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ML18304A062
Show incoming properties 
Category
Updated Final Safety Analysis Report (UFSAR)
ASME section
ASME Section IV +
Accession number
ML18304A062  +
Atomic Element
Boron +, Iodine +, Cesium +, Iron +, Nitrogen +, Carbon +, Oxygen +, Sodium +, Hydrogen +  and Lead +
CFR
10 CFR 50.67 +, 10 CFR 20 +, 10 CFR 100 +, 10 CFR 20.1902 +  and 10 CFR 20.2206 +
Correspondence
NL-18-069, Submittal of Revision 27 to Updated Final Safety Analysis Report +
Docket
05000247  +
Emergency Facility
Technical Support Center +
Engineering change
EC-31455 +  and EC-26250 +
Entergy procedure
EN-DC-162 +
Equipment
Portal monitor +
From
Entergy +
General design criterion
GDC 69 +, GDC 68 +, GDC 70 +  and GDC 17, Electric power systems +
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>.
ML18304A062 +, ML18304A062 +, ML18304A062 +, ML18304A062 +, ML18304A062 +, ML18304A062 +, ML18304A062 +, ML18304A062 +, ML18304A062 +  and ML18304A062 +
Hours
6.481481e-4 d (0.0156 hours, 9.259259e-5 weeks, 2.1308e-5 months)  +
In package
ML18304A080 +
Isotope
Tritium +, Co-60 +, Cs-137 +, Sr-90 +, Y-90 +, I-131 +, N-16 +, Nitrogen-16 +, Iodine-131 +, Mo-99 +  and Mn-54 +
Issue date
September 17, 2018  +
License amendment topic
Alternate Source Term +
Licensing Basis Document
Updated Final Safety Analysis Report +
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>.
15:02:37, 5 January 2025  +
NL
NL-18-069, Submittal of Revision 27 to Updated Final Safety Analysis Report +
NUREG
NUREG-1465, Provides Commission W/Results & Findings of Evaluation of Impact of Implementing Revised Source Term Described in NUREG-1465, Accident Source Terms for Light-Water Npps, for Operating Reactors +  and NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +
Page count
55  +
Power source
4V +
Project stage
Request  +
SSC
4x10-7 +, 2x10-7 +, 1x10-7 +, 1x10-4 +, 1x10-5 +, 2x10-6 +, 4x10-5 +, 11B-1 +, 11B-2 +, 11B-3 +, 11B-4 +, 11B-5 +, 5x10-8 +, 1x10-10 +, 6x10-5 +, 332x10-12 +, 8x10-7 +, 1x10-1 +, 8x10-3 +, 6x10-6 +, 3x10-12 +, 6x10-10 +, 4x10-4 +, 8x10-4 +, 2x10-16 +, 8x10-8 +, 11D-1 +, 11D-2 +, 11E-2 +...
Site
Indian Point +
Start date
September 17, 2018  +
State
New York +
System
Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Emergency Diesel Generator +, Residual Heat Removal +, Main Steam Line +, Control Rod +  and Containment Spray +
TS
TS-5.2.5 +
Title
7 to Updated Final Safety Analysis Report, Chapter 11, Waste Disposal and Radiation Protection System  +
To
Office of Nuclear Reactor Regulation +
Topic
Boric Acid +, Loop seal +, High Radiation Area +, Grab sample +, Offsite Dose Calculation Manual +, Safe Shutdown Earthquake +, Coatings +, Notice of Violation +, Annual Radiological Environmental Operating Report +, Process Control Program +, Loss of Offsite Power +, Main Steam Line Radiation Monitor +, Earthquake +, Fuel cladding +  and Depleted uranium +
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http://pbadupws.nrc.gov/docs/ML1830/ML18304A062.pdf  +
 
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