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Forwards listed documents ref in NUREG-1150,Vol 3,Apps J & N for placement in PDR.
Accession Number: ML20204G644
Date Released: Friday, August 7, 2020
Package Contents
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- ML20206C023 - Forwards listed documents ref in NUREG-1150,Vol 3,Apps J & N for placement in PDR. (6 page(s), 4/8/1987)
- ML20206J368 - Discusses latest calculations of molecular iodine (I2) & organic iodide (CH3I) scrubbing during TC1 sequence from draft plant rept. (3 page(s), 1/15/1986)
- ML20206F313 - Revised "Containment Hydrogen Analysis Review of DC Cook," program ltr rept.Related documentation encl. (341 page(s), 2/4/1985)
- ML20206J270 - Draft executive summary from "Analysis of Station Blackout Accidents for Bellefonte PWR." (12 page(s), 1/24/1986)
- ML20206H081 - "Some Sensitivities for Direct Containment Heating Loads." (8 page(s), 5/9/1986)
- ML20206H144 - "Direct Containment Heating Analysis W/CONTAIN Computer Code," ltr rept. (22 page(s), 9/2/1986)
- ML20206G928 - Discusses scoping analysis for direct heating in plant. Analysis of plant containment continuing.Aim to develop methodology that can be used in categorizing other containments. (4 page(s), 2/6/1987)
- ML20206J855 - Vols I & II to "Large-Scale Hydrogen Combustion Experiments, Research Project 1932-11," final rept. (1077 page(s), 12/31/1985)
- ML20206C234 - Draft "RELAP5/SCDAP/MOD0 Code Manual,Vol 1:Code Structure, Sys Models & Solution Methods," preliminary informal rept. (603 page(s), 9/30/1985)
- ML20206C066 - Draft "MELPROG-PWR/MOD1 Analysis of a TMLB' Accident Sequence." (69 page(s), 6/24/1986)
- ML20206F086 - Draft "COBRA-NC Analysis of Station Blackout Transient (TMLB') for Surry Plant." INEL viewgraphs entitled "Structural Failure Studies of RCS" also encl. (52 page(s), 2/28/1985)
- ML20206G821 - Preliminary draft "Containment Event Analysis for Postulated Severe Accidents at Peach Bottom Atomic Power Station," for review.Related documentation encl. (428 page(s), 5/12/1986)
- ML20206J403 - Summarizes preliminary scoping calculations for molecular iodine (I2) scrubbing in BWR pressure suppression pools. Calculations made for most recent TC1 sequence in draft plant rept. (7 page(s), 12/13/1985)
- ML20206H113 - Submits DHEAT2 parametric calculations for plant,per 860620 discussions.Calculations run assuming any steam spike would develop too slowly to contribute to DCH peak pressure. (2 page(s), 6/23/1986)
- ML20206F182 - Marked-up "Analysis of Station Blackout Transient W/Reactor Coolant Pump Seal Leakage for Seabrook Nuclear Plant." (25 page(s), 6/6/1985)
- ML20206J252 - Forwards early draft of executive summary from "Analysis of Station Blackout Accidents for Bellefonte PWR," per request. Initial draft of rept scheduled to be completed by 860315. (1 page(s), 1/24/1986)
- ML20206H285 - Summarizes initial data coming out of Severe Accident Risk Reduction Program (SARRP) in anticipation of upcoming meeting on direct heating.Portion of SARRP draft uncertainty analysis rept encl. (8 page(s), 4/9/1986)
- ML20206F071 - "Flow-Pattern Results for TMLB' Accident Sequence in Surry Plant Using MELPROG." (16 page(s), 4/8/1987)
- ML20206J600 - Advises that NUREG-0956 support calculations using ORNL TRENDS code to evaluate influence of containment chemistry or retention of HI can also provide useful info for general NUREG-1150 issue paper,per telcon discussion. (5 page(s), 8/8/1986)