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ML16180A149
Show incoming properties 
Category
Updated Final Safety Analysis Report (UFSAR)
ASME section
ASME Section III +
Accession number
ML16180A149  +
Atomic Element
Boron +, Cobalt +, Uranium +, Iron +, Nickel +, Carbon +, Xenon +, Cadmium +, Indium +, Lead +, Helium +, Chromium +, Niobium +, Silver +, Tin +  and Samarium +
CFR
10 CFR 50.46 +  and 10 CFR 50 Appendix A +
Docket
05000244  +
Equipment trip
Turbine Trip +  and Reactor Trip +
From
Exelon +
Fuel cladding
ZIRLO +  and Zircaloy +
General design criterion
GDC 20 +, GDC 10 +, GDC 12 +, GDC 14 +, GDC 11 +, GDC 13 +, GDC 25 +, GDC 28 +, GDC 29 +, GDC 27 +, GDC 1, Quality standards and records +  and GDC 26, Reactivity control system redundancy and capability +
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ML16180A149 +, ML16180A149 +, ML16180A149 +, ML16180A149 +, ML16180A149 +, ML16180A149 +, ML16180A149 +, ML16180A149 +, ML16180A149 +  and ML16180A149 +
Hours
0.0478 d (1.148 hours, 0.00683 weeks, 0.00157 months)  +
In package
ML16180A174 +
Issue date
May 5, 2016  +
License amendment topic
License Renewal Application +
Licensing Basis Document
Updated Final Safety Analysis Report +
Manufacturer
Westinghouse +  and Foxboro +
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>.
03:05:56, 10 January 2025  +
NRC information notice
Information Notice 98-11 +  and Information Notice 96-01 +
NUREG
NUREG-1786, Safety Evaluation Report, Related to License Renewal of R.E. Ginna Nuclear Power Plant +, NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +  and NUREG-0630, 09-09-80 Cladding Swelling and Rupture Models for LOCA Analysis - NUREG-0630 +
Page count
68  +
Project stage
Request  +
Regulatory Guide
Regulatory Guide 1.97 +  and Regulatory Guide 1.45 +
Site
Ginna +
Start date
May 5, 2016  +
System
Steam Generator +, Reactor Coolant System +, Feedwater +, Reactor Pressure Vessel +, Emergency Core Cooling System +, Decay Heat Removal +  and Control Rod +
Title
6 to the Updated Final Safety Analysis Report, Chapter 4, Reactor  +
To
Office of Nuclear Reactor Regulation +
Topic
Boric Acid +, Shutdown Margin +, Anticipated operational occurrence +, License Renewal +, Earthquake +, Fuel cladding +, Flow Induced Vibration +, Core Exit Thermocouple +  and Power Uprate +
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/ML1618/ML16180A149.pdf  +
WCAP
WCAP-15063-P-A +, WCAP-12610-P-A +, WCAP-12488-A +, WCAP-9226-P-A +, WCAP-11397-P-A +, WCAP-10851-P-A +, WCAP-8762 +, WCAP-8763 +, WCAP-8691 +, WCAP-9500 +, WCAP-8720 +, WCAP-8745 +, WCAP-10924-P-A +, WCAP-14565-P-A +, WCAP-13589-A +, WCAP-9273-A +, WCAP-9401-P-A +, WCAP-9402 +, WCAP-8218 +, WCAP-8964 +, WCAP-8219 +, WCAP-8762-P-A +, WCAP-2761 +, WCAP-3738 +, WCAP-13061-NP-A +, WCAP-13677-P-A +, WCAP-10966-NP-A +, WCAP-9748 +, WCAP-9749 +, WCAP-14460 +...
Westinghouse letter
NS-EPR-2515 +  and NS-EPR-2572 +
Westinghouse report
WCAP-15063-P-A +, WCAP-12610-P-A +, WCAP-12488-A +, WCAP-9226-P-A +, WCAP-11397-P-A +, WCAP-10851-P-A +, WCAP-8762 +, WCAP-8763 +, WCAP-8691 +, WCAP-9500 +, WCAP-8720 +, WCAP-8745 +, WCAP-10924-P-A +, WCAP-14565-P-A +, WCAP-13589-A +, WCAP-9273-A +, WCAP-9401-P-A +, WCAP-9402 +, WCAP-8218 +, WCAP-8964 +, WCAP-8219 +, WCAP-8762-P-A +, WCAP-2761 +, WCAP-3738 +, WCAP-13061-NP-A +, WCAP-13677-P-A +, WCAP-10966-NP-A +, WCAP-9748 +, WCAP-9749 +, WCAP-14460 +...
 
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