NL-2D17-2D0534-2C Technical Requirements Manual
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ASME code: IWA-2213
ASME section: ASME Section XI
accession number: ML17117A394
atomic element: Boron
atomic element: Iodine
atomic element: Nitrogen
atomic element: Oxygen
atomic element: Hydrogen
atomic element: Xenon
atomic element: Chloride
atomic element: Plutonium
atomic element: Samarium
CFR: 10 CFR 50.73
CFR: 10 CFR 50.72
CFR: 10 CFR 50
CFR: 10 CFR 50 Appendix J
CFR: 10 CFR 20 Appendix B
CFR: 10 CFR 50.59
CFR: 10 CFR 50.4
CFR: 10 CFR 50.65#a4
CFR: 10 CFR 50.55a#b3v
CFR: 10 CFR 70.39#c
CFR: 10 CFR 50.44#c3iii
code case: ASME Code Case OMN-13
cornerstone: Emergency Preparedness
docket: 05000348
docket: 05000364
emergency facility: Technical Support Center
emergency facility: Emergency Operations Facility
equipment trip: Turbine Trip
equipment trip: Reactor Trip
from: Southern Nuclear
general design criterion: GDC 60
hours: 24
hours: 72
hours: 6
hours: 4
hours: 12
hours: 36
hours: 1
hours: 100
hours: 48
in package: ML17117A380
isotope: Tritium
issue date: 2017-04-20Z
issue date#aux: 2457863.5
letter: ML20083E948
NUMARC: NUMARC 93-01
page count: 148
power source: 4.16kV
procedure: Emergency Operating Procedure
project stage: Request
regulatory guide: Regulatory Guide 1.97
regulatory guide: Regulatory Guide 1.27
regulatory guide: Regulatory Guide 1.182
regulatory guide: Regulatory Guide 1.7
regulatory guide: Regulatory Guide 1.106
regulatory guide: Regulatory Guide 1.23
SR: SR-3.0.3
SR: SR-3.6.3.5
SR: SR-3.4.12.1
site: Farley
start date: 2017-04-20Z
start date#aux: 2457863.5
state: Alabama
system: Steam Generator
system: Reactor Coolant System
system: Feedwater
system: Service water
system: Emergency Diesel Generator
system: Auxiliary Feedwater
system: Shutdown Cooling
system: Reactor Pressure Vessel
system: Residual Heat Removal

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NL-17-0534, Joseph M. Farley Nuclear Plant, Updated Final Safety Analysis Report, Revision 27, Effective Page Listing, Table of Contents, Chapter 1 Redacted, Introduction and General Description of the Plant
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NL-17-0534, Joseph M. Farley Nuclear Plant, Updated Final Safety Analysis Report, Revision 27, Chapter 8 Through Chapter 10
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NL-17-0534, Joseph M. Farley Nuclear Plant - Submittal of Updated Final Safety Analysis Report, 10 CFR 50.59 Report, Fire Hazard Analysis Changes, Technical Specifications Bases Changes, Technical Requirements Manual Changes, and Revised NRC Commitme
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