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ML20136F302
Show incoming properties 
Category
INTERNAL OR EXTERNAL MEMORANDUM  and MEMORANDUMS-CORRESPONDENCE
ASME section
ASME Section III +
Accession number
ML20136F302  +
Atomic Element
Nitrogen +, Oxygen +, Hydrogen +  and Lead +
CFR
10 CFR 50 +
Docket
05000000  +, 05000424  +  and 05000425  +
From
Johnston W +  and Office of Nuclear Reactor Regulation +
General design criterion
GDC 50 +, GDC 14 +, GDC 30 +, GDC 31 +, GDC 4, Environmental and dynamic effects design bases +  and GDC 1, Quality standards and records +
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>.
ML20136F302 +, ML20136F302 +, ML20136F302 +, ML20136F302 +, ML20136F302 +, ML20136F302 +, ML20136F302 +, ML20136F302 +, ML20136F302 +, ML20136F302 +  and ML20136F302 +
In package
ML082840446 +
Issue date
October 4, 1984  +
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>.
05:59:35, 12 December 2024  +
NUREG
NUREG-0577, Forwards Request for Addl Info Re Low Fracture Toughness Since Facility Has Been Classified as Group 1 According to NUREG-0577.Response Should Be Submitted within 30 Days of Receipt of Ltr.Further NRC Evaluation Will Be Required +  and NUREG-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting +
Page count
25  +
Project stage
Request  +
Regulatory Guide
Regulatory Guide 1.7 +, Regulatory Guide 1.43 +, Regulatory Guide 1.50 +, Regulatory Guide 1.31 +, Regulatory Guide 1.44 +, Regulatory Guide 1.34 +, Regulatory Guide 1.36 +, Regulatory Guide 1.71 +, Regulatory Guide 1.85 +  and Regulatory Guide 1.37, Quality Assurance Requirements for Cleaning of Fluid Systems and Associated Components of Water-Cooled Nuclear Power Plants +
Site
05000000 +  and Vogtle +
Start date
October 4, 1984  +
State
Georgia +
System
Steam Generator +, Feedwater +, Control Rod +, Main Steam +  and Containment Spray +
Title
Discusses Draft SER of FSAR Sections 4.5.1,4.5.2,5.2.3 & 5.3.1 Re Matls & 5.4.2.1,6.1.1 & 10.3.6 Re Fabrication. Acceptance Criteria Use in Accordance W/Srp,Or Described in Text of SER  +
To
Novak T +  and Office of Nuclear Reactor Regulation +
Topic
Anticipated operational occurrence +, Nondestructive Examination +  and Stress corrosion cracking +
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http://pbadupws.nrc.gov/docs/ML2013/ML20136F302.pdf  +
 
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