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ML22131A096
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Category
Updated Final Safety Analysis Report (UFSAR)
ANSI code
ANSI B31.1 +, ANSI B31.1-1967 +  and ANSI N45.2.1-73 +
ASME section
ASME Section XI +, ASME Section III +  and ASME Section VIII +
Accession number
ML22131A096  +
Atomic Element
Boron +, Iodine +, Iron +, Nickel +, Copper +, Nitrogen +, Carbon +, Oxygen +, Sodium +, Hydrogen +, Chloride +, Lead +, Phosphorus +, Sulfur +  and Titanium +
CFR
10 CFR 20 +, 10 CFR 50 +  and 10 CFR 50 Appendix I +
Correspondence
ND-2300 +
Docket
05000443  +
Equipment trip
Turbine Trip +, Reactor Trip +  and Circulating water pump trip +
From
NextEra Energy Seabrook +
General design criterion
GDC 57 +  and GDC 51 +
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ML22131A096 +, ML22131A096 +, ML22131A096 +, ML22131A096 +, ML22131A096 +, ML22131A096 +, ML22131A096 +, ML22131A096 +, ML22131A096 +  and ML22131A096 +
In package
ML22131A110 +
Issue date
May 5, 2022  +
Licensing Basis Document
Updated Final Safety Analysis Report +
Manufacturer
Westinghouse +  and General Electric +
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>.
07:40:58, 7 February 2025  +
ND
ND-2300 +
NUREG
NUREG-0577, Forwards Request for Addl Info Re Low Fracture Toughness Since Facility Has Been Classified as Group 1 According to NUREG-0577.Response Should Be Submitted within 30 Days of Receipt of Ltr.Further NRC Evaluation Will Be Required +
Page count
149  +
Project stage
Request  +
Regulatory Guide
Regulatory Guide 1.50 +, Regulatory Guide 1.31 +, Regulatory Guide 1.44 +, Regulatory Guide 1.36 +, Regulatory Guide 1.67 +  and Regulatory Guide 1.37, Quality Assurance Requirements for Cleaning of Fluid Systems and Associated Components of Water-Cooled Nuclear Power Plants +
SSC
71-1E7-MSLRF-P1 +
Scram
Manual Scram +
Site
Seabrook +
Start date
May 5, 2022  +
System
Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Auxiliary Feedwater +, Main Turbine +, Residual Heat Removal +, Circulating Water System +, Main Steam Safety Valve +, Remote shutdown +, Stator Cooling Water +, Decay Heat Removal +, Main Steam Line +, Safety Relief Valve +, Main Condenser +, Main Steam +, Extraction steam +, Turbine Gland Sealing System +  and Emergency Feedwater System +
Title
1 to Updated Final Safety Analysis Report, Chapter 10, Steam and Power Conversion System  +
To
Office of Nuclear Reactor Regulation +
Topic
Safe Shutdown +, Boric Acid +, Ultimate heat sink +, Grab sample +, Offsite Dose Calculation Manual +, Stroke time +, Hydrostatic +, Nondestructive Examination +, High Energy Line Break +, Feedwater Heater +, Loss of Offsite Power +, Turbine Missile +, Overspeed trip +, Overspeed +, Loss of condenser vacuum +  and Water hammer +
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http://pbadupws.nrc.gov/docs/ML2213/ML22131A096.pdf  +
Ultimate Heat Sink
Cooling Tower +
 
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