2)
• L-2011-342, ANP-3028(NP), Revision 0, St. Lucie Plant, Unit 1 EPU RAIs - Nuclear Performance & Code (Snpb)  + (ANP-3028(NP), Revision 0, St. Lucie Plant, Unit 1 EPU RAIs - Nuclear Performance & Code (Snpb))