Browse wiki

Jump to navigation Jump to search
ML17213A017
Show incoming properties 
Category
Report, Response to Request for Additional Information (RAI)  and Technical
ACI
ACI-318 +  and ACI-349 +
ASCE
ASCE 4-98 +, ASCE 43-05 +, ASCE/SEI 43-05 +  and ASCE 43 +
Accession number
ML17213A017  +
Agency
American Society of Civil Engineers +
Area
Switchyard +
Atomic Element
Hydrogen +, Lead +  and Tin +
CFR
10 CFR 50 +  and 10 CFR 50.54#f +
Cornerstone
Initiating Events +
Cross cutting aspect
P.3(l) +, H.2(f) +, P.3(s) +  and P.3(t) +
Docket
05000412  +, 00275  +  and 00323  +
EPRI
EPRI +
Equipment trip
Turbine Trip +  and Reactor Trip +
From
ABS Consulting +  and Rizzo Associates +
Generic letter
NRC Generic Letter 88-20, Individual Plant Examination for Severe Accident Vulnerabilities +
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>.
ML17213A017 +, ML17213A017 +, ML17213A017 +, ML17213A017 +, ML17213A017 +, ML17213A017 +, ML17213A017 +, ML17213A017 +, ML17213A017 +, ML17213A017 +, ML17213A017 +, ML17213A017 +, ML17213A017 +  and ML17213A017 +
In package
ML17213A014 +
Interim Staff Guidance
DC/COL-ISG-017 +
Issue date
May 11, 2017  +
Licensing Basis Document
Updated Final Safety Analysis Report +
Manufacturer
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>.
20:39:34, 8 January 2025  +
NEI
NEI 12-13 +
NFPA
NFPA 805 +
NUREG
NUREG/CR-6728 +, NUREG/CR-4334 +, NUREG/CR-5741 +, NUREG/CR-3558 +, NUREG-1738, Yellow Ticket 020010064 - Nuclear Energy Institute Comments on NUREG-1738, Technical Study of Spent Fuel Pool Accident Risk at Decommissioning Nuclear Power Plants +, NUREG-1855, Summary of 7/18/19 Public Meeting with Nuclear Energy Institute to Discuss Application of NUREG-1855, Guidance on the Treatment of Uncertainties Associated with PRAs in Risk-Informed Decision Making +, NUREG-1407, Forwards Staff Evaluation of Millstone Unit 3,individual Plant Exam of External Events Submitted on 911223 Re Response to GL 88-20 .Util Capable of Identifying Severe Accidents & Vulnerabilites & Met GL 88-20,Suppl 4 +, NUREG/CR-0098, Forwards SEP Position Re Consideration of Inelastic Response Using NUREG/CR-0098 Ductility Factor Approach,Providing Addl Guidance Regarding Application of Ductility Methodology +, NUREG-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting +  and NUREG/CR-6850, To Propose an Alternative Methodology to Distribute Transient Ignition Frequencies (Bins 3, 5, 6, 7, 11, 24, 25, 31, 36, 37) That Contains a More Structured Approach to Accounting for Influence Factor Variations within a Pau +
Page count
197  +
Power source
4kV +
Procedure
AM +, ST +, SAP +, SP +, RT +, CP +  and TOP +
Project stage
Request  +
Regulatory Guide
Regulatory Guide 1.200 +, Regulatory Guide 1.174 +  and Regulatory Guide 1.208 +
SSC
1E-6 +, 1E-11 +, 1E-5 +, 1E-4 +, 1E-7 +, 1E-06 +, 1E-07 +, 5E-07 +, 5E-08 +, 5E-7 +, 1E-09 +, 2x10-7 +, 1E-12 +, 1E-05 +, 2RCS-PCV455C +, 1E-14 +, 2E-03 +, 58E-10 +, 3E-04 +, 13E-07 +, 13E-03 +, 16E-04 +, 64E-06 +, 16E-06 +, 10E-08 +, 2RSS-P21A +, 1e-4 +, L0E-05 +, 04E-5 +, 2DGP-3 +...
Site
Beaver Valley +
Start date
May 11, 2017  +
State
Texas +, Ohio +, Tennessee +, Pennsylvania +, Washington +, California +, Massachusetts +, New York +  and Michigan +
System
Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Reactor Protection System +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Auxiliary Feedwater +, Main Transformer +, HVAC +, Reactor Pressure Vessel +, Residual Heat Removal +, Shield Building +, Safety Relief Valve +, Control Rod +, Main Steam +  and Containment Spray +
Title
Enclosure B: Beaver Valley, Unit 2, Seismic Probabilistic Risk Assessment in Response to 50.54(0 Letter with Regard to NTTF 2.1  +
To
FirstEnergy +  and Office of Nuclear Reactor Regulation +
Topic
Safe Shutdown +, Ultimate heat sink +, Mission time +, Safe Shutdown Earthquake +, Internal Flooding +, Probabilistic Risk Assessment +, FLEX +, Fukushima Dai-Ichi +, Seismically rugged +, Design basis earthquake +, Large early release frequency +, Loss of Offsite Power +, Earthquake +, Weak link +, Seismic Walkdown Report +  and Loss of condenser vacuum +
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/ML1721/ML17213A017.pdf  +
Ultimate Heat Sink
Cooling Tower +  and Susquehanna River +
 
Retrieved from "https://kanterella.com/Special:Browse/:ML17213A017"