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{{#Wiki_filter:UPDATED FINAL SAFETY ANALYSIS REPORT DUANE ARNOLD ENERGY CENTER | {{#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 INTRODUCTION== | ||
....................................................................................... 1.1 | ....................................................................................... 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 INTRODUCTION== | ||
....................................................................................... 7.1-1 7.2 | ....................................................................................... 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 INTRODUCTION== | ||
........................................................................................ 8.1-1 8.2 | ........................................................................................ 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 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}} |
Latest revision as of 05:59, 16 March 2019
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