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#REDIRECT [[NG-17-0111, Duane Arnold Energy Center, Revision 24 to Updated Final Safety Analysis Report, Table of Contents]]
{{Adams
| 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}}

Latest revision as of 05:59, 16 March 2019

Duane Arnold Energy Center, Revision 24 to Updated Final Safety Analysis Report, Table of Contents
ML17157B674
Person / Time
Site: Duane Arnold NextEra Energy icon.png
Issue date: 05/22/2017
From:
NextEra Energy Duane Arnold
To:
Office of Nuclear Reactor Regulation
Shared Package
ML17157B650 List:
References
NG-17-0111
Download: ML17157B674 (81)
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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

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