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AEP-NRC-2022-62, 1 to Updated Final Safety Analysis Report, Chapter 14.3, Reactor Coolant System Pipe Rupture (Loss of Coolant Accident) (Unit 1)
Show incoming properties 
Category
Updated Final Safety Analysis Report (UFSAR)  and Graphics incl Charts and Tables
ANSI code
ANSI/ANS-5.1-1979 +
Accession number
ML22340A216  +
Atomic Element
Boron +, Iodine +, Cesium +, Nitrogen +, Sodium +, Hydrogen +, Xenon +, Chloride +, Lead +  and Calcium +
CFR
10 CFR 50.67 +, 10 CFR 50.46 +, 10 CFR 50 Appendix K +, 10 CFR 50 +, 10 CFR 50.46#b1 +, 10 CFR 50.46#b +, 10 CFR 50.46#b5 +  and 10 CFR 50.46#b4 +
Correspondence
SECY-83-472 +
Cross cutting aspect
P.2(g) +
Docket
05000315  +, 05000316  +, 00315  +, 00413  +  and 00414  +
Document
ML073480324 +, ML073520295 +, ML043280007 +, ML043280631 +  and ML041550332 +
Equipment trip
Reactor Trip +
From
Indiana Michigan Power Co +
Fuel cladding
ZIRLO +
General design criterion
GDC 4, Environmental and dynamic effects design bases +  and GDC 50 +
Generic letter
NRC Generic Letter 04-02 +
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>.
AEP-NRC-2022-62, 1 to Updated Final Safety Analysis Report, Chapter 14.3, Reactor Coolant System Pipe Rupture (Loss of Coolant Accident) (Unit 1) +, AEP-NRC-2022-62, 1 to Updated Final Safety Analysis Report, Chapter 14.3, Reactor Coolant System Pipe Rupture (Loss of Coolant Accident) (Unit 1) +, AEP-NRC-2022-62, 1 to Updated Final Safety Analysis Report, Chapter 14.3, Reactor Coolant System Pipe Rupture (Loss of Coolant Accident) (Unit 1) +, AEP-NRC-2022-62, 1 to Updated Final Safety Analysis Report, Chapter 14.3, Reactor Coolant System Pipe Rupture (Loss of Coolant Accident) (Unit 1) +, AEP-NRC-2022-62, 1 to Updated Final Safety Analysis Report, Chapter 14.3, Reactor Coolant System Pipe Rupture (Loss of Coolant Accident) (Unit 1) +, AEP-NRC-2022-62, 1 to Updated Final Safety Analysis Report, Chapter 14.3, Reactor Coolant System Pipe Rupture (Loss of Coolant Accident) (Unit 1) +, AEP-NRC-2022-62, 1 to Updated Final Safety Analysis Report, Chapter 14.3, Reactor Coolant System Pipe Rupture (Loss of Coolant Accident) (Unit 1) +, AEP-NRC-2022-62, 1 to Updated Final Safety Analysis Report, Chapter 14.3, Reactor Coolant System Pipe Rupture (Loss of Coolant Accident) (Unit 1) +, AEP-NRC-2022-62, 1 to Updated Final Safety Analysis Report, Chapter 14.3, Reactor Coolant System Pipe Rupture (Loss of Coolant Accident) (Unit 1) +, AEP-NRC-2022-62, 1 to Updated Final Safety Analysis Report, Chapter 14.3, Reactor Coolant System Pipe Rupture (Loss of Coolant Accident) (Unit 1) +  and AEP-NRC-2022-62, 1 to Updated Final Safety Analysis Report, Chapter 14.3, Reactor Coolant System Pipe Rupture (Loss of Coolant Accident) (Unit 1) +
Hours
5.787037e-5 d (0.00139 hours, 8.267196e-6 weeks, 1.9025e-6 months)  +, 4.166667e-4 d (0.01 hours, 5.952381e-5 weeks, 1.3698e-5 months)  +, 5.555556e-4 d (0.0133 hours, 7.936508e-5 weeks, 1.8264e-5 months)  +, 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +, 1.851852e-4 d (0.00444 hours, 2.645503e-5 weeks, 6.088e-6 months)  +  and 3.472222e-4 d (0.00833 hours, 4.960317e-5 weeks, 1.1415e-5 months)  +
In package
ML22340A137 +
Isotope
U-235 +, U-238 +  and Pu-239 +
Issue date
November 30, 2022  +
License amendment topic
Alternate Source Term +
Licensing Basis Document
Updated Final Safety Analysis Report +
Manufacturer
Westinghouse +
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>.
00:32:05, 3 January 2025  +
NEI
NEI 04-07, Response to Request No. 2 in NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors. +
NUREG
NUREG/CR-5950 +, NUREG/CR-5249 +, NUREG/CR-6808 +, NUREG/CR-2900 +, NUREG/CR-5768 +, NUREG-0611, Forwards Safety Evaluation Finding Auxiliary Feedwater Sys Adequately Designed,Maintained & Operated.Finding Predicated on Implementation of Listed Recommendations Agreed to During 860929-1002 Visit +  and NUREG-1061, Summary of 890217 Meeting W/Util in Rockville,Md Re Resolution of Open Civil/Seismic Issues for Plant.List of Attendees & Slide Presentation Encl +
Page count
1  +
Project reference
TAC:MB9483 +  and TAC:MA6473 +
Project stage
Request  +
Regulatory Guide
Regulatory Guide 1.183 +, Regulatory Guide 1.97 +  and Regulatory Guide 1.157 +
SECY
SECY-83-472 +
Site
Cook +
Start date
November 30, 2022  +
State
Indiana +  and Michigan +
System
Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Auxiliary Feedwater +, HVAC +, Reactor Pressure Vessel +, Residual Heat Removal +, Emergency Core Cooling System +, Main Steam Line +, Control Rod +, Main Steam +  and Containment Spray +
Title
1 to Updated Final Safety Analysis Report, Chapter 14.3, Reactor Coolant System Pipe Rupture (Loss of Coolant Accident) (Unit 1)  +
To
Office of Nuclear Reactor Regulation +
Topic
Boric Acid +, Shutdown Margin +, Loop seal +, Mission time +, Fire Barrier +, Hydrostatic +, Coatings +, High Energy Line Break +, Loss of Offsite Power +, Earthquake +, Fuel cladding +, Power Uprate +, Measurement Uncertainty Recapture +, Leak-Before-Break +  and Leak Before Break +
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/ML2234/ML22340A216.pdf  +
Vendor
Framatome +  and MPR Associates +
WCAP
WCAP-8110 +, WCAP-16406-P +, WCAP-8822 +, WCAP-16793 +, WCAP-10325-P-A +, WCAP-17721-P +, WCAP-17721-NP +, WCAP-8354-P-A +, WCAP-8355-A +, WCAP-10079-P-A +, WCAP-10054-P-A +, WCAP-8301 +, WCAP-10326-A +, WCAP-7907-A +, WCAP-8860 +, WCAP-16009-P-A +, WCAP-12945-P-A +, WCAP-13451 +, WCAP-8709-A +, WCAP-8264-P-A +, WCAP-16793-NP +, WCAP-16530-NP +, WCAP-11145-P-A +, WCAP-8077 +, WCAP-8078 +, WCAP-15245 +, WCAP-15246 +, WCAP-8354 +, WCAP-8355 +, WCAP-9558 +...
Westinghouse report
WCAP-8110 +, WCAP-16406-P +, WCAP-8822 +, WCAP-16793 +, WCAP-10325-P-A +, WCAP-17721-P +, WCAP-17721-NP +, WCAP-8354-P-A +, WCAP-8355-A +, WCAP-10079-P-A +, WCAP-10054-P-A +, WCAP-8301 +, WCAP-10326-A +, WCAP-7907-A +, WCAP-8860 +, WCAP-16009-P-A +, WCAP-12945-P-A +, WCAP-13451 +, WCAP-8709-A +, WCAP-8264-P-A +, WCAP-16793-NP +, WCAP-16530-NP +, WCAP-11145-P-A +, WCAP-8077 +, WCAP-8078 +, WCAP-15245 +, WCAP-15246 +, WCAP-8354 +, WCAP-8355 +, WCAP-9558 +...
 
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