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ML20134C683
Show incoming properties 
Category
TECHNICAL SPECIFICATIONS & TEST REPORTS  and TEST/INSPECTION/OPERATING PROCEDURES
ASME section
ASME Section XI +
Accession number
ML20134C683  +
Atomic Element
Boron +  and Nitrogen +
CR
LO-PROC-9701-00031 +
Cross cutting aspect
S.2(y) +
Docket
05000445  +, 05000446  +  and 00445  +
Drawing
FV-2456 +, FV-2457 +, FV-4650A +, FV-4650B +, FV-4536 +, FV-4537 +  and FV-24538 +
Equipment trip
Reactor Trip +
From
Luminant +  and Mays R +
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>.
ML20134C683 +, ML20134C683 +, ML20134C683 +, ML20134C683 +, ML20134C683 +, ML20134C683 +, ML20134C683 +, ML20134C683 +, ML20134C683 +, ML20134C683 +  and ML20134C683 +
In package
ML20134C682 +
Issue date
January 31, 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>.
10:37:07, 12 December 2024  +
NRC information notice
Information Notice 87-01 +
NUREG
NUREG-1482, Revision 4, Guidelines for Inservice Testing at Nuclear Power Plants: Inservice Testing of Pumps and Valves and Inservice Examination and Testing of Dynamic Restraints (Snubbers) at Nuclear Power Plants Final Report +
Page count
100  +
Procedure
CH-0305 +, CH-0300 +, CH-0301 +, CH-0302 +, CH-0600 +  and CH-0601 +
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ML20134C683 +
Project stage
Request  +
SSC
2AF-0291 +, 2AF-0236 +, 2AF-0237 +, 2AF-0238 +, 2CS-8000 +, 2CC-1090 +, 2CC-1091 +, 2CC-1092 +, 2CC-1093 +, 2CC-1094 +, 1AF-0215 +, 1AF-0216 +, 1AF-0217 +, 1AF-0218 +, 1AF-0220 +, 2AF-0239 +, 2AF-0240 +, 2CC-0371 +, 2CC-0372 +, 2CC-0373 +, 2CC-0374 +, 2AF-0223 +, 2AF-0226 +, 2AF-0230 +, 1AF-0223 +, 2AF-0224 +, 2AF-0227 +, 1AF-0230 +, 2AF-0231 +, 1AF-0226 +...
Site
Comanche Peak +
Start date
January 31, 1997  +
System
Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Auxiliary Feedwater +, Shutdown Cooling +, Residual Heat Removal +, Emergency Core Cooling System +  and Containment Spray +
TS
TS-4.4.5.2 +, TS-4.5.2 +  and TS-4.4.8.3 +
Title
Rev 8 to Comanche Peak Steam Electric Station Units 1 & 2 Inservice Testing Plan for Pumps & Valves First Interval  +
Topic
Boric Acid +, Stroke time +  and Power Operated Valves +
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http://pbadupws.nrc.gov/docs/ML2013/ML20134C683.pdf  +
 
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