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ML23291A413
Show incoming properties
Category
Updated Final Safety Analysis Report (UFSAR)
ASME section
ASME Section III +  and ASME Section XI +
Accession number
ML23291A413  +
Area
Switchyard +
Atomic Element
Boron +, Oxygen +, Hydrogen +, Xenon +  and Hafnium +
CFR
10 CFR 50.67 +, 10 CFR 50 Appendix A +, 10 CFR 20 +, 10 CFR 50 Appendix K +, 10 CFR 50 +, 10 CFR 72 +, 10 CFR 50.44 +, 10 CFR 50 Appendix I +, 10 CFR 72.124 +, 10 CFR 72.126 +, 10 CFR 50.36a +, 10 CFR 50.55a +  and 10 CFR 72.125 +
Correspondence
PLA-8081, 1 to Updated Final Safety Analysis Report, Questions and Responses 121.1 Through 121.21 +
Docket
05000387  +  and 05000388  +
From
Susquehanna +
General design criterion
GDC 51 +, GDC 2, Design bases for protection against natural phenomena +, GDC 4, Environmental and dynamic effects design bases +, GDC 1, Quality standards and records +  and GDC 3, Fire protection +
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ML23291A413 +, ML23291A413 +, ML23291A413 +, ML23291A413 +, ML23291A413 +, ML23291A413 +, ML23291A413 +, ML23291A413 +, ML23291A413 +  and ML23291A413 +
In package
ML23291A105 +
Issue date
October 12, 2023  +
Licensing Basis Document
Updated Final Safety Analysis Report +
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>.
13:15:12, 25 November 2024  +
NRC information notice
Information Notice 88-39 +
Page count
1  +
Project stage
Request  +
Regulatory Guide
Regulatory Guide 1.183 +, Regulatory Guide 1.75 +, Regulatory Guide 1.52 +  and Regulatory Guide 1.21 +
Report
NEDO-32465 +, NEDO-31960 +  and NEDC-32410P +
Scram
Manual Scram +  and Automatic Scram +
Site
Susquehanna +
Start date
October 12, 2023  +
System
Steam Generator +, Reactor Coolant System +, Feedwater +, Secondary containment +, Service water +, High Pressure Coolant Injection +, Reactor Protection System +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Reactor Core Isolation Cooling +, Primary containment +, Shutdown Cooling +, HVAC +, Reactor Pressure Vessel +, Core Spray +, Reactor Building Ventilation +, Residual Heat Removal +, Standby Gas Treatment System +, Fuel Pool Cooling and Cleanup +, Automatic Depressurization System +, Standby Liquid Control +, Intermediate Range Monitor +, Remote shutdown +, Residual Heat Removal Service Water +, Spray Pond +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Safety Relief Valve +, Rod Worth Minimizer +...
Title
1 to Updated Final Safety Analysis Report, Chapter 3, Section 3.1, Conformance with NRC General Design Criteria  +
To
Office of Nuclear Reactor Regulation +
Topic
Safe Shutdown +, Ultimate heat sink +, Anticipated operational occurrence +, Abnormal operational transient +, Scram Discharge Volume +, Process Control Program +, Loss of Offsite Power +, Integrated leak rate test +, Earthquake +, Fuel cladding +, Pressure Boundary Leakage +, Fire Protection Program +, Power change +, Unidentified leakage +  and Spent fuel rack +
Trip
Turbine Control Valve Fast Closure +
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http://pbadupws.nrc.gov/docs/ML2329/ML23291A413.pdf  +
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