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NG-17-0086, Transmittal of Revision 24 of the DAEC Updated Final Safety Analysis Report and the Current DAEC Technical Specifications Bases
Show incoming properties 
Category
Updated Final Safety Analysis Report (UFSAR), Technical Specification, Bases Change  and Letter type:NG
AR
AR 02065602 +
ASME section
ASME Section XI +
Accession number
ML17123A445  +
Atomic Element
Nitrogen +  and Zirconium +
CFR
10 CFR 50.73 +, 10 CFR 50.72 +, 10 CFR 50.67 +, 10 CFR 50 Appendix K +, 10 CFR 50 +, 10 CFR 50.59 +, 10 CFR 2.390 +, 10 CFR 50 Appendix G +, 10 CFR 50 Appendix H +, 10 CFR 54.34#b +, 10 CFR 50.73#a2iA +, 10 CFR 50.72#b1iA +, 10 CFR 54.37#b +, 10 CFR 50.36#c2ii +, 10 CFR 50.48#c +, 10 CFR 2.390#d +  and 10 CFR 50.71#e +
Docket
05000331  +  and 00331  +
Document
NG-11-0267, Transition to 10 CFR 50.48(c) - NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants (2001 Edition) (TSCR-128) +
Engineering change
EC-281991 +, EC-283472 +, EC-280489 +, EC-283160 +, EC-283717 +, EC-283505 +, EC-283522 +, EC-285633 +, EC-286818 +, EC-285995 +, EC-287263 +  and EC-284397 +
Equipment trip
Reactor Trip +
Exelon procedure
FP-AB-100 +
From
NextEra Energy +  and Dean Curtland +
Generic letter
NRC Generic Letter 08-01, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems +  and NRC Generic Letter 84-15, Proposed Staff Actions to Improve and Maintain Diesel Generator Reliability +
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>.
NG-17-0086, Transmittal of Revision 24 of the DAEC Updated Final Safety Analysis Report and the Current DAEC Technical Specifications Bases +, NG-17-0086, Transmittal of Revision 24 of the DAEC Updated Final Safety Analysis Report and the Current DAEC Technical Specifications Bases +, NG-17-0086, Transmittal of Revision 24 of the DAEC Updated Final Safety Analysis Report and the Current DAEC Technical Specifications Bases +, NG-17-0086, Transmittal of Revision 24 of the DAEC Updated Final Safety Analysis Report and the Current DAEC Technical Specifications Bases +, NG-17-0086, Transmittal of Revision 24 of the DAEC Updated Final Safety Analysis Report and the Current DAEC Technical Specifications Bases +, NG-17-0086, Transmittal of Revision 24 of the DAEC Updated Final Safety Analysis Report and the Current DAEC Technical Specifications Bases +, NG-17-0086, Transmittal of Revision 24 of the DAEC Updated Final Safety Analysis Report and the Current DAEC Technical Specifications Bases +, NG-17-0086, Transmittal of Revision 24 of the DAEC Updated Final Safety Analysis Report and the Current DAEC Technical Specifications Bases +, NG-17-0086, Transmittal of Revision 24 of the DAEC Updated Final Safety Analysis Report and the Current DAEC Technical Specifications Bases +, NG-17-0086, Transmittal of Revision 24 of the DAEC Updated Final Safety Analysis Report and the Current DAEC Technical Specifications Bases +, NG-17-0086, Transmittal of Revision 24 of the DAEC Updated Final Safety Analysis Report and the Current DAEC Technical Specifications Bases +, NG-17-0086, Transmittal of Revision 24 of the DAEC Updated Final Safety Analysis Report and the Current DAEC Technical Specifications Bases +, NG-17-0086, Transmittal of Revision 24 of the DAEC Updated Final Safety Analysis Report and the Current DAEC Technical Specifications Bases +, NG-17-0086, Transmittal of Revision 24 of the DAEC Updated Final Safety Analysis Report and the Current DAEC Technical Specifications Bases +  and NG-17-0086, Transmittal of Revision 24 of the DAEC Updated Final Safety Analysis Report and the Current DAEC Technical Specifications Bases +
Hours
2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +, 2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +, 1.388889e-4 d (0.00333 hours, 1.984127e-5 weeks, 4.566e-6 months)  +  and 5.555556e-4 d (0.0133 hours, 7.936508e-5 weeks, 1.8264e-5 months)  +
IEEE
IEEE 308 +
In package
ML17157B650 +
Issue date
April 28, 2017  +
Licensing Basis Document
Updated Final Safety Analysis Report +
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>.
13:48:36, 9 January 2025  +
NEI
NEI 98-03, Submittal of Revision No. 19 to Updated Safety Analysis Report for Monticello +
NFPA
NFPA 805 +
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
73  +
Person
Dean Curtland +
Power source
4.16kV +
Procedure
ES +  and RT +
Project stage
Request  +
Regulatory Guide
Regulatory Guide 1.137 +, Regulatory Guide 1.9 +, Regulatory Guide 1.108 +, Regulatory Guide 1.93 +  and Regulatory Guide 1.99 +
Report
NEDE-30021 +
SR
SR-3.5.1.4 +, SR-3.5.1 +, SR-3.8.1.7 +, SR-3.0.1 +, SR-3.8.3.2 +, SR-3.4.3.1 +, SR-3.0.4 +, SR-3.8.1.8 +, SR-3.8.1.2 +, SR-3.5.3.1 +, SR-3.5.1.2 +, SR-3.0.2 +, SR-3.5.1.5 +, SR-3.5.1.3 +, SR-3.8.3.1 +, SR-3.8.3.3 +, SR-3.5.3.4 +, SR-3.5.3.3 +, SR-3.8.1.6 +, SR-3.4.9.4 +, SR-3.4.9.1 +, SR-3.6.2.3.1 +, SR-3.4.9.3 +, SR-3.5.3.5 +, SR-3.5.2.4 +, SR-3.4.9.2 +, SR-3.4.9.5 +, SR-3.5 +, SR-3.6.2.4.2 +, SR-3.4.3.2 +...
Scram
Automatic Scram +
Site
Duane Arnold +
Site license
DPR-49 +
Start date
April 28, 2017  +
State
Washington +
System
Reactor Coolant System +, Service water +, Reactor Protection System +, Emergency Diesel Generator +, Primary containment +, Shutdown Cooling +, Reactor Pressure Vessel +, Core Spray +, Residual Heat Removal +, Automatic Depressurization System +, Circulating Water System +, Remote shutdown +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Safety Relief Valve +, Control Rod +, Main Steam +  and Containment Spray +
TS
TS-3.8.1 +, TS-3.3.1.1 +, TS-3.3.5.1 +, TS-3.8.2 +, TS-3.3.5.2 +, TS-3.6.1.5 +  and TS-3.3.6.3 +
Test
Bench test +
Title
Transmittal of Revision 24 of the DAEC Updated Final Safety Analysis Report and the Current DAEC Technical Specifications Bases  +
To
Office of Nuclear Reactor Regulation +  and Document Control Desk +
Topic
Safe Shutdown +, Unanalyzed Condition +, Time of Discovery +, Reactor Vessel Water Level +, Stroke time +, Slow transfer +, Anticipated operational occurrence +, Internal Flooding +, Hydrostatic +, FLEX +, Abnormal operational transient +, Surveillance Frequency Control Program +, Fuel cladding +, Offsite Circuit +, Gas accumulation +, Operational convenience +  and Pressure Temperature Limits Report +
Turbine component
Turbine bypass valve +
URL"URL" is a <a href="/Special:Types/URL" title="Special:Types/URL">type</a> and predefined property provided by <a rel="nofollow" class="external text" href="https://www.semantic-mediawiki.org/wiki/Help:Special_properties">Semantic MediaWiki</a> to represent URI/URL values.
http://pbadupws.nrc.gov/docs/ML1712/ML17123A445.pdf  +
Ultimate Heat Sink
Cooling Tower +
 
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