ML17157B674

Duane Arnold Energy Center, Revision 24 to Updated Final Safety Analysis Report, Table of Contents

ML17157B674
Person / Time
Site:	Duane Arnold
Issue date:	05/22/2017
From:	NextEra Energy Duane Arnold
To:	Office of Nuclear Reactor Regulation
Shared Package
ML17157B650	List: ML17157B649 ML17157B674 ML17157B675 ML17157B677 ML17157B678 ML17157B679 ML17157B680 ML17157B681 ML17157B682 ML17157B683 ML17157B684 ML17157B685 ML17157B686 ML17157B687 ML17157B688 ML17157B689 ML17157B690 ML17157B691 ML17157B692 NG-17-0086, Transmittal of Revision 24 of the DAEC Updated Final Safety Analysis Report and the Current DAEC Technical Specifications Bases NG-17-0111, Duane Arnold Energy Center, Revision 24 to Updated Final Safety Analysis Report NG-17-0111, Duane Arnold Energy Center, Revision 24 to Updated Final Safety Analysis Report, Chapter 1, Introduction and General Description of Plant NG-17-0111, Duane Arnold Energy Center, Revision 24 to Updated Final Safety Analysis Report, Chapter 10, Steam and Power Conversion NG-17-0111, Duane Arnold Energy Center, Revision 24 to Updated Final Safety Analysis Report, Chapter 11, Radioactive Waste Management NG-17-0111, Duane Arnold Energy Center, Revision 24 to Updated Final Safety Analysis Report, Chapter 12, Radiation Protection NG-17-0111, Duane Arnold Energy Center, Revision 24 to Updated Final Safety Analysis Report, Chapter 13, Conduct of Operations NG-17-0111, Duane Arnold Energy Center, Revision 24 to Updated Final Safety Analysis Report, Chapter 14, Initial Test Program NG-17-0111, Duane Arnold Energy Center, Revision 24 to Updated Final Safety Analysis Report, Chapter 15, Accident Analyses NG-17-0111, Duane Arnold Energy Center, Revision 24 to Updated Final Safety Analysis Report, Chapter 16, Technical Specifications NG-17-0111, Duane Arnold Energy Center, Revision 24 to Updated Final Safety Analysis Report, Chapter 17, Quality Assurance NG-17-0111, Duane Arnold Energy Center, Revision 24 to Updated Final Safety Analysis Report, Chapter 3, Design of Structures, Components, Equipment, and Systems NG-17-0111, Duane Arnold Energy Center, Revision 24 to Updated Final Safety Analysis Report, Chapter 4, Reactor NG-17-0111, Duane Arnold Energy Center, Revision 24 to Updated Final Safety Analysis Report, Chapter 5, Reactor Coolant System and Connected Systems NG-17-0111, Duane Arnold Energy Center, Revision 24 to Updated Final Safety Analysis Report, Chapter 6, Engineered Safety Features NG-17-0111, Duane Arnold Energy Center, Revision 24 to Updated Final Safety Analysis Report, Chapter 7, Instrumentation and Controls NG-17-0111, Duane Arnold Energy Center, Revision 24 to Updated Final Safety Analysis Report, Chapter 8, Electric Power NG-17-0111, Duane Arnold Energy Center, Revision 24 to Updated Final Safety Analysis Report, Chapter 9, Auxiliary Systems NG-17-0111, Duane Arnold Energy Center, Revision 24 to Updated Final Safety Analysis Report, Table of Contents NG-17-0111, Redacted - Duane Arnold Energy Center, Revision 24 to Updated Final Safety Analysis Report, Chapter 2, Site Characteristics
References
NG-17-0111
Download: ML17157B674 (81)

Text

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