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ML20248L684
Show incoming properties 
Category
INTERNAL OR EXTERNAL MEMORANDUM  and MEMORANDUMS-CORRESPONDENCE
Accession number
ML20248L684  +
Atomic Element
Iodine +  and Lead +
CFR
10 CFR 100 +  and 10 CFR 50.109 +
Committee
Advisory Committee on Reactor Safeguards +  and Committee To Review Generic Requirements +
Correspondence
SECY-97-013 +  and L 11 +
Docket
00302  +, 00311  +, 00368  +  and 00317  +
Equipment trip
Reactor Trip +
From
NRC (Affiliation Not Assigned) +  and Sheron B +
Generic letter
NRC Generic Letter 95-05, Voltage-Based Repair Criteria for Westinghouse Steam Generator Tubes Affected by Outside Diameter Stress Corrosion Cracking +  and NRC Generic Letter 95-03, Circumferential Cracking of Steam Generator Tubes +
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>.
ML20248L684 +, ML20248L684 +, ML20248L684 +, ML20248L684 +, ML20248L684 +, ML20248L684 +, ML20248L684 +, ML20248L684 +  and ML20248L684 +
Hours
5.555556e-4 d (0.0133 hours, 7.936508e-5 weeks, 1.8264e-5 months)  +, 6.944444e-5 d (0.00167 hours, 9.920635e-6 weeks, 2.283e-6 months)  +  and 9.259259e-5 d (0.00222 hours, 1.322751e-5 weeks, 3.044e-6 months)  +
In package
ML20248L677 +
Issue date
September 19, 1997  +
L
L 11 +
Manufacturer
Westinghouse +  and General Electric +
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>.
19:34:01, 30 November 2024  +
NUREG
NUREG/CR-5214 +, NUREG/CR-4483 +, NUREG-1477, Discusses Technical Concerns W/Changes to Draft NUREG-1477 Re Probability of Leakage Curves +, NUREG-4483 +  and NUREG-1570, Summary of ACRS Subcommittees on Matls & Metallurgy and Severe Accidents Meeting on 970304-05 in Rockville,Md Re Staff Draft NUREG-1570, Risk Assessment of Severe Accident Induced Steam Generator Tube Rupture +
Page count
42  +
Procedure
RT +
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.
ML20248L684 +
Regulatory Guide
Regulatory Guide 1.121 +
SECY
SECY-97-013 +
SSC
2x10-s +
Start date
September 19, 1997  +
State
Texas +, Washington +, Florida +, Arkansas +  and Maine +
System
Steam Generator +, Reactor Coolant System +, Feedwater +, Auxiliary Feedwater +, Reactor Pressure Vessel +, Residual Heat Removal +, Emergency Core Cooling System +  and Main Steam Line +
Title
Discusses 970826-27 Meeting W/Acrs Matls & Metallurgy & Severe Accidents Subcommittee & 970903 Meeting W/Acrs Full Committee,To Discuss Proposed GL 97-XX, SG Tube Integrity. Opinion Issues Applicable to SG Tube Integrity Encl  +
To
Advisory Committee on Reactor Safeguards +  and Larkins J +
Topic
Probabilistic Risk Assessment +, Nondestructive Examination +, Intergranular Stress Corrosion Cracking +, Stress corrosion cracking +, Eddy Current Testing +, Backfit +, Operational leakage +  and Leak-Before-Break +
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http://pbadupws.nrc.gov/docs/ML2024/ML20248L684.pdf  +
 
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