ML19137A123

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Rev. 29 to Updated Safety Analysis Report,Section I, Table of Contents
ML19137A123
Person / Time
Site: Cooper 
Issue date: 04/24/2019
From:
Nebraska Public Power District (NPPD)
To:
Office of Nuclear Reactor Regulation
Shared Package
ML19137A206 List:
References
NLS2019023
Download: ML19137A123 (35)
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Text

VOLUME I - USAR 02/06/01 I - INTRODUCTION AND

SUMMARY

PAGE 1.0 PROJECT IDENTIFICATION I-1-1 1.1 Identification and Qualification of Contractors I-1-1 2.0 DEFINITIONS I-2-1 3.0 METHODS OF TECHNICAL PRESENTATION I-3-1 3.1 Purpose I-3-1 3.2 Radioactive Material Barrier Concept I-3-1 3.3 Organization of Contents I-3-1 3.4 Format Organization of Chapters I-3-1 4.0 PRINCIPAL DESIGN CRITERIA I-4-1 4.1 Principal Design Criteria-Functional Classification I-4-1 4.2 Principal Design Criteria, System-By-System I-4-7 5.0 CLASSIFICATION OF STRUCTURES, SYSTEMS, AND COMPONENTS I-5-1 5.1 Quality Group Classifications I-5-1 5.2 Loading Classification I-5-1 6.0 COMPARISON OF PRINCIPAL DESIGN CHARACTERISTICS I-6-1 6.1 Nuclear System Design Characteristics I-6-1 6.2 Power Conversion Systems Design Characteristics I-6-1 6.3 Electrical Power Systems Design Characteristics I-6-1 6.4 Containment Design Characteristics I-6-1 6.5 Structural Design Characteristics I-6-1 7.0 STATION RESEARCH DEVELOPMENT AND FURTHER INFORMATION; REQUIREMENTS AND RESOLUTIONS

SUMMARY

I-7-1

8.0 REFERENCES

FOR CHAPTER I I-8-1

VOLUME I - USAR 07/09/03 II - STATION SITE AND ENVIRONS PAGE

1.0 INTRODUCTION

AND

SUMMARY

DESCRIPTION II-1-1 1.1 Location II-1-1 1.2 Site Ownership II-1-1 1.3 Activities at the Site II-1-1 1.4 Access to the Site II-1-1 1.5 Description of the Environs II-1-1 2.0 SITE DESCRIPTION II-2-1 2.1 Location and Area II-2-1 2.2 Population Distribution II-2-1 2.3 Character of Site Surroundings II-2-2 2.4 Conclusions II-2-7 3.0 METEOROLOGY II-3-1 3.1 General II-3-1 3.2 Meteorological Design Bases II-3-3 3.3 Meteorological Monitoring II-3-8 4.0 HYDROLOGY II-4-1 4.1 General II-4-1 4.2 Stream Flow II-4-1 4.3 River Usage II-4-9 4.4 Ground Water II-4-10 4.5 Chemical and Bacteriological Quality of Water II-4-12 4.6 Conclusions II-4-12 5.0 GEOLOGY AND SEISMOLOGY II-5-1 5.1 Geology II-5-1 5.2 Seismology and Design Response Criteria II-5-2 6.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM II-6-1

7.0 REFERENCES

FOR CHAPTER II II-7-1

VOLUME I - USAR 02/20/17 III - REACTOR PAGE 1.0

SUMMARY

DESCRIPTION III-1-1 2.0 FUEL MECHANICAL DESIGN III-2-1 2.1 Safety Objective III-2-1 2.2 Safety Design Basis III-2-1 2.3 Power Generation Objective III-2-1 2.4 Power Generation Design Basis III-2-1 2.5 Description III-2-1 2.6 Safety Evaluation III-2-5 2.7 Inspection and Testing III-2-11 3.0 REACTOR VESSEL INTERNALS MECHANICAL DESIGN III-3-1 3.1 Safety Objective III-3-1 3.2 Safety Design Bases III-3-1 3.3 Power Generation Objectives III-3-1 3.4 Power Generation Design Bases III-3-1 3.5 Description III-3-2 3.6 Safety Evaluation III-3-9 3.7 Inspection and Testing III-3-16 4.0 REACTIVITY CONTROL MECHANICAL DESIGN III-4-1 4.1 Safety Objective III-4-1 4.2 Safety Design Bases III-4-1 4.3 Power Generation Objective III-4-1 4.4 Power Generation Design Basis III-4-1 4.5 Description III-4-1 4.6 Safety Evaluation III-4-3 4.7 Inspection and Testing III-4-4 5.0 CONTROL ROD DRIVE MECHANICAL DESIGN III-5-1 5.1 Safety Objective III-5-1 5.2 Safety Design Bases III-5-1 5.3 Power Generation Objective III-5-2 5.4 Power Generation Design Basis III-5-2 5.5 Description III-5-2 5.6 Safety Evaluation III-5-16 5.7 Inspection and Testing III-5-24 6.0 NUCLEAR DESIGN III-6-1 6.1 Safety Objective III-6-1 6.2 Safety Design Bases III-6-1 6.3 Power Generation Objective III-6-1 6.4 Power Generation Design Bases III-6-1 6.5 Nuclear Requirements III-6-1 6.6 Fuel Nuclear Characteristics III-6-2 6.7 Safety Evaluations III-6-11 6.8 Testing and Verification III-6-12

VOLUME I - USAR 02/05/10 III - REACTOR (CONT'D)

PAGE 7.0 THERMAL AND HYDRAULIC DESIGN III-7-1 7.1 Safety Objective III-7-1 7.2 Safety Design Bases III-7-1 7.3 Power Generation Objective III-7-1 7.4 Power Generation Design Bases III-7-1 7.5 Thermal and Hydraulic Limits III-7-1 7.6 Thermal and Hydraulic Characteristics III-7-3 7.7 Safety Evaluation III-7-14 7.8 Testing and Verification III-7-17 8.0 CONTROL ROD DRIVE HOUSING SUPPORTS III-8-1 8.1 Safety Objective III-8-1 8.2 Safety Design Bases III-8-1 8.3 Description III-8-1 8.4 Safety Evaluation III-8-2 8.5 Inspection and Testing III-8-3 9.0 STANDBY LIQUID CONTROL SYSTEM III-9-1 9.1 Safety Objective III-9-1 9.2 Safety Design Bases III-9-1 9.3 Description III-9-2 9.4 Safety Evaluation III-9-4 9.5 Inspection and Testing III-9-7 10.0 THERMAL-HYDRAULIC STABILITY ANALYSIS 10.1 Safety Objective III-10-1 10.2 Safety Design Basis III-10-1 10.3 Description and Performance Analysis III-10-1 10.4 Ultimate Performance Limit Criteria and Conformance III-10-2 10.5 Conclusion III-10-5

11.0 REFERENCES

FOR CHAPTER III III-11-1

VOLUME II - USAR 12/20/04 IV - REACTOR COOLANT SYSTEM PAGE 1.0

SUMMARY

DESCRIPTION IV-1-1 2.0 REACTOR VESSEL AND APPURTENANCES MECHANICAL DESIGN IV-2-1 2.1 Safety Objective IV-2-1 2.2 Safety Design Bases IV-2-1 2.3 Power Generation Objective IV-2-1 2.4 Power Generation Design Bases IV-2-1 2.5 Description IV-2-1 2.6 Safety Evaluation IV-2-10 2.7 Inspection and Testing IV-2-17 3.0 REACTOR RECIRCULATION SYSTEM IV-3-1 3.1 Safety Objective IV-3-1 3.2 Safety Design Bases IV-3-1 3.3 Power Generation Objective IV-3-1 3.4 Power Generation Design Bases IV-3-1 3.5 Description IV-3-1 3.6 Safety Evaluation IV-3-7 3.7 Inspection and Testing IV-3-8 4.0 NUCLEAR SYSTEM PRESSURE RELIEF SYSTEM IV-4-1 4.1 Safety Objective IV-4-1 4.2 Safety Design Bases IV-4-1 4.3 Power Generation Objective IV-4-1 4.4 Power Generation Design Bases IV-4-1 4.5 Description IV-4-2 4.6 Safety Evaluation IV-4-10 4.7 Power Generation Evaluation IV-4-13 4.8 Inspection and Testing IV-4-13 4.9 Overpressure Protection Analysis IV-4-14 5.0 MAINSTEAM LINE FLOW RESTRICTOR IV-5-1 5.1 Safety Objective IV-5-1 5.2 Safety Design Bases IV-5-1 5.3 Description IV-5-1 5.4 Safety Evaluation IV-5-1 5.5 Inspection and Testing IV-5-2 6.0 MAIN STEAM LINE ISOLATION VALVES IV-6-1 6.1 Safety Objectives IV-6-1 6.2 Safety Design Bases IV-6-1 6.3 Description IV-6-1 6.4 Safety Evaluation IV-6-4 6.5 Inspection and Testing IV-6-6

VOLUME II - USAR 02/23/01 IV - REACTOR COOLANT SYSTEM (CONT'D)

PAGE 7.0 REACTOR CORE ISOLATION COOLING SYSTEM IV-7-1 7.1 Safety Objective IV-7-1 7.2 Safety Design Bases IV-7-1 7.3 Power Generation Objective IV-7-1 7.4 Power Generation Design Bases IV-7-1 7.5 Description IV-7-1 7.6 Safety Evaluation IV-7-7 7.7 Inspection and Testing IV-7-8 8.0 RESIDUAL HEAT REMOVAL SYSTEM IV-8-1 8.1 Safety Objective IV-8-1 8.2 Safety Design Bases IV-8-1 8.3 Power Generation Objective IV-8-1 8.4 Power Generation Design Bases IV-8-1 8.5 Description IV-8-2 8.6 Safety Evaluation IV-8-6 8.7 Inspection and Testing IV-8-7 9.0 REACTOR WATER CLEANUP SYSTEM IV-9-1 9.1 Power Generation Objective IV-9-1 9.2 Power Generation Design Bases IV-9-1 9.3 Description IV-9-1 9.4 Inspection and Testing IV-9-5 10.0 REACTOR COOLANT SYSTEM LEAKAGE RATE LIMITS IV-10-1 10.1 Safety Objective IV-10-1 10.2 Safety Design Bases IV-10-1 10.3 Description IV-10-1 10.4 Safety Evaluation IV-10-6 10.5 Inspection and Testing IV-10-7 11.0 MAIN STEAM LINES AND FEEDWATER PIPING IV-11-1 11.1 Safety Objective IV-11-1 11.2 Safety Design Bases IV-11-1 11.3 Power Generation Objectives IV-11-1 11.4 Power Generation Design Bases IV-11-1 11.5 Description IV-11-1 11.6 Safety Evaluation IV-11-2 11.7 Inspection and Testing IV-11-3 12.0 HIGH ENERGY LINE BREAK (HELB) STUDY IV-12-1 12.1 Description IV-12-1 12.2 Subsequent HELB Analyses IV-12-3

13.0 REFERENCES

FOR CHAPTER IV IV-13-1

VOLUME II - USAR 05/28/03 V - CONTAINMENT PAGE 1.0

SUMMARY

DESCRIPTION V-1-1 1.1 General V-1-1 1.2 Primary Containment Systems V-1-1 1.3 Secondary Containment System V-1-1 2.0 PRIMARY CONTAINMENT V-2-1 2.1 Safety Objective V-2-1 2.2 Safety Design Basis V-2-1 2.3 Description V-2-1 2.4 Safety Evaluation V-2-55 2.5 Inspection and Testing V-2-63 3.0 SECONDARY CONTAINMENT V-3-1 3.1 Safety Objective V-3-1 3.2 Safety Design Basis V-3-1 3.3 Description V-3-1 3.4 Safety Evaluation V-3-5 3.5 Inspection and Testing V-3-9

4.0 REFERENCES

FOR CHAPTER V V-4-1

VOLUME II - USAR 06/03/08 VI - EMERGENCY CORE COOLING SYSTEMS PAGE 1.0 EMERGENCY CORE COOLING SYSTEMS VI-1-1 1.1 Safety Objective VI-1-1 2.0 SAFETY DESIGN BASES VI-2-1 3.0

SUMMARY

DESCRIPTION - EMERGENCY CORE COOLING SYSTEMS VI-3-1

4.0 DESCRIPTION

VI-4-1 4.1 High Pressure Coolant Injection System VI-4-1 4.2 Automatic Depressurization System VI-4-5 4.3 Core Spray System VI-4-6 4.4 Low Pressure Coolant Injection System VI-4-8 5.0 SAFETY EVALUATION VI-5-1 5.1 Summary VI-5-1 5.2 Performance Evaluation VI-5-1 5.3 ECCS Pumps NPSH VI-5-16 5.4 Protection Provisions VI-5-18 6.0 INSPECTION AND TESTING VI-6-1

7.0 REFERENCES

VI-7-1

VOLUME III - USAR 04/06/05 VII - CONTROL AND INSTRUMENTATION PAGE 1.0

SUMMARY

DESCRIPTION VII-1-1 1.1 Safety Systems VII-1-1 1.2 Power Generation Systems VII-1-1 1.3 Safety Functions VII-1-2 1.4 Station Operational Control VII-1-3 1.5 Definitions VII-1-4 1.6 System Suppliers and Design Basis VII-1-4 1.7 Design Criteria VII-1-5 2.0 REACTOR PROTECTION SYSTEM VII-2-1 2.1 Safety Objective VII-2-1 2.2 Safety Design Basis VII-2-1 2.3 Description VII-2-3 2.4 Safety Evaluation VII-2-14 2.5 Inspection and Testing VII-2-19 3.0 PRIMARY CONTAINMENT ISOLATION CONTROL AND INSTRUMENTATION SYSTEM VII-3-1 3.1 Safety Objective VII-3-1 3.2 Safety Design Basis VII-3-1 3.3 Description VII-3-3 3.4 Safety Evaluation VII-3-17 3.5 Inspection and Testing VII-3-20 4.0 EMERGENCY CORE COOLING SYSTEMS CONTROL AND INSTRUMENTATION VII-4-1 4.1 Safety Objective VII-4-1 4.2 Safety Design Basis VII-4-1 4.3 Power Generation Objective VII-4-2 4.4 Power Generation Design Basis VII-4-2 4.5 Description VII-4-3 4.6 Safety Evaluation VII-4-23 4.7 Inspection and Testing VII-4-25 5.0 NEUTRON MONITORING SYSTEM VII-5-1 5.1 Safety Objective VII-5-1 5.2 Safety Design Basis VII-5-1 5.3 Power Generation Objective VII-5-1 5.4 Power Generation Design Basis VII-5-1 5.5 Identification VII-5-1 5.6 Source Range Monitor Subsystem VII-5-1 5.7 Intermediate Range Monitor Subsystem VII-5-6 5.8 Local Power Range Monitor Subsystem VII-5-9 5.9 Average Power Range Monitor Subsystem VII-5-14 5.10 Rod Block Monitor Subsystem VII-5-18 5.11 Traversing In-Core Probe Subsystem VII-5-19

VOLUME III - USAR 04/22/02 VII - CONTROL AND INSTRUMENTATION (CONT'D)

PAGE 6.0 REFUELING INTERLOCKS VII-6-1 6.1 Safety Objective VII-6-1 6.2 Safety Design Basis VII-6-1 6.3 Description VII-6-1 6.4 Safety Evaluation VII-6-4 6.5 Inspection and Testing VII-6-5 7.0 REACTOR MANUAL CONTROL SYSTEM VII-7-1 7.1 Safety Objective VII-7-1 7.2 Safety Design Basis VII-7-1 7.3 Power Generation Objective VII-7-1 7.4 Power Generation Design Basis VII-7-1 7.5 Description VII-7-1 7.6 Safety Evaluation VII-7-10 7.7 Inspection and Testing VII-7-10 8.0 REACTOR VESSEL INSTRUMENTATION VII-8-1 8.1 Safety Objective VII-8-1 8.2 Safety Design Basis VII-8-1 8.3 Power Generation Objective VII-8-1 8.4 Power Generation Design Basis VII-8-1 8.5 Description VII-8-1 8.6 Safety Evaluation VII-8-7 8.7 Inspection and Testing VII-8-8 9.0 RECIRCULATION FLOW CONTROL SYSTEM VII-9-1 9.1 Safety Objective VII-9-1 9.2 Safety Design Basis VII-9-1 9.3 Power Generation Objective VII-9-1 9.4 Power Generation Design Basis VII-9-1 9.5 Description VII-9-1 9.6 Safety Evaluation VII-9-6 9.7 Inspection and Testing VII-9-6 10.0 FEEDWATER CONTROL SYSTEM VII-10-1 10.1 Power Generation Objective VII-10-1 10.2 Power Generation Design Bases VII-10-1 10.3 Description VII-10-1 10.4 Inspection and Testing VII-10-4 11.0 PRESSURE REGULATOR AND TURBINE-GENERATOR CONTROL VII-11-1 11.1 Power Generation Objective VII-11-1 11.2 Power Generation Design Basis VII-11-1 11.3 Description VII-11-1 11.4 Power Generation Evaluation VII-11-4 11.5 Inspection and Testing VII-11-4 12.0 PROCESS RADIATION MONITORING VII-12-1 12.1 Main Steam Line Radiation Monitoring System VII-12-1 12.2 Air Ejector Off-Gas Radiation Monitoring System VII-12-4

VOLUME III - USAR 01/17/14 VII - CONTROL AND INSTRUMENTATION (CONT'D)

PAGE 12.3 Process Liquid Radiation Monitors VII-12-5 12.4 Reactor Building Isolation Ventilation Radiation Monitoring System VII-12-8 12.5 Elevated Release Point Radiation Monitoring System VII-12-9 12.6 Radwaste/Augmented Radwaste Building Ventilation Radiation Monitoring System VII-12-10 12.7 Turbine Building Ventilation Radiation Monitoring System VII-12-12 12.8 Multi-Purpose Facility Building Ventilation Monitoring System VII-12-13 12.9 Reactor Building Ventilation Radiation Monitoring System VII-12-14 13.0 PLANT AND AUGMENTED RADWASTE (DRUM HANDLING) AREA RADIATION MONITORING SYSTEM VII-13-1 13.1 Power Generation Objective VII-13-1 13.2 Power Generation Design Bases VII-13-1 13.3 Description VII-13-1 13.4 Inspection and Testing VII-13-3 14.0 ENVIRONMENTAL RADIATION MONITORING INSTRUMENTS VII-14-1 14.1 General VII-14-1 14.2 Description VII-14-1 15.0 RADIOLOGICAL PROTECTION AND RADIOCHEMISTRY INSTRUMENTS VII-15-1 15.1 Portable Radiation Survey Instruments VII-15-1 15.2 Personnel Radiation Monitoring Devices VII-15-1 15.3 Personnel Contamination Monitoring Devices VII-15-1 15.4 Constant Air Monitors VII-15-1 15.5 Counting Room Instruments VII-15-1 15.6 Radiochemistry Instruments VII-15-1 15.7 Inspection and Testing VII-15-1 16.0 PROCESS COMPUTER SYSTEM VII-16-1 16.1 Power Generation Objective VII-16-1 16.2 Power Generation Design Basis VII-16-1 16.3 Description VII-16-1 16.4 Power Generation Evaluation VII-16-13 16.5 Inspection and Testing VII-16-13 17.0 STANDBY GAS TREATMENT SYSTEM VII-17-1 17.1 Safety Objective VII-17-1 17.2 Safety Design Basis VII-17-1 17.3 Description VII-17-1 17.4 Safety Evaluation VII-17-3 17.5 Inspection and Testing VII-17-3

VOLUME III - USAR 04/08/15 VII - CONTROL AND INSTRUMENTATION (CONT'D)

PAGE 18.0 ALTERNATE SHUTDOWN CAPABILITY VII-18-1 18.1 Safety Objective VII-18-1 18.2 Safety Design Basis VII-18-1 18.3 Description VII-18-1 18.4 System Operation VII-18-2 18.5 Safety Evaluation VII-18-2 18.6 Inspection and Testing VII-18-2

19.0 REFERENCES

FOR CHAPTER VII VII-19-1

VOLUME IV - USAR 04/08/15 VIII - ELECTRICAL POWER SYSTEMS PAGE 1.0

SUMMARY

DESCRIPTION VIII-1-1 2.0 NORMAL AND STARTUP AC POWER SOURCES VIII-2-1 2.1 Normal AC Power Source VIII-2-1 2.2 Startup AC Power Source VIII-2-2 2.3 Transmission Line Design Considerations VIII-2-6 3.0 EMERGENCY AC POWER SOURCE VIII-3-1 3.1 Safety Objective VIII-3-1 3.2 Safety Design Bases VIII-3-1 3.3 Power Generation Objective VIII-3-1 3.4 Power Generation Design Basis VIII-3-1 3.5 Description VIII-3-1 3.6 Safety Evaluation VIII-3-2 3.7 Inspection and Testing VIII-3-3 4.0 AUXILIARY POWER DISTRIBUTION SYSTEM VIII-4-1 4.1 Safety Objective VIII-4-1 4.2 Safety Design Bases VIII-4-1 4.3 Power Generation Objective VIII-4-1 4.4 Power Generation Design Basis VIII-4-1 4.5 Description VIII-4-1 4.6 Safety Evaluation VIII-4-3 4.7 Inspection and Testing VIII-4-7 5.0 STANDBY A-C POWER SOURCE VIII-5-1 5.1 Safety Objective VIII-5-1 5.2 Safety Design Basis VIII-5-1 5.3 Description VIII-5-7 5.4 Safety Evaluation VIII-5-14 5.5 Inspection and Testing VIII-5-15 6.0 125/250 VOLT DC POWER SYSTEMS VIII-6-1 6.1 Safety Objective VIII-6-1 6.2 Safety Design Bases VIII-6-1 6.3 Description VIII-6-1 6.4 Safety Evaluation VIII-6-2 6.5 Inspection and Testing VIII-6-3 7.0 24 VOLT DC POWER SYSTEM VIII-7-1 7.1 Power Generation VIII-7-1 7.2 Power Generation Design Bases VIII-7-1 7.3 Description VIII-7-1 7.4 Inspection and Testing VIII-7-2

VOLUME IV - USAR 02/06/01 VIII - ELECTRICAL POWER SYSTEMS (CONT'D)

PAGE 8.0 120/240 VOLT VITAL AC POWER SYSTEMS VIII-8-1 8.1 Power Generation Objectives VIII-8-1 8.2 Power Generation Design Bases VIII-8-1 8.3 Description VIII-8-1 8.4 Inspection and Testing VIII-8-2 9.0 OFF-SITE DISTRIBUTION POWER VIII-9-1 9.1 Power Generation Objective VIII-9-1 9.2 Power Generation Design Bases VIII-9-1 9.3 Description VIII-9-1 9.4 Inspection and Testing VIII-9-1

10.0 REFERENCES

FOR CHAPTER VIII VIII-10-1

VOLUME IV - USAR 03/21/13 IX - RADIOACTIVE WASTE SYSTEMS PAGE 1.0

SUMMARY

DESCRIPTION IX-1-1 2.0 LIQUID RADWASTE SYSTEM IX-2-1 2.1 Safety Objective IX-2-1 2.2 Safety Design Basis IX-2-1 2.3 Power Generation Objective IX-2-1 2.4 Power Generation Design Basis IX-2-1 2.5 Liquid Radwaste System (Non-Augmented)

IX-2-1 2.6 Augmented Liquid Radwaste (LRW) System IX-2-4 2.7 Safety Evaluation IX-2-4 2.8 Power Generation Evaluation IX-2-5 2.9 Inspection and Testing IX-2-5 3.0 SOLID RADWASTE SYSTEM IX-3-1 3.1 Power Generation Objective IX-3-1 3.2 Power Generation Design Basis IX-3-1 3.3 Description IX-3-1 3.4 Power Generation Evaluation IX-3-6 3.5 Inspection and Testing IX-3-6 4.0 GASEOUS RADWASTE SYSTEM IX-4-1 4.1 Power Generation Objective IX-4-1 4.2 Power Generation Design Basis IX-4-1 4.3 Off-Gas System (Non-Augmented)

IX-4-1 4.4 Augmented Off-Gas (AOG) System IX-4-5 4.5 Power Generation Evaluation IX-4-14 4.6 Inspection and Testing IX-4-17

5.0 REFERENCES

FOR CHAPTER IX IX-5-1

VOLUME IV - USAR 04/22/16 X - AUXILIARY SYSTEMS PAGE 1.0

SUMMARY

DESCRIPTION X-1-1 2.0 NEW FUEL STORAGE X-2-1 3.0 SPENT FUEL STORAGE X-3-1 3.1 Safety Objective X-3-1 3.2 Safety Design Basis X-3-1 3.3 Power Generation Objective X-3-1 3.4 Power Generation Design Basis X-3-1 3.5 Description X-3-1 3.6 Safety Evaluation X-3-6 3.7 Inspection and Testing X-3-9 4.0 FUEL HANDLING AND MOVEMENT OF HEAVY LOADS X-4-1 4.1 Introduction X-4-1 4.2 Fuel Servicing Equipment X-4-1 4.3 Refueling Equipment X-4-1 4.4 Reactor Building Crane X-4-2 4.5 Fuel Handling Operations X-4-3 4.6 Control of Heavy Loads X-4-6 5.0 FUEL POOL COOLING AND DEMINERALIZER SYSTEM X-5-1 5.1 Power Generation Objective X-5-1 5.2 Power Generation Design Basis X-5-1 5.3 Description X-5-1 5.4 Power Generation Evaluation X-5-4 5.5 Inspection and Testing X-5-5 6.0 REACTOR EQUIPMENT COOLING SYSTEM X-6-1 6.1 Safety Objective X-6-1 6.2 Safety Design Basis X-6-1 6.3 Power Generation Objective X-6-1 6.4 Power Generation Design Basis X-6-1 6.5 Description X-6-1 6.6 Safety Evaluation X-6-8 6.7 Inspection and Testing X-6-9 7.0 TURBINE EQUIPMENT COOLING SYSTEM X-7-1 7.1 Power Generation Objective X-7-1 7.2 Power Generation Design Basis X-7-1 7.3 Description X-7-1 7.4 Inspection and Testing X-7-4 8.0 SERVICE WATER AND RHR SERVICE WATER BOOSTER SYSTEM X-8-1 8.1 Service Water System X-8-1 8.2 RHR Service Water Booster Service X-8-7

VOLUME IV - USAR 07/28/15 X - AUXILIARY SYSTEMS (CONT'D)

PAGE 9.0 FIRE PROTECTION SYSTEM X-9-1 9.1 Power Generation Objective X-9-1 9.2 Power Generation Design Basis X-9-1 9.3 Description X-9-1 9.4 Codes and Standards X-9-5 9.5 Seismic Criteria X-9-5 9.6 Inspection and Testing X-9-6 10.0 HEATING, VENTILATION AND AIR CONDITIONING SYSTEMS X-10-1 10.1 General X-10-1 10.2 Reactor Building Heating and Ventilating System X-10-3 10.3 Control Building Heating and Ventilating System X-10-7 10.4 Main Control Room Air Conditioning System and Habitability Controls X-10-11 10.5 Diesel-Generator Building Heating and Ventilating Systems X-10-16 10.6 Non-Essential Heating, Ventilating, and Air Conditioning Systems X-10-18 11.0 MAKEUP WATER TREATMENT SYSTEM X-11-1 11.1 Power Generation Objective X-11-1 11.2 Power Generation Design Basis X-11-1 11.3 Description X-11-1 11.4 Inspection and Testing X-11-2 12.0 INSTRUMENT AND SERVICE AIR SYSTEMS X-12-1 12.1 Power Generation Objective X-12-1 12.2 Power Generation Design Basis X-12-1 12.3 Description X-12-1 12.4 Inspection and Testing X-12-6 13.0 POTABLE AND SANITARY WATER SYSTEMS X-13-1 13.1 Power Generation Objective X-13-1 13.2 Power Generation Design Basis X-13-1 13.3 Description X-13-1 13.4 Inspection and Testing X-13-1 14.0 EQUIPMENT AND FLOOR DRAINAGE SYSTEMS X-14-1 14.1 Safety Objective X-14-1 14.2 Safety Design Basis X-14-1 14.3 Power Generation Objective X-14-1 14.4 Power Generation Design Basis X-14-1 14.5 Description X-14-1 14.6 Safety Evaluation X-14-4 14.7 Inspection and Testing X-14-7 15.0 PROCESS SAMPLING AND POST-ACCIDENT SAMPLING SYSTEMS X-15-1 15.1 Power Generation Objective X-15-1 15.2 Power Generation Design Basis X-15-1 15.3 Description X-15-1 15.4 Inspection and Testing X-15-2

VOLUME IV - USAR 04/08/15 X - AUXILIARY SYSTEMS (CONT'D)

PAGE 16.0 COMMUNICATIONS SYSTEMS X-16-1 16.1 Power Generation Objective X-16-1 16.2 Power Generation Design Basis X-16-1 16.3 Description X-16-2 16.4 Inspection and Testing X-16-3 17.0 STATION LIGHTING SYSTEM X-17-1 17.1 Power Generation Objective X-17-1 17.2 Power Generation Design Basis X-17-1 17.3 Description X-17-1 17.4 Inspection and Testing X-17-1 18.0 OPTIMUM WATER CHEMISTRY (OWC) SYSTEM X-18-1 18.1 Power Generation Objective X-18-1 18.2 Power Generation Design Basis X-18-1 18.3 Description X-18-1 18.4 Inspection and Testing X-18-2

19.0 REFERENCES

X-19-1

VOLUME IV - USAR 01/17/14 XI - POWER CONVERSION SYSTEMS PAGE 1.0

SUMMARY

DESCRIPTION XI-1-1 2.0 TURBINE-GENERATOR XI-2-1 2.1 Power Generation Objective XI-2-1 2.2 Power Generation Design Basis XI-2-1 2.3 Description XI-2-1 2.4 Turbine Missile Analysis XI-2-1 2.5 Power Generation Evaluation XI-2-2 2.6 Inspection and Testing XI-2-2 3.0 MAIN CONDENSER XI-3-1 3.1 Safety Objective XI-3-1 3.2 Safety Design Basis XI-3-1 3.3 Power Generation Objective XI-3-1 3.4 Power Generation Design Basis XI-3-1 3.5 Description XI-3-1 3.6 Safety Evaluation XI-3-3 3.7 Inspection and Testing XI-3-3 4.0 MAIN CONDENSER GAS REMOVAL AND TURBINE SEALING SYSTEMS XI-4-1 4.1 Power Generation Objective XI-4-1 4.2 Power Generation Design Basis XI-4-1 4.3 Description XI-4-1 4.4 Inspection and Testing XI-4-3 5.0 TURBINE BYPASS SYSTEM XI-5-1 5.1 Power Generation Objective XI-5-1 5.2 Power Generation Design Basis XI-5-1 5.3 Description XI-5-1 5.4 Power Generation Evaluation XI-5-1 6.0 CIRCULATING WATER SYSTEM XI-6-1 6.1 Power Generation Objective XI-6-1 6.2 Power Generation Design Basis XI-6-1 6.3 Description XI-6-1 6.4 Inspection and Testing XI-6-2 7.0 CONDENSATE DEMINERALIZER SYSTEM XI-7-1 7.1 Power Generation Objective XI-7-1 7.2 Power Generation Design Basis XI-7-1 7.3 Description XI-7-1 7.4 Inspection and Testing XI-7-2 8.0 CONDENSATE AND FEEDWATER SYSTEM XI-8-1 8.1 Power Generation Objective XI-8-1 8.2 Power Generation Design Basis XI-8-1 8.3 Description XI-8-1 8.4 Inspection and Testing XI-8-2 9.0 CONDENSATE STORAGE SYSTEM XI-9-1 9.1 Power Generation Objective XI-9-1 9.2 Power Generation Design Basis XI-9-1 9.3 Description XI-9-1 9.4 Inspection and Testing XI-9-1

10.0 REFERENCES

FOR CHAPTER XI XI-10-1

VOLUME V - USAR 01/17/14 XII - STRUCTURES AND SHIELDING PAGE 1.0

SUMMARY

DESCRIPTION XII-1-1 2.0 STRUCTURAL DESIGN XII-2-1 2.1 Classification of Structures and Equipment XII-2-1 2.2 Description of Principal Structures XII-2-3 2.3 Loading Considerations XII-2-11 2.4 Foundation Analysis XII-2-34 3.0 SHIELDING AND RADIATION PROTECTION XII-3-1 3.1 Design Basis XII-3-1 3.2 Control of Access to Radiological Areas XII-3-3 3.3 Shielding Description XII-3-3 3.4 Inspection and Performance Analysis XII-3-7 3.5 Radioactive Material Safety XII-3-7

4.0 REFERENCES

FOR CHAPTER XII XII-4-1

VOLUME V - USAR 01/24/19 XIII - CONDUCT OF OPERATIONS PAGE 1.0

SUMMARY

DESCRIPTION XIII-1-1 2.0 ORGANIZATION AND RESPONSIBILITY XIII-2-1 2.1 Nuclear Organization XIII-2-1 2.2 Construction Testing Responsibility XIII-2-2 2.3 Preoperational Testing Responsibility XIII-2-2 2.4 Startup and Power Testing Responsibility XIII-2-2 2.5 Nuclear System Supplier Technical Direction XIII-2-2 2.6 Balance of Plant Technical Assistance XIII-2-3 3.0 PERSONNEL QUALIFICATIONS AND TRAINING XIII-3-1 3.1 Plant Personnel Training Program XIII-3-1 3.2 INPO Accredited Training Programs XIII-3-1 3.3 Simulator Training XIII-3-1 3.4 General Orientation Training XIII-3-2 3.5 Personnel Qualification Requirements XIII-3-2 3.6 Records XIII-3-2 4.0 CONSTRUCTION AND PREOPERATIONAL TEST PROGRAM XIII-4-1 4.1 Objectives XIII-4-1 4.2 Preoperational Test Schedule Considerations XIII-4-1 4.3 Summary of Construction Test Content XIII-4-2 4.4 Summary of Preoperational Test Content XIII-4-3 5.0 STARTUP AND POWER TEST PROGRAM XIII-5-1 5.1 General Objectives XIII-5-1 5.2 Discussion of Startup and Power Tests XIII-5-6 6.0 NORMAL OPERATIONS XIII-6-1 6.1 Administrative Procedures XIII-6-1 6.2 Site Support Procedures XIII-6-1 6.3 Operations Procedures XIII-6-1 6.4 Engineering Procedures XIII-6-2 6.5 Instrumentation Operations Procedures XIII-6-2 6.6 Emergency Procedures XIII-6-2 6.7 Surveillance Procedures XIII-6-3 6.8 Maintenance Procedures XIII-6-3 6.9 Chemistry Procedures XIII-6-3 6.10 Radiological Protection Procedures XIII-6-3 6.11 Nuclear Performance Procedures XIII-6-3 6.12 Station Computer Procedures XIII-6-3 6.13 Quality Control Procedures XIII-6-4 6.14 Performance Evaluation Procedures XIII-6-4 6.15 Instrument and Control Procedures XIII-6-4 6.16 Surveillance (Non-Technical Specification) Procedures XIII-6-4 6.17 Shift Crew Requirements XIII-6-4 7.0 EMERGENCY PLANNING XIII-7-1 8.0 RECORDS XIII-8-1 8.1 Initial Testing and Operations XIII-8-1 8.2 Normal Operations and Maintenance XIII-8-1

VOLUME V - USAR 04/08/15 XIII - CONDUCT OF OPERATIONS (CONT'D)

PAGE 9.0 OPERATIONAL REVIEW AND AUDITS XIII-9-1 9.1 Administrative Control XIII-9-1 9.2 Routine Reviews XIII-9-1 9.3 NPPD Safety Review and Audit Board XIII-9-1 10.0 FIRE PROTECTION PROGRAM XIII-10-1 10.1 Purpose and Importance of Fire Protection XIII-10-1 10.2 Fire Protection Regulatory Compliance XIII-10-1 10.3 Design Basis Summary XIII-10-1 10.4 NFPA 805 System Description XIII-10-3 10.5 Regulatory Evaluation XIII-10-6 10.6 Fire Protection Program Documentation, Configuration XIII-10-6 Control and Quality Assurance 11.0 IODINE MONITORING PROGRAM XIII-11-1 12.0 TECHNICAL REQUIREMENTS MANUAL XIII-12-1 13.0 PROCESS CONTROL PROGRAM XIII-13-1

14.0 REFERENCES

FOR CHAPTER XIII XIII-14-1

VOLUME V - USAR 07/14/11 XIV - STATION SAFETY ANALYSIS PAGE 1.0 SAFETY OBJECTIVE XIV-1-1 1.1 Background and Supporting Information XIV-1-1 2.0 SAFETY DESIGN BASES FOR ABNORMAL OPERATIONAL TRANSIENTS XIV-2-1 2.1 Safety Design Bases for Analyzed Special Plant Events XIV-2-1 3.0 SAFETY DESIGN BASES FOR ACCIDENTS XIV-3-1 4.0 APPROACH TO SAFETY ANALYSIS XIV-4-1 4.1 General XIV-4-1 4.2 Abnormal Operational Transients XIV-4-1 4.3 Accidents XIV-4-3 4.4 Barrier Damage Evaluations XIV-4-4 5.0 ANALYSES OF ABNORMAL OPERATIONAL TRANSIENTS XIV-5-1 5.1 Events Resulting in a Nuclear System Pressure Increase XIV-5-2 5.2 Events Resulting in a Reactor Vessel Water Temperature Decrease XIV-5-16 5.3 Events Resulting in a Positive Reactivity Insertion XIV-5-19 5.4 Events Resulting in a Reactor Vessel Coolant Inventory Decrease XIV-5-24 5.5 Events Resulting in a Core Coolant Flow Decrease XIV-5-31 5.6 Events Resulting in a Core Coolant Flow Increase XIV-5-36 5.7 Event Resulting in a Core Coolant Temperature Increase XIV-5-39 5.8 Event Resulting in Excess of Coolant Inventory XIV-5-40 5.9 Special Events XIV-5-42 6.0 ANALYSIS OF DESIGN BASIS ACCIDENTS XIV-6-1 6.1 Introduction XIV-6-1 6.2 Control Rod Drop Accident XIV-6-2 6.3 Loss-of-Coolant Accident XIV-6-11 6.4 Fuel Handling Accident XIV-6-31 6.5 Main Steam Line Break Accident XIV-6-41 7.0 RESULTS AND CONCLUSIONS XIV-7-1 7.1 Abnormal Operational Transient Analysis Results and Conclusions XIV-7-1 7.2 Special Events Analysis Results and Conclusions XIV-7-1 7.3 Accident Analysis Results and Conclusions XIV-7-2 8.0 EVALUATION OF ENGINEERED SAFETY FEATURE SYSTEMS USING TID-14844 SOURCE TERMS XIV-8-1 8.1 Source Terms Assumptions XIV-8-1 8.2 Standby Gas Treatment System XIV-8-1 8.3 ECCS Components XIV-8-5 8.4 Materials Within Primary Containment XIV-8-7 8.5 Summary XIV-8-7

9.0 REFERENCES

FOR CHAPTER XIV XIV-9-1

VOLUME VI - USAR 08/01/03 APPENDIX A - PRESSURE INTEGRITY OF PIPING AND EQUIPMENT PRESSURE PARTS PAGE 1.0 SCOPE A-1-1 1.1 Codes and Specifications A-1-1 2.0 CLASSIFICATION OF PIPING AND EQUIPMENT PRESSURE PARTS A-2-1 2.1 GE Company Classification and Pressure Integrity Requirements A-2-1 2.2 Engineer - Constructor's Classification and Definition of Piping, Equipment and In-Line Pressure Parts A-2-1 2.3 ASME XI Classification of Piping and Equipment A-2-2 2.4 Tabulation of Equivalencies A-2-3 3.0 DESIGN REQUIREMENTS A-3-1 3.1 Piping Design A-3-1 3.2 Valve Design A-3-3 3.3 Pump Design A-3-3 4.0 MATERIALS A-4-1 4.1 Material Application A-4-1 4.2 Brittle Fracture Control for Ferritic Steels A-4-2 5.0 FABRICATION AND INSTALLATION REQUIREMENTS A-5-1 5.1 Welding Procedures and Processes A-5-1 5.2 Bending and Forming A-5-2 5.3 Heat Treatment A-5-2 5.4 Descaling and Cleaning After Heat Treatment A-5-3 5.5 Nondestructive Examination Techniques and Acceptance Standards A-5-4 5.6 Pressure Testing A-5-4 5.7 Personnel Qualification Requirements A-5-4

6.0 REFERENCES

FOR APPENDIX A A-6-1

VOLUME VI - USAR 08/01/03 APPENDIX B - TECHNICAL SPECIFICATIONS The original FSAR submitted proposed Technical Specifications in Appendix B. The NRC revised the final Technical Specifications as Appendix A and B to the Facility Operating License. It is not intended that these current Technical Specifications become Appendix B to the USAR.

VOLUME VI - USAR 08/01/03 APPENDIX C - STRUCTURAL LOADING CRITERIA PAGE 1.0 SCOPE C-1-1 2.0 CONCRETE AND STEEL STRUCTURES C-2-1 2.1 Description C-2-1 2.2 Loads C-2-1 2.3 Load Combinations and Allowable Limits C-2-2 2.4 Method of Analysis C-2-5 2.5 Implementation of Criteria C-2-6 3.0 COMPONENTS C-3-1 3.1 Intent and Scope C-3-1 3.2 Loading Conditions and Allowable Limits C-3-1 3.3 Method of Analysis and Implementation of Criteria C-3-74

4.0 REFERENCES

C-4-1

VOLUME VI - USAR 08/01/03 APPENDIX D QUALITY ASSURANCE PROGRAM FOR OPERATION POLICY DOCUMENT This Appendix formerly contained the Policy Document for the Cooper Nuclear Station Quality Assurance Program for Operation. Although a part of the USAR, the Policy Document contents have been removed from this Appendix and are maintained, revised, and distributed under separate cover by the Quality Assurance Division.

Changes to the QA Policy Document are processed in accordance with the provisions of 10CFR50.54(a)(3).

VOLUME VI - USAR 08/01/03 APPENDIX D(1) - CONSTRUCTION PHASE QUALITY ASSURANCE PROGRAM PAGE 1.0 QUALITY ASSURANCE PROGRAM D(1)-1-1 1.1 Introduction D(1)-1-1 1.2 Purpose and Objectives of the Quality Assurance Program D(1)-1-1 1.3 Definition D(1)-1-3 1.4 Classification of Systems, Components, and Structures D(1)-1-3 2.0 SCOPE OF RESPONSIBILITIES D(1)-2-1 2.1 Nebraska Public Power District D(1)-2-1 2.2 Burns and Roe - Architect-Engineer D(1)-2-1 2.3 Stearns-Roger - Quality Assurance D(1)-2-2 2.4 Woodward-Moorhouse & Associates, Inc. - Quality Assurance D(1)-2-2 2.5 General Electric - NSSS Supplier D(1)-2-2 2.6 Burns & Roe, Inc. - Construction Management D(1)-2-2 3.0 STEARNS-ROGER QUALITY ASSURANCE D(1)-3-1 3.1 Introduction D(1)-3-1 3.2 Organization D(1)-3-1 3.3 Review of Contract Specifications D(1)-3-1 3.4 Quality Assurance Activities - Manufactured Items D(1)-3-2 3.5 Quality Assurance Activities - Construction and Field Fabrication D(1)-3-8 3.6 Special Activities D(1)-3-13 3.7 In-Process Document Control and Records D(1)-3-16 3.8 Non-Conforming Material or Workmanship D(1)-3-17 3.9 Owner's Final Plant Records D(1)-3-18 4.0 BURNS AND ROE QUALITY ASSURANCE PROCEDURE FOR ENGINEERING AND DESIGN D(1)-4-1 4.1 General D(1)-4-1 4.2 Project Operations Division D(1)-4-1 4.3 Engineering Division D(1)-4-1 4.4 Key Personnel Related to the Project D(1)-4-1 4.5 Quality Control D(1)-4-4 4.6 Design Reviews D(1)-4-4 4.7 Summary D(1)-4-5 5.0 QUALITY ASSURANCE OF EARTHWORK CONSTRUCTION D(1)-5-1 5.1 Summary D(1)-5-1 5.2 Earthwork Quality Assurance D(1)-5-1 5.3 Conclusions D(1)-5-6 5.4 Construction of Structural Fill D(1)-5-8 5.5 Construction of General Fill D(1)-5-11 5.6 Verification of As-Built Condition of Structural Fill by Standard Penetration Tests D(1)-5-12 5.7 Documented Results of Quality Control Inspection and Testing and Formal Reports D(1)-5-12

VOLUME VI - USAR 08/01/03 APPENDIX D(1) - CONSTRUCTION PHASE QUALITY ASSURANCE PROGRAM (CONT'D)

PAGE 6.0 GENERAL ELECTRIC QUALITY SYSTEM FOR BWR NUCLEAR STEAM SUPPLY PROJECTS D(1)-6-1 FOREWORD 6.1 General D(1)-6-1 6.2 Classification of Systems and Components D(1)-6-3 6.3 Design Control D(1)-6-4 6.4 NED Manufactured Products D(1)-6-7 6.5 APED Purchased (Engineered) Equipment D(1)-6-10 6.6 NED Installation Control D(1)-6-13 6.7 Preoperational Testing D(1)-6-15 6.8 Plant Start-Up D(1)-6-15 6.9 Quality Records D(1)-6-16 7.0 PREOPERATIONAL TESTING D(1)-7-1 7.1 Introduction D(1)-7-1 7.2 Construction Tests D(1)-7-1 7.3 Preoperational Tests D(1)-7-1 7.4 Instrument Calibration D(1)-7-3 8.0 COMPARISON OF COOPER NUCLEAR QUALITY ASSURANCE WITH AEC QUALITY ASSURANCE CRITERIA D(1)-8-1 8.1 Organization D(1)-8-1 8.2 Quality Assurance Program D(1)-8-1 8.3 Design Control D(1)-8-1 8.4 Procurement Document Control D(1)-8-1 8.5 Instructions, Procedures, and Drawings D(1)-8-1 8.6 Document Control D(1)-8-1 8.7 Control of Purchased Material, Equipment, and Services D(1)-8-1 8.8 Identification and Control of Materials, Parts, and Components D(1)-8-2 8.9 Control of Special Processes D(1)-8-2 8.10 Inspection D(1)-8-2 8.11 Test Control D(1)-8-2 8.12 Calibration of Measurement and Test Equipment D(1)-8-2 8.13 Handling, Storage, Shipping, and Preservation D(1)-8-2 8.14 Inspection, Test, and Operating Status D(1)-8-2 8.15 Non-Conforming Material, Parts, and Components D(1)-8-3 8.16 Corrective Action D(1)-8-3 8.17 Quality Assurance Records D(1)-8-3 8.18 Audits D(1)-8-3

VOLUME VII - USAR 08/01/03 APPENDIX E - ELEVATED RELEASE POINT (ERP) RELEASE RATE LIMIT CALCULATIONS FOR COOPER This Appendix formerly contained the model and methodology for performing release rate limit calculations for releases from the Cooper Nuclear Station Elevated Release Point (ERP). This information has been superseded by the CNS Offsite Dose Assessment Manual (ODAM), which is incorporated into the CNS USAR by reference.

Changes to the Offsite Dose Assessment Manual are processed in accordance with the provisions of CNS Technical Specifications Section 5.5.1.c. Major changes to radioactive waste treatment systems (liquid, gaseous, and solid) are subject to the provisions of 10 CFR 50.59 and 10 CFR 50.71(e) as specified in ODAM Section D 5.5.

VOLUME VII - USAR 08/01/03 APPENDIX F - CONFORMANCE TO AEC PROPOSED GENERAL DESIGN CRITERIA PAGE 1.0

SUMMARY

DESCRIPTION F-1-1 2.0 CRITERION CONFORMANCE F-2-1 2.1 Group I -- Overall Plant Requirements (Criteria 1-5)

F-2-1 2.2 Group II -- Protection by Multiple Fission Product Barriers (Criteria 6-10)

F-2-2 2.3 Group III -- Nuclear and Radiation Controls (Criteria 11-18)

F-2-4 2.4 Group IV -- Reliability and Testability of Protection Systems (Criteria 19-26)

F-2-7 2.5 Group V -- Reactivity Control (Criteria 27-32)

F-2-10 2.6 Group VI -- Reactor Coolant Pressure Boundary (Criteria 33-36)

F-2-12 2.7 Group VII -- Engineered Safety Features (Criteria 37-65) F-2-14 2.8 Group VIII -- Fuel and Waste Storage Systems (Criteria 66-69)

F-2-23 2.9 Group IX -- Plant Effluents (Criterion 70)

F-2-25

3.0 REFERENCES

FOR APPENDIX F F-3-1

VOLUME VII - USAR 10/16/03 APPENDIX G NUCLEAR SAFETY OPERATIONAL ANALYSIS PAGE 1.0 ANALYTICAL OBJECTIVE G-1-1 2.0 APPROACH TO OPERATIONAL NUCLEAR SAFETY G-2-1 2.1 Comprehensiveness of the Analysis G-2-1 2.2 Systematic Approach to the Analysis G-2-1 2.3 Relationship of the NSOA to the Station Safety Analysis G-2-2 2.4 Relationship of the NSOA to Safety-Related Structures, Systems, and Components G-2-3 2.5 Unacceptable Results G-2-5 2.6 Nuclear Safety Operational Criteria G-2-7 2.7 Origin of Unacceptable Results and Nuclear Safety Operational Criteria G-2-8 2.8 Plant Functions G-2-8 2.9 Event Acceptance Limits G-2-8 3.0 METHOD OF ANALYSIS G-3-1 3.1 BWR Operating States G-3-1 3.2 Selection of Events for Analysis G-3-3 3.3 Applicability of Events to Operating States G-3-8 3.4 Rules for Event Analysis G-3-8 3.5 Steps in Preparing Protection Sequence, Auxiliary System and Commonality Diagrams G-3-10 4.0 DISPLAY OF NUCLEAR SAFETY OPERATIONAL ANALYSIS RESULTS G-4-1 4.1 Protection Sequence, Auxiliary System and Commonality Diagrams G-4-4 5.0 NUCLEAR SAFETY OPERATIONAL ANALYSES FOR CNS G-5-1 5.1 Auxiliary Systems G-5-1 5.2 Planned Operations G-5-1 5.3 Abnormal Operational Transients G-5-8 5.4 Accidents G-5-21 5.5 Special Events G-5-26 5.6 Remainder of Nuclear Safety Operational Analysis G-5-29

6.0 CONCLUSION

S G-6-1

VOLUME VII - USAR 08/01/03 APPENDIX H - STATION RESEARCH, DEVELOPMENT, AND FURTHER INFORMATION, REQUIREMENTS, AND RESOLUTIONS PAGE 1.0

SUMMARY

DESCRIPTION H-1-1 2.0 AREAS SPECIFIED IN THE COOPER NUCLEAR STATION ACRS CONSTRUCTION PERMIT LETTER H-2-1 2.1 Introduction H-2-1 2.2 Station Foundation Support H-2-1 2.3 Emergency On-Site Power System H-2-1 2.4 AEC General Design Criteria Number 35 Intent Design H-2-2 2.5 Browns Ferry ACRS Comments (3/14/67) Applicable to Cooper Nuclear Station H-2-2 3.0 AREAS SPECIFIED IN THE COOPER NUCLEAR STATION AEC STAFF CONSTRUCTION PERMIT SAFETY EVALUATION REPORT H-3-1 3.1 Introduction H-3-1 3.2 General H-3-1 3.3 Development Program of Significance for all Large Water-Cooled Power Reactors H-3-1 3.4 Development Program of Significance for Boiling Water Reactors H-3-2 3.5 Areas Requiring Further Technical Information H-3-5 4.0 AREAS SPECIFIED IN OTHER RELATED AEC-ACRS CONSTRUCTION AND OPERATING PERMIT LETTERS (REFER TO TABLE I-11-4 OF CNS-SAR SUBSECTION I-11)

H-4-1 4.1 General H-4-1 4.2 LPCIS-Logic Control System Design H-4-1 4.3 Re-Evaluation of Main Steam Line Break Accident H-4-2 4.4 Design of Piping Systems to Withstand Earthquake Forces H-4-2 4.5 Fuel Clad Disintegration Limitations H-4-3 4.6 Automatic Pressure Relief System - Initiation Interlock H-4-3 4.7 Effects of Blowdown Forces on Reactor Primary System Components H-4-4 4.8 Separation of Control and Protection System Functions Concern H-4-4 4.9 Instrumentation for Prompt Detection of Gross Fuel Failure H-4-5 4.10 Scram Reliability Study H-4-5 4.11 Design Basis of Engineered Safety Features H-4-6 4.12 Hydrogen Generation Study H-4-6 4.13 Seismic Design and Analysis Models H-4-7 4.14 Automatic Pressure Relief System - Single Component Failure Capability - Manual Operation H-4-7 4.15 Flow Reference Scram H-4-7 4.16 Matters of Current Regulatory Staff-Applicant Discussion H-4-8 4.17 Future Items of Consideration for Incorporation H-4-8 4.18 Development of Instrumentation - Primary Containment Leakage Detection System - Increased Sensitivity Studies H-4-9 4.19 Development of Instrumentation - Vibration and Loose Parts Detection Studies H-4-9 4.20 CSCS Leakage Detection, Protection, and Isolation Capability H-4-10 4.21 Main Steam Lines - Standards for Fabrication, Q.C.,

and Inspection H-4-11 4.22 Conclusions H-4-11 5.0

SUMMARY

CONCLUSIONS H-5-1

VOLUME VII - USAR 08/01/03 APPENDIX J INSERVICE INSPECTION PROGRAM This Appendix formerly contained a condensed version of the First 10-Year Inservice Inspection Program at Cooper Nuclear Station. Although a part of the USAR, the Inservice Inspection Program has been removed from this Appendix and is currently maintained, revised, and distributed under separate cover. The program is based on the requirements of Section XI of the ASME Code as required by the provisions of 10CFR50.55a(g).

VOLUME VII - USAR 08/13/12 APPENDIX K LICENSE RENEWAL UPDATED SAFETY ANALYSIS REPORT SUPPLEMENT PAGE

1.0 INTRODUCTION

K-1-1 2.0 AGING MANAGEMENT PROGRAMS AND ACTIVITIES K-2-1 2.1 Aging Management Programs K-2-1 2.2 Evaluation of Time-Limited Aging Analyses K-2-26 2.3 Newly-Identified Structures, Systems, and Components K-2-32

3.0 REFERENCES

FOR APPENDIX K K-3-1 4.0 LICENSE RENEWAL COMMITMENTS K-4-1

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