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Responds to FOIA request for all records which form basis for NUREG-0956 conclusion about Mark I containment in severe accidents.Encl App A documents available in PDR.App B documents also available in PDR.
Accession Number: ML20209C518
Date Released: Wednesday, August 12, 2020
Package Contents
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- ML20210S081 - Responds to FOIA request for all records which form basis for NUREG-0956 conclusion about Mark I containment in severe accidents.Encl App A documents available in PDR.App B documents also available in PDR. (4 page(s), 9/26/1986)
- ML20211H661 - Discusses PRA analysis.NRC worked w/IDCOR to develop methodology less expensive & time consuming than full PRA. Methodology will be applied to specific plants,following NRC review & approval. (2 page(s), 6/20/1986)
- ML20210S239 - "High Risk:GE Mark I Pressure-Suppression Design." Public Citizen press release re natl coalition of citizen groups petitions NRC to revoke CPs for new nuclear plants encl. (21 page(s), 6/25/1986)
- ML20209C514 - Forwards Mechanical Engineering Branch safety evaluation of Mark I containment long-term program,excepting vacuum breakers.Mods approved. (5 page(s), 10/24/1983)
- ML20210S261 - Summary of 860630 meeting w/util & governor of State of VT in Montpelier,VT re 90% conditional failure probability of Mark I containments,given full core melt accident. (1 page(s), 7/1/1986)
- ML20210S282 - Forwards notice of 860806 meeting w/util & State of VT in Bethesda,MD to discuss status of Mark I containment safety study.Vermont Yankee containment safety study & safety objectives encl. (32 page(s), 7/15/1986)
- ML20210S250 - Expresses appreciation for NRC cooperation re State of VT study of plant containment sys. (1 page(s), 7/1/1986)
- ML20210S308 - Forwards Task Force review of bypass effects in GE pressure suppression containments.Acceptance of pressure suppression containment by all elements of nuclear field,including ACRS, firmly embedded in conventional wisdom. (14 page(s), 9/25/1972)
- ML20210S233 - Requests response to two addl questions on NRC evaluation of plant,including explanation of H Denton statement re ability of Mark I containments to survive severe accident. NRC response encl. (4 page(s), 6/25/1986)
