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Forwards NRC testimony on Commission Question 1 on risk from possible accidents.
Accession Number: ML20070N085
Date Released: Sunday, November 8, 2020
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- ML20070N082 - Forwards NRC testimony on Commission Question 1 on risk from possible accidents. (2 page(s), 1/24/1983)
- ML20070N127 - Testimony of F Rowsome & R Blond re Commission Question 1 on risk from possible accidents.Probabilistic Safety Study thorough in investigating challenges to containment by severe reactor accidents. (40 page(s), 1/24/1983)
- ML20070N156 - Testimony of S Israel,J Hickman,G Kolb,RG Easterling & AD Swain re Commission Question 1 & ASLB Question 1.1. Frequencies of plant damage states caused by internally initiated events provided.Prof qualifications encl. (31 page(s), 1/24/1983)
- ML20070N222 - Testimony of JW Reed on Commission Question 1.Mean frequencies of release better represented by values in Probabilistic Safety Study tables.Uncertainties in release frequencies very large.Prof qualifications encl. (8 page(s), 1/24/1983)
- ML20070N258 - Testimony of B Buchbinder & D Kubicki re Commission Question 1.Describes NRC assessment of manner in which potential fire accidents contribute to frequency of core melt at plants. Prof qualifications encl. (31 page(s), 1/24/1983)
- ML20070N283 - Testimony of FH Rowsome re damage state likelihoods. Steps taken to assemble accident likelihood estimates into input used by J Meyer evaluation of likelihood of release categories identified.Prof qualifications encl. (14 page(s), 1/24/1983)
- ML20070N301 - Testimony of JF Meyer & WT Pratt re Commission Question 1. NRC analysis & assessment of severe accident phenomena, containment bldg failure modes & radiological releases that could result from core melt accidents provided. (78 page(s), 1/24/1983)
- ML20070N322 - Testimony of S Acharya & RM Blond re NRC assessment of accident consequences & risks & calculational methodology of CRAC code.NRC assessment of potential consequences resulting from atmospheric release of radionuclides provided. (202 page(s), 1/24/1983)
- ML20070N353 - Testimony of RJ Neese re site-specific economic input parameters.Describes economic input parameters used to evaluate socioeconomic consequences of accident at plant. Prof qualifications encl. (7 page(s), 1/24/1983)
- ML20070N381 - Testimony of L Soffer re population info.Info used as input to NRC CRAC Code analysis was estimate of 1990 resident population around site.Population data from 1980 increased by county & regional projected growth factors. (10 page(s), 1/24/1983)
- ML20070N406 - Testimony of R Codell re Commission Question 1.NRC review of liquid pathway analyses in Probabilistic Safety Study presented & NRC independent analysis of risk posed by contamination of Hudson River or bodies of water described. (59 page(s), 1/24/1983)
- ML20070N429 - Testimony of RM Blond & FH Rowsome re risk posed by severe reactor accidents at plant as currently designed & operated. NRC testimony on risk summarized.Prof qualifications encl. (31 page(s), 1/24/1983)
- ML20070N484 - Testimony of F Rowsome & R Blond re Commission Question 1. Risk reduction attributable to improvements in emergency preparedness unknown but not expected to be large. (31 page(s), 1/24/1983)
- ML20070N515 - Testimony of FH Rowsome re accuracy of risk assessments. Uncertainties in predictions of risk posed by severe reactor accidents at plant large.Absolute risk cannot be pinpointed.Prof qualifications encl. (22 page(s), 1/24/1983)
- ML20070N552 - Testimony of FH Rowsome re Contention 1.1 & ASLB Question 1.1.Risks to health & property damage exist,but adjective "high" unwarranted.Risks must loom large against background of competing non-nuclear risks to be high risks. (12 page(s), 1/24/1983)
- ML20070N605 - Testimony of JR Sears on Contention 1.1 under Commission Question 1.Licensee std emergency classification & action level scheme discussed.Basis of scheme include facility sys & effluent parameters. (7 page(s), 1/24/1983)
- ML20070N638 - Testimony of JP Joyce re Commission Question 1, Contention 1.1.Completion of NRC review of licensee compliance w/Reg Guide 1.97,Rev 2 not prerequisite for continued operation.Review incomplete for all plants. (7 page(s), 1/24/1983)
- ML20070N669 - Testimony of FH Rowsome re ASLB Question 1.2.Precursor Study provides no clear indication of accuracy of accident likelihood assessment in Probabilistic Safety Study.Prof qualifications encl. (21 page(s), 1/24/1983)
- ML20070N690 - Testimony of R Blond re ASLB Question 1.3.Probability difficult to associate w/consequence estimates in B Palenik & J Beyea testimony since estimates not intended to represent Indian Point reactors.Prof qualifications encl. (14 page(s), 1/24/1983)
- ML20070N712 - Testimony of HW Woods & RW Klecker on ASLB Question 1.4. Plant ratings on pressurized thermal shock issue discussed. Prof qualifications encl. (15 page(s), 1/24/1983)