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ML19280A609
Show incoming properties 
Category
INTERNAL OR EXTERNAL MEMORANDUM  and MEMORANDUMS-CORRESPONDENCE
Accession number
ML19280A609  +
Atomic Element
Lead +  and Hydrogen +
CFR
10 CFR 50 Appendix A +, 10 CFR 100 +, 10 CFR 50 +  and 10 CFR 100 Appendix A +
Docket
05000289  +
From
Rosa F +  and Office of Nuclear Reactor Regulation +
General design criterion
GDC 20 +, GDC 22 +, GDC 17, Electric power systems +, GDC 2, Design bases for protection against natural phenomena +, GDC 4, Environmental and dynamic effects design bases +, GDC 1, Quality standards and records +  and GDC 3, Fire protection +
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ML19280A609 +, ML19280A609 +, ML19280A609 +, ML19280A609 +, ML19280A609 +, ML19280A609 +, ML19280A609 +, ML19280A609 +, ML19280A609 +, ML19280A609 +, ML19280A609 +  and ML19280A609 +
In package
ML111090060 +
Issue date
August 13, 1980  +
Manufacturer
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>.
05:53:14, 3 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-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-0585, Forwards NUREG-0578, TMI-2 Lessons Learned Task Force Status Report & Short-Term Requirements, & NUREG-0585, TMI-2 Lessons Learned Task Force Final Rept, in Response to .W/O Encl +  and NUREG-0660, 04-17-80 NUREG-0660 NRC Action Plans Developed as a Result of the TMI-2 Accident, Draft 3 +
Page count
11  +
Regulatory Guide
Regulatory Guide 1.29 +
Site
Crane +
Start date
August 13, 1980  +
State
Ohio +, Pennsylvania +, Maryland +  and California +
System
Reactor Coolant System +, Reactor Protection System +, Main Steam Isolation Valve +, Emergency Core Cooling System +  and Decay Heat Removal +
Title
Responds to 800724 Memo & Forswrds Prepared Testimony for Restart Hearing Including Summary of Involvement W/Facility Prof Qualification Summary  +
To
Tourtellotte J +  and NRC OFFICE OF THE EXECUTIVE LEGAL DIRECTOR (OELD) +
Topic
Safe Shutdown +  and Loss of Offsite Power +
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http://pbadupws.nrc.gov/docs/ML1928/ML19280A609.pdf  +
 
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