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ML021570378
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Category
Letter
ASME code
IWB-3522 +, IWB-3142 +  and IWA-2500 +
Accession number
ML021570378  +
Act
Atomic Energy Act of 1954 +
Atomic Element
Boron +, Carbon +, Sodium +  and Lead +
CFR
10 CFR 50 +, 10 CFR 50.55a +, 10 CFR 50.54#f +, 10 CFR 50.55a#g6ii +  and 10 CFR 55#a +
Contact
Dozier J, NRR/RLSB 415-1014 +
Docket
05000270  +, 05000287  +  and 05000313  +
Document
ML020770497 +, Information Notice 2002-13, Possible Indicators of Ongoing Reactor Pressure Vessel Head Degradation +, Information Notice 2002-11, Recent Experience with Degradation of Reactor Pressure Vessel Head +, ML012080284 +  and ML021570378 +
From
Beckner W +  and NRC/NRR/DRIP/RORP +
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 +  and NRC Generic Letter 97-01, Degradation of Control Rod Drive Mechanism Nozzle and Other Vessel Closure Head Penetrations +
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>.
ML021570378 +, ML021570378 +, ML021570378 +, ML021570378 +, ML021570378 +, ML021570378 +, ML021570378 +, ML021570378 +, ML021570378 +, ML021570378 +, ML021570378 +, ML021570378 +  and ML021570378 +
Hours
0.00162 d (0.0389 hours, 2.314815e-4 weeks, 5.327e-5 months)  +  and 0.00156 d (0.0375 hours, 2.232143e-4 weeks, 5.13675e-5 months)  +
Issue date
June 4, 2002  +
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>.
23:03:51, 16 January 2025  +
NRC bulletin
NRC Bulletin 02-01 +, NRC Bulletin 01-01 +  and NRC Bulletin 82-02 +
NRC information notice
Information Notice 80-27 +, Information Notice 94-63 +, Information Notice 90-10 +, Information Notice 96-11 +, Information Notice 82-06 +, Information Notice 2002-11, Recent Experience with Degradation of Reactor Pressure Vessel Head +, Information Notice 2001-05, Through-Wall Circumferential Cracking of Reactor Pressure Vessel Head Control Rod Drive Mechanism Penetration Nozzles at Oconee Nuclear Station Unit 3 +, Information Notice 01-01 +, Information Notice 02-11 +, Information Notice 02-13 +, Information Notice 02-01 +  and Information Notice 2002-13, E-mail from H. Nieh, Oedo to A. Levin, Ocm, Et Al., Issuance of Information Notice 2002-13, Fwd: E-mail from D. Pickett T Davis-Besse Communication Plan +
NUREG
NUREG/CR-6245 +
Page count
62  +
Person
Jerry Dozier +, Allen Hiser +  and Ian Jung +
Procedure
CP +
Site
Oconee +  and Arkansas Nuclear +
Start date
June 4, 2002  +
State
Washington +  and Arkansas +
System
Steam Generator +, Reactor Coolant System +, Service water +, Reactor Pressure Vessel +, Standby Liquid Control +  and Control Rod +
Title
Letter to Mr. Valeri Tolstykh Dated June 4, 2002 Operating Experience Report  +
To
International Atomic Energy Agency (IAEA) +  and Tolstykh V +
Topic
Boric Acid +, Nondestructive Examination +, VT-2 +, Stress corrosion cracking +, Pressure Boundary Leakage +, Through-Wall Leakage +, Backfit +, Unidentified leakage +  and Eddy-Current Testing +
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http://pbadupws.nrc.gov/docs/ML0215/ML021570378.pdf  +
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