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ML20235J380
Show incoming properties
Category
MEETING MINUTES & NOTES--CORRESPONDENCE  and MEETING SUMMARIES-INTERNAL (NON-TRANSCRIPT)
Accession number
ML20235J380  +
Atomic Element
Hydrogen +  and Lead +
ENS
ENS 0 +
From
Vissing G +  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>.
ML20235J380 +, ML20235J380 +, ML20235J380 +, ML20235J380 +, ML20235J380 +  and ML20235J380 +
Issue date
September 25, 1987  +
Manufacturer
C700 +  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>.
10:14:45, 3 December 2024  +
NUREG
NUREG-1197 +, NUREG-0471, Responds to 781113 Request & Encl Generic Task Problem Descriptions(NUREG-0471)& NRC Prog for Resolution of Generic Issues Related to Nuc Pwr Plants(NUREG-0410). W/O Encl +, NUREG-0606, Discusses 336th Meeting of ACRS on 880407-09 Re Proposed Resolution of USI A-47, Safety Implications of Control Sys. Disagrees That NRC Recommendations Constitute Resolution of USI A-47 as Originally Defined +, NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +, NUREG-0410, Speech Entitled Shutdown Decay Heat Removal, for Presentation at 890418-20 NRC Regulatory Info Conference in Washington,Dc +, NUREG-0371, Forwards NUREG-0371,NUREG-0471 & NUREG-0600.W/o Encl +, NUREG-1050, Forwards Regulatory Analysis of Generic Safety Issue 61, Safety/Relief Valve Discharge Line Break within Mark I or II Wetwell Airspace. Based on Results Discussed in NUREG/CR-4594,risk Lower than Previously Estimated +  and NUREG-0660, 04-17-80 NUREG-0660 NRC Action Plans Developed as a Result of the TMI-2 Accident, Draft 3 +
Page count
62  +
Person
Bob Fitzpatrick +
Procedure
ES +, ST +, MP +  and TP +
Processing error"Processing error" is a predefined property provided by <a rel="nofollow" class="external text" href="https://www.semantic-mediawiki.org/wiki/Help:Special_properties">Semantic MediaWiki</a> and represents errors that appeared in connection with improper value annotations or input processing.
ML20235J380 +
Start date
September 25, 1987  +
State
Maryland +  and Washington +
System
Steam Generator +, Service water +, Standby Gas Treatment System +, Emergency Core Cooling System +, Decay Heat Removal +  and Main Steam +
Title
Summary of 870917 Meeting w/C-E in Bethesda,Md Re USIs & Generic Issues for Sys 80+ Design.List of Attendees & Viewgraphs Encl  +
To
Office of Nuclear Reactor Regulation +
Topic
Ultimate heat sink +, Probabilistic Risk Assessment +, Operating Basis Earthquake +, Eddy Current Test +  and Leak-Before-Break +
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http://pbadupws.nrc.gov/docs/ML2023/ML20235J380.pdf  +
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