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ML042120323
Show incoming properties
Category
Letter
ASME section
ASME Section III +  and ASME Section XI +
Accession number
ML042120323  +
Atomic Element
Carbon +
CFR
10 CFR 50.73 +, 10 CFR 50 +, 10 CFR 50 Appendix B +, 10 CFR 50.55a +  and 10 CFR 50.54#f +
Docket
05000528  +, 05000529  +  and 05000530  +
Effective date
January 2, 2004  +
Equipment trip
Reactor Trip +
From
Mauldin D +  and Arizona Public Service +
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 +
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>.
ML042120323 +, ML042120323 +, ML042120323 +, ML042120323 +, ML042120323 +, ML042120323 +, ML042120323 +, ML042120323 +, ML042120323 +, ML042120323 +  and ML042120323 +
Issue date
July 22, 2004  +
Licensing Basis Document
Updated Final Safety Analysis Report +
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>.
07:01:05, 16 January 2025  +
NEI
NEI 03-08, Notification of Deviation from Electric Power Research Institute (EPRI) Materials Reliability Program (MRP) 2019-008, Materials Reliability Program: Interim Guidance for NEI 03-08 Needed Requirements for Us PWR Plants . +
NRC bulletin
NRC Bulletin 04-01 +
Page count
31  +
Procedure
RT +, RT-02-003 +, RT-02-001 +, RT-93-1368 +, RT-93-2632 +, RT-00-2099 +  and RT-94-3076 +
Project reference
TAC:MB8074 +  and TAC:MB1618 +
Project stage
Request  +
SSC
70TI-9ZC01 +, 73TI-9ZZ78 +  and 73T1-9ZZ78 +
Site
Palo Verde +
Start date
July 22, 2004  +
State
Texas +, Arizona +  and Maryland +
System
Main Turbine +  and Reactor Coolant System +
TS
TS-3.4.14 +
Title
APS 60-Day Response to the Information Requested by NRC Bulletin 2004-01  +
To
Document Control Desk +  and Office of Nuclear Reactor Regulation +
Topic
Boric Acid +, Non-Destructive Examination +, Hydrostatic +, VT-2 +, Condition Adverse to Quality +, Stress corrosion cracking +, Eddy Current Testing +, Liquid penetrant +, Pressure Boundary Leakage +, Through-Wall Leakage +, Dissimilar Metal Weld +, Unidentified leakage +, Affidavit +  and Operational leakage +
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http://pbadupws.nrc.gov/docs/ML0421/ML042120323.pdf  +
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