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ML22340A183
Show incoming properties
Category
Updated Final Safety Analysis Report (UFSAR)
ASME section
ASME Section III +  and ASME Section IX +
Accession number
ML22340A183  +
Atomic Element
Boron +, Nickel +, Copper +, Nitrogen +, Carbon +, Oxygen +, Hydrogen +, Cadmium +, Chloride +, Lead +  and Helium +
CFR
10 CFR 50 +, 10 CFR 50.61 +  and 10 CFR 50.55#a +
Code case
ASME Code Case N-10 +
Cross cutting aspect
P.3 +
Docket
05000315  +  and 05000316  +
Equipment trip
Turbine Trip +  and Reactor Trip +
From
Indiana Michigan Power Co +
Generic letter
NRC Generic Letter 84-04, Safety Evaluation of Westinghouse Topical Reports Dealing with Elimination of Postulated Pipe Breaks in PWR Primary Main Loops (Generic Letter 84-04) +
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>.
ML22340A183 +, ML22340A183 +, ML22340A183 +, ML22340A183 +, ML22340A183 +, ML22340A183 +, ML22340A183 +, ML22340A183 +, ML22340A183 +  and ML22340A183 +
In package
ML22340A137 +
Isotope
U-238 +
Issue date
November 30, 2022  +
Licensing Basis Document
Updated Final Safety Analysis Report +
Manufacturer
Westinghouse +
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16:57:18, 27 November 2024  +
NUREG
NUREG/CR-6721 +
Page count
1  +
Procedure
MP +
Project stage
Request  +
Regulatory Guide
Regulatory Guide 1.133 +
Site
Cook +
Start date
November 30, 2022  +
State
Indiana +  and Michigan +
System
Steam Generator +, Reactor Coolant System +, Feedwater +, Reactor Protection System +, Auxiliary Feedwater +, Reactor Pressure Vessel +, Residual Heat Removal +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Control Rod +, Main Steam +  and Containment Spray +
Title
1 to Updated Final Safety Analysis Report, Chapter 4, Reactor Coolant System  +
To
Office of Nuclear Reactor Regulation +
Topic
Safe Shutdown +, Boric Acid +, Reactor Vessel Water Level +, Loop seal +, Hydrostatic +, Operating Basis Earthquake +, Nondestructive Examination +, Design basis earthquake +, Stress corrosion cracking +, License Renewal +, Earthquake +, Fuel cladding +, Liquid penetrant +, Power change +, Core Exit Thermocouple +, Power Uprate +, Overspeed +, Water hammer +  and Leak-Before-Break +
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http://pbadupws.nrc.gov/docs/ML2234/ML22340A183.pdf  +
WCAP
WCAP-12135 +, WCAP-15131 +, WCAP-18455-NP +  and WCAP-7927 +
Westinghouse report
WCAP-12135 +, WCAP-15131 +, WCAP-18455-NP +  and WCAP-7927 +
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