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ML19309E916
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Category
Pages with broken file links, MEETING MINUTES & NOTES--CORRESPONDENCE  and MEETING SUMMARIES-INTERNAL (NON-TRANSCRIPT)
Accession number
ML19309E916  +
Agency
Energy Facility Site Evaluation Council +
Atomic Element
Hydrogen +  and Tin +
CFR
10 CFR 50 +
Cornerstone
Emergency Preparedness +
Docket
05000466  +, 05000471  +, 05000488  +, 05000489  +, 05000490  +, 05000514  +, 05000515  +, 05000522  +, 05000523  +, 05000556  +, 05000557  +, 00466  +  and 00471  +
Equipment trip
Reactor Trip +  and Turbine Trip +
From
Thomas C +  and Office of Nuclear Reactor Regulation +
Has query"Has query" is a predefined property that represents meta information (in form of a <a rel="nofollow" class="external text" href="https://www.semantic-mediawiki.org/wiki/Subobject">subobject</a>) about individual queries and is provided by <a rel="nofollow" class="external text" href="https://www.semantic-mediawiki.org/wiki/Help:Special_properties">Semantic MediaWiki</a>.
ML19309E916 +, ML19309E916 +, ML19309E916 +, ML19309E916 +, ML19309E916 +, ML19309E916 +, ML19309E916 +, ML19309E916 +, ML19309E916 +  and ML19309E916 +
Isotope
Carbon-14 +  and Tritium +
Issue date
April 7, 1980  +
Manufacturer
General Electric +
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>.
07:55:56, 2 January 2025  +
NUREG
NUREG-0565, Forwards Topical Rept Evaluation of BAW-10092P,Rev 3 & BAW-10154 B&W Owners Group Small Break LOCA Evaluation model,CRAFT2 (Rev 3).Two Confirmatory Issues Identified. Response Requested within 45 Days of Ltr Receipt +, NUREG-0635, Forwards SER Re TMI Item II.K.3.30 for C-E Plants,Per Conditional Acceptance of CEN-203(P),Rev 1, Response to NRC Action Plan Item II.K.3.30 Justification of Small Break LOCA Methods +, NUREG-0611, Forwards Safety Evaluation Finding Auxiliary Feedwater Sys Adequately Designed,Maintained & Operated.Finding Predicated on Implementation of Listed Recommendations Agreed to During 860929-1002 Visit +, NUREG-0626, Forwards NUREG-0645,Vols 1-2, Rept of Bulletins & Orders Task Force & NUREG-0626, Generic Evaluation of Feedwater Transients & Small Break LOCAs in GE-Designed Operating Plants & Near Term OL Applications. W/O Encl +  and NUREG-056 +
Page count
47  +
Procedure
CP +
Project stage
Request  +
Regulatory Guide
Regulatory Guide 1.97 +
SSC
07-79-06A +, 07-79-06B +, 07-79-05A +, 07-79-06C +, 07-79-05C +, 07-79-058 +  and 07-79-068 +
Scram
Manual Scram +  and Automatic Scram +
Site
05000514 +, 05000515 +, 05000471 +, Allens Creek +, Perkins +, Skagit +  and Black Fox +
Start date
April 7, 1980  +
State
Texas +, Tennessee +, Pennsylvania +, Connecticut +, Kansas +, Georgia +, Illinois +, Maryland +, North Carolina +, Washington +, California +, Massachusetts +, Virginia +, New York +, Michigan +, Oklahoma +, Missouri +, New Hampshire +  and Oregon +
System
Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Auxiliary Feedwater +, Core Spray +  and Emergency Core Cooling System +
Title
Summary of 800402 Meeting w/Near-Term CP Applicants Group in Bethesda,Md Re Progress Made Establishing Proposed Requirements Stemming from TMI-2 Accident.Proposed Requirement Category Assignments Encl  +
To
Office of Nuclear Reactor Regulation +
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http://pbadupws.nrc.gov/docs/ML1930/ML19309E916.pdf  +
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