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ML022460102
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Category
E-Mail
ASME code
IWB-3640 +, IWB-2500 +, IWB-3522 +, IWB-3142 +, IWA-5000 +, IWA-5242 +  and IWA-2500 +
Accession number
ML022460102  +
Atomic Element
Boron +, Uranium +, Carbon +, Lead +, Lithium +  and Tungsten +
CFR
10 CFR 50.46 +, 10 CFR 50 Appendix K +, 10 CFR 50 +, 10 CFR 50.56 +  and 10 CFR 50.55a +
CR
CR-ANO-21-00080 +
Code case
ASME Code Case N-638 +
Cornerstone
Initiating Events +
Correspondence
L-01 +
Docket
05000269  +, 05000270  +, 05000287  +, 05000315  +, 05000316  +  and 05000346  +
Document
ML012550307 +  and ML012550290 +
FOIA
FOIA/PA-2002-0229 +
From
Office of Nuclear Reactor Regulation +  and Chung J +
General design criterion
GDC 14 +, GDC 31 +  and GDC 32 +
Generic letter
NRC Generic Letter 88-05, Boric Acid Corrosion of Carbon Steel Reactor Pressure Boundary Components in PWR plants +, NRC Generic Letter 97-01, Degradation of Control Rod Drive Mechanism Nozzle and Other Vessel Closure Head Penetrations +  and NRC Generic Letter 88-20, Individual Plant Examination for Severe Accident Vulnerabilities +
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ML022460102 +, ML022460102 +, ML022460102 +, ML022460102 +, ML022460102 +, ML022460102 +, ML022460102 +, ML022460102 +, ML022460102 +, ML022460102 +, ML022460102 +, ML022460102 +, ML022460102 +, ML022460102 +, ML022460102 +  and ML022460102 +
Issue date
February 6, 2002  +
L
L-01 +
LER
05000269/LER-2000-006 +, 05000270/LER-2001-002 +  and 05000287/LER-2001-001-01, Regarding Reactor Pressure Vessel Head Leakage Due to Stress Corrosion Cracks Found in Nine Control Rod Drive Nozzle Penetrations +
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>.
21:05:40, 16 January 2025  +
NRC bulletin
NRC Bulletin 01-01 +
NUMARC
NUMARC 93-01 +
Page count
62  +
Procedure
MP +  and TP-1 +
Project stage
Request  +
Regulatory Guide
Regulatory Guide 1.174 +  and Regulatory Guide 1.182 +
SSC
07-01-002 +, I1B-3514 +  and I1AOE-3 +
Site
Davis Besse +, Oconee +  and Cook +
Start date
February 6, 2002  +
State
Texas +, Virginia +, Michigan +, Indiana +  and Arkansas +
System
Steam Generator +, Reactor Coolant System +, Reactor Pressure Vessel +, Emergency Core Cooling System +  and Control Rod +
Title
E-mail from J Chung, NRR to Fm Reinhart, NRR, PRA Perspective in Technical Assessment Report  +
To
Office of Nuclear Reactor Regulation +  and Reinhart F +
Topic
Boric Acid +, Non-Destructive Examination +, Weld Overlay +, Probabilistic Risk Assessment +, VT-2 +, Large early release frequency +, Stress corrosion cracking +, Fuel cladding +, Liquid penetrant +, Pressure Boundary Leakage +, Through-Wall Leakage +, Eddy Current Test +  and Eddy-Current Testing +
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http://pbadupws.nrc.gov/docs/ML0224/ML022460102.pdf  +
Vendor
Framatome +
 
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