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ML20129F806
Show incoming properties 
Category
INTERNAL OR EXTERNAL MEMORANDUM  and MEMORANDUMS-CORRESPONDENCE
Accession number
ML20129F806  +
Atomic Element
Carbon +, Hydrogen +, Zirconium +, Lead +  and Sulfur +
CFR
10 CFR 100 +
Committee
Advisory Committee on Reactor Safeguards +
Cross cutting aspect
P.1(l) +
From
NRC (Affiliation Not Assigned) +  and Rosalyn Jones +
Fuel cladding
Zircaloy +
General design criterion
GDC 14 +
Generic letter
NRC Generic Letter 95-05, Voltage-Based Repair Criteria for Westinghouse Steam Generator Tubes Affected by Outside Diameter Stress Corrosion Cracking +
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>.
ML20129F806 +, ML20129F806 +, ML20129F806 +, ML20129F806 +, ML20129F806 +, ML20129F806 +, ML20129F806 +  and ML20129F806 +
Hours
5.787037e-5 d (0.00139 hours, 8.267196e-6 weeks, 1.9025e-6 months)  +  and 0 d (0 hours, 0 weeks, 0 months)  +
Issue date
September 24, 1996  +
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>.
16:21:28, 12 December 2024  +
NUREG
NUREG-0452 +, NUREG/CR-4550 +, NUREG/CR-4551 +, NUREG/CR-6075 +, NUREG/CR-4393 +, NUREG-0103, Safety Evaluation Supporting Relief from Inservice Insp Requirements of ASME Boiler & Pressure Vessel Code Requiring Quarterly Stroke Testing of RCS Valves & Denying Relief from Code Requirements for Valve RC-11 Testing +, NUREG-1150, Weekly Info Rept for Wk Ending 890922 +, NUREG-0844, Forwards NUREG-0844, NRC Integrated Program for Resolution of USIs A-3,A-4 & A-5 Re Steam Generator Tube Integraty. Rept Documents Final Resolution of Subj Usis.W/O Encl +  and NUREG-0212, Safety Evaluation Supporting Amend 99 to License DPR-20 +
Page count
1  +
Procedure
Emergency Operating Procedure +
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.
ML20129F806 +
Start date
September 24, 1996  +
State
Washington +  and Illinois +
System
Steam Generator +, Reactor Coolant System +, Feedwater +, Auxiliary Feedwater +, Main Steam Safety Valve +, Main Steam Line +, Control Rod +  and Auxiliary Feed Water +
Title
Forwards Complete NEI Response Including Info on SG Inlet Mixing Requested by Catton During ACRS Meeting on 960604  +
To
Advisory Committee on Reactor Safeguards +  and Dudley N +
Topic
Hydrostatic +, Eddy-Current Testing +  and Operational leakage +
URL"URL" is a <a href="/Special:Types/URL" title="Special:Types/URL">type</a> and predefined property provided by <a rel="nofollow" class="external text" href="https://www.semantic-mediawiki.org/wiki/Help:Special_properties">Semantic MediaWiki</a> to represent URI/URL values.
http://pbadupws.nrc.gov/docs/ML2012/ML20129F806.pdf  +
 
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