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ML23129A269
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Category
Updated Final Safety Analysis Report (UFSAR)
ASME section
ASME Section I +
Accession number
ML23129A269  +
Act
Atomic Energy Act of 1954 +  and Energy Reorganization Act of 1974 +
Atomic Element
Boron +, Uranium +, Nitrogen +, Carbon +, Hydrogen +, Xenon +  and Zirconium +
CFR
10 CFR 50.67 +, 10 CFR 50 Appendix A +, 10 CFR 20 +, 10 CFR 50.46 +, 10 CFR 50 Appendix K +, 10 CFR 50 +, 10 CFR 50.63 +, 10 CFR 50.59 +, 10 CFR 61 +, 10 CFR 50.49 +, 10 CFR 50.62 +, 10 CFR 50.54#a +, 10 CFR 50.34#b +, 10 CFR 50.59#a +, 10 CFR 50.55a#g +  and 10 CFR 50.71#e +
Committee
Advisory Committee on Reactor Safeguards +
Docket
05000298  +  and 00298  +
Equipment trip
Turbine Trip +
From
Nebraska Public Power District +
Generic letter
NRC Generic Letter 83-28, Required Actions Based on Generic Implications of Salem ATWS Events +
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ML23129A269 +, ML23129A269 +, ML23129A269 +, ML23129A269 +, ML23129A269 +, ML23129A269 +, ML23129A269 +, ML23129A269 +, ML23129A269 +  and ML23129A269 +
IEEE
IEEE 279 +
In package
ML23129A261 +
Isotope
U-235 +  and H-3 +
Issue date
April 20, 2023  +
Manufacturer
General Electric +  and 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>.
10:02:03, 27 November 2024  +
NFPA
NFPA 805 +
Page count
1  +
Person
None none +
Power source
345kV +
Procedure
CP +
Project stage
Request  +
Report
NEDO-10045 +  and NEDO-10189 +
Site
Cooper +
Start date
April 20, 2023  +
State
Connecticut +, California +, Nebraska +  and Vermont +
System
Reactor Coolant System +, Feedwater +, Secondary containment +, Service water +, High Pressure Coolant Injection +, Reactor Protection System +, Reactor Core Isolation Cooling +, Primary containment +, Main Turbine +, Shutdown Cooling +, Core Spray +, Residual Heat Removal +, Reactor Water Cleanup +, Standby Gas Treatment System +, Fuel Pool Cooling and Cleanup +, Automatic Depressurization System +, Standby Liquid Control +, Circulating Water System +, Intermediate Range Monitor +, Core Standby Cooling System +, Emergency Core Cooling System +, Main Steam Line +, Rod Worth Minimizer +, Control rod blade +, Main Condenser +  and Control Rod +
TS
TS-1.1 +
Title
1 to Updated Safety Analysis Report, Section I, Introduction and Summary  +
To
Office of Nuclear Reactor Regulation +
Topic
Safe Shutdown +, Reactor Vessel Water Level +, Ultimate heat sink +, Anticipated operational occurrence +, Safe Shutdown Earthquake +, Incorporated by reference +, Abnormal operational transient +, Process Control Program +, Earthquake +, Deep Dose Equivalent +, Turbine Missile +, Fuel cladding +, Fire Protection Program +, Power Uprate +, Measurement Uncertainty Recapture +, Overexposure +  and Control Room Habitability +
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http://pbadupws.nrc.gov/docs/ML2312/ML23129A269.pdf  +
 
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