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ML20062L051
Show incoming properties 
Category
LEGAL TRANSCRIPTS & ORDERS & PLEADINGS, TRANSCRIPTS, DEPOSITIONS  and NARRATIVE TESTIMONY
ASME section
ASME Section VI +
Accession number
ML20062L051  +
Act
Atomic Energy Act of 1954 +
Agency
Environmental Protection Agency +
Atomic Element
Iodine +, Americium +, Uranium +, Carbon +, Sodium +, Lead +  and Plutonium +
CFR
10 CFR 100 +, 10 CFR 50 +, 10 CFR 100.2 +, 10 CFR 20.101 +, 10 CFR 5100 +, 10 CFR 50.46#b3 +  and 10 CFR 50.44#c3iii +
Committee
Advisory Committee on Reactor Safeguards +
Cornerstone
Initiating Events +
Docket
05000537  +, 00537  +, 00231  +  and 00328  +
Equipment trip
Reactor Trip +
FR
27 FR 3509 +, 46 FR 57521 +, 26 FR 1224 +  and 46 FR 57522 +
From
Cochran T +  and National Resources Defense Council +
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ML20062L051 +, ML20062L051 +, ML20062L051 +, ML20062L051 +, ML20062L051 +, ML20062L051 +, ML20062L051 +, ML20062L051 +, ML20062L051 +, ML20062L051 +, ML20062L051 +, ML20062L051 +, ML20062L051 +  and ML20062L051 +
Hours
2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +
In package
ML20062L054 +
Intervenor
Natural Resources Defense Council +  and Sierra Club +
Isotope
I-131 +  and Po-210 +
Issue date
August 16, 1982  +
Manufacturer
General Electric +  and Westinghouse +
Modification date"Modification date" is a predefined property that corresponds to the date of the last modification of a subject and is provided by <a rel="nofollow" class="external text" href="https://www.semantic-mediawiki.org/wiki/Help:Special_properties">Semantic MediaWiki</a>.
03:33:55, 17 December 2024  +
NUREG
NUREG-0786, Summarizes ACRS 267th Meeting on 820708-10 Re NUREG-0786, Site Suitability Rept in Matter of Crbr. Crbr Can Be Designed So as to Present No Greater Risk than Lwr.Proposed Site Suitable +, NUREG-0358, Forwards NRC Review of Fast Flux Test Facility Power Addition Safety Documents,Per Vaughn .Concludes That Proper Issues Being Addressed & That DOE Plan for Addressing Issues Appears Adequate +  and NUREG/CR-0400, Forwards NRC Policy Statement Re Reactor Safety Study,Review by the Lewis Committee (NUREG/CR-0400) & Survey of NRC Uses of WASH-1400.All Documents Have Been Furnished to ASLB & Aslab Panel Members.W/O Encl +
Page count
169  +
Person
Harold Denton +
Procedure
CP +
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ML20062L051 +
Project stage
Request  +
Site
Clinch River +
Start date
August 16, 1982  +
State
Tennessee +, Colorado +, Washington +, California +, Virginia +, Idaho +, Michigan +  and Arkansas +
System
Reactor Coolant System +, Secondary containment +, Reactor Protection System +, Auxiliary Feedwater +, Primary containment +, Residual Heat Removal +, Emergency Core Cooling System +, Decay Heat Removal +, Control Rod +  and Containment Spray +
Title
Testimony of TB Cochran on Contentions 1a,3b & 3d Re Core Disruptive Accidents & DBAs & Contentions 2 & 3c Re Site Suitability Analysis Under 10CFR100  +
Topic
Safe Shutdown +, Probabilistic Risk Assessment +, Fuel cladding +, Failure to Scram +  and Affidavit +
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http://pbadupws.nrc.gov/docs/ML2006/ML20062L051.pdf  +
 
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