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ML20076G690
Show incoming properties 
Category
CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE  and UTILITY TO NRC
Accession number
ML20076G690  +
Atomic Element
Chloride +, Lead +  and Tin +
Cross cutting aspect
P.1(t) +
Docket
05000352  +, 05000353  +  and 00352  +
Equipment trip
Turbine Trip +
From
Exelon +, (FORMERLY PHILADELPHIA ELECTRIC +  and Bradley E +
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>.
ML20076G690 +, ML20076G690 +, ML20076G690 +, ML20076G690 +, ML20076G690 +, ML20076G690 +, ML20076G690 +, ML20076G690 +, ML20076G690 +, ML20076G690 +, ML20076G690 +, ML20076G690 +, ML20076G690 +, ML20076G690 +, ML20076G690 +, ML20076G690 +, ML20076G690 +, ML20076G690 +  and ML20076G690 +
Issue date
June 13, 1983  +
Letter
ML20069L811 +  and ML20071E950 +
Manufacturer
General Electric +  and Target Rock +
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>.
07:39:04, 15 December 2024  +
Page count
58  +
Person
None none +
Procedure
AM +, ES +  and RT +
Project stage
Request  +
Regulatory Guide
Regulatory Guide 1.45 +  and Regulatory Guide 1.70 +
Report
NEDO-10802 +, NEDO-10899 +, NEDE-10958 +  and NEDO-10959 +
SSC
303A-IERIIWi +  and 49rt-L8 +
Site
Limerick +
Start date
June 13, 1983  +
State
Washington +  and Pennsylvania +
System
Feedwater +, Secondary containment +, High Pressure Coolant Injection +, Reactor Protection System +, Main Steam Isolation Valve +, Reactor Core Isolation Cooling +, Primary containment +, Main Turbine +, Main Steam Line +, Safety Relief Valve +, Electrohydraulic Control +, Main Condenser +, Control Rod +, Main Steam +  and Main Turbine Bypass System +
Title
Forwards Draft FSAR Page Changes,In Response to Reactor Sys Branch Draft SER Item 1, Odyn Analysis of Pressurization Transients. Changes Will Be Incorporated Into FSAR Rev Scheduled for Jul 1983  +
To
Schwencer A +  and Office of Nuclear Reactor Regulation +
Topic
Safe Shutdown +, Stroke time +, Abnormal operational transient +, Feedwater Heater +, Feedwater Controller Failure +  and Overspeed +
Turbine component
Turbine bypass valve +
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http://pbadupws.nrc.gov/docs/ML2007/ML20076G690.pdf  +
 
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