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ML20217F007
Show incoming properties
Category
ARCHIVE RECORDS  and OPERATIONS SUPPORT-CALCULATIONS
ASME section
ASME Section XI +
Accession number
ML20217F007  +
Atomic Element
Carbon +, Oxygen +, Chloride +  and Lead +
Cornerstone
Initiating Events +  and Mitigating Systems +
Docket
05000368  +
Equipment trip
Turbine Trip +  and Reactor Trip +
From
Entergy +, INC. +, ABB COMBUSTION ENGINEERING NUCLEAR FUEL (FORMERLY +, Jaquith R +, Weston R +  and Bauer A +
Generic letter
NRC Generic Letter 88-01, NRC Position on Intergranular Stress Corrosion Cracking (IGSCC) in BWR Austenitic 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>.
ML20217F007 +, ML20217F007 +, ML20217F007 +, ML20217F007 +, ML20217F007 +, ML20217F007 +, ML20217F007 +, ML20217F007 +, ML20217F007 +, ML20217F007 +, ML20217F007 +, ML20217F007 +, ML20217F007 +, ML20217F007 +  and ML20217F007 +
In package
ML20217E904 +
Issue date
August 15, 1997  +
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>.
13:57:07, 3 December 2024  +
NRC bulletin
NRC Bulletin 79-13, Cracking in Feedwater System Piping +
Page count
65  +
Person
None none +
Procedure
AM +
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.
ML20217F007 +
Project stage
Request  +
Regulatory Guide
Regulatory Guide 1.36 +
SSC
2CV-0740 +, 2E-24B +, 2E-2 +, 2CV-0748 +, 2E-24A +, 2CV-1074-1 +, 07-17-002 +, 07-17-010 +, 07-17-015 +, 07-17-009 +, 07-17-023 +, 2CV-1024-1 +, 2CV-1023-2 +, 01A-2 +, 2E-248 +, 07-17-025 +, 07-19-008 +, 2FW-5A +, 2SV-0205 +, 2E-24 +, 2FW-5B +, 07-19-003 +, 07-19-010 +, 07-19-019 +, 07-19-014 +, 2CV-1024 +, 07-19-022 +, 2DBB-2-18 +, 2DBB-1-18 +, 07-64-003 +...
Site
Arkansas Nuclear +
Start date
August 15, 1997  +
State
Arkansas +
System
Steam Generator +, Feedwater +, Auxiliary Feedwater +, Decay Heat Removal +, Main Steam +  and Containment Spray +
Title
Rev 0 to A-PENG-CALC-018, Implementation of EPRI Risk- Informed ISI Evaluation for Main Feedwater Sys at ANO-2  +
Topic
Anticipated operational occurrence +, Internal Flooding +, High Energy Line Break +, Flow Accelerated Corrosion +, Feedwater Heater +, Intergranular Stress Corrosion Cracking +, Microbiologically influenced corrosion +, Stress corrosion cracking +, Loss of Offsite Power +, Thermal fatigue +  and Water hammer +
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http://pbadupws.nrc.gov/docs/ML2021/ML20217F007.pdf  +
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