ML20003A917

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Follows Up 801230 Response to NUREG-0737.Forwards Reactor Vessel Brittle Fracture Analyses During Small Break LOCA Events W/Extended Loss of Feedwater & Info Re power-operated Relief Valve Opening Probability
Date released: 01/17/2020 Download: ML20003A917


Final Version of Reactor Vessel Brittle Fracture Analyses During Small Break LOCA Events W/Extended Loss of Feedwater. Info Re power-operated Relief Valve Opening Probability Encl
ML20003A924
Person / Time
Site: Davis Besse Cleveland Electric icon.png
Issue date: 12/30/1980
From:
BABCOCK & WILCOX CO.
To:
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.E.4.2, TASK-2.K.3, TASK-2.K.3.07, TASK-2.K.3.30, TASK-TM
Download: ML20003A924 (115)
Follows Up 801230 Response to NUREG-0737.Forwards Reactor Vessel Brittle Fracture Analyses During Small Break LOCA Events W/Extended Loss of Feedwater & Info Re power-operated Relief Valve Opening Probability
ML20003A916
Person / Time
Site: Davis Besse Cleveland Electric icon.png
Issue date: 01/30/1981
From: Crouse R
TOLEDO EDISON CO.
To: EISENHUT D G
Office of Nuclear Reactor Regulation
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.E.4.2, TASK-2.K.2.13, TASK-2.K.2.14, TASK-2.K.3, TASK-2.K.3.02, TASK-2.K.3.07, TASK-2.K.3.30, TASK-TM
Download: ML20003A916 (3)