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ML17051A094
Show incoming properties 
Category
Updated Final Safety Analysis Report (UFSAR)
ACI
ACI-318 +
ASME section
ASME Section XI +, ASME Section III +, ASME Section V +, ASME Section II +  and ASME Section VIII +
Accession number
ML17051A094  +
Agency
American Society of Civil Engineers +
Atomic Element
Boron +, Cesium +, Iron +, Germanium +, Copper +, Nitrogen +, Carbon +, Oxygen +, Hydrogen +, Xenon +, Chloride +, Lead +, Lithium +, Aluminum +, Silicon +, Chromium +, Hafnium +  and Plutonium +
CFR
10 CFR 50 Appendix A +, 10 CFR 50 +, 10 CFR 2.390 +, 10 CFR 50.12 +, 10 CFR 50.61 +, 10 CFR 50 Appendix H +, 10 CFR 50.55a +, 10 CFR 54.21#c1ii +, 10 CFR 50.55a#g6i +  and 10 CFR 50.60#b +
Code case
ASME Code Case N-10 +  and ASME Code Case N-629 +
Correspondence
L-2016-198, Redacted Turkey Point, Units 3 & 4, Updated Final Safety Analysis Report, Chapter 14, Safety Analysis +  and L-77-296, Letter Consists of Steam Generator Repair Report Which Evaluates All Safety Related Aspects of the Repair Effort +
Docket
05000250  +  and 05000251  +
Document
ML15271A325 +
Engineering change
EC-281319 +
Equipment trip
Reactor Trip +
From
NextEra Energy +
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 84-04, Safety Evaluation of Westinghouse Topical Reports Dealing with Elimination of Postulated Pipe Breaks in PWR Primary Main Loops (Generic Letter 84-04) +
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>.
ML17051A094 +, ML17051A094 +, ML17051A094 +, ML17051A094 +, ML17051A094 +, ML17051A094 +, ML17051A094 +, ML17051A094 +, ML17051A094 +, ML17051A094 +, ML17051A094 +, ML17051A094 +  and ML17051A094 +
Hours
2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +, 1.157407e-5 d (2.777778e-4 hours, 1.653439e-6 weeks, 3.805e-7 months)  +, 0.00111 d (0.0267 hours, 1.587302e-4 weeks, 3.6528e-5 months)  +, 0.0231 d (0.556 hours, 0.00331 weeks, 7.61e-4 months)  +, 8.333333e-4 d (0.02 hours, 1.190476e-4 weeks, 2.7396e-5 months)  +  and 0.00104 d (0.025 hours, 1.488095e-4 weeks, 3.4245e-5 months)  +
In package
ML16330A191 +
Isotope
U-235 +, U-238 +  and Cobalt-60 +
Issue date
October 29, 2016  +
L
L-2016-198, Redacted Turkey Point, Units 3 & 4, Updated Final Safety Analysis Report, Chapter 14, Safety Analysis +  and L-77-296, Letter Consists of Steam Generator Repair Report Which Evaluates All Safety Related Aspects of the Repair Effort +
Letter
05000251/LER-2010-002, Regarding Reactor Trip Resulting from Steam Generator Feedwater Pump Trip +
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>.
19:25:34, 9 January 2025  +
NUREG
NUREG-0020, Responds to Encl Re Spent Fuel Storage Capacity at Plant.Spent Fuel Pool at Plant Has Sufficient Space to Accommodate Addl Fuel Storage Racks of Current Design +
Page count
156  +
Person
Jason Paige +
Procedure
RT +
Project reference
TAC:ME6334 +  and TAC:M91494 +
Project stage
Request  +
Regulatory Guide
Regulatory Guide 1.147 +, Regulatory Guide 1.190 +, Regulatory Guide 1.58 +, Regulatory Guide 1.28 +, Regulatory Guide 1.31 +, Regulatory Guide 1.64 +, Regulatory Guide 1.83 +, Regulatory Guide 1.38 +, Regulatory Guide 1.123 +, Regulatory Guide 1.48 +, Regulatory Guide 1.88 +  and Regulatory Guide 1.37, Quality Assurance Requirements for Cleaning of Fluid Systems and Associated Components of Water-Cooled Nuclear Power Plants +
SSC
4A-1 +, 4B-1 +, 4A-2 +, 4A-5 +, 4A-3 +, 4A-4 +, 4A-6 +, 4A-7 +, 4A-8 +, 4A-9 +, 4A-11 +, 4A-9a +, 4C-1 +, 4C-2 +, 4C-3 +, 4C-4 +, 4C-5 +, 4C-6 +, 4C-7 +, 4C-8 +, 4C-9 +, 4C-10 +, 4C-11 +, 4C-12 +, 4C-13 +, 4C-14 +, 4C-15 +, 4C-16 +, 4C-17 +, 4C-18 +...
Scram
Manual Scram +
Site
Turkey Point +
Start date
October 29, 2016  +
State
Washington +, New York +  and Florida +
System
Steam Generator +, Reactor Coolant System +, Feedwater +, Auxiliary Feedwater +, Reactor Pressure Vessel +, Residual Heat Removal +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +  and Control Rod +
TS
TS-3.4.9 +  and TS-5.6 +
Title
Redacted Turkey Point, Units 3 & 4, Updated Final Safety Analysis Report, Chapter 4, Reactor Coolant System  +
To
Office of Nuclear Reactor Regulation +
Topic
Boric Acid +, Hydrostatic +, Nondestructive Examination +, Stress corrosion cracking +, Exemption Request +, Earthquake +, Liquid penetrant +, Power change +, Core Exit Thermocouple +, GOTHIC +, Power Uprate +  and Leak-Before-Break +
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http://pbadupws.nrc.gov/docs/ML1705/ML17051A094.pdf  +
Vendor
Framatome +  and Flowserve +
WCAP
WCAP-14040-A +, WCAP-8324-A +, WCAP-8693 +, WCAP-8370 +, WCAP-15338 +, WCAP-17152-P +, WCAP-14237 +, WCAP-15092 +, WCAP-14291 +  and WCAP-8577-A +
Westinghouse report
WCAP-14040-A +, WCAP-8324-A +, WCAP-8693 +, WCAP-8370 +, WCAP-15338 +, WCAP-17152-P +, WCAP-14237 +, WCAP-15092 +, WCAP-14291 +  and WCAP-8577-A +
 
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