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ML20154L992
Show incoming properties
Category
CORRESPONDENCE-LETTERS  and INCOMING CORRESPONDENCE
Accession number
ML20154L992  +
Atomic Element
Hydrogen +  and Lead +
CFR
10 CFR 20 +, 10 CFR 55.43 +, 10 CFR 55.43#b6 +  and 10 CFR 55.43#b +
Docket
05000498  +, 05000499  +  and 00498  +
Drawing
FV-9776 +
Equipment trip
Turbine Trip +  and Reactor Trip +
From
Creating Houston Lighting and Power Company +  and Chitwood G +
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>.
ML20154L992 +, ML20154L992 +, ML20154L992 +, ML20154L992 +, ML20154L992 +, ML20154L992 +, ML20154L992 +, ML20154L992 +, ML20154L992 +, ML20154L992 +, ML20154L992 +  and ML20154L992 +
Hours
6.944444e-5 d (0.00167 hours, 9.920635e-6 weeks, 2.283e-6 months)  +
In package
ML20154L930 +
Issue date
February 27, 1998  +
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>.
05:02:39, 11 December 2024  +
NUREG
NUREG-1021, Revised Effectiveness Review Plan for NUREG-1021 Revision 12 (Public) +
Page count
84  +
Power source
4.16KV +
Procedure
PSP +, Emergency Operating Procedure +, CP-3 +, CP-10 +, ES-401 +, ES-401-5 +, ES-301-1 +, ES-301-2 +, ES-301-5 +, ES-301-6 +, ES-401-3 +, ES-D-1 +, ES-D-2 +, ES-301 +  and RT-8038 +
SSC
9M01-A1 +, 5M03-E2 +  and 0POPO4-RP-0004 +
Scram
Manual Scram +  and Automatic Scram +
Site
South Texas +
Start date
February 27, 1998  +
State
Texas +
System
Steam Generator +, Reactor Coolant System +, Main Steam Isolation Valve +, Residual Heat Removal +, Main Steam Line +, Main Condenser +, Control Rod +, Main Steam +  and Containment Spray +
TS
TS-3.7.3 +  and TS-3.3.1 +
Title
Provides Draft Exam Matls for Plant Senior Reactor Upgrade Exam,Scheduled for 980601  +
To
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) +  and Bundy H +
Topic
Probabilistic Risk Assessment +  and Core Exit Thermocouple +
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http://pbadupws.nrc.gov/docs/ML2015/ML20154L992.pdf  +
Retrieved from "https://kanterella.com/Special:Browse/:ML20154L992"