Browse wiki

Jump to navigation Jump to search
RC-18-0080, Virgil C. Summer Nuclear Station, Unit 1, Updated Final Safety Analysis Report, Chapter 10.0, Steam and Power Conversion System
Show incoming properties 
Category
Updated Final Safety Analysis Report (UFSAR)
ANSI code
ANSI B31.1 +, ANSI B16.5 +, ANSI N45.2.1 +  and ANSI B31.1.0 +
ASME section
ASME Section XI +, ASME Section III +  and ASME Section VIII +
Accession number
ML18221A180  +
Atomic Element
Boron +, Iodine +, Iron +, Carbon +, Oxygen +, Sodium +, Hydrogen +, Chloride +, Lead +  and Lithium +
CFR
10 CFR 50.55a +
Correspondence
L 13 +, L 11 +  and ND-2311 +
Docket
05000395  +
Drawing
FV-3536 +, FV-3541 +, FV-3551 +, FV-3546 +  and FV-3556 +
Equipment trip
Turbine Trip +  and Reactor Trip +
From
South Carolina Electric & Gas Company +
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>.
RC-18-0080, Virgil C. Summer Nuclear Station, Unit 1, Updated Final Safety Analysis Report, Chapter 10.0, Steam and Power Conversion System +, RC-18-0080, Virgil C. Summer Nuclear Station, Unit 1, Updated Final Safety Analysis Report, Chapter 10.0, Steam and Power Conversion System +, RC-18-0080, Virgil C. Summer Nuclear Station, Unit 1, Updated Final Safety Analysis Report, Chapter 10.0, Steam and Power Conversion System +, RC-18-0080, Virgil C. Summer Nuclear Station, Unit 1, Updated Final Safety Analysis Report, Chapter 10.0, Steam and Power Conversion System +, RC-18-0080, Virgil C. Summer Nuclear Station, Unit 1, Updated Final Safety Analysis Report, Chapter 10.0, Steam and Power Conversion System +, RC-18-0080, Virgil C. Summer Nuclear Station, Unit 1, Updated Final Safety Analysis Report, Chapter 10.0, Steam and Power Conversion System +, RC-18-0080, Virgil C. Summer Nuclear Station, Unit 1, Updated Final Safety Analysis Report, Chapter 10.0, Steam and Power Conversion System +, RC-18-0080, Virgil C. Summer Nuclear Station, Unit 1, Updated Final Safety Analysis Report, Chapter 10.0, Steam and Power Conversion System +, RC-18-0080, Virgil C. Summer Nuclear Station, Unit 1, Updated Final Safety Analysis Report, Chapter 10.0, Steam and Power Conversion System +  and RC-18-0080, Virgil C. Summer Nuclear Station, Unit 1, Updated Final Safety Analysis Report, Chapter 10.0, Steam and Power Conversion System +
Hours
1.273148e-4 d (0.00306 hours, 1.818783e-5 weeks, 4.1855e-6 months)  +, 2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +, 4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months)  +  and 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +
IEEE
IEEE 382-1972 +
In package
ML18221A142 +
Isotope
Tritium +
Issue date
May 31, 2018  +
L
L 13 +  and L 11 +
Licensing Basis Document
Updated Final Safety Analysis Report +
Manufacturer
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>.
19:40:34, 12 September 2018  +
ND
ND-2311 +
NUREG
NUREG-1482, Revision 4, Guidelines for Inservice Testing at Nuclear Power Plants: Inservice Testing of Pumps and Valves and Inservice Examination and Testing of Dynamic Restraints (Snubbers) at Nuclear Power Plants Final Report +  and NUREG/CR-2907, Responds to 851105 Request for Info Re Radwaste & Containment Spray Sys.Nrc Methodology for Estimating Radwaste Generation Delineated in Encl NUREG-0017.USA Experience Summarized in Encl NUREG/CR-2907.W/o Encls +
Page count
141  +
Procedure
AM +, ST +, MP +  and SP-61 +
Project stage
Request  +
Regulatory Guide
Regulatory Guide 1.50 +, Regulatory Guide 1.48 +, Regulatory Guide 1.71 +  and Regulatory Guide 1.37, Quality Assurance Requirements for Cleaning of Fluid Systems and Associated Components of Water-Cooled Nuclear Power Plants +
SSC
07-02-022 +, 1MS-27-247 +, 170x595-21 +, 690eJE-LW +, 6g00A-LWISEE +, L04A-L +, L04S-LW +, S903B-LW +, L04C-LW +, L04D-LW +, 0L-1 +, 07-06-041 +  and 07-98-053 +
Site
Summer +
Start date
May 31, 2018  +
State
South Carolina +
System
Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Main Steam Isolation Valve +, Main Turbine +, Residual Heat Removal +, Circulating Water System +, Main Steam Safety Valve +, Main Steam Line +, Moisture Separator Reheater +, Main Condenser +, Main Steam +, Extraction steam +, Turbine Gland Sealing System +  and Emergency Feedwater System +
Title
Virgil C. Summer Nuclear Station, Unit 1, Updated Final Safety Analysis Report, Chapter 10.0, Steam and Power Conversion System  +
To
Office of Nuclear Reactor Regulation +
Topic
Safe Shutdown +, Boric Acid +, Grab sample +, Tornado Missile +, Post Accident Monitoring +, Hydrostatic +, Feedwater Heater +, Process Control Program +, Eddy Current Testing +, Loss of condenser vacuum +  and Water hammer +
Turbine component
Turbine bypass valve +
URL"URL" is a <a href="/Special:Types/URL" title="Special:Types/URL">type</a> and predefined property provided by <a rel="nofollow" class="external text" href="https://www.semantic-mediawiki.org/wiki/Help:Special_properties">Semantic MediaWiki</a> to represent URI/URL values.
http://pbadupws.nrc.gov/docs/ML1822/ML18221A180.pdf  +
Ultimate Heat Sink
Cooling Tower +
 
Retrieved from "https://kanterella.com/Special:Browse/:RC-2D18-2D0080,-20Virgil-20C.-20Summer-20Nuclear-20Station,-20Unit-201,-20Updated-20Final-20Safety-20Analysis-20Report,-20Chapter-2010.0,-20Steam-20and-20Power-20Conversion-20System"