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NL-14-121, Indian Point, Unit 2, Updated Final Safety Analysis Report (Ufsar), Revision 25, Chapter 4 - Reactor Coolant System
Show incoming properties 
Category
Updated Final Safety Analysis Report (UFSAR)
ANSI code
ANSI B31.1 +
ASME section
ASME Section XI +, ASME Section III +, ASME Section IX +  and ASME Section VIII +
Accession number
ML14287A299  +
Atomic Element
Boron +, Iron +, Nitrogen +, Carbon +, Oxygen +, Chloride +, Lead +, Aluminum +, Tungsten +  and Plutonium +
CFR
10 CFR 50 Appendix A +, 10 CFR 20 +, 10 CFR 50 +, 10 CFR 50 Appendix G +, 10 CFR 50 Appendix H +, 10 CFR 50.54#f +  and 10 CFR 50.61#b2 +
Code case
ASME Code Case N-640 +, ASME Code Case N-588 +  and ASME Code Case N-20 +
Correspondence
NL-14-121, Updated Final Safety Analysis Report (Ufsar), Revision 25, Chapter 14, Figures, Part 2 of 2 +
Docket
05000247  +
Equipment trip
Turbine Trip +  and Reactor Trip +
From
Entergy +
General design criterion
GDC 33 +, GDC 34 +, GDC 16 +, GDC 40 +, GDC 9 +, GDC 36 +, 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 5, Sharing of structures, systems, and components +
Generic letter
NRC Generic Letter 81-21, Natural Circulation Cooldown +  and NRC Generic Letter 92-01, Reactor Vessel Structural Integrity +
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>.
NL-14-121, Indian Point, Unit 2, Updated Final Safety Analysis Report (Ufsar), Revision 25, Chapter 4 - Reactor Coolant System +, NL-14-121, Indian Point, Unit 2, Updated Final Safety Analysis Report (Ufsar), Revision 25, Chapter 4 - Reactor Coolant System +, NL-14-121, Indian Point, Unit 2, Updated Final Safety Analysis Report (Ufsar), Revision 25, Chapter 4 - Reactor Coolant System +, NL-14-121, Indian Point, Unit 2, Updated Final Safety Analysis Report (Ufsar), Revision 25, Chapter 4 - Reactor Coolant System +, NL-14-121, Indian Point, Unit 2, Updated Final Safety Analysis Report (Ufsar), Revision 25, Chapter 4 - Reactor Coolant System +, NL-14-121, Indian Point, Unit 2, Updated Final Safety Analysis Report (Ufsar), Revision 25, Chapter 4 - Reactor Coolant System +, NL-14-121, Indian Point, Unit 2, Updated Final Safety Analysis Report (Ufsar), Revision 25, Chapter 4 - Reactor Coolant System +, NL-14-121, Indian Point, Unit 2, Updated Final Safety Analysis Report (Ufsar), Revision 25, Chapter 4 - Reactor Coolant System +, NL-14-121, Indian Point, Unit 2, Updated Final Safety Analysis Report (Ufsar), Revision 25, Chapter 4 - Reactor Coolant System +  and NL-14-121, Indian Point, Unit 2, Updated Final Safety Analysis Report (Ufsar), Revision 25, Chapter 4 - Reactor Coolant System +
In package
ML14287A282 +
Isotope
U-238 +
Issue date
September 17, 2014  +
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>.
15:45:28, 13 July 2018  +
NL
NL-14-121, Updated Final Safety Analysis Report (Ufsar), Revision 25, Chapter 14, Figures, Part 2 of 2 +
NRC bulletin
NRC Bulletin 88-11 +  and NRC Bulletin 88-02 +
NUREG
NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +
Page count
85  +
Procedure
RT +
Project reference
TAC:68318 +, TAC:66684 +  and TAC:72961 +
Project stage
Request  +
Regulatory Guide
Regulatory Guide 1.99 +  and Regulatory Guide 1.83 +
SSC
4C-1 +, 4C-2 +, 4C-3 +, 4hr-AC +, 60hr-FC +, 50hr-FC +, 40hr-FC +, 4c-1 +, 4c-2 +  and 4c-3 +
Site
Indian Point +
Start date
September 17, 2014  +
State
New York +
System
Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Auxiliary Feedwater +, Reactor Pressure Vessel +, Residual Heat Removal +, Decay Heat Removal +, Main Steam Line +, Control Rod +  and Main Steam +
TS
TS-4.5.1 +
Title
Indian Point, Unit 2, Updated Final Safety Analysis Report (Ufsar), Revision 25, Chapter 4 - Reactor Coolant System  +
To
Office of Nuclear Reactor Regulation +
Topic
Hot Short +, Safe Shutdown +, Boric Acid +, Safe Shutdown Earthquake +, Weld Overlay +, Hydrostatic +, Stress corrosion cracking +, Loss of Offsite Power +, Earthquake +, Fuel cladding +, Liquid penetrant +, Unidentified leakage +, Unidentified leak +, Power Uprate +, Overspeed +, Leak-Before-Break +  and Leak Before Break +
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/ML1428/ML14287A299.pdf  +
WCAP
WCAP-15666-A +, WCAP-14040-NP-A +, WCAP-9804 +, WCAP-12187 +, WCAP-9117 +, WCAP-7323 +, WCAP-15629 +  and WCAP-9130 +
Westinghouse report
WCAP-15666-A +, WCAP-14040-NP-A +, WCAP-9804 +, WCAP-12187 +, WCAP-9117 +, WCAP-7323 +, WCAP-15629 +  and WCAP-9130 +
 
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