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Forwards CEN-189, "Evaluation of Pressurized Thermal Shock Effects Due to Small Break LOCAs W/Loss of Feedwater for C-E NSSS," & Apps A-J,in response to TMI Action Plan Requirement II.K.2.13.
Accession Number: ML13308A045
Date Released: Saturday, February 22, 2020
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- ML13308A044 - Forwards CEN-189, "Evaluation of Pressurized Thermal Shock Effects Due to Small Break LOCAs W/Loss of Feedwater for C-E NSSS," & Apps A-J,in response to TMI Action Plan Requirement II.K.2.13. (24 page(s), 12/31/1981)
- ML14092A301 - "Evaluation of Pressurized Thermal Shock Effects Due to Small Break LOCAs W/Loss of Feedwater for C-E NSSS." (155 page(s), 12/31/1981)
- ML20039F858 - "Evaluation of Pressurized Thermal Shock Effects Due to Small Break LOCAs W/Loss of Feedwater for Fort Calhoun Reactor Vessel." (37 page(s), 12/31/1981)
- ML20039F861 - "Evaluation of Pressurized Thermal Shock Effects Due to Small Break LOCAs W/Loss of Feedwater for Calvert Cliffs 1 & 2 Reactor Vessels." (44 page(s), 12/31/1981)
- ML20039F862 - "Evaluation of Pressurized Thermal Shock Effects Due to Small Break LOCAs W/Loss of Feedwater for Palisades Reactor Vessel." (29 page(s), 12/31/1981)
- ML20039F863 - "Evaluation of Pressurized Thermal Shock Effects Due to Small Break LOCA W/Loss of Feedwater for Millstone 2 Reactor Vessel." (34 page(s), 12/31/1981)
- ML20039F867 - "Evaluation of Pressurized Thermal Shock Effects Due to Small Break LOCAs W/Loss of Feedwater for St Lucie 1 & 2 Reactor Vessels." (34 page(s), 12/31/1981)
- ML20039F868 - "Evaluation of Pressurized Thermal Shock Effects Due to Small Break LOCAs W/Loss of Feedwater for AR Nuclear One- Unit 2 Reactor Vessel." (14 page(s), 12/31/1981)
- ML20039F860 - "Evaluation of Pressurized Thermal Shock Effects Due to Small Break LOCAs W/Loss of Feedwater for San Onofre 2 & 3 Reactor Vessels." (14 page(s), 12/31/1981)
- ML20039F866 - "Evaluation of Pressurized Thermal Shock Effects Due to Small Break LOCAs W/Loss of Feedwater for Waterford Reactor Vessel." (7 page(s), 12/31/1981)
- ML17297B168 - "Evaluation of Pressurized Thermal Shock Effects Due to Small Break LOCAs W/Loss of Feedwater for Palo Verde 1,2 & 3 Reactor Vessels." (28 page(s), 12/31/1981)