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ML20209C276
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Category
TEXT-SAFETY REPORT  and SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
ASME code
IWB-3640 +
Accession number
ML20209C276  +
Atomic Element
Carbon +  and Tungsten +
Docket
05000278  +  and 00278  +
From
Office of Nuclear Reactor Regulation +
Generic letter
NRC Generic Letter 84-11, Inspections of BWR Stainless Steel Piping +
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>.
ML20209C276 +, ML20209C276 +, ML20209C276 +, ML20209C276 +, ML20209C276 +, ML20209C276 +, ML20209C276 +, ML20209C276 +, ML20209C276 +  and ML20209C276 +
Hours
0.0845 d (2.028 hours, 0.0121 weeks, 0.00278 months)  +, 1.388889e-4 d (0.00333 hours, 1.984127e-5 weeks, 4.566e-6 months)  +  and 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +
In package
ML20209C152 +
Issue date
March 20, 1986  +
Manufacturer
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>.
23:32:06, 6 December 2024  +
NRC bulletin
NRC Bulletin 80-13 +, NRC Bulletin 82-03 +  and NRC Bulletin 83-02 +
Page count
16  +
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.
ML20209C276 +
Project stage
Request  +
SSC
10-1B-11 +  and 316L-inlet +
Site
Peach Bottom +
Start date
March 20, 1986  +
State
North Carolina +
System
Reactor Coolant System +, Primary containment +, Core Spray +, Residual Heat Removal +  and Control Rod +
Title
Safety Evaluation Supporting Insp & Repair of RCS Piping, Recirculation Safe Ends & Core Spray Spargers.Summary of 1985 IGSCC Insp at Facility Encl  +
Topic
Weld Overlay +, Nondestructive Examination +, Finite Element Analysis +, Intergranular Stress Corrosion Cracking +, Stress corrosion cracking +, Liquid penetrant +  and Unidentified leakage +
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http://pbadupws.nrc.gov/docs/ML2020/ML20209C276.pdf  +
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