NG-17-0111, Duane Arnold Energy Center, Revision 24 to Updated Final Safety Analysis Report, Table of Contents
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