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WATTS BAR TABLE OF CONTENTS Section Title

WATTS BAR
WBNP-76
TABLE OF CONTENTS
Section
Title
Page
028_TVA_WB_FSAR_Section_17.0.pdf
027_TVA_WB_FSAR_Section_16.pdf
026_TVA_WB_FSAR_Section_15.pdf
024_TVA_WB_FSAR_Section_13.pdf
018_TVA_WB_FSAR_Section_8
017_TVA_WB_FSAR_Section_7.pdf
014_TVA_WB_FSAR_Section_5.pdf
013_TVA_WB_FSAR_Section_4.pdf
005_TVA_WB_FSAR_Section_2_B.pdf
004_TVA_WB_FSAR_Section_2_A.pdf
003_TVA_WB_FSAR_Section_1.pdf
1.0
1.1
INTRODUCTION AND GENERAL DESCRIPTION OF PLANT
INTRODUCTION
1.1.1
1.1.2
1.1.3
1.2
Introduction
Licensing Basis Documents
NRC Commitments
GENERAL PLANT DESCRIPTION
1.2.1
1.2.1.1
1.2.1.2
1.2.1.3
1.2.1.4
1.2.1.5
1.2.1.6
1.2.2
1.2.2.1
1.2.2.2
1.2.2.3
1.2.2.4
1.2.2.5
1.2.2.6
1.2.2.7
1.2.2.8
1.2.2.9
1.2.2.10
1.2.2.11
1.2.2.12
1.2.2.13
1.2.2.14
1.2.2.15
1.2.2.16
1.2.3
1.3
1.3.1
1.3.2
Site Characteristics
Location
Demography
Meteorology
Hydrology
Geology
Seismology
Facility Description
Design Criteria
Nuclear Steam Supply System (NSSS)
Control and Instrumentation
Fuel Handling System
Waste Processing System
Steam and Power Conversion System
Plant Electrical System
Cooling Water
Component Cooling System
Chemical and Volume Control System
Sampling and Water Quality System
Ventilation
Fire Protection System
Compressed Air Systems
Engineered Safety Features
Shared Facilities and Equipment
General Arrangement of Major Structures and Equipment
COMPARISON TABLES
Comparisons With Similar Facility Designs
Comparison Of Final And Preliminary Designs
1.1-1
1.1-1
1.1-1
1.1-2
1.2-1
1.2-1
1.2-1
1.2-1
1.2-1
1.2-1
1.2-1
1.2-2
1.2-2
1.2-2
1.2-2
1.2-4
1.2-5
1.2-5
1.2-5
1.2-6
1.2-7
1.2-7
1.2-7
1.2-8
1.2-9
1.2-9
1.2-9
1.2-9
1.2-10
1.2-13
1.3-1
1.3-1
1.3-1
1.4
IDENTIFICATION OF AGENTS AND CONTRACTORS
1.4-1
1.5
REQUIREMENTS FOR FURTHER TECHNICAL INFORMATION
1.5-1
1.5.1
1.5.1.1
1.5.1.2
17 x 17 Fuel Assembly
Rod Cluster Control Spider Tests
Grid Tests
Table of Contents
1.5-1
1.5-1
1.5-1
1-xxxvii
WATTS BAR
WBNP-76
TABLE OF CONTENTS
Section
1.5.1.3
1.5.1.4
1.5.1.5
1.5.2
1.5.2.1
1.5.2.2
Title
Fuel Assembly Structural Tests
Guide Tube Tests
Prototype Assembly Tests
Heat Transfer Tests (17 x 17)
17 x 17 LOCA Heat Transfer Tests
Departure from Nucleate Boiling (DNB)
Page
1.5-1
1.5-2
1.5-2
1.5-2
1.5-2
1.5-2
1.6
MATERIAL INCORPORATED BY REFERENCE
1.6-1
1.7
ELECTRICAL, INSTRUMENTATION, AND CONTROL DRAWINGS
1.7-1
1.8
TECHNICAL QUALIFICATION OF APPLICANT
1.8-1
1.9
NUCLEAR PERFORMANCE PLAN
1.9-1
1.9.1
1.9.1.1
1.9.1.2
1.9.1.3
1.9.1.4
1.9.1.5
1.9.1.6
1.9.1.7
1.9.1.8
1.9.1.9
1.9.1.10
1.9.1.11
1.9.1.12
1.9.1.13
1.9.1.14
1.9.1.15
1.9.1.16
1.9.1.17
1.9.1.18
1.9.2
1.9.2.1
1.9.2.2
1.9.2.3
1.9.2.4
1.9.2.5
1.9.2.6
1.9.2.7
1.9.2.8
1.9.2.9
1.9.2.10
1.9.2.11
1-xxxviii
Corrective Action Plans
Cable Issues
Cable Tray and Cable Tray Supports
Design Baseline and Verification Program (DBVP)
Electrical Conduit and Conduit Support
Electrical Issues
Equipment Seismic Qualification
Fire Protection
Hanger and Analysis Update Program (HAAUP)
Heat Code Traceability
Heating, Ventilation, and Air Conditioning (HVAC) Duct Supports
Instrument Lines
Prestart Test Program
QA Records
Q-LIST
Replacement Items Program (RIP-CAP)
Seismic Analysis
Vendor Information
Welding
Special Programs (SPs)
Concrete Quality Program
Containment Cooling
Detailed Control room Design Review
Environmental Qualification Program
Master Fuse List
Mechanical Equipment Qualification
Microbiologically Induced Corrosion (MIC)
Moderate Energy Line Break Flooding (MELB)
Radiation Monitoring System
Soil Liquefaction
Use-As-Is CAQs
1.9-1
1.9-1
1.9-2
1.9-2
1.9-2
1.9-2
1.9-3
1.9-3
1.9-3
1.9-3
1.9-3
1.9-4
1.9-4
1.9-4
1.9-4
1.9-4
1.9-5
1.9-5
1.9-5
1.9-5
1.9-6
1.9-6
1.9-6
1.9-6
1.9-6
1.9-6
1.9-7
1.9-7
1.9-7
1.9-7
1.9-7
Table of Contents
WATTS BAR
WBNP-76
TABLE OF CONTENTS
Section
1.9.3
Title
REFERENCES
2.0
2.1
2.1.1
2.1.1.1
2.1.1.2
2.1.1.3
2.1.2
2.1.2.1
2.1.2.2
2.1.2.3
2.1.2.4
2.1.3
2.1.3.1
2.1.3.2
2.1.3.3
2.1.3.4
2.1.3.5
2.1.3.6
2.2
2.2.1
2.2.2
2.2.2.1
2.2.2.2
2.2.2.3
2.2.2.4
2.2.2.5
2.2.2.6
2.2.3
2.2.3.1
2.3
2.3.1
2.3.1.1
2.3.1.2
2.3.1.3
2.3.2
2.3.2.1
2.3.2.2
2.3.2.3
2.3.2.4
Page
1.9-7
SITE CHARACTERISTICS
GEOGRAPHY AND DEMOGRAPHY
Site Location and Description
Specification of Location
Site Area Map
Boundaries for Establishing Effluent Limits
Exclusion Area Authority And Control
Authority
Control of Activities Unrelated to Plant Operation
Arrangements for Traffic Control
Abandonment or Relocation of Roads
Population Distribution
Population Within 10 Miles
Population Between 10 and 50 Miles
Transient Population
Low Population Zone
Population Center
Population Density
NEARBY INDUSTRIAL, TRANSPORTATION, AND MILITARY FACILITIES
Location and Route
Descriptions
Description of Facilities
Description of Products and Materials
Pipelines
Waterways
Airports
Projections of Industrial Growth
Evaluation of Potential Accidents
REFERENCES
METEOROLOGY
Regional Climate
Data Sources
General Climate
Severe Weather
Local Meteorology
Data Sources
Normal and Extreme Values of Meteorological Parameters
Potential Influence of the Plant and Its Facilities on Local Meteorology
Local Meteorological Conditions for Design and Operating Bases
Table of Contents
2.1-1
2.1-1
2.1-1
2.1-1
2.1-2
2.1-2
2.1-2
2.1-2
2.1-2
2.1-2
2.1-2
2.1-3
2.1-3
2.1-4
2.1-4
2.1-4
2.1-4
2.2-1
2.2-1
2.2-1
2.2-1
2.2-1
2.2-1
2.2-1
2.2-2
2.2-2
2.2-2
2.2-3
2.3-1
2.3-1
2.3-1
2.3-1
2.3-2
2.3-5
2.3-5
2.3-6
2.3-8
2.3-9
1-xxxix
WATTS BAR
WBNP-76
TABLE OF CONTENTS
Section
2.3.3
2.3.3.1
2.3.3.2
2.3.3.3
2.3.4
2.3.4.1
2.3.4.2
2.3.5
2.4
HYDROLOGIC ENGINEERING
2.4.1
2.4.1.1
2.4.1.2
2.4.2
2.4.2.1
2.4.2.2
2.4.2.3
2.4.3
2.4.3.1
2.4.3.2
2.4.3.3
2.4.3.4
2.4.3.5
2.4.3.6
2.4.4
2.4.4.1
2.4.4.2
2.4.4.3
2.4.5
2.4.6
2.4.7
2.4.8
2.4.9
2.4.10
2.4.11
2.4.11.1
2.4.11.2
2.4.11.3
2.4.11.4
2.4.11.5
2.4.12
2.4-45
2.4.12.1
2.4.12.2
1-xl
Title
Onsite Meteorological Measurements Program
Preoperational Program
Operational Meteorological Program
Onsite Data Summaries of Parameters for Dispersion Meteorology
Short-Term (Accident) Diffusion Estimates
Objective
Calculation Results
Long-Term (Routine) Diffusion Estimates
Page
2.3-9
2.3-9
2.3-12
2.3-12
2.3-13
2.3-13
2.3-15
2.3-16
2.4-1
Hydrological Description
2.4-1
Sites and Facilities
2.4-1
Hydrosphere
2.4-2
Floods
2.4-6
Flood History
2.4-6
Flood Design Considerations
2.4-7
Effects of Local Intense Precipitation
2.4-9
Probable Maximum Flood (PMF) on Streams and Rivers
2.4-12
Probable Maximum Precipitation (PMP)
2.4-13
Precipitation Losses
2.4-14
Runoff and Stream Course Model
2.4-14
Probable Maximum Flood Flow
2.4-18
Water Level Determinations
2.4-25
Coincident Wind Wave Activity
2.4-26
Potential Dam Failures, Seismically Induced
2.4-28
Dam Failure Permutations
2.4-28
Unsteady Flow Analysis of Potential Dam Failures
2.4-39
Water Level at Plantsite
2.4-40
Probable Maximum Surge and Seiche Flooding
2.4-40
Probable Maximum Tsunami Flooding
2.4-40
Ice Effects
2.4-40
Cooling Water Canals and Reservoirs
2.4-41
Channel Diversions
2.4-42
Flooding Protection Requirements
2.4-42
Low Water Considerations
2.4-42
Low Flow in Rivers and Streams
2.4-42
Low Water Resulting From Surges, Seiches, or Tsunami
2.4-43
Historical Low Water
2.4-43
Future Control
2.4-43
Plant Requirements
2.4-44
Dispersion, Dilution, and Travel Times of Accidental Releases of Liquid Effluents
Radioactive Liquid Wastes
Accidental Slug Releases to Surface Water
2.4-45
2.4-45
Table of Contents
WATTS BAR
WBNP-76
TABLE OF CONTENTS
Section
2.4.12.2.1
2.4.12.3
2.4.13
2.4.13.1
2.4.13.2
2.4.13.3
2.4.13.4
2.4.13.5
2.4.14
2.4.14.1
2.4.14.1.1
2.4.14.1.2
2.4.14.1.3
2.4.14.1.4
2.4.14.2
2.4.14.2.1
2.4.14.2.2
2.4.14.2.3
2.4.14.3
2.4.14.4
2.4.14.4.1
2.4.14.4.2
2.4.14.4.3
2.4.14.5
2.4.14.5.1
2.4.14.5.2
2.4.14.5.3
2.4.14.5.4
2.4.14.6
2.4.14.7
2.4.14.8
2.4.14.8.1
2.4.14.8.2
2.4.14.9
2.4.14.9.1
2.4.14.9.2
2.4.14.9.3
2.4.14.9.4
2.4.14.9.5
2.4.14.9.6
2.4.14.10
2.4.14.11
2.5
Title
Calculations
Effects on Ground Water
Groundwater
Description and On-Site Use
Sources
Accident Effects
Monitoring and Safeguard Requirements
Design Basis for Subsurface Hydrostatic Loading
Flooding Protection Requirements
Introduction
Design Basis Flood
Combinations of Events
Post Flood Period
Localized Floods
Plant Operation During Floods Above Grade
Flooding of Structures
Fuel Cooling
Cooling of Plant Loads
Warning Scheme
Preparation for Flood Mode
Reactor Initially Operating at Power
Reactor Initially Refueling
Plant Preparation Time
Equipment
Equipment Qualification
Temporary Modification and Setup
Electric Power
Instrument, Control, Communication and Ventilation Systems
Supplies
Plant Recovery
Warning Plan
Rainfall Floods
Seismically-Induced Dam Failure Floods
Basis For Flood Protection Plan In Rainfall Floods
Overview
TVA Forecast System
Basic Analysis
Hydrologic Basis for Warning System
Hydrologic Basis for Target States
Communications Reliability
Basis for Flood Protection Plan in Seismic-Caused Dam Failures
Special Condition Allowance
Page
2.4-46
2.4-47
2.4-48
2.4-48
2.4-48
2.4-50
2.4-50
2.4-51
2.4-51
2.4-51
2.4-51
2.4-52
2.4-52
2.4-52
2.4-52
2.4-52
2.4-53
2.4-54
2.4-55
2.4-55
2.4-55
2.4-55
2.4-56
2.4-56
2.4-56
2.4-56
2.4-56
2.4-57
2.4-57
2.4-57
2.4-58
2.4-58
2.4-58
2.4-59
2.4-59
2.4-59
2.4-61
2.4-61
2.4-62
2.4-63
2.4-64
2.4-65
GEOLOGY, SEISMOLOGY, AND GEOTECHNICAL ENGINEERING SUMMARY OF
Table of Contents
1-xli
WATTS BAR
WBNP-76
TABLE OF CONTENTS
Section
Title
FOUNDATION CONDITIONS
2.5.1
2.5.1.1
2.5.1.1.1
2.5.1.1.2
2.5.1.1.3
2.5.1.1.4
2.5.1.1.5
2.5.1.1.6
2.5.1.1.7
2.5.1.2
2.5.1.2.1
2.5.1.2.2
2.5.1.2.3
2.5.1.2.4
2.5.1.2.5
2.5.1.2.6
2.5.1.2.7
2.5.1.2.8
2.5.1.2.9
2.5.1.2.10
2.5.1.2.11
2.5.1.2.12
2.5.2
2.5.2.1
2.5.2.2
2.5.2.3
inces
2.5.2.4
2.5.2.5
2.5.2.6
2.5.2.7
2.5.3
2.5.3.1
2.5.3.2
2.5.3.3
2.5.3.4
2.5.3.5
2.5.3.6
2.5.3.7
2.5.3.8
2.5.4
2.5.4.1
2.5.4.2
1-xlii
Page
2.5-1
Basic Geology and Seismic Information
2.5-2
Regional Geology
2.5-3
Regional Physiography
2.5-3
Regional Tectonics and Geology
2.5-7
Regional Geologic Setting
2.5-9
Regional Geologic History
2.5-10
Regional Lithologic, Stratigraphic, and Structural Geology
2.5-20
Regional Tectonics
2.5-22
Groundwater
2.5-26
Site Geology
2.5-26
Site Physiography
2.5-26
Site Lithologic, Stratigraphic, and Structural Geologic Conditions 2.5-27
Site Structural Geology
2.5-29
Surface Geology
2.5-30
Site Geologic History
2.5-31
Plot Plan
2.5-31
Bedrock Foundation Characteristics
2.5-31
Excavation and Backfill
2.5-31
Evaluation of Geologic Conditions
2.5-32
Groundwater
2.5-33
Geophysical Surveys
2.5-33
Soil and Rock Properties
2.5-34
Vibratory Ground Motion
2.5-34
Seismicity
2.5-34
Geologic Structures and Tectonic Activity
2.5-41
Correlation of Earthquake Activity With Geologic Structures to Tectonic Prov2.5-42
Maximum Earthquake Potential
2.5-42
Seismic Wave Transmission Characteristics of the Site
2.5-44
Safe Shutdown Earthquake
2.5-45
Operating Basis Earthquake
2.5-45
Surface Faulting
2.5-45
Geologic Conditions of the Site
2.5-45
Evidence of Fault Offset
2.5-45
Earthquakes Associated With Capable Faults
2.5-54
Investigations of Capable Faults
2.5-54
Correlation of Epicenters With Capable Faults
2.5-56
Description of Capable Faults
2.5-56
Zone Requiring Detailed Faulting Investigation
2.5-56
Results of Faulting Investigations
2.5-56
Stability of Subsurface Materials
2.5-56
Geologic Features
2.5-56
Properties of Subsurface Materials
2.5-57
Table of Contents
WATTS BAR
WBNP-76
TABLE OF CONTENTS
Section
Title
2.5.4.2.1
In Situ Soils
General Description 57
Investigations 57
Test Results and Selection of Design Properties 61
2.5.4.2.2
Rock
Engineering Description of Bedrock 74
Test Program 75
Description of Testing Techniques 75
Test Results for Menard Pressuremeter 77
Comparison of Results from Menard Pressuremeter and Birdwell 3D Sonic Logger 78
Settlement Analysis 78
Behavior of Watts Bar Lock 83
Excavation Experience in the Rutledge Shale at Watts Bar Lock 85
Evaluation of Settlement 86
2.5.4.3
Exploration
2.5.4.4
Geophysical Surveys
2.5.4.4.1
Rock Characteristics
2.5.4.4.2
Soil Characteristics
Equipment 90
Velocity Measurement Procedures 90
Data Analysis and Results 91
Data Analysis and Results - Evaluation Seismic Criteria and New 93
2.5.4.5
Excavations and Backfill
2.5.4.5.1
Earthfill
Investigation 93
Test Results 94
Field Work 97
Construction Control 98
2.5.4.5.2
Granular Fill
General 98
Section 1032 Material 98
Section 1075 Material 100
2.5.4.6
Groundwater Conditions
2.5.4.7
Response of Soil and Rock to Dynamic Loading
2.5.4.8
Liquefaction Potential
2.5.4.9
Earthquake Design Basis
2.5.4.10
Static Analysis
2.5.4.10.1
Settlement
2.5.4.10.2
Bearing Capacity
2.5.4.11
Safety-Related Criteria for Foundations
2.5.4.11.1
General
2.5.4.11.2
Rock Strength
2.5.4.11.3
Soil Strength
2.5.4.12
Techniques to Improve Subsurface Conditions
Table of Contents
Page
2.5-57
2.5-74
2.5-89
2.5-90
2.5-90
2.5-90
2.5-93
2.5-93
2.5-98
2.5-101
2.5-103
2.5-103
2.5-113
2.5-113
2.5-113
2.5-114
2.5-115
2.5-115
2.5-115
2.5-115
2.5-115
1-xliii
WATTS BAR
WBNP-76
TABLE OF CONTENTS
Section
2.5.4.13
2.5.5
2.5.5.1
2.5.5.1.1
2.5.5.1.2
2.5.5.2
2.5.5.2.1
2.5.5.2.2
2.5.5.2.3
2.5.5.3
2.5.5.4
2.5.6
Title
Page
Construction Notes
2.5-118
Stability of Slopes
2.5-118
Slope Characteristics
2.5-118
Essential Raw Cooling Water Intake Channel Slopes
2.5-118
Underground Barrier for Protection Against Potential Soil Liquefaction
2.5-118
Design Criteria and Analysis
2.5-120
Design Criteria and Analyses for the Essential Raw Coolant Water 2.5120
Additional Analyses Due to Unexpected Soil Conditions Encountered
During Excavation of the Intake Channel
2.5-123
Design Criteria and Analysis for the Underground Barrier for the ERCW
Pipeline and 1E Conduit Alignment
2.5-125
Logs of Borings
2.5-127
Compaction Specifications
2.5-127
Embankments
2.5-127
3.0 DESIGN OF STRUCTURES, COMPONENTS, EQUIPMENT, AND SYSTEMS
3.1
CONFORMANCE WITH NRC GENERAL DESIGN CRITERIA
3.1.1
3.1.2
3.1.2.1
3.1.2.2
3.1.2.3
3.1.2.4
3.1.2.5
3.1.2.6
3.2
Introduction
WBNP Conformance with GDCs
Overall Requirements
Protection By Multiple Fission Product Barriers
Protection and Reactivity Control Systems
Fluid Systems
Reactor Containment
Fuel and Radioactivity Control
CLASSIFICATION OF STRUCTURES, SYSTEMS, AND COMPONENTS
3.2.1
3.2.2
3.2.2.1
3.2.2.2
3.2.2.3
3.2.2.4
3.2.2.5
ponents
3.2.2.6
3.2.2.7
3.2.3
3.2.3.1
3.2.3.2
1-xliv
3.1-1
3.1-1
3.1-1
3.1-1
3.1-5
3.1-12
3.1-17
3.1-30
3.1-35
3.2-1
Seismic Classifications
3.2-1
System Quality Group Classification
3.2-1
Class A
3.2-2
Class B
3.2-2
Class C
3.2-2
Class D
3.2-2
Relationship of Applicable Codes to Safety Classification for Mechanical Com3.2-3
Nonnuclear Safety Class (NNS)
3.2-3
Heating, Ventilation and Air Conditioning (HVAC) Safety Classification 3.2-3
Code Cases and Code Editions and Addenda
3.2-3
TVA Design and Fabrication
3.2-3
Purchased Materials and Components
3.2-4
Table of Contents
WATTS BAR
WBNP-76
TABLE OF CONTENTS
Section
3.3
Title
Wind and Tornado Loading
Page
3.3-1
3.3.1
Wind Loadings
3.3-1
3.3.1.1
Design Wind Velocity
3.3-1
3.3.1.2
Determination of Applied Force
3.3-1
3.3.2
Tornado Loadings
3.3-1
3.3.2.1
Applicable Design Parameters
3.3-1
3.3.2.2
Determination of Forces on Structures
3.3-2
3.3.2.3
Ability of Category I Structures to Perform Despite Failure of Structures Not
Designed for Tornado Loads
3.3-3
3.4
WATER LEVEL (FLOOD) DESIGN
3.4.1
3.4.2
3.5
3.4-1
Flood Protection
Analysis Procedure
3.4-1
3.4-1
MISSILE PROTECTION
3.5-1
3.5.1
3.5.1.1
3.5.1.1.1
3.5.1.1.2
3.5.1.1.3
3.5.1.1.4
3.5.1.1.5
3.5.1.1.6
3.5.1.1.7
3.5.1.2
3.5.1.2.1
3.5.1.2.2
3.5.1.2.3
3.5.1.2.4
3.5.1.2.5
3.5.1.2.6
3.5.1.3
3.5.1.3.1
3.5.1.3.2
3.5.1.3.3
3.5.1.3.4
3.5.1.3.5
3.5.1.3.6
3.5.1.4
3.5.1.5
3.5.1.6
3.5.2
3.5.3
3.5.3.1
Missile Selection and Description
3.5-2
Internally Generated Missiles (Outside Containment)
3.5-2
Shield Building
3.5-2
North and South Steam Valve Rooms
3.5-2
Auxiliary Building
3.5-3
Control Building
3.5-4
ERCW Structures
3.5-4
ERCW Pipe Tunnels and RWST Foundations
3.5-4
Diesel Generator Building
3.5-4
Internally Generated Missiles (Inside Containment)
3.5-5
Missile Selection
3.5-5
Missile Description
3.5-7
Electrical Cables
3.5-8
Upper Compartment
3.5-8
Ice Condenser Compartment
3.5-8
Lower Compartment
3.5-8
Turbine Missiles
3.5-9
Introduction
3.5-9
Potential Missile Sources and Missile Characteristics
3.5-10
Primary Safety-Related Equipment Installations and Structures
3.5-15
Turbine Missile Protection Criterion
3.5-15
Turbine Missile Hazard Evaluation
3.5-16
Turbine Missile Selection
3.5-22
Missiles Generated By Natural Phenomena
3.5-23
Missiles Generated by Events Near the Site.
3.5-23
Aircraft Hazards
3.5-24
Systems To Be Protected
3.5-24
Barrier Design Procedures
3.5-25
Additional Diesel Generator Building (And Other Category I Structures Added
Table of Contents
1-xlv
WATTS BAR
WBNP-76
TABLE OF CONTENTS
Section
After July 1979)
Title
Page
3.5-28
3.5.A ESTIMATES OF VELOCITIES OF JET PROPELLED MISSILES
3.6
ED
3.5-1
PROTECTION AGAINST DYNAMIC EFFECTS ASSOCIATED WITH THE POSTULATRUPTURE OF PIPING
3.6-1
3.6A PROTECTION AGAINST DYNAMIC EFFECTS ASSOCIATED WITH THE POSTULATED RUPTURE OF PIPING (EXCLUDING REACTOR COOLANT SYSTEM PIPING)
3.6-1
3.6A.1
Postulated Piping Failures in Fluid Systems Inside and Outside Containment 3.6-8
3.6A.1.1
Design Bases
3.6-8
3.6A.1.1.1
List of Potential Targets
3.6-8
3.6A.1.1.2
Interaction Criteria
3.6-8
3.6A.1.1.3
Acceptability Criteria
3.6-9
3.6A.1.1.4
Protective Measures
3.6-10
3.6A.1.2
Description of Piping System Arrangement
3.6-10
3.6A.1.3
Safety Evaluation
3.6-10
3.6A.2
Determination of Break Locations and Dynamic Effects Associated with the Postulated Rupture of Piping
3.6-11
3.6A.2.1
Criteria Used to Define Break and Crack Location and Configuration 3.6-11
3.6A.2.1.1
Pipe Failure Type, Size, and Orientation
3.6-11
3.6A.2.1.2
Break Location
3.6-12
3.6A.2.1.3
Failure Consequences
3.6-15
3.6A.2.1.4
Flooding
3.6-16
3.6A.2.1.5
Leak-Before-Break Application
3.6-17
3.6A.2.2
Analytical Methods to Define Forcing Functions and Response Models 3.6-17
3.6A.2.2.1
Assumptions
3.6-17
3.6A.2.2.2
Blowdown Thrust Loads
3.6-17
3.6A.2.2.3
Jet Impingement Loads
3.6-19
3.6A.2.3
Dynamic Analysis Methods to Verify Integrity and Operability
3.6-21
3.6A.2.3.1
General Criteria for Pipe Whip Evaluation
3.6-21
3.6A.2.3.2
Main Reactor Coolant Loop Piping System
3.6-21
3.6A.2.3.3
Other Piping Systems
3.6-21
3.6A.2.3.4
Simplified Pipe Whip Analysis
3.6-22
3.6A.2.3.5
Pipe Whip Restraint Design
3.6-23
3.6A.2.3.6
Energy Absorbing Materials
3.6-24
3.6A.2.4
Guard Pipe Assembly Design Criteria
3.6-24
3.6A.2.5
Summary of Dynamic Analysis Results
3.6-25
3.6A.2.5.1
Stress Summary and Isometrics - Inside Containment
3.6-25
3.6A.2.5.2
Summary of Protection Requirements and Isometrics-Outside Containment
3.6-26
3.6B PROTECTION AGAINST DYNAMIC EFFECTS ASSOCIATED WITH THE POSTULATED RUPTURE OF PIPING
3.6-26
3.6B.1
1-xlvi
Break Locations And Dynamic Effects Associated With Postulated Primary
Loop
Table of Contents
WATTS BAR
WBNP-76
TABLE OF CONTENTS
Section
Title
Page
Pipe Rupture
3.6-26
3.6B.2
Analytical Methods to Define Forcing Function and Response Models
3.6-27
3.6B.3
Dynamic Analysis of the Reactor Coolant Loop Piping Equipment Supports and Pipe
Whip Restraints
3.6-29
3.7
SEISMIC DESIGN
3.7-1
3.7.1
3.7.1.1
3.7.1.1.1
3.7.1.1.2
3.7.1.2
3.7.1.2.1
Seismic Input
3.7-2
Ground Response Spectra
3.7-2
Original Site Ground Response Spectra (Set A and Set C)
3.7-2
Site Specific Ground Response Spectra (Set B)
3.7-2
Design Time Histories
3.7-2
Time Histories for Original Site Ground Response Spectra (Set A and Set
C)
3.7-2
3.7.1.2.2
Time Histories for Site Specific Ground Response Spectra (Set B) 3.7-2
3.7.1.3
Critical Damping Values
3.7-3
3.7.1.4
Supporting Media for Seismic Category I Structures
3.7-3
3.7.2
Seismic System Analysis
3.7-3
3.7.2.1
Seismic Analysis Methods
3.7-4
3.7.2.1.1
Category I Rock-Supported Structures - Original Analyses (Set A) 3.7-4
3.7.2.1.2
Category I Rock - Supported Structures - Evaluation and New Design or
Modification Analyses (Set B and Set B+C)
3.7-9
3.7.2.1.3
Category I Soil-Supported Structures - Original Analysis (Set A) 3.7-13
3.7.2.1.4
Category I Soil-Supported Structures - Evaluation and New Design/Modification Analysis (Set B and Set B+C)
3.7-18
3.7.2.1.5
Category I Pile-Supported Structures - Original Analysis (Set A) 3.7-19
3.7.2.1.6
Category I Pile-Supported Structures - Evaluation and New Design/Modification Analyses (Set B and Set B+C)
3.7-21
3.7.2.2
Natural Frequencies and Response Loads for NSSS
3.7-22
3.7.2.3
Procedures Used for Modeling
3.7-22
3.7.2.3.1
Other Than NSSS
3.7-22
3.7.2.3.2
For NSSS Analysis
3.7-22
3.7.2.4
Soil/Structure Interaction
3.7-23
3.7.2.4.1
Original Analysis (Set A)
3.7-23
3.7.2.4.2
Evaluation and New Design or Modification Analyses3.7-23
3.7.2.5
Development of Floor Response Spectra
3.7-24
3.7.2.5.1
Original Analysis
3.7-24
3.7.2.5.2
Evaluation and New Design or Modification Analysis
3.7-24
3.7.2.6
Three Components of Earthquake Motion
3.7-25
3.7.2.6.1
Original Analysis (Set A)
3.7-25
3.7.2.6.2
Evaluation and New Design/Modification Analyses (Set B and Set C)
3.7-25
3.7.2.7
Combination of Modal Responses
3.7-26
3.7.2.7.1
Other Than NSSS
3.7-26
Original Analysis (Set A) 26
Table of Contents
1-xlvii
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TABLE OF CONTENTS
Section
Title
Page
Evaluation and New Design or Modification Analyses 26
3.7.2.7.2
NSSS System
3.7-27
3.7.2.8
Interaction of Non-Category I Structures With Seismic Category I Structures
3.7-29
3.7.2.9
Effects of Parameter Variations on Floor Response Spectra
3.7-29
3.7.2.10
Use of Constant Vertical Load Factors
3.7-29
3.7.2.10.1
Other Than NSSS
3.7-29
Original Analysis (Set A) 29
Evaluation and New Design or Modification Analyses 30
3.7.2.10.2
For NSSS
3.7-30
3.7.2.11
Methods Used to Account for Torsional Effects
3.7-30
3.7.2.12
Comparison of Responses - Set A versus Set B
3.7-30
3.7.2.13
Methods for Seismic Analysis of Dams
3.7-31
3.7.2.14
Determination of Category I Structure Overturning Moments
3.7-31
3.7.2.14.1
Original Analysis
3.7-31
3.7.2.14.2
Evaluation and New Design or Modification Analysis
3.7-31
3.7.2.15
Analysis Procedure for Damping
3.7-31
3.7.3
Seismic Subsystem Analysis
3.7-31
3.7.3.1
Seismic Analysis Methods for Other Than NSSS
3.7-31
3.7.3.2
Determination of Number of Earthquake Cycles
3.7-32
3.7.3.2.1
Category I Systems and Components Other Than NSSS
3.7-32
3.7.3.2.2
NSSS System
3.7-33
3.7.3.3
Procedure Used for Modeling
3.7-33
3.7.3.3.1
Other Than NSSS
3.7-33
Modeling of Piping Systems for Detailed Rigorous Analysis 33
Modeling of Equipment 33
Modeling of HVAC, Conduit, and Cable Tray Subsystems 33
3.7.3.3.2
Modeling of NSSS Subsystems
3.7-34
3.7.3.4
Basis for Selection of Frequencies
3.7-34
3.7.3.4.1
Other Than NSSS
3.7-34
3.7.3.4.2
NSSS Basis for Selection of Forcing Frequencies
3.7-34
3.7.3.5
Use of Equivalent Static Load Method of Analysis
3.7-35
3.7.3.5.1
Other Than NSSS
3.7-35
3.7.3.5.2
Use of Equivalent Static Load Method of Analysis for NSSS
3.7-36
3.7.3.6
Three Components of Earthquake Motion
3.7-36
3.7.3.6.1
Piping Subsystems
3.7-36
3.7.3.6.2
HVAC Ducting, Conduit, and Cable Tray Subsystems
3.7-36
3.7.3.6.3
Other Than NSSS Equipment and Components
3.7-36
3.7.3.7
Combination of Modal Responses
3.7-37
3.7.3.7.1
Other Than NSSS
3.7-37
3.7.3.7.2
Combination of Modal Responses of NSSS
3.7-37
3.7.3.8
Analytical Procedures for Piping Other Than NSSS
3.7-37
3.7.3.8.1
General
3.7-37
3.7.3.8.2
Detailed Seismic Analysis (Rigorous) for Piping Systems
3.7-41
1-xlviii
Table of Contents
WATTS BAR
WBNP-76
TABLE OF CONTENTS
Section
3.7.3.8.3
3.7.3.8.4
Title
Page
Alternate (Simplified) Analysis for Piping Systems
3.7-43
Seismic Analysis of Piping Systems That Span Two or More Seismic Support Zones Such as Buildings, Portions of Buildings, or Primary Components
3.7-44
3.7.3.9
Multiple Supported Equipment and Components with Distinct Inputs 3.7-44
3.7.3.9.1
Other Than NSSS
3.7-44
3.7.3.9.2
Multiple Supported NSSS Equipment and Components with Distinct Inputs
3.7-44
3.7.3.10
Use of Constant Vertical Load Factors
3.7-45
3.7.3.10.1
Use of Constant Load Factors for Equipment Other Than NSSS 3.7-45
3.7.3.10.2
Use of Constant Vertical Load Factors for NSSS
3.7-45
3.7.3.11
Torsional Effects of Eccentric Masses
3.7-45
3.7.3.11.1
Piping Other Than NSSS
3.7-45
3.7.3.11.2
Torsional Effects of Eccentric Masses of NSSS
3.7-46
3.7.3.12
Buried Seismic Category I Piping Systems
3.7-46
3.7.3.13
Interaction of Other Piping with Seismic Category I Piping
3.7-52
3.7.3.14
Seismic Analyses for Fuel Elements, Control Rod Assemblies, Control Rod
Drives, and Reactor Internals
3.7-52
3.7.3.15
Analysis Procedure for Damping
3.7-54
3.7.3.16
Seismic Analysis and Qualification of Category I Equipment Other Than NSSS
3.7-54
3.7.3.16.1
Dynamic Analysis Method For Equipment and Components
3.7-55
3.7.3.16.2
Simplified Dynamic Analysis Method For Equipment and Components
3.7-55
3.7.3.16.3
Equivalent Static Load Method
3.7-56
3.7.3.16.4
Testing Method
3.7-56
3.7.3.16.5
Equipment and Component Mounting Considerations
3.7-56
3.7.3.17
Seismic Analysis and Design of HVAC Duct and Duct Support Systems 3.757
3.7.3.17.1
Description of HVAC Duct and Duct Support Subsystems
3.7-57
3.7.3.17.2
Applicable Codes, Standards, and Specifications
3.7-57
3.7.3.17.3
Loads and Load Combinations
3.7-58
3.7.3.17.4
Analysis and Design Procedures
3.7-59
3.7.3.17.5
Structural Acceptance Criteria
3.7-59
3.7.3.17.6
Materials and Quality Control
3.7-60
3.7.3.18
Seismic Qualification of Main Control Room Suspended Ceiling and Air Delivery Components
3.7-61
3.7.4
Seismic Instrumentation Program
3.7-61
3.7.4.1
Comparison with Regulatory Guide 1.12
3.7-61
3.7.4.2
Location and Description of Instrumentation
3.7-61
3.7.4.3
Control Room Operator Notification
3.7-64
3.7.4.4
Controlled Shutdown Logic
3.7-64
3.7.4.5
Comparison of Measured and Predicted Responses
3.7-65
3.7.4.5.1
Retrieval of Data
3.7-65
Table of Contents
1-xlix
WATTS BAR
WBNP-76
TABLE OF CONTENTS
Section
3.7.4.5.2
3.8
Page
3.7-66
DESIGN OF CATEGORY I STRUCTURES
3.8.1
3.8.1.1
3.8.1.1.1
3.8.1.2
3.8.1.3
3.8.1.4
3.8.1.5
3.8.1.6
3.8.1.6.1
3.8.1.6.2
3.8.1.6.3
3.8.1.7
3.8.2
3.8.2.1
3.8.2.1.1
3.8.2.1.2
3.8.2.2
3.8.2.2.1
3.8.2.2.2
3.8.2.2.3
3.8.2.3
3.8.2.3.1
3.8.2.3.2
3.8.2.4
3.8.2.4.1
3.8.2.4.2
3.8.2.4.3
3.8.2.4.4
3.8.2.4.5
3.8.2.4.6
3.8.2.4.7
3.8.2.4.8
3.8.2.5
3.8.2.5.1
3.8.2.6
3.8.2.6.1
3.8.2.6.2
3.8.2.6.3
3.8.2.6.4
3.8.2.6.5
1-l
Title
Evaluation of Recorded Earthquake
3.8-1
Concrete Shield Building
Description of the Shield Building
Equipment Hatch Doors and Sleeves
Applicable Codes, Standards, and Specifications
Loads and Loading Combinations
Design and Analysis Procedures
Structural Acceptance Criteria
Materials, Quality Control and Special Construction Techniques
Materials
Quality Control
Construction Techniques (Historical Information)
Testing and Inservice Surveillance Requirements
3.8-1
3.8-1
3.8-2
3.8-3
3.8-5
3.8-7
3.8-10
3.8-10
3.8-11
3.8-11
3.8-12
3.8-13
Steel Containment System3.8-1
Description of the Containment and Penetrations3.8-1
Description of the Containment
3.8-1
Description of Penetrations
3.8-1
Applicable Codes, Standards and Specifications3.8-3
Codes
3.8-3
Design Specification Summary
3.8-4
NRC Regulatory Guides
3.8-6
Loads and Loading Combinations3.8-7
Design Loads
3.8-7
Loading Conditions
3.8-9
Design and Analysis Procedures3.8-12
Introduction
3.8-12
Static Stress Analysis
3.8-12
Dynamic Seismic Analysis
3.8-13
Non-Axisymmetric Pressure Loading Analysis
3.8-13
Thermal Analysis
3.8-14
Penetrations Analysis
3.8-15
Interaction of Containment and Attached Equipment
3.8-17
Anchorage
3.8-17
Structural Acceptance Criteria3.8-18
Margin of Safety
3.8-18
Materials, Quality Control, and Special Construction Techniques3.8-19
Materials - General
3.8-19
Corrosion Protection
3.8-22
Protective Coatings
3.8-24
Tolerances
3.8-24
Vessel Material Inspection and Test
3.8-25
Table of Contents
WATTS BAR
WBNP-76
TABLE OF CONTENTS
Section
Title
Page
3.8.2.6.6
Impact Testing
3.8-25
3.8.2.6.7
Post-Weld Heat Treatment
3.8-25
3.8.2.6.8
Welding
3.8-25
3.8.2.7
Testing and Inservice Inspection Requirements3.8-26
3.8.2.7.1
Bottom Liner Plates Test - Historical Information
3.8-26
3.8.2.7.2
Vertical Wall and Dome Tests - Historical Information
3.8-26
3.8.2.7.3
Soap Bubble Tests - Historical Information
3.8-26
3.8.2.7.4
Overpressure Tests - Historical Information
3.8-26
3.8.2.7.5
Leakage Rate Test - Historical Information
3.8-26
3.8.2.7.6
Operational Testing - Historical Information
3.8-27
3.8.2.7.7
Leak Testing Airlocks - Historical Information
3.8-27
3.8.2.7.8
Penetration Tests - Historical Information
3.8-27
3.8.2.7.9
Inservice Inspection Requirements
3.8-27
Components Subject to Examination and/or Test 27
Accessibility 28
Examination Techniques and Procedures 28
Inspection Intervals 28
Examination Categories and Requirements 28
Evaluation of Examination Results 28
System Pressure Tests 28
3.8.3
Concrete Interior Structure
3.8.3.1
3.8.3.1.1
3.8.3.1.2
3.8.3.1.3
3.8.3.1.4
3.8.3.1.5
3.8.3.1.6
3.8.3.1.7
3.8.3.1.8
3.8.3.1.9
3.8.3.1.10
3.8.3.1.11
3.8.3.2
3.8.3.3
3.8.3.4
3.8.3.4.1
3.8.3.4.2
3.8.3.4.3
3.8.3.4.4
3.8.3.4.5
3.8.3.4.6
3.8.3.4.7
Description of the Interior Structure
General
Containment Floor Structural Fill Slab
Reactor Cavity Wall
Compartment Above Reactor
Refueling Canal Walls and Floor (Divider Barrier)
Crane Wall
Steam Generator Compartments (Divider Barrier)
Pressurizer Compartment (Divider Barrier)
Divider Deck at Elevation 756.63 (Divider Barrier)
Ice Condenser Support Floor - Elevation 744.5 (Divider Barrier)
Penetrations Through the Divider Barrier
Applicable Codes, Standards and Specifications
Loads and Loading Combinations
Design and Analysis Procedures
General
Structural Fill Slab on Containment Floor
Reactor Cavity Wall
Compartment Above Reactor
Seals Between Upper and Lower Compartments
Refueling Canal Walls and Floor (Divider Barrier)
Crane Wall
Table of Contents
3.8-1
3.8-1
3.8-1
3.8-1
3.8-2
3.8-2
3.8-3
3.8-3
3.8-5
3.8-5
3.8-5
3.8-5
3.8-6
3.8-7
3.8-13
3.8-16
3.8-16
3.8-16
3.8-16
3.8-18
3.8-18
3.8-19
3.8-20
1-li
WATTS BAR
WBNP-76
TABLE OF CONTENTS
Section
3.8.3.4.8
3.8.3.4.9
3.8.3.4.10
3.8.3.4.11
3.8.3.4.12
3.8.3.4.13
3.8.3.5
3.8.3.5.1
3.8.3.5.2
3.8.3.5.3
3.8.3.5.4
3.8.3.5.5
3.8.3.5.6
3.8.3.5.7
3.8.3.5.8
3.8.3.5.9
3.8.3.5.10
3.8.3.5.11
3.8.3.5.12
3.8.3.6
3.8.3.6.1
3.8.3.6.2
3.8.3.6.3
3.8.3.6.4
3.8.3.7
3.8.3.8
3.8.4
Other Category I Structures
3.8.4.1
3.8.4.1.1
3.8.4.1.2
3.8.4.1.3
3.8.4.1.4
3.8.4.1.5
3.8.4.1.6
3.8.4.1.7
3.8.4.1.8
3.8.4.2
3.8.4.2.1
3.8.4.2.2
3.8.4.3
3.8.4.3.1
3.8.4.3.2
3.8.4.4
1-lii
Title
Steam Generator Compartments (Divider Barrier)
Pressurizer Compartment (Divider Barrier)
Operating Deck at Elevation 756.63 (Divider Barrier)
Ice Condenser Support Floor Elevation 744.5 (Divider Barrier)
Ice Condenser
Penetrations Through the Divider Barrier
Structural Acceptance Criteria
General
Structural Fill Slab on Containment Floor
Reactor Cavity Wall and Compartment Above Reactor
Refueling Canal Walls and Floor
Crane Wall
Steam Generator and Pressurizer Compartment
Operating Deck at Elevation 756.63
Ice Condenser Support Floor Elevation 744.5
Penetrations Through the Divider Barrier
Personnel Access Doors in Crane Wall
Seals Between Upper and Lower Compartments
Ice Condenser
Materials, Quality Control and Special Construction Techniques
Materials
Quality Control
Construction Technique - Historical Information
Ice Condenser
Testing and Inservice Surveillance Requirements
Environmental Effects
Page
3.8-23
3.8-25
3.8-26
3.8-27
3.8-28
3.8-28
3.8-31
3.8-31
3.8-31
3.8-31
3.8-31
3.8-31
3.8-32
3.8-32
3.8-32
3.8-32
3.8-33
3.8-33
3.8-33
3.8-34
3.8-34
3.8-35
3.8-35
3.8-36
3.8-38
3.8-38
3.8-1
Description of the Structures
Auxiliary-Control Building
Diesel Generator Building
Category I Water Tanks and Pipe Tunnels
Class 1E Electrical System Manholes and Duct Runs
North Steam Valve Room
Intake Pumping Station and Retaining Walls
Miscellaneous Essential Raw Cooling Water (ERCW) Structures
Additional Diesel Generator Building
Applicable Codes, Standards, and Specifications
List of Documents
Basis for Use of the 1963 Edition of ACI 318
Loads and Loading Combinations
Description of Loads
Load Combinations and Allowable Stresses
Design and Analysis Procedures
3.8-1
3.8-1
3.8-10
3.8-11
3.8-13
3.8-13
3.8-14
3.8-15
3.8-16
3.8-17
3.8-17
3.8-19
3.8-21
3.8-21
3.8-22
3.8-23
Table of Contents
WATTS BAR
WBNP-76
TABLE OF CONTENTS
Section
3.8.4.4.1
3.8.4.4.2
3.8.4.4.3
3.8.4.4.4
3.8.4.4.5
3.8.4.4.6
3.8.4.4.7
3.8.4.4.8
3.8.4.5
3.8.4.5.1
3.8.4.5.2
3.8.4.5.3
3.8.4.5.4
3.8.4.5.5
3.8.4.5.6
3.8.4.6
3.8.4.6.1
3.8.4.6.2
3.8.4.6.3
3.8.4.7
3.8.4.7.1
3.8.4.7.2
3.8.4.7.3
3.8.4.7.4
3.8.5
Title
Auxiliary-Control Building
Diesel Generator Building
Category I Water Tanks and Pipe Tunnels
Class 1E Electrical System Manholes
North Steam Valve Room
Intake Pumping Station and Retaining Walls
Miscellaneous ERCW Structures
Additional Diesel Generator Building
Structural Acceptance Criteria
Concrete
Structural and Miscellaneous Steel
Miscellaneous Components of the Auxiliary Building
Intake Pumping Station Traveling Water Screens
Diesel Generator Building Doors and Bulkheads
Additional Diesel Generator Building Missile Barriers
Materials, Quality Control, and Special Construction Techniques
Materials
Quality Control
Special Construction Techniques
Testing and Inservice Surveillance Requirements
Concrete and Structural Steel Portions of Structures
Miscellaneous Components of Auxiliary-Control Building
Deleted by Amendment 79
Miscellaneous Components of the Intake Pumping Station
Foundations and Concrete Supports
3.8.5.1
3.8.5.1.1
3.8.5.1.2
3.8.5.2
3.8.5.3
3.8.5.4
3.8.5.4.1
3.8.5.4.2
3.8.5.4.3
3.8.5.4.4
3.8.5.4.5
3.8.5.5
3.8.5.5.1
3.8.5.5.2
3.8.5.6
3.8.5.6.1
3.8.5.6.2
3.8.5.6.3
Description of Foundations and Supports
Primary Containment
Foundations of Other Category I Structures
Applicable Codes, Standards, and Specifications
Loads and Loading Combinations
Design and Analysis Procedure
Primary Containment Foundation
Auxiliary-Control Building
Intake Pumping Station
Soil-Supported Structures
Pile Supported Structures
Structural Acceptance Criteria
Primary Containment Foundation
Foundations of Other Category I Structures Auxiliary-Control Building
Materials, Quality Control, and Special Construction Techniques
Materials
Quality Control
Special Construction Techniques
Table of Contents
Page
3.8-23
3.8-30
3.8-31
3.8-31
3.8-31
3.8-32
3.8-32
3.8-33
3.8-35
3.8-35
3.8-35
3.8-36
3.8-37
3.8-37
3.8-37
3.8-37
3.8-37
3.8-38
3.8-38
3.8-38
3.8-39
3.8-39
3.8-40
3.8-40
3.8-1
3.8-1
3.8-1
3.8-1
3.8-3
3.8-4
3.8-4
3.8-4
3.8-4
3.8-4
3.8-5
3.8-5
3.8-5
3.8-5
3.8-5
3.8-6
3.8-6
3.8-7
3.8-7
1-liii
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WBNP-76
TABLE OF CONTENTS
Section
3.8.6
Title
Category I(L) Cranes
3.8.6.1
3.8.6.1.1
3.8.6.1.2
3.8.6.1.3
3.8.6.1.4
3.8.6.1.5
3.8.6.1.6
3.8.6.1.7
3.8.6.1.8
3.8.6.2
3.8.6.2.1
3.8.6.2.2
3.8.6.2.3
3.8.6.2.4
3.8.6.2.5
3.8.6.2.6
3.8.6.2.7
3.8.6.2.8
3.8-1
Polar Cranes
Description
Applicable Codes, Standards, and Specifications
Loads, Loading Combinations, and Allowable Stresses
Design and Analysis Procedure
Structural Acceptance Criteria
Materials, Quality Controls, and Special Construction Techniques
Testing and In-service Surveillance Requirements
Safety Features
Auxiliary Building Crane
Description
Applicable Codes, Standards, and Specifications
Loads, Loading Combinations, and Allowable Stresses
Design and Analysis Procedure
Structural Acceptance Criteria
Materials, Quality Controls, and Special Construction Techniques
Testing and In-service Surveillance Requirements
Safety Features
3.8A
3.8B
Page
3.8-1
3.8-1
3.8-1
3.8-2
3.8-2
3.8-2
3.8-3
3.8-3
3.8-3
3.8-4
3.8-4
3.8-5
3.8-5
3.8-5
3.8-6
3.8-6
3.8-7
3.8-7
SHELL TEMPERATURE TRANSIENTS3.8-1
BUCKLING STRESS CRITERIA
3.8-1
3.8B.1
INTRODUCTION
3.8-1
3.8B.2
SHELLS STIFFENED WITH CIRCUMFERENTIAL STIFFENERS
3.8-1
3.8B.2.1
Circular Cylindrical Shells Under Axial Compression
3.8-1
3.8B.2.2
Circular Cylindrical Shells in Circumferential Compression
3.8-2
3.8B.2.3
Circular Cylindrical Shells Under Torsion
3.8-2
3.8B.2.4
Circular Cylindrical Shells Under Bending
3.8-3
3.8B.2.5
Circular Cylindrical Shell Under Combined Loads
3.8-4
3.8B.3
SHELLS STIFFENED WITH A COMBINATION OF CIRCUMFERENTIAL AND
VERTICAL STIFFENERS
3.8-5
3.8B.4
SPHERICAL SHELLS
3.8-7
3.8B.2.1
The critical buckling stress in the spherical dome, except for external pressure,
was determined by the following equation:
3.8-7
3.8B.2.2
Spherical Shell Under Combined Loads
3.8-8
3.8B.3
FACTOR OF SAFETY
3.8-8
3.8C
DOCUMENTATION OF CB&I COMPUTER PROGRAMS
3.8-1
3.8C.1
INTRODUCTION
3.8-1
3.8C.2
PROGRAM 1017-MODAL ANALYSIS OF STRUCTURES USING THE EIGEN
VALUE TECHNIQUE
3.8-1
3.8C.3
PROGRAM 1044-SEISMIC ANALYSIS of VESSEL APPENDAGES
3.8-1
3.8C.4
PROGRAM E1668-SPECTRAL ANALYSIS FOR ACCELERATION RECORDS
1-liv
Table of Contents
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WBNP-76
TABLE OF CONTENTS
Section
Title
Page
DIGITIZED AT EQUAL INTERVALS
3.8-3
3.8C.5
PROGRAM 1642-TRANSIENT PRESSURE BEAM ANALYSIS
3.8-3
3.8C.6
PROGRAM E1623-POST PROCESSOR PROGRAM FOR PROGRAM E1374 3.84
3.8C.7
PROGRAM E1374-SHELL DYNAMIC ANALYSIS
3.8-5
3.8C.7.1
Introduction
3.8-5
3.8C.8
PROGRAM E1622-LOAD GENERATION PREPROCESSOR FOR PROGRAM
E1374
3.8-6
3.8C.9
PROGRAM E1624 SPCGEN-SPECTRAL CURVE GENERATION
3.8-7
3.8C.10
PROGRAM 781, METHOD OF MODELING VERTICAL STIFFENERS
3.8-7
3.8C.11
PROGRAM 119-CHECK of FLANGE DESIGN
3.8-7
3.8C.12
PROGRAM 772-NOZZLE REINFORCEMENT CHECK
3.8-7
3.8C.13
PROGRAM 1027-WRC 107 STRESS INTENSITIES AT LOADED ATTACHMENTS FOR SPHERES OR CYLINDERS WITH ROUND OR SQUARE ATTACHMENT 3.88
3.8C.14
PROGRAM 1036M-STRESS INTENSITIES IN JUMBO INSERT PLATES 3.8-8
3.8D
COMPUTER PROGRAMS FOR STRUCTURAL ANALYSIS
3.8-1
3.8E CODES, LOAD DEFINITIONS AND LOAD COMBINATIONS FOR THE MODIFICATION
AND EVALUATION OF EXISTING STRUCTURES AND FOR THE DESIGN OF NEW FEATURES ADDED TO EXISTING STRUCTURES AND THE DESIGN OF STRUCTURES INITIATED AFTER JULY 1979
3.8-1
3.8E.1
3.8E.2
3.8E.3
3.8E.4
3.9
Application Codes and Standards
Load Definitions
Load Combinations - Concrete
Load Combinations - Structural Steel
3.8-1
3.8-1
3.8-3
3.8-5
MECHANICAL SYSTEMS AND COMPONENTS
3.9-1
3.9.1
General Topic for Analysis of Seismic Category I ASME Code and Non-Code Items
3.9-1
3.9.1.1
Design Transients
3.9-1
3.9.1.2
Computer Programs Used in Analysis and Design
3.9-1
3.9.1.2.1
Other Than NSSS Systems, Components, Equipment, and Supports 3.9-1
3.9.1.2.2
Programs Used for Category I Components of NSSS
3.9-3
3.9.1.3
Experimental Stress Analysis
3.9-3
3.9.1.4
Consideration for the Evaluation of the Faulted Condition
3.9-3
3.9.1.4.1
Subsystems and Components Analyzed by Westinghouse
3.9-3
3.9.1.4.2
Subsystems and Components Analyzed by TVA
3.9-3
3.9.2
Dynamic Testing and Analysis
3.9-4
3.9.2.1
Preoperational Vibration and Dynamic Effects Testing on Piping
3.9-4
3.9.2.2
Seismic Qualification Testing of Safety-Related Mechanical Equipment 3.9-6
3.9.2.3
Dynamic Response Analysis of Reactor Internals Under Operational Flow
Transients and Steady-State Conditions
3.9-8
3.9.2.4
Preoperational Flow-Induced Vibration Testing of Reactor Internals
3.9-10
Table of Contents
1-lv
WATTS BAR
WBNP-76
TABLE OF CONTENTS
Section
3.9.2.5
3.9-12
3.9.2.5.1
3.9.2.5.2
3.9.2.5.3
3.9.2.5.4
Title
Page
Dynamic System Analysis of the Reactor Internals Under Faulted Conditions
Design Criteria
3.9-12
Internals Evaluation
3.9-13
LOCA Forces Analysis
3.9-13
Structural Response of Reactor Internals During LOCA and Seismic Conditions
3.9-14
Seismic Analysis
3.9-18
Results and Acceptance Criteria
3.9-18
Results and Acceptance Criteria
3.9-19
Structural Adequacy of Reactor Internals Components
3.9-19
Correlations of Reactor Internals Vibration Tests With the Analytical Results
3.9.2.5.5
3.9.2.5.6
3.9.2.5.7
3.9.2.5.8
3.9.2.6
3.9-21
3.9.3
ASME Code Class 1, 2 and 3 Components, Component Supports and Core Support
Structures
3.9-22
3.9.3.1
Loading Combinations, Design Transients, and Stress Limits
3.9-22
3.9.3.1.1
Subsystems and Components Supplied by Westinghouse
3.9-22
Plant Conditions and Design Loading Combinations For ASME Code Class 2 and 3 Components
Supplied by Westinghouse 24
Design Loading Combinations by Westinghouse 24
Design Stress Limits By Westinghouse 24
3.9.3.1.2
Subsystems and Components Analyzed or Specified by TVA
3.9-25
3.9.3.2
Pumps and Valve Operability Assurance
3.9-29
3.9.3.2.1
Active* ASME Class 1, 2, & 3 Pumps and Valves
3.9-29
3.9.3.2.2
Operability Assurance
3.9-30
Westinghouse Scope of Supply 30
TVA Scope of Supply 35
3.9.3.2.3
Criteria For Assuring Functional Adequacy of Active Seismic Category I
Fluid System Components (Pumps and Valves) and Associated Essential
Auxiliary Equipment
3.9-36
3.9.3.3
Design and Installation Details for Mounting of Pressure Relief Devices3.9-41
3.9.3.4
Component Supports
3.9-43
3.9.3.4.1
Subsystem and Component Supports Analyzed or Specified by Westinghouse
3.9-43
3.9.3.4.2
Subsystem and Component Supports Analyzed or Specified by TVA 3.944
3.9.4
Control Rod System
3.9-48
3.9.4.1
Descriptive Information of CRDS
3.9-48
3.9.4.2
Applicable CRDS Design Specifications
3.9-48
3.9.4.3
Design Loadings, Stress Limits, and Allowable Deformations
3.9-48
3.9.4.4
CRDS Performance Assurance Program
3.9-48
3.9.5
Reactor Pressure Vessel Internals
3.9-48
3.9.5.1
Design Arrangements
3.9-48
3.9.5.2
Design Loading Conditions
3.9-48
1-lvi
Table of Contents
WATTS BAR
WBNP-76
TABLE OF CONTENTS
Section
3.9.5.3
3.9.5.4
3.9.6
Title
Design Loading Categories
Design Basis
Inservice Testing of Pumps and Valves
Page
3.9-48
3.9-48
3.9-48
3.10 SEISMIC DESIGN OF CATEGORY I INSTRUMENTATION AND ELECTRICAL EQUIPMENT
3.10-1
3.10.1
Seismic Qualification Criteria
3.10-1
3.10.2
Methods And Procedures For Qualifying Electrical Equipment And Instrumentation
3.10-6
3.10.3
Methods of Qualifying TVA-Designed Supports for Electrical Equipment Instrumentation and Cables
3.10-6
3.10.3.1
Electrical Equipment and Instrumentation Assemblies
3.10-7
3.10.3.2
Cable Trays and Supports
3.10-7
3.10.3.2.1
Cable Trays
3.10-7
3.10.3.2.2
Supports
3.10-7
3.10.3.3
Conduit and Supports
3.10-8
3.10.3.3.1
Conduit
3.10-8
3.10.3.3.2
Supports
3.10-8
3.10.3.4
Conduit Banks
3.10-9
3.10.4
Operating License Review
3.10-9
3.10.4.1
TVA Supplied Instrumentation and Electrical Equipment
3.10-9
3.11
1
ENVIRONMENTAL DESIGN OF MECHANICAL AND ELECTRICAL EQUIPMENT 3.11-
3.11.1
3.11.1.1
3.11.1.2
3.11.2
3.11.2.1
3.11.2.2
3.11.3
3.11.4
3.11.5
3.11.6
3.11.7
3.11.7.1
3.11.7.2
3.11.7.2.1
3.11.7.2.2
Equipment Identification and Environmental Conditions
Identification of Safety Systems and Justification
Identification of Equipment in Harsh Environments
Environmental Conditions
Harsh Environment
Mild Environment
Electrical Equipment Within the Scope of 10 CFR 50.49
Qualification Tests and Analyses
Qualification Test Results
Loss of Heating, Ventilating, and Air-Conditioning (HVAC)
Estimated Chemical and Radiation Environment
Chemical Spray
Radiation
Inside Containment
Radiation - Auxiliary Building Spaces
4.0
3.11-1
3.11-1
3.11-1
3.11-2
3.11-2
3.11-3
3.11-3
3.11-4
3.11-4
3.11-4
3.11-4
3.11-4
3.11-5
3.11-5
3.11-6
REACTOR
4.1
SUMMARY DESCRIPTION
4.1-1
4.2
MECHANICAL DESIGN
4.2-1
Table of Contents
1-lvii
WATTS BAR
WBNP-76
TABLE OF CONTENTS
Section
4.2.1
4.2.1.1
4.2.1.1.1
4.2.1.1.2
4.2.1.2
4.2.1.2.1
4.2.1.2.2
4.2.1.3
4.2.1.3.1
4.2.1.3.2
4.2.1.3.3
4.2.1.3.4
4.2.1.3.5
4.2.1.4
4.2.1.4.1
4.2.1.4.2
4.2.1.4.3
4.2.1.4.4
4.2.2
4.2.2.1
4.2.2.2
4.2.2.3
4.2.2.4
4.2.2.5
4.2.3
4.2.3.1
4.2.3.1.1
4.2.3.1.2
4.2.3.1.3
4.2.3.1.4
4.2.3.2
4.2.3.2.1
4.2.3.2.2
4.2.3.3
4.2.3.3.1
4.2.3.3.2
4.2.3.4
4.2.3.4.1
4.2.3.4.2
4.2.3.5
4.2.4
4.3
1-lviii
Page
Fuel
4.2-2
Design Bases
4.2-2
Fuel Rods
4.2-2
Fuel Assembly Structure
4.2-3
Design Description
4.2-5
Fuel Rods4.2-6
Fuel Assembly Structure
4.2-6
Design Evaluation
4.2-10
Fuel Rods
4.2-10
Fuel Assembly Structure
4.2-17
Operational Experience
4.2-18
Test Rod and Test Assembly Experience
4.2-18
Evaluation of the Reactor Core for a Limiting LOCA Load - Accumulator
Line Break
4.2-18
Tests and Inspections
4.2-19
Quality Assurance Program
4.2-19
Quality Control
4.2-19
Tests and Inspections by Others
4.2-22
Onsite Inspection
4.2-22
Reactor Vessel Internals
4.2-22
Design Bases
4.2-22
Description and Drawings
4.2-23
Design Loading Conditions
4.2-27
Design Loading Categories
4.2-27
Design Criteria Basis
4.2-28
Reactivity Control System
4.2-29
Design Bases
4.2-29
Design Stresses
4.2-29
Material Compatibility
4.2-29
Reactivity Control Components
4.2-29
Control Rod Drive Mechanisms
4.2-31
Design Description
4.2-32
Reactivity Control Components
4.2-33
Control Rod Drive Mechanism (CRDM)
4.2-37
Design Evaluation
4.2-42
Reactivity Control Components
4.2-42
Control Rod Drive Mechanism
4.2-48
Tests, Verification, and Inspections
4.2-51
Reactivity Control Components
4.2-51
Control Rod Drive Mechanisms
4.2-52
Instrumentation Applications
4.2-53
Tritium Producing Burnable Absorber Rod - Tritium Production Core
4.2-54
NUCLEAR DESIGN
Title
4.3-1
Table of Contents
WATTS BAR
WBNP-76
TABLE OF CONTENTS
Section
4.3.1
4.3.1.1
4.3.1.2
4.3.1.3
4.3.1.4
4.3.1.5
4.3.1.6
4.3.1.7
4.3.1.8
4.3.2
4.3.2.1
4.3.2.2
4.3.2.2.1
4.3.2.2.2
4.3.2.2.3
4.3.2.2.4
4.3.2.2.5
4.3.2.2.6
4.3.2.2.7
4.3.2.2.8
4.3.2.3
4.3.2.3.1
4.3.2.3.2
4.3.2.3.3
4.3.2.3.4
4.3.2.3.5
4.3.2.4
4.3.2.4.1
4.3.2.4.2
4.3.2.4.3
4.3.2.4.4
4.3.2.4.5
4.3.2.4.6
4.3.2.4.7
4.3.2.4.8
4.3.2.4.9
4.3.2.5
4.3.2.5.1
4.3.2.5.2
4.3.2.5.3
4.3.2.5.4
4.3.2.5.5
4.3.2.5.6
Page
DESIGN BASES
4.3-1
Fuel Burnup
4.3-2
Negative Reactivity Feedbacks (Reactivity Coefficient)
4.3-2
Control of Power Distribution
4.3-3
Maximum Controlled Reactivity Insertion Rate
4.3-3
Shutdown Margins With Vessel Head in Place
4.3-4
Shutdown Margin for Refueling
4.3-4
Stability
4.3-5
Anticipated Transients Without Trip
4.3-5
Description
4.3-5
Nuclear Design Description
4.3-5
Power Distributions
4.3-7
Definitions
4.3-7
Radial Power Distributions
4.3-9
Assembly Power Distributions
4.3-9
Axial Power Distribution
4.3-9
Limiting Power Distributions
4.3-10
Experimental Verification of Power Distribution Analysis
4.3-14
Testing
4.3-15
Monitoring Instrumentation
4.3-16
Reactivity Coefficients
4.3-16
Fuel Temperature (Doppler) Coefficient
4.3-16
Moderator Coefficients
4.3-17
Power Coefficient
4.3-18
Comparison of Calculated and Experimental Reactivity Coefficients 4.318
Reactivity Coefficients Used in Transient Analysis
4.3-19
Control Requirements
4.3-19
Doppler
4.3-20
Variable Average Moderator Temperature
4.3-20
Redistribution
4.3-20
Void Content
4.3-20
Rod Insertion Allowance
4.3-20
Burnup
4.3-20
Xenon and Samarium Concentrations
4.3-21
pH Effects
4.3-21
Experimental Confirmation
4.3-21
Control
4.3-21
Chemical Shim
4.3-21
Rod Cluster Control Assemblies
4.3-21
Burnable Absorbers
4.3-22
Peak Xenon Startup
4.3-22
Load Follow Control and Xenon Control
4.3-22
Burnup
4.3-23
Table of Contents
Title
1-lix
WATTS BAR
WBNP-76
TABLE OF CONTENTS
Section
4.3.2.6
4.3.2.7
4.3.2.8
4.3.2.8.1
4.3.2.8.2
4.3.2.8.3
4.3.2.8.4
4.3.2.8.5
4.3.2.8.6
4.3.2.9
4.3.3
4.3.3.1
4.3.3.2
4.3.3.3
4.4
Title
Control Rod Patterns and Reactivity Worth
Criticality of Fuel Assemblies
Stability
Introduction
Stability Index
Prediction of the Core Stability
Stability Measurements
Comparison of Calculations with Measurements
Stability Control and Protection
Vessel Irradiation
Analytical Methods
Fuel Temperature (Doppler) Calculations
Macroscopic Group Constants
Spatial Few-Group Diffusion Calculations
THERMAL AND HYDRAULIC DESIGN
Page
4.3-23
4.3-24
4.3-28
4.3-28
4.3-28
4.3-29
4.3-29
4.3-31
4.3-31
4.3-32
4.3-33
4.3-33
4.3-34
4.3-35
4.4-1
4.4.1
Design Bases
4.4-1
4.4.1.1
Departure from Nucleate Boiling Design Basis
4.4-1
4.4.1.2
Fuel Temperature Design Basis
4.4-2
4.4.1.3
Core Flow Design Basis
4.4-3
4.4.1.4
Hydrodynamic Stability Design Bases
4.4-3
4.4.1.5
Other Considerations
4.4-3
4.4.2
Description
4.4-4
4.4.2.1
Summary Comparison
4.4-4
4.4.2.2
Fuel and Cladding Temperatures
4.4-4
4.4.2.2.1
UO2 Thermal Conductivity
4.4-4
4.4.2.2.2
Radial Power Distribution in UO2 Fuel Rods
4.4-5
4.4.2.2.3
Gap Conductance
4.4-6
4.4.2.2.4
Surface Heat Transfer Coefficients
4.4-6
4.4.2.2.5
Fuel Clad Temperatures
4.4-6
4.4.2.2.6
Treatment of Peaking Factors
4.4-6
4.4.2.3
Critical Heat Flux Ratio or Departure from Nucleate Boiling Ratio and Mixing
Technology
4.4-7
4.4.2.3.1
Departure from Nucleate Boiling Technology
4.4-7
4.4.2.3.2
Definition of Departure from Nucleate Boiling Ratio
4.4-8
4.4.2.3.3
Mixing Technology
4.4-10
4.4.2.3.4
Hot Channel Factors
4.4-11
4.4.2.3.5
Effects of Rod Bow on DNBR
4.4-13
4.4.2.4
Flux Tilt Considerations
4.4-13
4.4.2.5
Void Fraction Distribution
4.4-14
4.4.2.6
Deleted
4.4-14
4.4.2.7
Core Pressure Drops and Hydraulic Loads
4.4-14
4.4.2.7.1
Core Pressure Drops
4.4-14
4.4.2.7.2
Hydraulic Loads
4.4-15
1-lx
Table of Contents
WATTS BAR
WBNP-76
TABLE OF CONTENTS
Section
4.4.2.8
4.4.2.8.1
4.4.2.8.2
4.4.2.8.3
4.4.2.9
4.4.2.10
4.4.2.10.1
4.4.2.10.2
4.4.2.10.3
4.4.2.10.4
4.4.2.10.5
4.4.2.10.6
4.4.2.10.7
4.4.2.10.8
4.4.2.11
4.4.3
4.4.3.1
4.4.3.1.1
4.4.3.1.2
4.4.3.1.3
4.4.3.2
4.4.3.2.1
4.4.3.2.2
4.4.3.3
4.4.3.4
4.4.3.4.1
4.4.3.4.2
4.4.3.4.3
4.4.3.5
4.4.3.6
4.4.3.7
4.4.3.8
4.4.3.9
4.4.3.10
4.4.4
4.4.4.1
4.4.4.2
4.4.4.3
4.4.5
4.4.5.1
4.4.5.2
4.4.5.3
Title
Page
Correlation and Physical Data
4.4-15
Surface Heat Transfer Coefficients
4.4-15
Total Core and Vessel Pressure Drop
4.4-16
Void Fraction Correlation
4.4-17
Thermal Effects of Operational Transients
4.4-17
Uncertainties in Estimates
4.4-18
Uncertainties in Fuel and Clad Temperatures
4.4-18
Uncertainties in Pressure Drops
4.4-18
Uncertainties Due to Inlet Flow Maldistribution
4.4-19
Uncertainties in DNB Correlation
4.4-19
Uncertainties in DNBR Calculations
4.4-19
Uncertainties in Flow Rates
4.4-19
Uncertainties in Hydraulic Loads
4.4-19
Uncertainties in Mixing Coefficient
4.4-20
Plant Configuration Data
4.4-20
EVALUATION
4.4-20
Core Hydraulics
4.4-20
Flow Paths Considered in Core Pressure Drop and Thermal Design 4.420
Inlet Flow Distributions
4.4-21
Empirical Friction Factor Correlations
4.4-22
Influence of Power Distribution
4.4-22
Nuclear Enthalpy Rise Hot Channel Factor, FN∆H
4.4-22
Axial Heat Flux Distributions
4.4-23
Core Thermal Response
4.4-24
Analytical Techniques
4.4-24
Core Analysis
4.4-24
Fuel Temperatures
4.4-26
Hydrodynamic Instability
4.4-26
Hydrodynamic and Flow Power Coupled Instability
4.4-26
Temperature Transient Effects Analysis
4.4-28
Potentially Damaging Temperature Effects During Transients
4.4-29
Energy Release During Fuel Element Burnout
4.4-29
Deleted
4.4-30
Fuel Rod Behavior-Effects from Coolant Flow Blockage
4.4-30
Testing and Verification
4.4-31
Tests Prior to Initial Criticality
4.4-31
Initial Power and Plant Operation
4.4-31
Component and Fuel Inspections
4.4-31
Instrumentation Application
4.4-31
Incore Instrumentation
4.4-31
Overtemperature and Overpower ∆T Instrumentation
4.4-32
Instrumentation to Limit Maximum Power Output
4.4-32
Table of Contents
1-lxi
WATTS BAR
WBNP-76
TABLE OF CONTENTS
Section
5.0
5.1
5.1.1
5.1.2
5.1.3
5.2
Title
REACTOR COOLANT SYSTEM
SUMMARY DESCRIPTION
Schematic Flow Diagram
Piping and Instrumentation Diagrams
Elevation Drawing
INTEGRITY OF REACTOR COOLANT PRESSURE BOUNDARY
Page
5.1-1
5.1-6
5.1-6
5.1-6
5.2-1
5.2.1
Design of Reactor Coolant Pressure Boundary Components
5.2-2
5.2.1.1
Performance Objectives
5.2-2
5.2.1.2
Design Parameters
5.2-3
5.2.1.3
Compliance with 10 CFR Part 50, Section 50.55a
5.2-4
5.2.1.4
Applicable Code Cases
5.2-4
5.2.1.5
Design Transients
5.2-4
5.2.1.6
Identification of Active Pumps and Valves
5.2-14
5.2.1.7
Design of Active Pumps and Valves
5.2-14
5.2.1.8
Inadvertent Operation of Valves
5.2-14
5.2.1.9
Stress and Pressure Limits
5.2-14
5.2.1.10
Stress Analysis for Structural Adequacy
5.2-14
5.2.1.10.1
Loading Conditions
5.2-15
5.2.1.10.2
Analysis of the Reactor Coolant Loop and Supports
5.2-15
5.2.1.10.3
Reactor Coolant Loop Models and Methods
5.2-16
5.2.1.10.4
Primary Component Supports Models and Methods
5.2-23
5.2.1.10.5
Analysis of Primary Components
5.2-24
5.2.1.10.6
Reactor Vessel Support LOCA Loads
5.2-26
Introduction 26
Interface Information 27
Loading Conditions 27
Reactor Vessel and Internals Modeling 28
A detailed discussion on Reactor Pressure Vessel (RPV) / Internals modeling and the RPV system
dynamic analysis under faulted condition is provided in Section 3.9.2.5.Analytical Methods 28
Results of the Analysis 28
5.2.1.10.7
Stress Criteria for Class 1 Components and Component Supports 5.2-30
5.2.1.10.8
Computer Program Descriptions
5.2-32
5.2.1.10.9
LOCA Evaluation of the Control Rod Drive Mechanisms
5.2-32
5.2.1.11
Analysis Methods For Faulted Conditions
5.2-32
5.2.1.12
Protection Against Environmental Factors
5.2-32
5.2.1.13
Compliance With Code Requirements
5.2-33
5.2.1.14
Stress Analysis For Faulted Conditions Loadings
5.2-33
5.2.1.15
Stress Levels in Category I Systems
5.2-33
5.2.1.16
Analytical Methods for Stresses in Pumps and Valves
5.2-33
5.2.1.17
Analytical Methods for Evaluation of Pump Speed and Bearing Integrity 5.233
5.2.1.18
Operation of Active Valves Under Transient Loadings
5.2-33
1-lxii
Table of Contents
WATTS BAR
WBNP-76
TABLE OF CONTENTS
Section
Title
Page
5.2.2
Overpressurization Protection
5.2-33
5.2.2.1
Location of Pressure Relief Devices
5.2-33
5.2.2.2
Mounting of Pressure Relief Devices
5.2-33
5.2.2.3
Report on Overpressure Protection
5.2-34
5.2.2.4
RCS Pressure Control During Low Temperature Operation
5.2-35
5.2.2.4.1
System Operation
5.2-35
5.2.2.4.2
Pressure Transient Analyses
5.2-36
Evaluation of Low Temperature Overpressure Transients 36
Operating Basis Earthquake Evaluation 36
5.2.2.4.3
Administrative Procedures
5.2-37
5.2.3
General Material Considerations
5.2-39
5.2.3.1
Material Specifications
5.2-39
5.2.3.2
Compatibility With Reactor Coolant
5.2-40
5.2.3.3
Compatibility With External Insulation and Environmental Atmosphere 5.2-40
5.2.3.4
Chemistry of Reactor Coolant
5.2-40
5.2.4
Fracture Toughness
5.2-42
5.2.4.1
Compliance With Code Requirements
5.2-42
5.2.4.2
Acceptable Fracture Energy Levels
5.2-42
5.2.4.3
Operating Limitations During Startup and Shutdown
5.2-42
5.2.5
Austenitic Stainless Steel
5.2-45
5.2.5.1
Cleaning and Contamination Protection Procedures
5.2-45
5.2.5.2
Solution Heat Treatment Requirements
5.2-46
5.2.5.3
Material Inspection Program
5.2-46
5.2.5.4
Unstablilized Austenitic Stainless Steels
5.2-46
5.2.5.5
Prevention of Intergranular Attack of Unstabilized Austenitic Stainless Steels
5.2-47
5.2.5.6
Retesting Unstabilized Austenitic Stainless Steel Exposed to Sensitization
Temperatures
5.2-49
5.2.5.7
Control of Delta Ferrite in Austenitic Stainless Steel Welding
5.2-50
5.2.6
Pump Flywheels
5.2-52
5.2.6.1
Design Basis
5.2-52
5.2.6.2
Fabrication and Inspection
5.2-52
5.2.6.3
Acceptance Criteria and Compliance with Regulatory Guide 1.14
5.2-52
5.2.7
RCPB Leakage Detection Systems
5.2-53
5.2.7.1
Collection of Identified Leakage
5.2-53
5.2.7.2
Unidentified Leakage to Containment
5.2-54
5.2.7.3
Methods of Detection
5.2-54
5.2.7.3.1
Containment Air Particulate Monitors and Containment Radioactive 5.255
5.2.7.3.2
Reactor Building Floor and Equipment Drain (RBF&ED) Sump and the
RBF&ED Pocket Sump Level Monitors
5.2-56
5.2.7.3.3
Humidity Monitors
5.2-57
5.2.7.3.4
Temperature Monitors
5.2-57
5.2.7.4
Intersystem Leakage Detection
5.2-57
Table of Contents
1-lxiii
WATTS BAR
WBNP-76
TABLE OF CONTENTS
Section
5.2.7.4.1
5.2.7.4.2
5.2.7.4.3
5.2.7.4.4
5.2.7.5
5.2.7.5.1
5.2.7.5.2
5.2.7.5.3
5.2.7.5.4
5.2.7.6
5.2.7.7
5.2.7.7.1
5.2.7.7.2
5.2.7.7.3
5.2.7.7.4
5.2.7.8
5.2.8
5.2.8.1
5.2.8.2
5.2.8.3
5.2.8.4
5.2.8.5
5.2.8.6
5.2.8.7
5.3
5.3.1
5.3.2
5.3.3
5.3.4
5.3.5
5.3.6
5.3.7
5.4
5.4.1
5.4.1.1
5.4.1.2
5.4.1.3
5.4.1.4
5.4.2
5.4.2.1
1-lxiv
Title
Page
ECCS Intersystem Leakage
5.2-57
Condenser Vacuum Pump Air Exhaust Monitors
5.2-59
Component Cooling System Liquid Effluent Monitors
5.2-60
Steam Generator Blowdown Liquid Effluent Monitor
5.2-61
Unidentified Leakage System Sensitivity and Response Time
5.2-61
Containment Air Particulate Monitors and Containment Radioactive Gas
Monitors
5.2-61
Reactor Building Floor and Equipment Drain (RBF&ED) Pocket Sump
5.2-62
Humidity Monitors
5.2-62
Temperature Monitors
5.2-63
Seismic Capability
5.2-63
Indicators and Alarms
5.2-63
Radiation Monitors
5.2-63
RBF&ED Pocket Sump Level Monitors
5.2-63
Humidity Monitors
5.2-64
Temperature Monitors
5.2-64
Testing
5.2-64
Inservice Inspection of ASME Code Class 1 Components
5.2-64
Components Subject to Examination and/or Test
5.2-64
Accessibility
5.2-64
Examination Techniques and Procedures
5.2-66
Inspection Intervals
5.2-66
Examination Categories and Requirements
5.2-66
Evaluation of Examination Results
5.2-66
System Pressure Tests
5.2-66
THERMAL HYDRAULIC SYSTEM DESIGN
Analytical Methods and Data
Operating Restrictions On Pumps
Power-Flow Operating Map (BWR)
Temperature-Power Operating Map
Load Following Characteristics
Transient Effects
Thermal and Hydraulic Characteristics Summary Table
REACTOR VESSEL AND APPURTENANCES
Design Bases
Codes and Specifications
Design Transients
Protection Against Non-Ductile Failure
Inspection
Description
Fabrication Processes
5.3-1
5.3-1
5.3-1
5.3-1
5.3-1
5.3-1
5.3-1
5.3-1
5.4-1
5.4-1
5.4-1
5.4-1
5.4-2
5.4-2
5.4-2
5.4-3
Table of Contents
WATTS BAR
WBNP-76
TABLE OF CONTENTS
Section
5.4.2.2
5.4.3
5.4.3.1
5.4.3.2
5.4.3.3
5.4.3.4
5.4.3.5
5.4.3.6
5.4.3.6.1
Title
Page
Protection of Closure Studs
5.4-4
Evaluation
5.4-4
Steady State Stresses
5.4-4
Fatigue Analysis Based on Transient Stresses
5.4-4
Thermal Stresses Due to Gamma Heating
5.4-4
Thermal Stresses Due to Loss of Coolant Accident
5.4-4
Heatup and Cooldown
5.4-4
Irradiation Surveillance Programs
5.4-4
Measurement of Integrated Fast Neutron (E>l.0MeV) Flux at the Irradiation Samples
5.4-6
Determination of Sensor Reaction Rates 7
Corrections to Reaction Rate Data 8
Least Squares Adjustment Procedure 9
5.4.3.6.2
Calculation of Integrated Fast Neutron (E > 1.0 MeV) Flux at the Irradiation Samples
5.4-12
Reference Forward Calculation 13
Cycle Specific Adjoint Calculations 14
5.4.3.7
Capability for Annealing the Reactor Vessel
5.4-14
5.4.4
Tests and Inspections
5.4-15
5.4.4.1
Ultrasonic Examinations
5.4-15
5.4.4.2
Penetrant Examinations
5.4-15
5.4.4.3
Magnetic Particle Examination
5.4-15
5.4.4.4
Inservice Inspection
5.4-16
5.5
COMPONENT AND SUBSYSTEM DESIGN
5.5.1
5.5.1.1
5.5.1.2
5.5.1.3
5.5.1.3.1
5.5.1.3.2
5.5.1.3.3
5.5.1.3.4
5.5.1.3.5
5.5.1.3.6
5.5.1.3.7
5.5.1.3.8
5.5.1.3.9
5.5.1.3.10
5.5.1.3.11
5.5.1.3.12
5.5.1.3.13
5.5.1.3.14
5.5.1.3.15
Reactor Coolant Pumps
Design Bases
Design Description
Design Evaluation
Pump Performance
Coastdown Capability
Flywheel Integrity
Bearing Integrity
Locked Rotor
Critical Speed
Missile Generation
Pump Cavitation
Pump Overspeed Considerations
Anti-Reverse Rotation Device
Shaft Seal Leakage
Seal Discharge Piping
Spool Piece
Motor Air Coolers
Discharge Nozzle Weir
Table of Contents
5.5-1
5.5-1
5.5-1
5.5-1
5.5-3
5.5-3
5.5-4
5.5-4
5.5-4
5.5-5
5.5-5
5.5-5
5.5-5
5.5-6
5.5-6
5.5-6
5.5-7
5.5-7
5.5-7
5.5-7
1-lxv
WATTS BAR
WBNP-76
TABLE OF CONTENTS
Section
5.5.1.4
5.5.2
5.5.2.1
5.5.2.2
5.5.2.3
5.5.2.3.1
5.5.2.3.2
5.5.2.3.3
5.5.2.3.4
5.5.2.3.5
5.5.2.3.6
5.5.2.4
5.5.3
5.5.3.1
5.5.3.2
5.5.3.3
5.5.3.3.1
5.5.3.3.2
5.5.3.3.3
5.5.3.4
5.5.4
5.5.4.1
5.5.4.2
5.5.4.3
5.5.4.4
5.5.5
5.5.6
5.5.6.1
5.5.6.2
5.5.6.2.1
5.5.6.2.2
5.5.6.3
5.5.6.3.1
5.5.6.3.2
5.5.6.3.3
5.5.6.3.4
5.5.7
5.5.7.1
5.5.7.2
5.5.7.2.1
5.5.7.2.2
5.5.7.3
5.5.7.3.1
5.5.7.3.2
1-lxvi
Title
Tests and Inspections
Steam Generators
Design Basis
Design Description
Design Evaluation
Forced Convection
Natural Circulation Flow
Tube and Tubesheet Stress Analyses
Corrosion
Compatibility of Steam Generator Tubing with Primary and
Flow Induced Vibration
Tests and Inspections
Reactor Coolant Piping
Design Bases
Design Description
Design Evaluation
Material Corrosion/Erosion Evaluation
Sensitized Stainless Steel
Contaminant Control
Tests and Inspections
Steam Outlet Flow Restrictor (Steam Generator)
Design Basis
Description
Evaluation
Tests and Inspections
Main Steam Line Isolation System
Reactor Vessel Head Vent System
Design Basis
System Description
Component Description
System Operation
Design Evaluation
System Availability and Reliability
Leakage Provisions
Pipe Rupture Provisions
Radiological Considerations
Residual Heat Removal System
Design Bases
System Description
Component Description
System Operation
Design Evaluation
System Availability and Reliability
Leakage Provisions and Activity Release
Page
5.5-7
5.5-8
5.5-8
5.5-8
5.5-9
5.5-9
5.5-9
5.5-10
5.5-10
5.5-11
5.5-12
5.5-14
5.5-15
5.5-15
5.5-16
5.5-18
5.5-18
5.5-19
5.5-19
5.5-19
5.5-20
5.5-20
5.5-20
5.5-20
5.5-20
5.5-20
5.5-20
5.5-20
5.5-21
5.5-22
5.5-22
5.5-22
5.5-22
5.5-23
5.5-23
5.5-23
5.5-23
5.5-23
5.5-24
5.5-25
5.5-27
5.5-29
5.5-29
5.5-29
Table of Contents
WATTS BAR
WBNP-76
TABLE OF CONTENTS
Section
5.5.7.3.3
5.5.7.3.4
5.5.7.3.5
5.5.7.3.6
5.5.7.4
5.5.8
5.5.9
5.5.10
5.5.10.1
5.5.10.1.1
5.5.10.1.2
5.5.10.2
5.5.10.2.1
5.5.10.2.2
5.5.10.3
5.5.10.3.1
5.5.10.3.2
5.5.10.3.3
5.5.10.3.4
5.5.10.3.5
5.5.10.4
5.5.11
5.5.11.1
5.5.11.2
5.5.11.2.1
5.5.11.2.2
5.5.11.2.3
5.5.11.3
5.5.12
5.5.12.1
5.5.12.2
5.5.12.3
5.5.12.4
5.5.13
5.5.13.1
5.5.13.2
5.5.13.3
5.5.13.4
5.5.14
5.5.14.1
5.5.14.2
5.5.14.3
5.5.14.4
Title
Page
Overpressurization Protection
5.5-30
Prevention of Exposure of the Residual Heat Removal System to Normal
Reactor Coolant System Operating Pressure
5.5-30
Shared Function
5.5-31
Radiological Consideration
5.5-31
Tests and Inspections
5.5-31
Reactor Coolant Cleanup System
5.5-32
Main Steam Line and Feedwater Piping
5.5-32
Pressurizer
5.5-32
Design Bases
5.5-32
Pressurizer Surge Line
5.5-32
Pressurizer Volume
5.5-32
Design Description
5.5-33
Pressurizer Surge Line
5.5-33
Pressurizer Vessel
5.5-33
Design Evaluation
5.5-34
System Pressure
5.5-34
Pressurizer Performance
5.5-35
Pressure Setpoints
5.5-35
Pressurizer Spray
5.5-35
Pressurizer Design Analysis
5.5-36
Tests and Inspections
5.5-36
Pressurizer Relief Tank
5.5-37
Design Bases
5.5-37
Design Description
5.5-37
Pressurizer Relief Tank Pressure
5.5-38
Pressurizer Relief Tank Level
5.5-38
Pressurizer Relief Tank Water Temperature
5.5-38
Design Evaluation
5.5-38
Valves
5.5-39
Design Bases
5.5-39
Design Description
5.5-39
Design Evaluation
5.5-40
Tests and Inspections
5.5-40
Safety and Relief Valves
5.5-40
Design Bases
5.5-40
Design Description
5.5-41
Design Evaluation
5.5-41
Tests and Inspections
5.5-41
Component Supports
5.5-41
Design Bases
5.5-41
Description
5.5-42
Evaluation
5.5-43
Tests and Inspections
5.5-44
Table of Contents
1-lxvii
WATTS BAR
WBNP-76
TABLE OF CONTENTS
Section
5.6
INSTRUMENTATION APPLICATION
6.0
6.1
Title
Page
5.6-1
ENGINEERED SAFETY FEATURES
ENGINEERED SAFETY FEATURE MATERIALS
6.1-1
6.1.1
Metallic Materials
6.1-1
6.1.1.1
Materials Selection and Fabrication
6.1-1
6.1.1.2
Composition, Compatibility, and Stability of Containment and Core Spray
Coolants
6.1-2
6.1.2
Organic Materials
6.1-3
6.1.2.1
Electrical Insulation
6.1-3
6.1.2.2
Surface Coatings
6.1-3
6.1.2.3
Ice Condenser Equipment
6.1-4
6.1.2.4
Identification Tags
6.1-4
6.1.2.5
Valves and Instruments within Containment
6.1-4
6.1.2.6
Heating and Ventilating Door Seals
6.1-5
6.1.2.7
Miscellaneous
6.1-5
6.1.3
Post-Accident Chemistry
6.1-5
6.1.3.1
Boric Acid, H3BO3
6.1-5
6.1.3.2
Lithium Hydroxide
6.1-5
6.1.3.3
Sodium Tetraborate
6.1-5
6.1.3.4
Final Post-Accident Chemistry
6.1-6
6.1.4
Degree of Compliance with Regulatory Guide 1.54 for Paints and Coatings Inside
Containment
6.1-6
6.2
CONTAINMENT SYSTEMS
6.2.1
6.2.1.1
6.2.1.1.1
6.2.1.2
6.2.1.3
6.2.1.3.1
6.2.1.3.2
6.2.1.3.3
6.2.1.3.4
6.2.1.3.5
6.2.1.3.6
6.2.1.3.7
6.2.1.3.8
6.2.1.3.9
6.2.1.3.10
6.2.1.3.11
6.2.2
1-lxviii
Containment Functional Design
Design Bases
Primary Containment Design Bases
Primary Containment System Design
Design Evaluation
Primary Containment Evaluation
General Description of Containment Pressure Analysis
Long-Term Containment Pressure Analysis
Short-Term Blowdown Analysis
Effect of Steam Bypass
Mass and Energy Release Data
Accident Chronology
Mass and Energy Balance Tables
Containment Pressure Differentials
Steam Line Break Inside Containment
Maximum Reverse Pressure Differentials
CONTAINMENT HEAT REMOVAL SYSTEMS
6.2-1
6.2-1
6.2-1
6.2-1
6.2-3
6.2-3
6.2-3
6.2-4
6.2-4
6.2-9
6.2-17
6.2-21
6.2-30
6.2-30
6.2-32
6.2-35
6.2-40
6.2-1
Table of Contents
WATTS BAR
WBNP-76
TABLE OF CONTENTS
Section
6.2.2.1
6.2.2.2
6.2.2.3
6.2.2.4
6.2.2.5
6.2.2.6
6.2.3
Design Bases
Secondary Containment Enclosures
Emergency Gas Treatment System (EGTS)
Auxiliary Building Gas Treatment System (ABGTS)
System Design
Secondary Containment Enclosures
Emergency Gas Treatment System (EGTS)
Auxiliary Building Gas Treatment System (ABGTS)
Design Evaluation
Secondary Containment Enclosures
Emergency Gas Treatment System (EGTS)
Auxiliary Building Gas Treatment System (ABGTS)
Tritium Production Core Evaluation (Unit 1 Only)
Test and Inspections
Emergency Gas Treatment System (EGTS)
Auxiliary Building Gas Treatment System (ABGTS)
Instrumentation Requirements
Emergency Gas Treatment System (EGTS)
Auxiliary Building Gas Treatment System (ABGTS)
Containment Isolation Systems
6.2.4.1
6.2.4.2
6.2.4.2.1
6.2.4.2.2
6.2.4.2.3
6.2.4.3
6.2.4.3.1
6.2.4.4
6.2.5
Design Bases
System Design
Design Evaluation
Testing and Inspections
Instrumentation Requirements
Materials
Secondary Containment Functional Design
6.2.3.1
6.2.3.1.1
6.2.3.1.2
6.2.3.1.3
6.2.3.2
6.2.3.2.1
6.2.3.2.2
6.2.3.2.3
6.2.3.3
6.2.3.3.1
6.2.3.3.2
6.2.3.3.3
6.2.3.3.4
6.2.3.4
6.2.3.4.1
6.2.3.4.2
6.2.3.5
6.2.3.5.1
6.2.3.5.2
6.2.4
Title
Page
6.2-1
6.2-3
6.2-5
6.2-8
6.2-8
6.2-9
6.2-1
6.2-1
6.2-1
6.2-1
6.2-2
6.2-2
6.2-2
6.2-6
6.2-10
6.2-12
6.2-12
6.2-14
6.2-19
6.2-22
6.2-22
6.2-22
6.2-22
6.2-23
6.2-23
6.2-23
6.2-1
Design Bases
System Design
Design Requirements
Containment Isolation Operation
Penetration Design
Design Evaluation
Possible Leakage Paths
Tests and Inspections
6.2-1
6.2-4
6.2-5
6.2-6
6.2-6
6.2-12
6.2-14
6.2-17
Combustible Gas Control in Containment
6.2-1
6.2.5.1
The containment combustible gas control system is designed to control the concentration of hydrogen that may be released into the containment following a beyond-design-basis accident to ensure that containment structural integrity is maintained. The combustible gas control
system of the containment air return system, the hydrogen analyzer system (HAS) and the hydrogen mitigation system (HMS) which conform to 10CFR50.44 requirements.Design Bases 6.2-1
Table of Contents
1-lxix
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TABLE OF CONTENTS
Section
6.2.5.2
6.2.5.3
6.2.5.4
6.2.5.5
6.2.6
System Design
Design Evaluation
Testing and Inspections
Instrumentation Application
6.2-1
Containment Integrated Leak Rate Test
Containment Penetration Leakage Rate Test
Scheduling and Reporting of Periodic Tests
6.2-1
6.2-2
6.2-6
EMERGENCY CORE COOLING SYSTEM
6.3.1
6.3.1.1
6.3.1.2
6.3.1.3
6.3.1.4
6.3.2
6.3.2.1
6.3.2.2
6.3.2.3
6.3.2.4
6.3.2.5
6.3.2.6
6.3.2.7
6.3.2.8
6.3.2.9
6.3.2.10
6.3.2.11
6.3.2.11.1
6.3.2.11.2
6.3.2.11.3
6.3.2.12
6.3.2.13
6.3.2.14
6.3.2.15
6.3.2.16
6.3.2.17
6.3.2.18
6.3.2.19
6.3.3
6.3.3.1
6.3.3.2
6.3.3.3
6.3.3.4
1-lxx
Page
6.2-2
6.2-4
6.2-5
6.2-5
Containment Leakage Testing
6.2.6.1
6.2.6.2
6.2.6.3
6.3
Title
6.3-1
Design Bases
Range of Coolant Ruptures and Leaks
Fission Product Decay Heat
Reactivity Required for Cold Shutdown
Capability To Meet Functional Requirements
System Design
Schematic Piping and Instrumentation Diagrams
Equipment and Component Design
Applicable Codes and Classifications
Materials Specifications and Compatibility
Design Pressures and Temperatures
Coolant Quantity
Pump Characteristics
Heat Exchanger Characteristics
ECCS Flow Diagrams
Relief Valves
System Reliability
Definitions
Active and Passive Failure Criteria
Subsequent Leakage from Components in Safeguards Systems
Protection Provisions
Provisions for Performance Testing
Net Positive Suction Head
Control of Motor-Operated Isolation Valves
Motor-Operated Valves and Controls
Manual Actions
Process Instrumentation
Materials
Performance Evaluation
Evaluation Model
ECCS Performance
Alternate Analysis Methods
Fuel Rod Perforations
6.3-1
6.3-1
6.3-2
6.3-2
6.3-2
6.3-2
6.3-2
6.3-2
6.3-15
6.3-15
6.3-16
6.3-16
6.3-16
6.3-16
6.3-17
6.3-17
6.3-17
6.3-17
6.3-18
6.3-19
6.3-21
6.3-22
6.3-22
6.3-22
6.3-23
6.3-23
6.3-23
6.3-23
6.3-23
6.3-23
6.3-24
6.3-24
6.3-25
Table of Contents
WATTS BAR
WBNP-76
TABLE OF CONTENTS
Section
Title
6.3.3.5
Effects of ECCS Operation on the Core
6.3.3.6
Use of Dual Function Components
6.3.3.7
Lag Times
6.3.3.8
Thermal Shock Considerations
6.3.3.9
Limits on System Parameters
6.3.3.10
Use of RHR Spray
6.3.4
Tests and Inspections
6.3.4.1
Preoperational Tests
(Historical Information - Not Updated)
6.3.4.2
Component Testing
6.3.4.3
Periodic System Testing
6.3.5
Instrumentation Application
6.3.5.1
Temperature Indication
6.3.5.2
Pressure Indication
6.3.5.3
Flow Indication
6.3.5.4
Level Indication
6.3.5.5
Valve Position Indication
6.4
HABITABILITY SYSTEMS
6.4.1
6.4.2
6.4.2.1
6.4.2.2
6.4.2.3
6.4.2.4
6.4.2.4.1
6.4.2.4.2
6.4.2.5
6.4.2.6
6.4.2.7
6.4.3
6.4.4
6.4.4.1
6.4.4.2
6.4.5
6.4.6
6.5
Design Bases
System Design
Definition of MCRHS Area
Ventilation System Design
Leak Tightness
Interaction with Other Zones and Pressure-Containing Equipment
Other Ventilation Zones
Pressure-Containing Equipment
Shielding Design
Control Room Emergency Provisions
MCRHS Fire Protection
System Operational Procedures
Design Evaluations
Radiological Protection
Toxic Gas Protection
Testing and Inspection
Instrumentation Requirements
FISSION PRODUCT REMOVAL AND CONTROL SYSTEMS
6.5.1
6.5.1.1
6.5.1.1.1
6.5.1.1.2
6.5.1.1.3
6.5.1.1.4
Engineered Safety Feature (ESF) Filter Systems
Design Bases
Emergency Gas Treatment System Air Cleanup Units
Auxiliary Building Gas Treatment System Air Cleanup Units
Reactor Building Purge Air System Air Cleanup Units
Main Control Room Emergency Air Cleanup Units
Table of Contents
Page
6.3-25
6.3-25
6.3-27
6.3-27
6.3-27
6.3-27
6.3-28
6.3-28
6.3-29
6.3-29
6.3-30
6.3-30
6.3-30
6.3-30
6.3-31
6.3-32
6.4-1
6.4-1
6.4-1
6.4-1
6.4-2
6.4-2
6.4-3
6.4-3
6.4-4
6.4-4
6.4-4
6.4-4
6.4-5
6.4-7
6.4-7
6.4-7
6.4-9
6.4-9
6.5-1
6.5-1
6.5-1
6.5-1
6.5-1
6.5-1
6.5-2
1-lxxi
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WBNP-76
TABLE OF CONTENTS
Section
6.5.1.2
6.5.1.2.1
6.5.1.2.2
6.5.1.2.3
6.5.1.2.4
6.5.1.3
6.5.1.3.1
6.5.1.3.2
6.5.1.3.3
6.5.1.3.4
6.5.1.4
6.5.1.4.1
6.5.1.4.2
6.5.1.4.3
6.5.1.4.4
6.5.1.5
6.5.1.5.1
6.5.1.5.2
6.5.1.5.3
6.5.1.5.4
6.5.1.6
6.5.1.6.1
6.5.1.6.2
6.5.1.6.3
6.5.1.6.4
6.5.2
6.5.2.1
6.5.2.2
6.5.2.3
6.5.2.4
6.5.2.5
6.5.2.6
6.5.3
6.5.3.1
6.5.3.2
6.5.4
6.5.4.1
6.5.4.2
6.5.4.2.1
6.5.4.2.2
6.5.4.3
6.5-11
6.5.4.4
6.5.4.4.1
1-lxxii
Title
Page
System Design
6.5-2
Emergency Gas Treatment System Air Cleanup Units
6.5-2
Auxiliary Building Gas Treatment System Air Cleanup Units
6.5-3
Reactor Building Purge System Air Cleanup Units
6.5-4
Main Control Room Emergency Air Cleanup Units
6.5-4
Design Evaluation
6.5-5
Emergency Gas Treatment System Air Cleanup Units
6.5-5
Auxiliary Building Gas Treatment System Air Cleanup Units
6.5-5
Reactor Building Purge System Air Cleanup Units
6.5-5
Main Control Room Emergency Air Cleanup Units
6.5-5
Tests and Inspections
6.5-5
Emergency Gas Treatment System Air Cleanup Units
6.5-5
Auxiliary Building Gas Treatment System Air Cleanup Units
6.5-6
Reactor Building Purge System Air Cleanup Units
6.5-6
Main Control Room Emergency Air Cleanup Units
6.5-6
Instrumentation Requirements
6.5-6
Emergency Gas Treatment System Air Cleanup Units
6.5-6
Auxiliary Building Gas Treatment System Air Cleanup Units
6.5-7
Reactor Building Purge System Air Cleanup Units
6.5-7
Main Control Room Emergency Air Cleanup Units
6.5-7
Materials
6.5-7
Emergency Gas Treatment System Air Cleanup Units
6.5-7
Auxiliary Building Gas Treatment System Air Cleanup Units
6.5-7
Reactor Building Purge System Air Cleanup Units
6.5-7
Main Control Room Emergency Air Cleanup Units
6.5-8
Containment Spray System for Fission Product Cleanup
6.5-8
Design Bases
6.5-8
System Design
6.5-8
Design Evaluation
6.5-8
Tests and Inspections
6.5-8
Instrumentation Requirements
6.5-8
Materials
6.5-8
Fission Product Control Systems
6.5-8
Primary Containment
6.5-8
Secondary Containments
6.5-10
Ice Condenser as a Fission Product Cleanup System
6.5-10
Ice Condenser Design Basis (Fission Product Cleanup Function)
6.5-11
Ice Condenser System Design
6.5-11
Component Description
6.5-11
System Operation
6.5-11
Ice Condenser System Design Evaluation (Fission Product Cleanup Function)
Condenser System Tests and Inspections
Ice Condenser System Instrumentation
6.5-13
6.5-14
Table of Contents
WATTS BAR
WBNP-76
TABLE OF CONTENTS
Section
6.5.4.5
6.6
6.6.1
6.6.2
6.6.3
6.6.4
6.6.5
6.6.6
6.6.7
6.6.8
6.7
6.7.1
6.7.1.1
6.7.1.2
6.7.1.3
6.7.2
6.7.2.1
6.7.2.2
6.7.2.3
6.7.3
6.7.3.1
6.7.3.2
6.7.3.3
6.7.4
6.7.4.1
6.7.4.2
6.7.4.3
6.7.5
6.7.5.1
6.7.5.2
6.7.5.3
6.7.6
6.7.6.1
6.7.6.2
6.7.6.3
6.7.7
6.7.7.1
6.7.7.2
6.7.7.3
6.7.8
6.7.8.1
6.7.8.2
Title
Ice Condenser Materials
INSERVICE INSPECTION OF ASME CODE CLASS 2 AND 3 COMPONENTS
Components Subject to Examination and/or Test
Accessibility
Examination Techniques and Procedures
Inspection Intervals
Examination Categories and Requirements
Evaluation of Examination Results
System Pressure Tests
Protection against Postulated Piping Failures
ICE CONDENSER SYSTEM
Floor Structure and Cooling System
Design Bases
System Design
Design Evaluation
Wall Panels
Design Basis
System Design
Design Evaluation
Lattice Frames and Support Columns
Design Basis
System Design
Design Evaluation
Ice Baskets
Design Basis
System Design
Design Evaluation
Crane and Rail Assembly
Design Basis
System Design
Design Evaluation
Refrigeration System
Design Basis
System Design
Design Evaluation
Air Handling Units
Design Basis
System Design
Design Evaluation
Lower Inlet Doors
Design Basis
System Design
Table of Contents
Page
6.5-14
6.6-1
6.6-1
6.6-1
6.6-1
6.6-1
6.6-1
6.6-1
6.6-2
6.6-2
6.7-1
6.7-1
6.7-1
6.7-4
6.7-5
6.7-8
6.7-8
6.7-8
6.7-9
6.7-9
6.7-9
6.7-12
6.7-13
6.7-14
6.7-14
6.7-16
6.7-18
6.7-20
6.7-20
6.7-21
6.7-21
6.7-22
6.7-22
6.7-23
6.7-26
6.7-30
6.7-30
6.7-31
6.7-31
6.7-32
6.7-32
6.7-35
1-lxxiii
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WBNP-76
TABLE OF CONTENTS
Section
6.7.8.3
6.7.9
6.7.9.1
6.7.9.2
6.7.9.3
6.7.10
6.7.10.1
6.7.10.2
6.7.11
6.7.11.1
6.7.11.2
6.7.11.3
6.7.12
6.7.12.1
6.7.12.2
6.7.12.3
6.7.13
6.7.13.1
6.7.13.2
6.7.13.3
6.7.14
6.7.14.1
6.7.14.2
6.7.14.3
6.7.15
6.7.15.1
6.7.15.2
6.7.15.3
6.7.16
6.7.16.1
6.7.16.2
6.7.16.3
6.7.16.4
6.7.17
6.7.17.1
6.7.17.2
6.7.17.3
6.7.18
6.7.18.1
6.7.18.2
6.7.18.3
6.7.18.4
6.7.19
1-lxxiv
Title
Design Evaluation
Lower Support Structure
Design Basis
System Design
Design Evaluation
Top Deck and Doors
Design Basis
System Design
Intermediate Deck and Doors
Design Basis
System Design
Design Evaluation
Air Distribution Ducts
Design Basis
System Design
Design Evaluation
Equipment Access Door
Design Basis
System Design
Design Evaluation
Ice Technology, Ice Performance, and Ice Chemistry
Design Basis
System Design
Design Evaluation
Ice Condenser Instrumentation
Design Basis
Design Description
Design Evaluation
Ice Condenser Structural Design
Applicable Codes, Standards, and Specifications
Loads and Loading Combinations
Design and Analytical Procedures
Structural Acceptance Criteria
Seismic Analysis
Seismic Analysis Methods
Seismic Load Development
Vertical Seismic Response
Materials
Design Criteria
Environmental Effects
Compliance with 10 CFR 50, Appendix B
Materials Specifications
Tests and Inspections
Page
6.7-37
6.7-38
6.7-38
6.7-39
6.7-41
6.7-50
6.7-50
6.7-52
6.7-55
6.7-55
6.7-56
6.7-57
6.7-58
6.7-58
6.7-59
6.7-59
6.7-59
6.7-59
6.7-60
6.7-60
6.7-60
6.7-60
6.7-61
6.7-61
6.7-66
6.7-66
6.7-67
6.7-69
6.7-69
6.7-69
6.7-69
6.7-70
6.7-70
6.7-71
6.7-71
6.7-74
6.7-75
6.7-75
6.7-75
6.7-77
6.7-78
6.7-79
6.7-80
Table of Contents
WATTS BAR
WBNP-76
TABLE OF CONTENTS
Section
6.8
Title
AIR RETURN FANS
6.8.1
6.8.2
6.8.3
6.8.4
6.8.5
Design Bases
System Description
Safety Evaluation
Inspection and Testing
Instrumentation Requirements
7.0
7.1
6.8-1
6.8-1
6.8-1
6.8-2
6.8-3
6.8-3
INSTRUMENTATION AND CONTROLS
INTRODUCTION
7.1.1
7.1.1.1
7.1.1.1.1
7.1.1.1.2
7.1.1.1.3
7.1.1.1.4
7.1.1.2
7.1.1.3
7.1.1.4
7.1.2
7.1.2.1
7.1.2.1.1
7.1.2.1.2
7.1.2.1.3
7.1.2.1.4
7.1.2.1.5
7.1.2.1.6
7.1.2.1.7
7.1.2.1.8
7.1.2.1.9
7.1.2.2
7.1.2.2.1
7.1.2.2.2
7.1.2.2.3
7.1.2.3
7.1.2.4
7.2
Page
Identification of Safety-Related Systems
Safety-Related Systems
Reactor Trip System
Engineered Safety Features Actuation System
Vital Instrumentation and Control Power Supply System
Auxiliary Control Air System
Safety-Related Display Instrumentation
Instrumentation and Control System Designers
Plant Comparison
Identification of Safety Criteria
Design Bases
Reactor Trip System
Engineered Safety Features Actuation System (ESFAS)
Vital Control Power Supply System
Standby Power
Interlocks
Bypasses
Equipment Protection
Diversity
Trip Setpoints
Independence of Redundant Safety-Related Systems
General
Specific Systems
Fire Protection
Physical Identification of Safety-Related Equipment
Process Signal Isolation Relays
REACTOR TRIP SYSTEM
7.2.1
7.2.1.1
7.2.1.1.1
7.2.1.1.2
7.2.1.1.3
7.2.1.1.4
7.1-1
7.1-4
7.1-4
7.1-4
7.1-4
7.1-4
7.1-4
7.1-5
7.1-5
7.1-5
7.1-5
7.1-8
7.1-8
7.1-9
7.1-10
7.1-10
7.1-10
7.1-10
7.1-10
7.1-11
7.1-11
7.1-11
7.1-12
7.1-12
7.1-14
7.1-14
7.1-16
7.2-1
Description
7.2-1
System Description
7.2-1
Functional Performance Requirements
7.2-2
Reactor Trips
7.2-2
Reactor Trip System Interlocks
7.2-10
Reactor Coolant Temperature Sensor Arrangement and Calculational
Table of Contents
1-lxxv
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TABLE OF CONTENTS
Section
7.2.1.1.5
7.2.1.1.6
7.2.1.1.7
7.2.1.1.8
7.2.1.1.9
7.2.1.1.10
7.2.1.1.11
7.2.1.2
7.2.1.2.1
7.2.1.2.2
7.2.1.2.3
7.2.1.2.4
7.2.1.2.5
7.2.1.2.6
7.2.1.3
7.2.2
7.2.2.1
7.2.2.1.1
7.2.2.1.2
7.2.2.2
7.2.2.3
7.2.2.3.1
7.2.2.3.2
7.2.2.3.3
7.2.2.3.4
7.2.2.3.5
7.2.2.4
7.2.3
7.3
Methodology
Pressurizer Water Level Reference Leg Arrangement
Process Protection System
Solid State Logic Protection System
Isolation Devices
Energy Supply and Environmental Variations
Setpoints
Seismic Design
Design Bases Information
Generating Station Conditions
Generating Station Variables
Spatially Dependent Variables
Limits, Margins and Levels
Abnormal Events
Minimum Performance Requirements
Final Systems Drawings
Analyses
Evaluation of Design Limits
Trip Setpoint Discussion
Reactor Coolant Flow Measurement
Evaluation of Compliance to Applicable Codes and Standards
Specific Control and Protection Interactions
Neutron Flux
Reactor Coolant Temperature
Pressurizer Pressure
Pressurizer Water Level
Steam Generator Water Level
Additional Postulated Accidents
Tests and Inspections
ENGINEERED SAFETY FEATURES ACTUATION SYSTEM
7.3.1
7.3.1.1
7.3.1.1.1
7.3.1.1.2
7.3.1.1.3
7.3.1.1.4
7.3.1.1.5
7.3.1.2
7.3.1.2.1
7.3.1.2.2
7.3.1.2.3
7.3.1.2.4
7.3.1.2.5
1-lxxvi
Title
Description
System Description
Function Initiation
Process Protection Circuitry
Logic Circuitry
Final Actuation Circuitry
Support Systems
Design Bases Information
Generating Station Conditions
Generating Station Variables
Spatially Dependent Variables
Limits, Margin and Levels
Abnormal Events
Page
7.2-12
7.2-15
7.2-15
7.2-15
7.2-16
7.2-16
7.2-16
7.2-16
7.2-16
7.2-16
7.2-17
7.2-17
7.2-17
7.2-18
7.2-18
7.2-19
7.2-19
7.2-20
7.2-20
7.2-22
7.2-22
7.2-32
7.2-32
7.2-32
7.2-33
7.2-34
7.2-34
7.2-35
7.2-35
7.3-1
7.3-1
7.3-1
7.3-2
7.3-3
7.3-4
7.3-4
7.3-5
7.3-6
7.3-6
7.3-6
7.3-6
7.3-6
7.3-7
Table of Contents
WATTS BAR
WBNP-76
TABLE OF CONTENTS
Section
7.3.1.2.6
7.3.1.3
7.3.2
7.3.2.1
7.3.2.2
7.3.2.2.1
7.3.2.2.2
7.3.2.2.3
7.3.2.2.4
7.3.2.2.5
7.3.2.2.6
7.3.2.3
7.3.2.4
7.3.2.4.1
7.3.2.4.2
7.4
SYSTEMS REQUIRED FOR SAFE SHUTDOWN
7.4.1
7.4.1.1
7.4.1.2
7.4.1.2.1
7.4.1.2.2
7.4.1.2.3
7.4.1.2.4
7.4.1.3
7.4.2
7.5
Title
Page
Minimum Performance Requirements
7.3-7
Final System Drawings
7.3-8
Analysis
7.3-8
System Reliability/Availability and Failure Mode and Effect Analyses 7.3-8
Compliance With Standards and Design Criteria
7.3-8
Single Failure Criterion
7.3-9
Equipment Qualification
7.3-9
Channel Independence
7.3-9
Control and Protection System Interaction
7.3-9
Capability for Sensor Checks and Equipment Test and Calibration 7.3-9
Manual Initiation, Reset and Blocks of Protective Actions7.3-15
Further Considerations
7.3-15
Summary
7.3-16
Loss-of-Coolant Protection
7.3-16
Steam Line Break Protection
7.3-17
Description
Monitoring Indicators
Controls
General Considerations
Pumps and Fans
Diesel Generators
Valves and Heaters
Equipment and Systems Available for Cold Shutdown
Analysis
INSTRUMENTATION SYSTEMS IMPORTANT TO SAFETY
7.5.1
7.5.1.1
7.5.1.2
7.5.1.3
7.5.1.4
7.5.1.4.1
7.5.1.4.2
7.5.1.4.3
7.5.1.4.4
7.5.1.4.5
7.5.1.5
7.5.1.5.1
7.5.1.5.2
7.5.1.6
7.5.1.7
7.5.1.7.1
Post Accident Monitoring Instrumentation (PAM)
System Description
Variable Types
Variable Categories
Design Bases
Definitions
Selection Criteria
Design Criteria For Category 1 Variables
Design Criteria For Category 2 Variables
Design Criteria For Category 3 Variables
General Requirements
Display Requirements
Identification
Analysis
Tests and Inspections
Programs
Table of Contents
7.4-1
7.4-1
7.4-1
7.4-2
7.4-2
7.4-3
7.4-4
7.4-4
7.4-5
7.4-5
7.5-1
7.5-1
7.5-1
7.5-1
7.5-2
7.5-3
7.5-3
7.5-3
7.5-4
7.5-5
7.5-5
7.5-6
7.5-6
7.5-6
7.5-7
7.5-7
7.5-7
1-lxxvii
WATTS BAR
WBNP-76
TABLE OF CONTENTS
Section
7.5.1.7.2
7.5.1.7.3
7.5.2
7.5.2.1
7.5.2.1.1
7.5.2.1.2
7.5.2.2
7.5.2.3
7.5.2.3.1
7.5.2.3.2
7.6
7.6-1
120V ac and 125V dc Vital Plant Control Power System
Residual Heat Removal Isolation Valves
Description
Analysis
Refueling Interlocks
Deleted by Amendment 63.
Accumulator Motor-Operated Valves
Spurious Actuation Protection for Motor Operated Valves
Loose Part Monitoring System (LPMS) System Description
Interlocks for RCS Pressure Control During Low Temperature Operation
Analysis of Interlock
Switchover From Injection to Recirculation Mode Following a LOCA
CONTROL SYSTEMS
7.7.1
7.7.1.1
7.7.1.1.1
7.7.1.1.2
7.7.1.2
7.7.1.2.1
7.7.1.2.2
7.7.1.3
7.7.1.3.1
7.7.1.3.2
7.7.1.3.3
7.7.1.3.4
7.7.1.3.5
7.7.1.3.6
7.7.1.4
7.7.1.4.1
7.7.1.4.2
1-lxxviii
Page
7.5-8
7.5-8
7.5-8
7.5-8
7.5-8
7.5-9
7.5-11
7.5-13
7.5-13
7.5-13
ALL OTHER SYSTEMS REQUIRED FOR SAFETY
7.6.1
7.6.2
7.6.2.1
7.6.2.2
7.6.3
7.6.4
7.6.5
7.6.6
7.6.7
7.6.8
7.6.8.1
7.6.9
7.7
Title
Removal of Channels from Service
Administrative Control
Plant Computer System
Safety Parameter Display System
System Description
Design Bases
Bypassed and Inoperable Status Indication System (BISI)
Technical Support Center and Nuclear Data Links
Technical Support Center
Communication Data Links
7.6-1
7.6-1
7.6-1
7.6-2
7.6-2
7.6-2
7.6-2
7.6-3
7.6-4
7.6-8
7.6-9
7.6-10
7.7-1
Description
7.7-1
Control Rod Drive Reactor Control System
7.7-1
Reactor Control Input Signals Unit 2 Only)
7.7-1
Rod Speed Control Program
7.7-3
Rod Control System
7.7-4
Rod Control System Function
7.7-4
Rod Control System Failures
7.7-5
Plant Control Signals for Monitoring and Indicating
7.7-10
Monitoring Functions Provided by the Nuclear Instrumentation System
7.7-10
Main Control Room Rod Position Indication
7.7-11
Control Bank Rod Insertion Monitoring
7.7-12
Rod Deviation Alarm
7.7-14
Rods At Bottom
7.7-14
Bypassed and Inoperable Status Indication System (BISI)
7.7-15
Plant Control System Interlocks
7.7-15
Rod Stops
7.7-15
Automatic Turbine Load Runback
7.7-15
Table of Contents
WATTS BAR
WBNP-76
TABLE OF CONTENTS
Section
7.7.1.5
7.7.1.6
7.7.1.7
7.7.1.8
7.7.1.8.1
7.7.1.8.2
7.7.1.8.3
7.7.1.9
7.7.1.9.1
7.7.1.9.2
7.7.1.9.3
7.7.1.10
7.7.1.11
7.7.1.12
7.7.2
7.7.2.1
7.7.2.2
7.7.2.3
7.7.2.4
7.7.2.5
7.7.2.6
Title
Pressurizer Pressure Control
Pressurizer Water Level Control
Steam Generator Water Level Control
Steam Dump Control
Load Rejection Steam Dump Controller
Plant Trip Steam Dump Controller
Steam Header Pressure Controller
Incore Instrumentation System
Thermocouples
Incore Instrumentation System
Incore Instrumentation System Neutron Signal Processing
Control Board
Deleted
Anticipated Transient Without Scram Mitigation System Actuation
Analysis
Separation of Protection and Control System
Response Considerations of Reactivity
Step Load Changes Without Steam Dump
Loading and Unloading
Load Rejection Furnished By Steam Dump System
Turbine-Generator Trip With Reactor Trip
7A
7A.1
INSTRUMENTATION IDENTIFICATIONS AND SYMBOLS
IDENTIFICATION SYSTEM
7A.1.1
7A.1.1.1
7A.1.1.2
7A.1.1.3
7A.1.1.4
7A.1.1.5
7A.1.1.6
7A.1.1.7
7A.1.2
7A.1.2.1
7A.1.2.1.1
7A.1.3
7A.1.3.1
7A.1.3.2
7A.2
7A.2.1
Page
7.7-16
7.7-16
7.7-17
7.7-17
7.7-18
7.7-18
7.7-19
7.7-19
7.7-19
7.7-20
7.7-20
7.7-20
7.7-21
7.7-21
7.7-22
7.7-23
7.7-23
7.7-25
7.7-26
7.7-26
7.7-26
7A.1-1
FUNCTIONAL IDENTIFICATION
Principal Function
Measured Variable
Readout or Passive Functions
Modifying Letters
Tagging Symbols
Special Identifying Letters
Pilot Lights
SYSTEM IDENTIFICATION
Identification Numbers
Instruments Common to Multiple Process Systems
LOOP IDENTIFICATION
Instruments Common to Multiple Control Loops
Multiple Instruments with a Common Function
SYMBOLS
7A.1-3
INSTRUMENT SYMBOL
8.0
Table of Contents
7A.1-1
7A.1-1
7A.1-2
7A.1-2
7A.1-2
7A.1-2
7A.1-2
7A.1-2
7A.1-3
7A.1-3
7A.1-3
7A.1-3
7A.1-3
7A.1-3
7A.1-4
ELECTRIC POWER
1-lxxix
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TABLE OF CONTENTS
Section
8.1
Title
INTRODUCTION
8.1.1
8.1.2
8.1.3
8.1.4
8.1.5
8.1.5.1
8.1.5.2
8.1.5.3
Utility Grid and Interconnections
Plant Electrical Power System
Safety-Related Loads
Design Bases
Design Criteria and Standards
Design Criteria
Other Standards and Guides
Compliance to Regulatory Guides and IEEE Standards
8.2
Page
8.1-1
8.1-1
8.1-1
8.1-2
8.1-2
8.1-4
8.1-4
8.1-4
8.1-8
8.2-1
8.2.1
Description
8.2-1
8.2.1.1
Preferred Power Supply
8.2-1
8.2.1.2
Transmission Lines, Switchyard, and Transformers
8.2-3
8.2.1.3
Arrangement of the Start Boards, Unit Boards, Common Boards, and Reactor
Coolant Pump (RCP) Boards
8.2-4
8.2.1.4
Arrangement of Electrical Control Area (Nuclear Plant)
8.2-5
8.2.1.5
Switchyard Control and Relaying
8.2-5
8.2.1.6
6.9kV Start Boards Control and Relaying
8.2-8
8.2.1.7
6.9kV Unit and RCP Board Control and Relaying
8.2-10
8.2.1.8
Conformance with Standards
8.2-11
8.2.2
Analysis
8.2-18
8.3
ONSITE (STANDBY) POWER SYSTEM
8.3.1
8.3.1.1
8.3.1.2
8.3.1.2.1
8.3.1.2.2
8.3.1.2.3
8.3.1.3
8.3-36
8.3.1.4
8.3.1.4.1
8.3.1.4.2
8.3.1.4.3
8.3.1.4.4
8.3.1.4.5
8.3.1.4.6
8.3.1.4.7
1-lxxx
8.3-1
AC Power System
8.3-1
Description
8.3-1
Analysis
8.3-26
Standby AC Power Systems
8.3-26
Analysis of Vital 120V AC Control Power Systems AC Distribution
Boards and Inverters
8.3-29
Safety-Related Equipment in a LOCA Environment
8.3-32
Physical Identification of Safety-Related Equipment in AC Power Systems
Independence of Redundant ac Power Systems
8.3-37
Cable Derating and Raceway Fill
8.3-38
Cable Routing and Separation Criteria
8.3-38
Sharing of Cable Trays and Routing of Non-Safety Related Cables8.3-46
Fire Detection and Protection in Areas Where Cables are Installed 8.3-50
Cable and Cable Tray Markings
8.3-51
Spacing of Power and Control Wiring and Components Comprising the
Class 1E Electrical Systems in Control Boards, Panels, and Relay Racks
8.3-52
Fire Barriers and Separation Between Redundant Trays
8.3-53
Table of Contents
WATTS BAR
WBNP-76
TABLE OF CONTENTS
Section
8.3.2
8.3.2.1
8.3.2.1.1
8.3.2.1.2
8.3.2.2
8.3.2.3
66
8.3.2.4
8.3.3
Title
Page
DC Power System
8.3-53
Description
8.3-53
Vital 125V dc Control Power System
8.3-53
Non-Safety-Related DC Power Systems
8.3-60
Analysis of Vital 125V DC Control Power Supply System
8.3-61
Physical Identification of Safety-Related Equipment in dc Power Systems 8.3Independence of Redundant DC Power Systems
Fire Protection for Cable Systems
8.3-66
8.3-67
8A
Analysis of Submerged Electrical Equipment (During Post LOCA) Powered from
Auxiliary Power System
8-1
8B
Analysis of Submerged Electrical Equipment (During Post LOCA) Powered from Instrumentation and Control Power System
8-3
8C
Deleted by Amendment 75
8-5
8D
IEEE STD 387-1984 FOR DIESEL-GENERATING UNITS APPLIED AS STANDBY
POWER
8-6
8E
Probability/Reliability Analysis of Protection Device Schemes for Associated and
Non-Class 1E Cables
8-8
9.0
9.1
AUXILIARY SYSTEMS
FUEL STORAGE AND HANDLING
9.1.1
9.1.1.1
9.1.1.2
9.1.1.3
9.1.2
9.1.2.1
9.1.2.2
9.1.2.3
9.1.2.4
9.1.3
9.1.3.1
9.1.3.1.1
9.1.3.1.2
9.1.3.1.3
9.1.3.1.4
9.1.3.2
9.1.3.2.1
9.1.3.3
New Fuel Storage
Design Bases
Facilities Description
Safety Evaluation
SPENT FUEL STORAGE
Design Bases
Facilities Description
Safety Evaluation
Materials
Spent Fuel Pool Cooling and Cleanup System (SFPCCS)
Design Bases
Spent Fuel Pool Cooling
Spent Fuel Pool Dewatering Protection
Water Purification
Flood Mode Cooling
System Description
Component Description
Safety Evaluation
Table of Contents
9.1-1
9.1-1
9.1-1
9.1-1
9.1-1
9.1-2
9.1-2
9.1-2
9.1-3
9.1-4
9.1-4
9.1-4
9.1-4
9.1-5
9.1-5
9.1-5
9.1-5
9.1-7
9.1-8
1-lxxxi
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TABLE OF CONTENTS
Section
9.1.3.3.1
9.1.3.3.2
9.1.3.3.3
9.1.3.3.4
9.1.3.3.5
9.1.3.4
9.1.3.5
9.1.3.5.1
9.1.3.5.2
9.1.3.5.3
9.1.3.5.4
9.1.4
9.1.4.1
9.1.4.2
9.1.4.2.1
9.1.4.2.2
9.1.4.3
9.1.4.3.1
9.1.4.3.2
9.1.4.3.3
9.1.4.3.4
9.1.4.4
9.2
WATER SYSTEMS
9.2.1
9.2.1.1
9.2.1.2
9.2.1.3
9.2.1.4
9.2.1.5
9.2.1.5.1
9.2.1.5.2
9.2.1.5.3
9.2.1.5.4
9.2.1.5.5
9.2.1.5.6
9.2.1.6
9.2.1.7
9.2.2
9.2.2.1
9.2.2.2
9.2.2.3
9.2.2.3.1
9.2.2.3.2
1-lxxxii
Title
Availability and Reliability
Spent Fuel Pool Dewatering
Pool and Fuel Temperatures
Water Quality
Leakage Detection for the Spent Fuel Pool
Tests and Inspections
Instrument Application
Temperature
Pressure
Flow
Level
FUEL HANDLING SYSTEM
Design Bases
System Description
Refueling Procedure
Component Description
Design Evaluation
Safe Handling
Seismic Considerations
Containment Pressure Boundary Integrity
Radiation Shielding
Tests and Inspections
Essential Raw Cooling Water (ERCW)
Design Bases
System Description
Safety Evaluation
Tests and Inspections
Instrument Applications
General Description
Pressure Instrumentation
Flow Instrumentation
Temperature Instrumentation
Deleted by Amendment 87
Control Valves
Corrosion, Organic Fouling, and Environmental Qualification
Design Codes
Component Cooling System (CCS)
Design Bases
System Description
Components
Component Cooling Heat Exchangers
Component Cooling Pumps
Page
9.1-8
9.1-9
9.1-9
9.1-11
9.1-11
9.1-11
9.1-11
9.1-11
9.1-12
9.1-12
9.1-12
9.1-12
9.1-12
9.1-13
9.1-14
9.1-17
9.1-20
9.1-20
9.1-25
9.1-25
9.1-25
9.1-25
9.2-1
9.2-1
9.2-1
9.2-1
9.2-4
9.2-7
9.2-7
9.2-7
9.2-8
9.2-8
9.2-8
9.2-9
9.2-9
9.2-9
9.2-10
9.2-11
9.2-11
9.2-12
9.2-15
9.2-16
9.2-16
Table of Contents
WATTS BAR
WBNP-76
TABLE OF CONTENTS
Section
9.2.2.3.3
9.2.2.3.4
9.2.2.3.5
9.2.2.3.6
9.2.2.3.7
9.2.2.4
9.2.2.5
9.2.2.6
9.2.2.7
9.2.2.7.1
9.2.2.7.2
9.2.2.7.3
9.2.2.7.4
9.2.2.7.5
9.2.2.7.6
9.2.2.7.7
9.2.2.8
9.2.2.9
9.2.2.10
9.2.3
9.2.3.1
9.2.3.2
9.2.3.3
9.2.3.4
9.2.3.5
9.2.4
9.2.4.1
9.2.4.1.1
9.2.4.1.2
9.2.4.1.3
9.2.4.1.4
9.2.4.2
9.2.4.2.1
9.2.4.2.2
9.2.4.2.3
9.2.4.2.4
9.2.4.2.5
9.2.5
9.2.5.1
9.2.5.2
9.2.5.3
9.2.5.4
9.2.6
9.2.6.1
Title
Thermal Barrier Booster Pumps
Component Cooling Surge Tanks
Seal Leakage Return Unit
Valves
Piping
Safety Evaluation
Leakage Provisions
Incidental Control
Instrument Applications
General Description
Flow Instrumentation
Level Instrumentation
Pressure Instrumentation
Temperature Instrumentation
Valves
Conclusion
Malfunction Analysis
Tests and Inspections - Historical Information
Codes and Classification
Demineralized Water Makeup System
Design Bases
System Description
Safety Evaluation
Test and Inspection
Instrumentation Applications
Potable and Sanitary Water Systems
Potable Water System
System Description
Safety Evaluation
Tests and Inspections
Instrumentation Applications
Sanitary Water System
Design Bases
System Description
Safety Evaluation
Tests And Inspections
Instrumentation Applications
Ultimate Heat Sink
General Description
Design Bases
Safety Evaluation
Instrumentation Application
Condensate Storage Facilities
Design Bases
Table of Contents
Page
9.2-16
9.2-16
9.2-16
9.2-17
9.2-18
9.2-18
9.2-19
9.2-19
9.2-20
9.2-20
9.2-20
9.2-20
9.2-21
9.2-21
9.2-21
9.2-21
9.2-21
9.2-22
9.2-22
9.2-22
9.2-22
9.2-23
9.2-23
9.2-24
9.2-24
9.2-24
9.2-24
9.2-24
9.2-25
9.2-25
9.2-25
9.2-25
9.2-25
9.2-26
9.2-27
9.2-28
9.2-28
9.2-28
9.2-28
9.2-29
9.2-30
9.2-31
9.2-31
9.2-32
1-lxxxiii
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WBNP-76
TABLE OF CONTENTS
Section
9.2.6.2
9.2.6.3
9.2.6.4
9.2.6.5
9.2.7
9.2.7.1
9.2.8
9.2.8.1
9.2.8.2
9.2.8.3
9.2.8.4
9.3
Title
System Description
Safety Evaluation
Test and Inspections
Instrument Applications
Refueling Water Storage Tank
ECCS Pumps Net Positive Suction Head (NPSH)
Raw Cooling Water System
Design Bases
System Description
Safety Evaluation
Tests and Inspection
PROCESS AUXILIARIES
Page
9.2-32
9.2-33
9.2-33
9.2-34
9.2-34
9.2-36
9.2-37
9.2-37
9.2-38
9.2-40
9.2-41
9.3-1
9.3.1
Compressed Air System
9.3-1
9.3.1.1
Design Basis
9.3-1
9.3.1.2
System Description
9.3-1
9.3.1.3
Safety Evaluation
9.3-2
9.3.1.4
Tests and Inspections
9.3-5
9.3.1.5
Instrumentation Applications
9.3-5
9.3.2
Process Sampling System
9.3-5
9.3.2.1
Design Basis
9.3-5
9.3.2.2
System Description
9.3-5
9.3.2.3
Safety Evaluation
9.3-8
9.3.2.4
Tests and Inspections
9.3-8
9.3.2.5
Instrumentation Applications
9.3-8
9.3.2.6
Postaccident Sampling Subsystem - (Unit 1 Only)
9.3-8
9.3.2.6.1
System Description
9.3-9
9.3.2.6.2
Postaccident Sampling Facility
9.3-9
9.3.2.6.3
Sampling Equipment
9.3-9
Liquid Sampling Panel 10
Chemical Analysis Panel 10
Containment Air Sampling Panel (CASP) 10
HRSS Control Panels 11
9.3.2.6.4
Sample Points
9.3-11
9.3.2.6.5
Postaccident Counting Facilities
9.3-11
9.3.2.6.6
Piping, Tubing, and Valves
9.3-11
9.3.2.6.7
Safety Evaluation
9.3-12
9.3.2.6.8
Tests and Inspections
9.3-12
9.3.3
Equipment and Floor Drainage System
9.3-12
9.3.3.1
Design Bases
9.3-12
9.3.3.2
System Design
9.3-12
9.3.3.2.1
Drains from Lowest Floor Level in the Auxiliary Building
9.3-13
9.3.3.2.2
Residual Heat Removal Pump (RHR) and Containment Spray Pump
(CSP) Compartments
9.3-13
1-lxxxiv
Table of Contents
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WBNP-76
TABLE OF CONTENTS
Section
9.3.3.2.3
9.3.3.2.4
9.3.3.2.5
9.3.3.3
9.3.3.4
9.3.3.5
9.3.3.6
9.3.3.7
9.3.4
9.3.4.1
9.3.4.2
9.3.4.2.1
9.3.4.2.2
9.3.4.3
9.3.4.4
9.3.4.5
9.3.5
9.3.6
9.3.6.1
9.3.6.2
9.3.6.3
9.3.6.4
9.3.6.5
9.3.7
9.3.8
9.4
Title
Page
CVCS Holdup Tank Compartment and Tritiated Drain Collector Tank
Room
9.3-14
Volume Control Tanks
9.3-14
Boric Acid Tanks
9.3-14
Drains - Reactor Building
9.3-15
Design Evaluation
9.3-15
Tests and Inspections
9.3-15
Instrumentation Application
9.3-15
Drain List
9.3-15
Chemical and Volume Control System
9.3-16
Design Bases
9.3-16
System Description
9.3-17
Component Description
9.3-23
System Operation
9.3-33
Safety Evaluation
9.3-36
Tests and Inspections
9.3-38
Instrumentation Application
9.3-38
Failed Fuel Detection System
9.3-39
Auxiliary Charging System
9.3-39
Design Bases
9.3-39
System Design Description
9.3-40
Design Evaluation
9.3-41
Tests and Inspection
9.3-41
Instrument Application
9.3-41
Boron Recycle System
9.3-42
Heat Tracing
9.3-42
AIR CONDITIONING, HEATING, COOLING, AND VENTILATION SYSTEMS
9.4.1
9.4.1.1
9.4.1.2
9.4.1.3
9.4.1.4
9.4.2
9.4.2.1
9.4.2.2
9.4.2.3
9.4.2.4
9.4.3
9.4.3.1
9.4.3.2
9.4.3.2.1
9.4.3.2.2
9.4.3.2.3
Control Room Area Ventilation System
Design Bases
System Description
Safety Evaluation
Tests and Inspection
Fuel Handling Area Ventilation System
Design Bases
System Description
Safety Evaluation
Inspection and Testing
Auxiliary Building and Radwaste Area Ventilation System
Design Bases
System Description
Building Air Supply and Exhaust Systems (General Ventilation)
Building Cooling System (Chilled Water)
Safety Feature Equipment Coolers
Table of Contents
9.4-1
9.4-1
9.4-1
9.4-3
9.4-7
9.4-8
9.4-9
9.4-9
9.4-10
9.4-10
9.4-12
9.4-12
9.4-12
9.4-13
9.4-14
9.4-15
9.4-15
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TABLE OF CONTENTS
Section
9.4.3.2.4
9.4.3.2.5
9.4.3.2.6
9.4.3.2.7
Title
Page
Shutdown Board Room Air-Conditioning System
9.4-15
Auxiliary Board Rooms Air-Conditioning Systems
9.4-16
Shutdown Transformer Room Ventilating Systems
9.4-17
Auxiliary Building Miscellaneous Ventilation and Air Conditioning Systems
9.4-18
9.4.3.3
Safety Evaluation
9.4-18
9.4.3.3.1
Auxiliary Building General Ventilation System
9.4-18
9.4.3.3.2
Building Cooling System
9.4-20
9.4.3.3.3
Safety Feature Equipment Coolers
9.4-20
9.4.3.3.4
Shutdown Board Room Air-Conditioning System
9.4-20
9.4.3.3.5
Auxiliary Board Rooms Air-Conditioning System
9.4-20
9.4.3.3.6
Shutdown Transformer Room Ventilating System
9.4-22
9.4.3.3.7
Auxiliary Building Miscellaneous Ventilation and Air-Conditioning System
9.4-22
9.4.3.4
Inspection and Testing Requirements
9.4-23
9.4.4
Turbine Building Area Ventilation System
9.4-23
9.4.4.1
Design Bases
9.4-23
9.4.4.2
System Description
9.4-23
9.4.4.2.1
Elevation 755.0 Ventilation
9.4-24
9.4.4.2.2
Elevation 729.0 and Elevation 708.0 Ventilation
9.4-24
9.4.4.2.3
El. 685.5 Ventilation
9.4-24
9.4.4.2.4
Cold Weather Building Pressurization
9.4-24
9.4.4.2.5
Miscellaneous Ventilating Systems
9.4-24
9.4.4.2.6
Coolers
9.4-25
Space Coolers 25
Pump Coolers 25
9.4.4.2.7
Building Heating System
9.4-25
9.4.4.3
Safety Evaluation
9.4-26
9.4.4.4
Inspection and Testing Requirements
9.4-26
9.4.5
Engineered Safety Feature Ventilation Systems
9.4-26
9.4.5.1
ERCW Intake Pumping Station (IPS)
9.4-26
9.4.5.1.1
Design Bases
9.4-26
9.4.5.1.2
System Description
9.4-27
9.4.5.1.3
Safety Evaluation
9.4-28
9.4.5.1.4
Inspection and Testing Requirements
9.4-28
9.4.5.2
Diesel Generator Buildings
9.4-28
9.4.5.2.1
Diesel Generator Building
9.4-28
Design Bases 28
System Description 30
Safety Evaluation 31
Tests and Inspections 33
9.4.5.3
Auxiliary Building Engineered Safety Features (ESF) Equipment Coolers 9.433
9.4.5.3.1
Design Bases
9.4-33
1-lxxxvi
Table of Contents
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WBNP-76
TABLE OF CONTENTS
Section
9.4.5.3.2
9.4.5.3.3
9.4.5.3.4
9.4.6
9.4.6.1
9.4.6.2
9.4.6.3
9.4.6.4
9.4.7
9.4.7.1
9.4.7.2
9.4.7.2.1
9.4.7.2.2
9.4.7.2.3
9.4.7.2.4
9.4.7.2.5
9.4.7.3
9.4.7.4
9.4.8
tem
9.4.9
9.5
9.5.1
9.5.1.1
9.5.1.2
9.5.1.3
9.5.1.4
9.5.1.5
9.5.2
9.5.2.1
9.5.2.2
9.5.2.3
9.5.2.4
9.5.2.5
9.5.3
9.5.3.1
9.5.3.2
9.5.3.3
9.5.3.4
9.5.3.5
9.5.4
9.5.4.1
9.5.4.2
Title
Page
System Description
9.4-34
Safety Evaluation
9.4-35
Inspection and Testing Requirements
9.4-37
Reactor Building Purge Ventilating System (RBPVS)
9.4-37
Design Bases
9.4-37
System Description
9.4-40
Safety Evaluation
9.4-41
Inspection and Testing Requirements
9.4-43
Containment Air Cooling System
9.4-43
Design Bases
9.4-43
System Description
9.4-45
Lower Compartment Air Cooling System
9.4-45
Control Rod Drive Mechanisms Air Cooling System
9.4-45
Upper Compartment Air Cooling System
9.4-46
Reactor Building Instrument Room Air Cooling System
9.4-46
Controls and Instrumentation
9.4-46
Safety Evaluation
9.4-47
Test and Inspection Requirements
9.4-47
Condensate Demineralizer Waste Evaporator Building Environmental Control Sys9.4-48
Postaccident Sampling Facility (PASF) Environmental Control System
9.4-48
OTHER AUXILIARY SYSTEMS
Fire Protection System
Deleted by Amendment 87
Deleted by Amendment 87
Deleted by Amendment 87
Deleted by Amendment 87
Deleted by Amendment 87
Plant Communications System
Design Bases
General Description Intraplant Communications
General Description Interplant System
Evaluation
Inspection and Tests
Lighting Systems
Design Bases
Description of the Plant Lighting System
Diesel Generator Building Lighting System
Safety Related Functions of the Lighting Systems
Inspection and Testing Requirements
Diesel Generator Fuel Oil Storage and Transfer System
Design Basis
System Description
Table of Contents
9.5-1
9.5-1
9.5-1
9.5-1
9.5-1
9.5-1
9.5-1
9.5-1
9.5-1
9.5-1
9.5-4
9.5-5
9.5-7
9.5-8
9.5-8
9.5-8
9.5-9
9.5-10
9.5-10
9.5-10
9.5-10
9.5-11
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TABLE OF CONTENTS
Section
9.5.4.3
9.5.4.4
9.5.5
9.5.5.1
9.5.5.2
9.5.5.3
9.5.5.4
9.5.6
9.5.6.1
9.5.6.2
9.5.6.3
9.5.6.4
9.5.7
9.5.7.1
9.5.7.2
9.5.7.3
9.5.7.4
9.5.8
9.5.8.1
9.5.8.2
9.5.8.3
9.5.8.4
10.0
Title
Safety Evaluation
Tests and Inspections
Diesel Generator Cooling Water System
Design Bases
System Description
Safety Evaluation
Tests and Inspections
Diesel Generator Starting System
Design Bases
System Description
Safety Evaluation
Tests and Inspections
Diesel Engine Lubrication System
Design Bases
System Description
Safety Evaluation
Test and Inspections
Diesel Generator Combustion Air Intake and Exhaust System
Design Bases
System Descriptions
Safety Evaluation
Tests and Inspection
Page
9.5-14
9.5-15
9.5-15
9.5-15
9.5-15
9.5-16
9.5-16
9.5-17
9.5-17
9.5-17
9.5-18
9.5-18
9.5-18
9.5-18
9.5-19
9.5-20
9.5-21
9.5-21
9.5-21
9.5-21
9.5-22
9.5-22
MAIN STEAM AND POWER CONVERSION SYSTEMS
10.1
SUMMARY DESCRIPTION
10.1-1
10.2
TURBINE-GENERATOR
10.2-1
10.2.1
10.2.2
10.2.3
10.2.3.1
10.2.3.2
10.2.3.3
10.2.3.4
10.2.3.5
10.2.3.5.1
10.2.3.5.2
10.2.3.5.3
10.2.3.6
10.2.3.6.1
10.2.3.6.2
10.2.3.6.3
10.2.4
1-lxxxviii
Design Bases
Description
Turbine Rotor and Disc Integrity
Materials Selection
Fracture Toughness
High Temperature Properties
Turbine Disc Design
Preservice Inspection
Low Pressure Turbine Rotor
High Pressure Turbine Rotor
Preoperational and Initial Startup Testing
Inservice Inspection
Turbine Rotors
Turbine Overspeed Protection
Other Turbine Protection Features
Evaluation
10.2-1
10.2-1
10.2-5
10.2-5
10.2-8
10.2-9
10.2-10
10.2-10
10.2-10
10.2-11
10.2-11
10.2-11
10.2-11
10.2-12
10.2-13
10.2-13
Table of Contents
WATTS BAR
WBNP-76
TABLE OF CONTENTS
Section
10.3
MAIN STEAM SUPPLY SYSTEM
10.3.1
10.3.2
10.3.2.1
10.3.2.2
10.3.3
10.3.4
10.3.5
10.3.5.1
10.3.5.2
10.3.5.3
10.3.5.4
10.3-5
10.3.6
10.3.6.1
10.3.6.2
10.4
Title
10.3-1
Design Bases
10.3-1
System Description
10.3-1
System Design
10.3-1
Material Compatibility, Codes, and Standards
10.3-2
Design Evaluation
10.3-2
Inspection and Testing Requirements
10.3-3
Water Chemistry
10.3-4
Purpose
10.3-4
Feedwater Chemistry Specifications
10.3-4
Operating Modes
10.3-4
Effect of Water Chemistry on the Radioactive Iodine Partition Coefficient
Steam and Feedwater System Materials
Fracture Toughness
Materials Selection and Fabrication
OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM
10.4.1
10.4.1.1
10.4.1.2
10.4.1.3
10.4.1.4
10.4.1.5
10.4.2
10.4.2.1
10.4.2.2
10.4.2.3
10.4.2.4
10.4.2.5
10.4.3
10.4.3.1
10.4.3.2
10.4.3.3
10.4.3.4
10.4.3.5
10.4.4
10.4.4.1
10.4.4.2
10.4.4.3
10.4.4.4
10.4.4.5
10.4.5
Page
Main Condenser
Design Bases
System Description
Safety Evaluation
Inspection and Testing
Instrumentation
Main Condenser Evacuation System
Design Bases
System Description
Safety Evaluation
Inspection and Testing
Instrumentation
Turbine Gland Sealing System
Design Bases
System Description
Safety Evaluation
Inspection and Testing
Instrumentation
Turbine Bypass System
Design Bases
System Description
Safety Evaluation
Inspection and Testing
Instrumentation
Condenser Circulating Water System
Table of Contents
10.3-5
10.3-5
10.3-6
10.4-1
10.4-1
10.4-1
10.4-1
10.4-4
10.4-5
10.4-5
10.4-5
10.4-5
10.4-5
10.4-6
10.4-6
10.4-6
10.4-7
10.4-7
10.4-7
10.4-7
10.4-8
10.4-8
10.4-8
10.4-8
10.4-9
10.4-9
10.4-10
10.4-11
10.4-11
1-lxxxix
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TABLE OF CONTENTS
Section
10.4.5.1
10.4.5.2
10.4.5.3
10.4.5.4
10.4.5.5
10.4.6
10.4.6.1
10.4.6.2
10.4.6.3
10.4.6.4
10.4.6.5
10.4.7
10.4.7.1
10.4.7.2
10.4.7.3
10.4.7.4
10.4.7.5
10.4.8
10.4.8.1
10.4.8.2
10.4.8.3
10.4.8.4
10.4.9
10.4.9.1
10.4.9.2
10.4.9.3
10.4.9.4
10.4.9.5
11.0
11.1
11.2.1
1-xc
Page
10.4-11
10.4-11
10.4-14
10.4-14
10.4-14
10.4-15
10.4-15
10.4-16
10.4-17
10.4-18
10.4-18
10.4-19
10.4-19
10.4-19
10.4-27
10.4-29
10.4-29
10.4-29
10.4-29
10.4-30
10.4-31
10.4-32
10.4-32
10.4-32
10.4-33
10.4-34
10.4-37
10.4-38
Design Basis
System Description
Safety Evaluation
Inspection and Testing
Instrumentation Application
Condensate Polishing Demineralizer System
Design Bases - Power Conversion
System Description
Safety Evaluation
Inspection and Testing
Instrumentation
Condensate and Feedwater Systems
Design Bases
System Description
Safety Evaluation
Inspection and Testing
Instrumentation
Steam Generator Blowdown System
Design Bases
System Description and Operation
Safety Evaluation
Inspections and Testing
Auxiliary Feedwater System
Design Bases
System Description
Safety Evaluation
Inspection and Testing Requirements
Instrumentation Requirements
RADIOACTIVE WASTE MANAGEMENT
SOURCE TERMS
11.1.1
11.1.1.1
11.1.1.2
11.1.1.3
11.1.1.4
11.1.1.5
11.1.2
11.1.3
11.1.4
11.2
Title
11.1-1
Historical Design Model for Radioactivities in Systems and Components
Reactor Coolant Historical Design Activity
Volume Control Tank Historical Design Activity
Pressurizer Historical Design Activity
Gaseous Waste Processing System Historical Design Activities
Secondary Coolant Historical Design Activities
Realistic Model for Radioactivities in Systems and Components
Plant Leakage
Additional Sources
LIQUID WASTE SYSTEMS
DESIGN OBJECTIVES
11.1-1
11.1-1
11.1-2
11.1-2
11.1-2
11.1-2
11.1-2
11.1-3
11.1-3
11.2-1
11.2-1
Table of Contents
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WBNP-76
TABLE OF CONTENTS
Section
Title
Page
11.2.2
SYSTEMS DESCRIPTIONS
11.2-1
11.2.3
SYSTEM DESIGN
11.2-4
11.2.3.1
Component Design
11.2-4
11.2.3.2
Instrumentation Design
11.2-9
11.2.4
Operating Procedure
11.2-10
11.2.5
PERFORMANCE TESTS
11.2-16
11.2.6
ESTIMATED RELEASES
11.2-17
11.2.6.1
NRC Requirements
11.2-17
11.2.6.2
Westinghouse PWR Release Experience
11.2-17
11.2.6.3
Expected Liquid Waste Processing System Releases
11.2-17
11.2.6.4
Turbine Building (TB) Drains
11.2-17
11.2.6.4.1
Purpose
11.2-17
11.2.6.4.2
Description
11.2-17
Condensate Polishing Demineralizer System Drains 18
Other Turbine Building Drainage 18
Oil and Oily Water Drainage 18
11.2.6.5
Estimated Total Liquid Releases
11.2-18
11.2.7
RELEASE POINTS
11.2-18
11.2.8
DILUTION FACTORS
11.2-19
11.2.9
ESTIMATED DOSES FROM RADIONUCLIDES IN LIQUID EFFLUENTS 11.219
11.2.9.1
Assumptions and Calculational Methods
11.2-19
11.2.9.2
Summary of Dose from Radionuclides in Liquid Effluents
11.2-21
11.3
GASEOUS WASTE SYSTEMS
11.3.1
11.3.2
11.3.3
11.3.3.1
11.3.3.2
11.3.4
11.3.5
11.3.6
11.3.7
11.3.7.1
11.3.7.2
11.3.7.3
11.3.7.4
11.3.7.5
11.3.8
11.3.9
11.3.10
11.3.10.1
11.3.10.2
Design Bases
SYSTEM DESCRIPTIONS
SYSTEM DESIGN
Component Design
Instrumentation Design
Operating Procedure
Performance Tests
Deleted by Amendment 77
Radioactive Releases
NRC Requirements
Westinghouse PWR Experience Releases
Expected Gaseous Waste Processing System Releases
Releases from Ventilation Systems
Estimated Total Releases
Release Points
Atmospheric Dilution
Estimated Doses from Radionuclides in Gaseous Effluents
Assumptions and Calculational Methods
Summary of Annual Population Doses
Table of Contents
11.3-1
11.3-1
11.3-1
11.3-3
11.3-3
11.3-3
11.3-4
11.3-6
11.3-6
11.3-6
11.3-6
11.3-6
11.3-7
11.3-7
11.3-7
11.3-7
11.3-9
11.3-9
11.3-9
11.3-12
1-xci
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TABLE OF CONTENTS
Section
11.4
TEM
Design Objectives
System Inputs
Systems Description
Wet Active Waste Handling
Dry Active Waste Handling
Miscellaneous Waste Handling
Equipment Operation
Mobile Solidification System (MSS)
Storage Facilities
Inplant Storage Area
Outside Radwaste Storage
Shipment
Offsite Radiological Monitoring Program
11.6.1
11.6.2
11.6.2.1
11.6.2.2
11.6.3
11.6.4
11.6.5
1-xcii
Design Objectives
Continuous Monitors
Liquid Monitors
Waste Disposal System Liquid Effluent Monitor
Essential Raw Cooling Water Effluent Monitors
Component Cooling System Liquid Effluent Monitors
Steam Generator Blowdown Effluent Monitor
Condensate Demineralizer Regenerant Effluent Monitor
Turbine Building Sump Effluent Monitor
Gaseous Monitors
Waste Gas Holdup System Effluent Monitor
Condenser Vacuum Air Exhaust Monitors
Spent Fuel Pool Accident Radiation Monitors
Ventilation Monitors and Containment Atmosphere Monitors
Main Control Room Air Intake Monitors
Containment Purge Air Exhaust Monitors
Main Steamline Radiation Monitors
SAMPLING
CALIBRATION AND MAINTENANCE
SOLID WASTE MANAGEMENT SYSTEM
11.5.1
11.5.2
11.5.3
11.5.3.1
11.5.3.2
11.5.3.3
11.5.4
11.5.4.1
11.5.5
11.5.5.1
11.5.5.2
11.5.6
11.6
Page
PROCESS AND EFFLUENT RADIOLOGICAL MONITORING AND SAMPLING SYS11.4-1
11.4.1
11.4.2
11.4.2.1
11.4.2.1.1
11.4.2.1.2
11.4.2.1.3
11.4.2.1.4
11.4.2.1.5
11.4.2.1.6
11.4.2.2
11.4.2.2.1
11.4.2.2.2
11.4.2.2.3
11.4.2.2.4
11.4.2.2.5
11.4.2.2.6
11.4.2.2.7
11.4.3
11.4.4
11.5
Title
Expected Background
Critical Pathways to Man
Doses from Gaseous Effluents
Internal Doses from Liquid Effluents
Sampling Media, Locations, and Frequency
Analytical Sensitivity
Data Analysis and Presentation
11.4-1
11.4-2
11.4-2
11.4-2
11.4-2
11.4-3
11.4-3
11.4-3
11.4-3
11.4-4
11.4-4
11.4-4
11.4-5
11.4-5
11.4-7
11.4-8
11.4-8
11.4-8
11.4-9
11.5-1
11.5-1
11.5-1
11.5-1
11.5-1
11.5-3
11.5-4
11.5-4
11.5-4
11.5-4
11.5-4
11.5-4
11.5-5
11.6-1
11.6-2
11.6-2
11.6-3
11.6-3
11.6-4
11.6-4
11.6-4
Table of Contents
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TABLE OF CONTENTS
Section
11.6.6
Title
Program Statistical Sensitivity
11A
Page
11.6-4
TRITIUM CONTROL
11A.1 SYSTEM SOURCES
11A.1-1
11A.1.1
11A.1.2
11A.1.3
11A.1.4
11A.1-1
11A.1-1
11A.1-1
11A.1-2
The Fission Source
Control Rod Source
Boric Acid Source
Burnable Shim Rod Source
11A.2 Tritium Releases
11A.1-2
11A.3 Design Bases
11A.1-2
11A.4 Design Evaluation
11A.1-2
11A.5 Tritium Lead Test Assembly (This section to be provided at a later date)
11A.1-3
11A.6 Tritium Producing Burnable Absorber Rod (TPBAR) Source (Unit 1 Only)
11A.1-3
12.0
RADIATION PROTECTION
12.1 Assuring that Occupational Radiation Exposures Are as Low as Reasonably
Achievable (ALARA)
12.1-1
12.1.1
12.1.2
12.1.3
12.2
Policy Considerations
Design Considerations
ALARA Operational Considerations
RADIATION SOURCES
12.2.1
12.2.1.1
12.2.1.1.1
12.2.1.1.2
12.2.1.2
12.2.1.2.1
12.2.1.2.2
12.2.1.2.3
12.2.1.2.4
12.2.1.2.5
12.2.1.2.6
12.2.1.2.7
12.2.1.2.8
12.1-1
12.1-1
12.1-1
12.2-3
Contained Sources
12.2-3
Primary System Sources
12.2-3
Sources Shielded by Primary Shield Concrete
12.2-3
Sources Shielded by Secondary Shield Concrete
12.2-4
Auxiliary Systems Sources
12.2-4
Chemical and Volume Control System - Mixed-Bed Demineralizers
12.2-4
Chemical and Volume Control System - Cation Bed Demineralizer 12.24
Chemical and Volume Control System - Volume Control Tanks 12.2-5
Chemical and Volume Control System - Reactor Coolant Filter 12.2-5
Chemical and Volume Control System - Seal Water Return Filter 12.2-5
Chemical and Volume Control System - Seal Water Injection Filters
12.2-6
Chemical and Volume Control System - Holdup Tanks
12.2-6
Chemical and Volume Control System - Evaporator Feed Mixed-Bed Ion
Table of Contents
1-xciii
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TABLE OF CONTENTS
Section
Page
Exchangers
12.2-6
12.2.1.2.9
Chemical and Volume Control System - Evaporator Feed Cation Bed Ion
Exchanger
12.2-7
12.2.1.2.10
Chemical and Volume Control System - Ion Exchange Filters
12.2-7
12.2.1.2.11
Gas Stripper and Boric Acid Evaporator Package
12.2-7
12.2.1.2.12
Spent Fuel Pool Cooling System Demineralizer and Filters
12.2-8
12.2.1.3
Sources During Refueling
12.2-10
12.2.1.4
Maximum Hypothetical Accident (MHA) Sources
12.2-10
12.2.1.5
Condensate Demineralizer Waste Evaporator
12.2-11
12.2.2
Airborne Radioactive Material Sources
12.2-11
12.3
Title
RADIATION PROTECTION DESIGN FEATURES
12.3-1
12.3.1
Facility Design Features
12.3.2
Shielding
12.3.2.1
Design Objectives
12.3.2.2
Design Description
12.3.3
Ventilation
12.3.3.1
Airflow Control
12.3.3.2
Typical System
12.3.3.3
Additional Radiation Controls
12.3.4
Area Radiation and Airborne Radioactivity Monitoring Instrumentation
12.3.4.1
Area Radiation Monitoring Instrumentation
12.3.4.1.1
Objectives and Design Basis
12.3.4.1.2
Operation Characteristics
Area Monitor Detector 18
Main Control Room Ratemeter (0-M-12, 1-,2-M-30) 18
Local Indicator-Alarm Panel 19
Multipoint Recorders (Main Control Room 0-M-12, 1-,2-M-31) 19
Monitor Sensitivity and Range 19
12.3.4.1.3
Area Monitor Calibration and Maintenance
12.3.4.2
Airborne Particulate Radioactivity Monitoring
12.3.4.2.1
Design Basis
12.3.4.2.2
Airborne Monitoring Channels
12.3.4.2.3
Operational Characteristics
12.3.4.2.4
Component Descriptions
12.3.4.2.5
Sensitivity, Range and Set Point
12.3.4.3
Deleted by Amendment 84.
12.3.4.4
Special Radiation Monitors
12.3.4.4.1
Portal Monitors
12.3.4.4.2
Personnel Contamination Monitors
12.3.4.4.3
Deleted by Amendment 84.
12.4
1-xciv
DOSE ASSESSMENT
12.3-1
12.3-3
12.3-3
12.3-3
12.3-15
12.3-16
12.3-16
12.3-17
12.3-17
12.3-17
12.3-17
12.3-18
12.3-19
12.3-20
12.3-20
12.3-20
12.3-21
12.3-21
12.3-22
12.3-22
12.3-22
12.3-22
12.3-22
12.3-22
12.4-1
Table of Contents
WATTS BAR
WBNP-76
TABLE OF CONTENTS
Section
12.5
Title
RADIATION PROTECTION PROGRAM
12.5.1
12.5.2
12.5.3
Organization
Equipment, Instrumentation, and Facilities
Procedures
13.0
13.1
12.5-1
12.5-1
12.5-2
12.5-4
CONDUCT OF OPERATIONS
ORGANIZATIONAL STRUCTURE OF APPLICANT
13.1.1
13.1.1.1
13.1.2
13.1.2.1
13.1.2.2
13.1.3
13.2
Page
Corporate Organization
Design Responsibilities
Nuclear Power
Offsite Organizations
Onsite Organization
Qualification Requirements for Nuclear Facility Personnel
TRAINING PROGRAMS
13.2.1
13.2.2
13.2.3
Accredited Training Programs
General Employee and Fitness for Duty Training Programs
Other Training Programs
13.1-1
13.1-1
13.1-1
13.1-2
13.1-2
13.1-2
13.1-2
13.2-1
13.2-1
13.2-1
13.2-2
13.3
Emergency Planning
13.3-1
13.4
REVIEW AND AUDIT
13.4-1
13.4.1
13.4.2
13.5
Onsite Review
Independent Review and Audit
SITE PROCEDURES
13.5.1
13.5.1.1
13.5.1.2
13.5.1.3
13.5.2
13.5.2.1
13.5.2.1.1
13.5.2.1.2
13.5.2.1.3
13.5.2.1.4
13.5.2.1.5
13.5.2.1.6
13.5.2.2
13.5.2.2.1
13.5.2.2.2
13.5.2.2.3
13.5.2.2.4
13.5.2.2.5
SYSTEM OF SITE PROCEDURES
Conformance with Regulatory Guide 1.33
Preparation of Procedures
Administrative Procedures
Operating and Maintenance Procedures
Operating Procedures
General Operating Instructions
System Operating Instructions
Abnormal Operating Instructions
Emergency Instructions
Alarm Response Instructions
Fuel Handling Instructions
Other Procedures
Maintenance Instructions and Modification Procedures
Instrument Maintenance Instructions
Surveillance Instructions and Technical Requirement Instructions
Technical Instructions
Miscellaneous Procedures
Table of Contents
13.4-1
13.4-1
13.5-1
13.5-1
13.5-1
13.5-1
13.5-2
13.5-2
13.5-2
13.5-2
13.5-2
13.5-3
13.5-3
13.5-3
13.5-3
13.5-3
13.5-3
13.5-3
13.5-4
13.5-4
13.5-4
1-xcv
WATTS BAR
WBNP-76
TABLE OF CONTENTS
Section
13.5.2.2.6
13.6
PLANT RECORDS
13.6.1
13.6.2
13.6.3
13.7
Title
Power Escalation Tests
13.6-1
Plant History
Operating Records
Event Records
13.6-1
13.6-1
13.6-1
NUCLEAR SECURITY
13.7.1
13.7.2
13.7.3
13.7-1
Physical Security and Contingency Plan
Personnel and Program Evaluation
Physical Security of TPBARs
14.0
Page
13.5-4
13.7-1
13.7-1
13.7-1
INITIAL TEST PROGRAM
14.1 SPECIFIC INFORMATION TO BE INCLUDED IN PRELIMINARY SAFETY ANALYSIS
REPORT
14.1-1
14.2
TEST PROGRAM
14.2.1
14.2.2
14.2.2.1
14.2.2.1.1
14.2.2.1.2
14.2.2.1.3
14.2.2.2
14.2.2.2.1
14.2.2.2.2
14.2.2.2.3
14.2.2.2.4
14.2.2.3
14.2.2.4
14.2.2.4.1
14.2.2.4.2
14.2.2.4.3
14.2.2.5
14.2.2.5.1
14.2.2.6
14.2.2.6.1
14.2.2.7
14.2.3
14.2.3.1
14.2.3.2
14.2.3.3
14.2.3.4
14.2.3.5
1-xcvi
Summary of Test Program and Objectives
Organization and Staffing
PSE
Preoperational Startup Manager
Section deleted by Amendment 84
System Test Engineers
Plant Operating Organization
Power Ascension Test Manager
Power Ascension Test Engineers
Operations
Maintenance Manager (under VP, Unit 2)
Nuclear Assurance
Major Participating Organizations
Nuclear Engineering
Construction
Westinghouse Electric Corporation
Joint Test Group
JTG Membership
Test Review Group
TRG Membership
Personnel Qualifications
Test Procedures and Instructions
General
Development of Procedures
Review and Approval of Test Procedures and Instruction
Format of Test Instructions/Procedures
Test Instruction/Procedure Revisions/Changes
14.2-1
14.2-1
14.2-3
14.2-3
14.2-3
14.2-4
14.2-4
14.2-5
14.2-5
14.2-5
14.2-6
14.2-6
14.2-6
14.2-6
14.2-6
14.2-7
14.2-7
14.2-7
14.2-8
14.2-8
14.2-8
14.2-9
14.2-9
14.2-9
14.2-10
14.2-10
14.2-10
14.2-11
Table of Contents
WATTS BAR
WBNP-76
TABLE OF CONTENTS
Section
Title
Page
14.2.4
Conduct of Test Program
14.2-12
14.2.4.1
Administrative Procedures
14.2-12
14.2.4.2
Component Testing
14.2-12
14.2.4.3
Preoperational and Acceptance Testing
14.2-13
14.2.4.4
Power Ascension Testing
14.2-13
14.2.4.5
Test Prerequisites
14.2-13
14.2.4.6
Phase Evaluation
14.2-13
14.2.4.7
Design Modifications
14.2-14
14.2.5
Review, Evaluation, and Approval of Test Results
14.2-14
14.2.6
Test Records
14.2-14
14.2.7
Conformance of Test Programs with Regulatory Guides
14.2-15
14.2.8
Utilization of Reactor Operating and Testing Experience in Development of Test Program
14.2-29
14.2.9
Trial Use of Plant Operating and Emergency Procedures
14.2-29
14.2.10
Initial Fuel Loading, Postloading Tests, Initial Criticality, Low Power Tests and Power Ascension
14.2-30
14.2.10.1
Fuel Loading
14.2-30
14.2.10.2
Postloading Tests
14.2-32
14.2.10.3
Initial Criticality
14.2-32
14.2.10.4
Low Power Tests
14.2-33
14.2.10.5
Power Ascension
14.2-33
14.2.11
Test Program Schedule
14.2-34
14.2.12
Individual Test Descriptions
14.2-35
14.2.12.1
Preoperational Tests
14.2-35
14.2.12.2
Power Ascension Tests
14.2-35
15.0
15.1
ACCIDENT ANALYSES
CONDITION I - NORMAL OPERATION AND OPERATIONAL TRANSIENTS
15.1-1
15.1.1
Optimization of Control Systems
15.1-3
15.1.2
Initial Power Conditions Assumed In Accident Analyses
15.1-3
15.1.2.1
Power Rating
15.1-3
15.1.2.2
Initial Conditions
15.1-4
15.1.2.3
The thermal design and minimum measured flowrates are given in Table 15.11.Power Distribution
15.1-4
15.1.3
Trip Points And Time Delays To Trip Assumed In Accident Analyses
15.1-5
15.1.4
Instrumentation Drift And Calorimetric Errors - Power Range Neutron Flux 15.1-5
15.1.5
Rod Cluster Control Assembly Insertion Characteristic
15.1-6
15.1.6
Reactivity Coefficients
15.1-7
15.1.7
Fission Product Inventories
15.1-8
15.1.7.1
Radioactivity in the Core
15.1-8
15.1.7.2
Radioactivity in the Fuel Pellet Clad Gap
15.1-8
15.1.8
Residual Decay Heat
15.1-8
15.1.8.1
Fission Product Decay Energy
15.1-9
Table of Contents
1-xcvii
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WBNP-76
TABLE OF CONTENTS
Section
15.1.8.2
15.1.8.3
15.1.8.4
15.1.9
15.1.9.1
15.1.9.2
15.1.9.3
15.1.9.4
15.1.9.5
15.1.9.6
15.1.9.7
15.2
Title
Decay of U-238 Capture Products
Residual Fissions
Distribution of Decay Heat Following Loss of Coolant Accident
Computer Codes Utilized
FACTRAN
LOFTRAN
LEOPARD
TURTLE
TWINKLE
VIPRE-01
LOFTTR
CONDITION II - FAULTS OF MODERATE FREQUENCY
Page
15.1-9
15.1-10
15.1-10
15.1-11
15.1-11
15.1-11
15.1-12
15.1-12
15.1-12
15.1-13
15.1-13
15.2-1
15.2.1
Uncontrolled Rod Cluster Control Assembly Bank Withdrawal from a Subcritical
Condition
15.2-2
15.2.1.1
Identification of Causes and Accident Description
15.2-2
15.2.1.2
Analysis of Effects and Consequences
15.2-3
15.2.1.3
Conclusions
15.2-5
15.2.2
UNCONTROLLED ROD CLUSTER CONTROL ASSEMBLY BANK WITHDRAWAL AT POWER
15.2-5
15.2.2.1
Identification of Causes and Accident Description
15.2-5
15.2.2.2
Analysis of Effects and Consequences
15.2-6
15.2.2.3
Conclusions
15.2-9
15.2.3
ROD CLUSTER CONTROL ASSEMBLY MISALIGNMENT
15.2-9
15.2.3.1
Identification of Causes and Accident Description
15.2-9
15.2.3.2
Analysis of Effects and Consequences
15.2-11
15.2.3.3
Conclusions
15.2-13
15.2.4
UNCONTROLLED BORON DILUTION
15.2-13
15.2.4.1
Identification of Causes and Accident Description
15.2-13
15.2.4.2
Analysis of Effects and Consequences
15.2-14
15.2.4.2.1
Method of Analysis
15.2-14
15.2.4.2.2
Dilution During Refueling
15.2-14
15.2.4.2.3
Dilution During Startup
15.2-14
15.2.4.2.4
Dilution at Power
15.2-15
15.2.4.3
Conclusions
15.2-15
15.2.4.3.1
For Dilution During Refueling
15.2-15
15.2.4.3.2
For Dilution During Startup
15.2-15
15.2.4.3.3
For Dilution Following Reactor Shutdown
15.2-16
15.2.4.3.4
For Dilution During Full Power Operation
15.2-16
15.2.5
PARTIAL LOSS OF FORCED REACTOR COOLANT FLOW
15.2-17
15.2.5.1
Identification of Causes and Accident Description
15.2-17
15.2.5.2
Analysis of Effects and Consequences
15.2-17
15.2.5.3
Conclusions
15.2-18
15.2.6
Startup of an Inactive Reactor Coolant Loop
15.2-19
1-xcviii
Table of Contents
WATTS BAR
WBNP-76
TABLE OF CONTENTS
Section
Title
Page
15.2.6.1
Identification of Causes and Accident Description
15.2-19
15.2.6.2
Conclusions
15.2-19
15.2.7
LOSS OF EXTERNAL ELECTRICAL LOAD AND/OR TURBINE TRIP 15.2-20
15.2.7.1
Identification of Causes and Accident Description
15.2-20
15.2.7.2
Analysis of Effects and Consequences
15.2-21
15.2.7.3
Conclusions
15.2-23
15.2.8
LOSS OF NORMAL FEEDWATER
15.2-23
15.2.8.1
Identification of Causes and Accident Description
15.2-23
15.2.8.2
Analysis of Effects and Consequences
15.2-24
15.2.8.3
Conclusions
15.2-27
15.2.9
COINCIDENT LOSS OF ONSITE AND EXTERNAL (OFFSITE) AC POWER TO
THE STATION - LOSS OF OFFSITE POWER TO THE STATION AUXILIARIES
15.2-27
15.2.10
EXCESSIVE HEAT REMOVAL DUE TO FEEDWATER SYSTEM MALFUNCTIONS
15.2-28
15.2.10.1
Identification of Causes and Accident Description
15.2-28
15.2.10.2
Analysis of Effects and Consequences
15.2-28
15.2.10.3
Conclusions
15.2-30
15.2.11
Excessive Load Increase Incident
15.2-31
15.2.11.1
Identification of Causes and Accident Description
15.2-31
15.2.11.2
Analysis of Effects and Consequences
15.2-31
15.2.11.3
Conclusions
15.2-33
15.2.12
ACCIDENTAL DEPRESSURIZATION OF THE REACTOR COOLANT SYSTEM
15.2-33
15.2.12.1
Identification of Causes and Accident Description
15.2-33
15.2.12.2
Analysis of Effects and Consequences
15.2-33
15.2.12.3
Conclusions
15.2-34
15.2.13
ACCIDENTAL DEPRESSURIZATION OF THE MAIN STEAM SYSTEM 15.234
15.2.13.1
Identification of Causes and Accident Description
15.2-34
15.2.13.2
Analysis of Effects and Consequences
15.2-35
15.2.13.3
Conclusions
15.2-37
15.2.14
Inadvertent Operation of Emergency Core Cooling System
15.2-37
15.2.14.1
Identification of Causes and Accident Description
15.2-37
15.2.14.2
Analysis of Effects and Consequences
15.2-38
15.2.14.3
Conclusions
15.2-42
15.3
CONDITION III - INFREQUENT FAULTS
15.3-1
15.3.1
Loss of Reactor Coolant From Small Ruptured Pipes or From Cracks in Large Pipes
Which Actuate the Emergency Core Cooling System
15.3-1
15.3.1.1
Identification of Causes and Accident Description
15.3-1
15.3.1.2
Analysis of Effects and Consequences
15.3-2
15.3.1.3
Reactor Coolant System Pipe Break Results
15.3-3
15.3.1.4
Conclusions - Thermal Analysis
15.3-4
15.3.2
Minor Secondary System Pipe Breaks
15.3-5
Table of Contents
1-xcix
WATTS BAR
WBNP-76
TABLE OF CONTENTS
Section
15.3.2.1
15.3.2.2
15.3.2.3
15.3.3
15.3.3.1
15.3.3.2
15.3.3.3
15.3.4
15.3.4.1
15.3.4.2
15.3.4.3
15.3.5
15.3.5.1
15.3.5.2
15.3.6
15.3.6.1
15.3.6.2
15.3.6.3
15.4
CONDITION IV - LIMITING FAULTS
15.4.1
15.4.1.1
15.4.1.1.1
15.4.1.1.2
15.4.1.1.3
15.4.1.1.4
15.4.1.1.5
15.4.1.1.6
15.4.1.2
15.4.1.2.1
15.4.2
15.4.2.1
15.4.2.1.1
15.4.2.1.2
15.4.2.1.3
15.4.2.2
15.4.2.2.1
15.4.2.2.2
15.4.2.2.3
15.4.3
15.4.3.1
15.4.3.2
15.4.3.3
1-c
Title
Identification of Causes and Accident Description
Analysis of Effects and Consequences
Conclusions
Inadvertent Loading of a Fuel Assembly Into an Improper Position
Identification of Causes and Accident Description
Analysis of Effects and Consequences
Conclusions
Complete Loss of Forced Reactor Coolant Flow
Identification of Causes and Accident Description
Analysis of Effects and Consequences
Conclusions
Waste Gas Decay Tank Rupture
Identification of Causes and Accident Description
Analysis of Effects and Consequences
Single Rod Cluster Control Assembly Withdrawal at Full Power
Identification of Causes and Accident Description
Analysis of Effects and Consequences
Conclusions
Page
15.3-5
15.3-5
15.3-5
15.3-5
15.3-5
15.3-6
15.3-7
15.3-7
15.3-7
15.3-9
15.3-9
15.3-10
15.3-10
15.3-10
15.3-10
15.3-10
15.3-11
15.3-12
15.4-1
Major Reactor Coolant System Pipe Ruptures (Loss of Coolant Accident)
15.4-1
Thermal Analysis
15.4-2
Westinghouse Performance Criteria for Emergency Core Cooling System
15.4-2
Method of Thermal Analysis
15.4-3
Containment Analysis
15.4-7
Results of Large Break Limiting Transient
15.4-8
CONCLUSIONS - THERMAL ANALYSIS
15.4-10
PLANT OPERATING RANGE
15.4-12
Hydrogen Production and Accumulation
15.4-12
15.4-12
Major Secondary System Pipe Rupture
15.4-12
Major Rupture of a Main Steam Line
15.4-12
Identification of Causes and Accident Description
15.4-12
Analysis of Effects and Consequences
15.4-14
Conclusions
15.4-18
Major Rupture of a Main Feedwater Pipe
15.4-19
Identification of Causes and Accident Description
15.4-19
Analysis of Effects and Consequences
15.4-20
Conclusions
15.4-23
Steam Generator Tube Rupture
15.4-23
Identification of Causes and Accident Description
15.4-23
Analysis of Effects and Consequences
15.4-26
Conclusions
15.4-32
Table of Contents
WATTS BAR
WBNP-76
TABLE OF CONTENTS
Section
15.4.4
15.4.4.1
15.4.4.2
15.4.4.3
15.4.5
15.4.5.1
15.4.5.2
15.4.6
Ejection)
15.4.6.1
15.4.6.1.1
15.4.6.1.2
15.4.6.2
15.4.6.3
15.5
15.5.1
iaries
15.5.2
2
15.5.3
15.5.4
15.5.5
22
15.5.6
15.5.7
Title
Page
Single Reactor Coolant Pump Locked Rotor
15.4-32
Identification of Causes and Accident Description
15.4-32
Analysis of Effects and Consequences
15.4-33
Conclusions
15.4-35
Fuel Handling Accident
15.4-35
Identification of Causes and Accident Description
15.4-35
Analysis of Effects and Consequences
15.4-35
Rupture of a Control Rod Drive Mechanism Housing (Rod Cluster Control Assembly
15.4-36
Identification of Causes and Accident Description
15.4-36
Design Precautions and Protection
15.4-36
Limiting Criteria
15.4-38
Analysis of Effects and Consequences
15.4-39
Conclusions
15.4-44
ENVIRONMENTAL CONSEQUENCES OF ACCIDENTS
15.5-1
Environmental Consequences of a Postulated Loss of AC Power to the Plant Auxil15.5-1
Environmental Consequences of a Postulated Waste Gas Decay Tank Rupture 15.5Environmental Consequences of a Postulated Loss of Coolant Accident
15.5-3
Environmental Consequences of a Postulated Steam Line Break
15.5-20
Environmental Consequences of a Postulated Steam Generator Tube Rupture 15.5Environmental Consequences of a Postulated Fuel Handling Accident
Environmental Consequences of a Postulated Rod Ejection Accident
15.5-23
15.5-25
15A DOSE MODELS USED TO EVALUATE THE ENVIRONMENTAL CONSEQUENCES OF ACCIDENTS
15A.1 INTRODUCTION
15A-1
15A.2 ASSUMPTIONS
15A-1
15A.3 GAMMA DOSE AND BETA DOSE
15A-1
15A.4 THYROID INHALATION DOSE
15A-2
16.0
TECHNICAL SPECIFICATIONS
16.1
PROPOSED TECHNICAL SPECIFICATIONS (NOT USED)
16.1-1
16.2
PROPOSED FINAL TECHNICAL SPECIFICATIONS
16.2-1
16.3
RELOCATED SPECIFICATIONS
16.1-1
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Section
16.3.1
16.3.2
16.3.3
17.0
17.1
17.1.1
17.1.2
17.1A
17.2
17.2.1
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Title
Discussion
Document Control
Changes to the Relocated Specifications
QUALITY ASSURANCE
Quality Assurance During Design and Construction
TVA Organization
Quality Assurance Program
Westinghouse Quality Management System
QUALITY ASSURANCE FOR STATION OPERATION
Identification of Safety-Related Features
Page
16.1-1
16.1-1
16.1-1
17-1
17-1
17-1
17-1
17-2
17.2-1
17.2-1
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Title
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Table of Contents