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ML20055E399
Show incoming properties 
Category
INTERNAL OR EXTERNAL MEMORANDUM  and MEMORANDUMS-CORRESPONDENCE
Accession number
ML20055E399  +
Atomic Element
Lead +
CFR
10 CFR 50 +
Docket
05000206  +  and 05000312  +
Emergency Facility
Technical Support Center +
Exelon procedure
RV-MA-1 +  and RV-MA-4 +
From
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) +  and Kirsch D +
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>.
ML20055E399 +, ML20055E399 +, ML20055E399 +, ML20055E399 +, ML20055E399 +, ML20055E399 +, ML20055E399 +, ML20055E399 +, ML20055E399 +, ML20055E399 +, ML20055E399 +, ML20055E399 +  and ML20055E399 +
In package
ML20055C206 +
Issue date
May 28, 1987  +
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>.
02:41:43, 27 May 2025  +
NRC bulletin
NRC Bulletin 79-27 +
NUREG
NUREG-0667, 06-10-80 Report on NUREG-0667 Transient Response of Babcock - Wilcox-Designed Reactors +, NUREG-0560, Forwards NRC Response to Congressman Matsui Re Broader Issues Related to B&W Design.Efforts to Enhance Response & Review of Events Underway.Plans to Reexam B&W Design in Progress +, NUREG-1195, Forwards Response to Re NRC Reexam of B&W Reactor Design.Review Efforts Intensified After TMI Accident.Nrr Reorganized Last Yr to Increase Attention to Major Vendor Product Lines.Action Plan Under Development for Rancho Seco +  and NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +
Page count
14  +
Procedure
TSG +
Project stage
Request  +
Regulatory Guide
Regulatory Guide 1.23 +  and Regulatory Guide 1.97 +
Site
San Onofre +  and Rancho Seco +
Start date
May 28, 1987  +
System
Steam Generator +, Feedwater +, Safety Parameter Display System +, HVAC +, Emergency Feedwater Initiation and Control +, Main Steam Line +  and Main Steam +
Title
Informs That Region V Continuing to Inspect Util Activities Re Preparation for Restart of Facility Following 851226 Transient.Util Has Partially Performed,Developed & Implemented Necessary Corrective Action Programs  +
To
Crutchfield D +  and Office of Nuclear Reactor Regulation +
Topic
Loss of Offsite Power +
Turbine component
Turbine bypass valve +
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http://pbadupws.nrc.gov/docs/ML2005/ML20055E399.pdf  +
 
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