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ML18038A322
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Category
CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE  and UTILITY TO NRC
ANSI code
ANSI/ANS 3.5 +, ANSI 3.5 +, ANSI A3.3 +  and ANSI 81.2.3 +
Accession number
ML18038A322  +
Administrative procedure
AP-6.0 +, AP-6.1 +  and AP-6.2 +
Atomic Element
Hydrogen +, Lead +  and Tin +
CFR
10 CFR 55 +  and 10 CFR 55.45#b5 +
Correspondence
ND-100 +
Docket
05000410  +  and 00410  +
Drawing
ESK-5SWP1-12 +
Equipment trip
Turbine Trip +
From
Burkhardt L +  and Niagara Mohawk +
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>.
ML18038A322 +, ML18038A322 +, ML18038A322 +, ML18038A322 +, ML18038A322 +, ML18038A322 +, ML18038A322 +, ML18038A322 +, ML18038A322 +, ML18038A322 +  and ML18038A322 +
Issue date
August 24, 1990  +
Manufacturer
General Electric +
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>.
06:05:52, 7 January 2025  +
ND
ND-100 +
NRC form
NRC Form 474 +
NUREG
NUREG-1021, Revised Effectiveness Review Plan for NUREG-1021 Revision 12 (Public) +
Page count
121  +
Power source
115KV +  and 4.16KV +
Procedure
MST +, ES +  and CH +
Regulatory Guide
Regulatory Guide 1.149 +
SSC
T2HJB-UB1 +, T2BTX-XHBL +, 2BLB-VEX3A +, 2SLS-VEX3B +, 2IHC-3 +  and 2SWP-2 +
Scram
Manual Scram +
Site
Nine Mile Point +
Site license
Nine Mile Point +
Start date
August 24, 1990  +
State
Washington +  and New York +
System
Reactor Coolant System +, Feedwater +, Service water +, Main Steam Isolation Valve +, Reactor Core Isolation Cooling +, Primary containment +, Main Turbine +, Reactor Recirculation Pump +, High Pressure Core Spray +, Core Spray +, Residual Heat Removal +, Intermediate Range Monitor +, Main Steam Line +, Safety Relief Valve +, Moisture Separator Reheater +  and Control Rod +
Title
Forwards NRC Form 474, Simulation Facility Certification & Supporting Documentation  +
To
Office of Information Resources Management +
Topic
Emergency Lighting +, Job Performance Measure +, Feedwater Heater +, Fuel cladding +  and Coast down +
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http://pbadupws.nrc.gov/docs/ML1803/ML18038A322.pdf  +
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