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{{Adams
#REDIRECT [[NG-17-0111, Duane Arnold Energy Center, Revision 24 to Updated Final Safety Analysis Report, Table of Contents]]
| number = ML17157B674
| issue date = 05/22/2017
| title = Duane Arnold Energy Center, Revision 24 to Updated Final Safety Analysis Report, Table of Contents
| author name =
| author affiliation = NextEra Energy Duane Arnold, LLC
| addressee name =
| addressee affiliation = NRC/NRR
| docket = 05000331
| license number = DPR-049
| contact person =
| case reference number = NG-17-0111
| package number = ML17157B650
| document type = Updated Final Safety Analysis Report (UFSAR)
| page count = 81
}}
 
=Text=
{{#Wiki_filter:UPDATED FINAL SAFETY ANALYSIS REPORT DUANE ARNOLD ENERGY CENTER TABLE OF CONTENTS Section                                                      Title                                                        Page i Revision 17 - 10/03 VOLUME I 1        INTRODUCTION AND GENERAL DESCRIPTION OF THE PLANT .. 1.1-1
 
==1.1      INTRODUCTION==
....................................................................................... 1.1-1 1.2      GENERAL PLANT DESCRIPTION .......................................................... 1.2-1 1.3      COMPARISON TABLES ........................................................................... 1.3-1 1.4      IDENTIFICATION OF AGENTS AND CONTRACTORS ....................... 1.4-1 1.5      REQUIREMENTS FOR FURTHER TECHNICAL INFORMATION ...... 1.5-1 1.6      MATERIAL INCORPORATED BY REFERENCE ................................... 1.6-1 1.7      DRAWINGS AND OTHER DETAILED INFORMATION ...................... 1.7-1
 
1.8      CONFORMANCE TO NRC REGULATORY GUIDES ............................ 1.8-1 1.9      STANDARD DESIGNS .............................................................................. 1.9-1
 
VOLUME II
 
2        SITE CHARACTERISTICS ........................................................................ 2.1-1
 
2.1      GEOGRAPHY AND DEMOGRAPHY ...................................................... 2.1-1 2.2      NEARBY INDUSTRIAL, TRANSPORTATION, AND MILITARY FACILITIES ................................................................................................ 2.2-1 2.3      METEOROLOGY ....................................................................................... 2.3-1 2.4      HYDROLOGIC ENGINEERING ............................................................... 2.4-1 2.5      GEOLOGY, SEISMOLOGY, AND GEOTECHNICAL ENGINEERING 2.5-1
 
VOLUME III
 
3        DESIGN OF STRUCTURES, COMPONENTS, EQUIPMENT, AND            SYSTEMS .................................................................................................... 3.1-1
 
3.1      CONFORMANCE TO AEC GENERAL DESIGN CRITERIA FOR 
 
NUCLEAR POWER PLANTS .................................................................... 3.1-1 3.2      CLASSIFICATION OF STRUCTURES, SYSTEMS, AND COMPONENTS .......................................................................................... 3.2-1 3.3      WIND AND TORNADO LOADINGS ....................................................... 3.3-1 3.4      WATER LEVEL (FLOOD) DESIGN ......................................................... 3.4-1 3.5      MISSILE PROTECTION ............................................................................ 3.5-1
 
3.6      PROTECTION AGAINST DYNAMIC EFFECTS ASSOCIATED WITH UPDATED FINAL SAFETY ANALYSIS REPORT DUANE ARNOLD ENERGY CENTER TABLE OF CONTENTS Section                                                      Title                                                        Page ii Revision 17 - 10/03            THE POSTULATED RUPTURE OF PIPING ............................................ 3.6-1
 
VOLUME IV
 
3.7      SEISMIC DESIGN ...................................................................................... 3.7-1 3.8      DESIGN OF SEISMIC CATEGORY I STRUCTURES ............................ 3.8-1 3.9      MECHANICAL SYSTEMS AND COMPONENTS .................................. 3.9-1
 
3.10    SEISMIC QUALIFICATION OF SEISMIC CATEGORY I INSTRUMENTATION AND ELECTRICAL EQUIPMENT .................. 3.10-1 3.11    ENVIRONMENTAL DESIGN OF ELECTRICAL EQUIPMENT .......... 3.11-1
 
4        REACTOR ................................................................................................... 4.1-1
 
4.1     
 
==SUMMARY==
DESCRIPTION ...................................................................... 4.1-1 4.2      FUEL SYSTEM DESIGN ........................................................................... 4.2-1 4.3      NUCLEAR DESIGN ................................................................................... 4.3-1 4.4      THERMAL-HYDRAULIC DESIGN .......................................................... 4.4-1 4.5      REACTOR MATERIALS ........................................................................... 4.5-1 4.6      FUNCTIONAL DESIGN OF REACTIVITY CONTROL SYSTEMS ...... 4.6-1
 
VOLUME V 5        REACTOR COOLANT SYSTEM AND CONNECTED SYSTEMS ........ 5.1-1
 
5.1     
 
==SUMMARY==
DESCRIPTION ...................................................................... 5.1-1 5.2      INTEGRITY OF REACTOR COOLANT PRESSURE BOUNDARY ...... 5.2-1 5.3      REACTOR VESSELS ................................................................................. 5.3-1 5.4      COMPONENT AND SUBSYSTEM DESIGN ........................................... 5.4-1 5A      SITE ASSEMBLY OF THE REACTOR PRESSURE VESSEL ................ 5A-1 5B      OVER PRESSURIZATION PROTECTION ................................................5B-1 VOLUME  VI
 
6        ENGINEERED SAFETY FEATURES ....................................................... 6.1-1
 
6.1      ENGINEERED SAFETY FEATURE MATERIALS ................................. 6.1-1 6.2      CONTAINMENT SYSTEMS ..................................................................... 6.2-1 UPDATED FINAL SAFETY ANALYSIS REPORT DUANE ARNOLD ENERGY CENTER TABLE OF CONTENTS Section                                                      Title                                                        Page iii Revision 12 - 10/95 6.3      EMERGENCY CORE COOLING SYSTEMS ........................................... 6.3-1 6.4      HABITABILITY SYSTEMS ...................................................................... 6.4-1 6.5      FISSION PRODUCT REMOVAL AND CONTROL SYSTEMS .............. 6.5-1 6.6      INSERVICE INSPECTION OF CLASS 2 AND 3 COMPONENTS ......... 6.6-1
 
6.7      MAIN STEAM ISOLATION VALVE LEAKAGE TREATMENT PATH ........................................................................................................... 6.7
-1 VOLUME VII
 
7        INSTRUMENTATION AND CONTROLS ................................................ 7.1-1
 
==7.1      INTRODUCTION==
....................................................................................... 7.1-1 7.2      REACTOR PROTECTION SYSTEM ........................................................ 7.2-1 7.3      ENGINEERED SAFETY FEATURES SYSTEM ...................................... 7.3-1
 
7.4    SYSTEMS REQUIRED FOR SAFE SHUTDOWN .................................... 7.4-1 7.5    SAFETY-RELATED DISPLAY INSTRUMENTATION ........................... 7.5-1
 
7.6    ALL OTHER INSTRUMENTATION SYSTEMS REQUIRED FOR SAFETY ....................................................................................................... 7.6-1 7.7    CONTROL SYSTEMS NOT REQUIRED FOR SAFETY ......................... 7.7-1
 
VOLUME VIII
 
8        ELECTRIC POWER .................................................................................... 8.1-1
 
==8.1    INTRODUCTION==
........................................................................................ 8.1-1 8.2    OFFSITE POWER SYSTEM ....................................................................... 8.2-1 8.3    ONSITE POWER SYSTEMS ...................................................................... 8.3-1
 
9        AUXILIARY SYSTEMS ............................................................................. 9.1-1
 
9.1    FUEL STORAGE AND HANDLING ......................................................... 9.1-3 9.2    WATER SUPPLY SYSTEMS...................................................................... 9.2-1 9.3    PROCESS AUXILIARIES ........................................................................... 9.3-1
 
9.4    AIR-CONDITIONING, HEAT ING, COOLING, AND VENTILATION          SYSTEMS ..................................................................................................... 9.4-1 9.5    OTHER AUXILIARY SYSTEMS ............................................................... 9.5-1 UPDATED FINAL SAFETY ANALYSIS REPORT DUANE ARNOLD ENERGY CENTER TABLE OF CONTENTS Section                                                      Title                                                        Page iv Revision 16 - 11/01 VOLUME IX
 
10      STEAM AND POWER CONVERSION ................................................... 10.1-1 10.1   
 
==SUMMARY==
DESCRIPTION .................................................................... 10.1-1 10.2    TURBINE-GENERATOR ......................................................................... 10.2-1 10.3    MAIN STEAM SUPPLY SYSTEM .......................................................... 10.3-1 10.4    OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM .................................................................................................... 10.4-1
 
11      RADIOACTIVE WASTE MANAGEMENT ............................................ 11.1-1
 
11.1    SOURCE TERMS ..................................................................................... 11.1-1 11.2    LIQUID WASTE MANAGEMENT SYSTEM ........................................ 11.2-1 11.3    GASEOUS WASTE MANAGEMENT SYSTEM .................................... 11.3-1 11.4    SOLID WASTE MANAGEMENT SYSTEM .......................................... 11.4-1
 
11.5    PROCESS AND EFFLUENT RADIATION MONITORING AND SAMPLING SYSTEMS ............................................................................ 11.5-1 11A    GASEOUS RELEASE RATE LIMIT CALCULATIONS ........................ 11A-1
 
VOLUME X 12        RADIATION PROTECTION .................................................................. 12.1-1
 
12.1    ENSURING THAT OCCUPATIONAL RADIATION EXPOSURES ARE AS LOW AS IS REASONABLY ACHIEVABLE ......................... 12.1-1 12.2    RADIATION SOURCES ......................................................................... 12.2-1 12.3    RADIATION PROTECTION DESIGN FEATURES .............................. 12.3-1 12.4    DOSE ASSESSMENT .............................................................................. 12.4-1 12.5    HEALTH PHYSICS PROGRAM ............................................................ 12.5-1
 
13        CONDUCT OF OPERATIONS ............................................................... 13.1-1
 
13.1 ORGANIZATIONAL STRUCTURE OF DUANE ARNOLD ENERGY            CENTER. .................................................................................................. 13.1-1 13.2    TRAINING ............................................................................................... 13.2-1 13.3    EMERGENCY PLANNING .................................................................... 13.3-1 13.4    REVIEW AND AUDITS .......................................................................... 13.4-1 13.5    PLANT PROCEDURES ........................................................................... 13.5-1 13.6    INDUSTRIAL SECURITY ...................................................................... 13.6-1 13.7    FIRE PROTECTION PROGRAM ........................................................... 13.7-1 UPDATED FINAL SAFETY ANALYSIS REPORT DUANE ARNOLD ENERGY CENTER TABLE OF CONTENTS Section                                                      Title                                                        Page v Revision 21 - 5/11
 
14        INITIAL TEST PROGRAM ..................................................................... 14.1-1
 
14.1    SPECIFIC INFORMATION TO BE INCLUDED IN PRELIMINARY SAFETY ANALYSIS REPORTS ............................................................ 14.1-1
 
14.2    SPECIFIC INFORMATION TO BE INCLUDED IN FINAL SAFETY ANALYSIS REPORT .............................................................................. 14.2-1
 
VOLUME XI
 
15        ACCIDENT ANALYSES ........................................................................ 15.0-1
 
15.0    PLANT SAFETY ANALYSIS ................................................................. 15.0-1 15.1    TRANSIENTS .......................................................................................... 15.1-1 15.2    ACCIDENTS ............................................................................................ 15.2-1 15.3    SPECIAL EVENTS .................................................................................. 15.3-1
 
16      TECHNICAL SPECIFICATIONS ............................................................ 16.0-1
 
16.0    TECHNICAL REQUIREMENTS MANUAL ........................................... 16.0-1
 
17      QUALITY ASSURANCE ......................................................................... 17.1-1
 
17.1    QUALITY ASSURANCE DURING DESIGN AND CONSTRUCTION ..................................................................................... 17.1-1 17.2    QUALITY ASSURANCE DURING THE OPERATIONS PHASE ........ 17.2-1
 
18      LICENSE RENEWAL ............................................................................... 18.1-1 18.1    AGING MANAGEMENT PROGRAMS .................................................. 18.1-1 18.2    TLAA EVALUATION OF AGING MANAGEMENT PROGRAMS  UNDER 10 CFR 54.21(c)(1)(iii) ............................................................. 18.1-19 18.3    TIME-LIMITED AGING ANALYSIS ................................................... 18.1-21 18.4    LIST OF LICENSE RENEWAL COMMITMENTS .............................. 18.1-33
 
==18.5    REFERENCES==
........................................................................................ 18.1-34}}

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