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ML21125A472
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Category
Updated Final Safety Analysis Report (UFSAR)
ACI
ACI-318 +
ANSI code
ANSI B31.1 +  and ANSI B31.1.0-1967 +
ASME section
ASME Section III +
Accession number
ML21125A472  +
Atomic Element
Boron +, Sodium +, Lead +, Helium +  and Aluminum +
CFR
10 CFR 50.49 +
Correspondence
RS-80-01 +
Docket
05000315  +  and 05000316  +
Engineering change
EC-0000051586 +
Equipment trip
Turbine Trip +  and Reactor Trip +
From
Indiana Michigan Power Co +
Generic letter
NRC Generic Letter 87-11, Relaxation in Arbitrary Intermediate Pipe Rupture Requirements +
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>.
ML21125A472 +, ML21125A472 +, ML21125A472 +, ML21125A472 +, ML21125A472 +, ML21125A472 +, ML21125A472 +, ML21125A472 +, ML21125A472 +  and ML21125A472 +
Hours
0.00194 d (0.0467 hours, 2.777778e-4 weeks, 6.3924e-5 months)  +
IEEE
IEEE 279 +
In package
ML21126A238 +
Issue date
April 19, 2021  +
Licensing Basis Document
Updated Final Safety Analysis Report +
Manufacturer
Westinghouse +
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14:12:12, 29 November 2024  +
NRC information notice
Information Notice 84-90 +
NUREG
NUREG-800 +  and NUREG/CR-2913, Amend 181 to License DPR-72,incorporating Changes to GL 87-01, Relaxation in Arbitrary Intermediate Pipe Rupture Requirements, & NUREG/CR-2913, Two-Phase Jet Loads, +
Page count
53  +
Power source
4kV +  and 600V +
Project reference
TAC:MA8893 +
Project stage
Request  +
RS
RS-80-01 +
SSC
3l8-63 +
Site
Cook +
Start date
April 19, 2021  +
State
Indiana +  and Michigan +
System
Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Main Steam Isolation Valve +, Auxiliary Feedwater +, HVAC +, Residual Heat Removal +, Main Steam Line +, Control Rod +, Main Steam +  and Containment Spray +
Title
0 to Updated Final Safety Analysis Report, Chapter 14.4, Environmental Qualification Analyses (Unit 2)  +
To
Office of Nuclear Reactor Regulation +
Topic
Safe Shutdown +, Boric Acid +, Anticipated operational occurrence +, Operating Basis Earthquake +, High Energy Line Break +, Design basis earthquake +, Feedwater Heater +, Loss of Offsite Power +, GOTHIC +, Measurement Uncertainty Recapture +  and Control Room Habitability +
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http://pbadupws.nrc.gov/docs/ML2112/ML21125A472.pdf  +
WCAP
WCAP-8078 +  and WCAP-7391 +
Westinghouse report
WCAP-8078 +  and WCAP-7391 +
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