ML23291A344
Text
SSES-FSAR Text Rev. 71
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TABLE OF CONTENTS Chapter 1
1.0 INTRODUCTION
AND GENERAL DESCRIPTION OF PLANT 1.1 Introduction 1.1.1 Type of License 1.1.2 Identification of Applicant 1.1.3 Number of Plant Units 1.1.4 Description of Location 1.1.5 Type of Nuclear Steam Supply 1.1.6 Type of Containment 1.1.7 Core Thermal Power Levels 1.1.8 Scheduled Fuel Load and Operation Data 1.1.9 FSAR Organization 1.2 General Plant Description 1.2.1 Principal Design Criteria 1.2.2 Plant Description 1.3 Comparison Tables 1.3.1 Comparison With Similar Facility Designs 1.3.2 Comparison of Final and Preliminary Information 1.4 Identification of Agents and Contractors 1.4.1 Pennsylvania Power & Light Company (Applicant) 1.4.2 Architect Engineer 1.4.3 Nuclear Steam Supply System 1.4.4 Turbine-Generator Vendor 1.4.5 Other Consultants 1.5 Requirements for Further Technical Information 1.5.1 Development of BWR Technology 1.5.2 Programs Conducted During Operations Phase 1.6 Material Incorporated by Reference 1.6.1 General Electric Topical Reports 1.6.2 Bechtel Topical Reports 1.6.3 Other Topical Reports 1.7 Electrical, Instrumentation, and Control Drawings 1.8 Symbols and Terms Used in Engineering and Text 1.8.1 Text Definitions and Abbreviations 1.8.2 Drawing Index and Symbols 1.8.3 Piping Identification 1.8.4 Valve Identification 1.8.5 Instrument Identification 1.8.6 Electrical Component Identification FSAR Rev. 71 Page 1 of 113
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TABLE OF CONTENTS Chapter 1 Tables 1.3-1 Comparison of Nuclear Steam Supply System Design Characteristics 1.3-2 Comparison of Power Conversion System Design Characteristics 1.3-3 Comparison of Engineered Safety Features Design Characteristics 1.3-4 Comparison of Containment Design Characteristics 1.3-5 Radioactive Waste Management Systems Design Characteristics 1.3-6 Comparison of Structural Design Characteristics 1.3-7 Comparison of Electrical Power Systems Design Characteristics 1.3-8 Significant Design Changes from PSAR to FSAR 1.4-1 Commercial Nuclear Reactors Completed, Under Construction, or in Design By General Electric 1.6-1 General Electric Topical Reports 1.6-2 Bechtel Topical Reports 1.6-4 Other Topical Reports 1.7-1 Electrical Drawings 1.8-1 SSES-Project Glossary Terms 1.8-2 Acronyms 1.8-3 Technical Abbreviations 1.8-5 Drawing Abbreviations 1.8-6 Piping and Valve Class Identification FSAR Rev. 71 Page 2 of 113
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TABLE OF CONTENTS Chapter 1 Figures 1.2-1 Figure replaced by Drawing M-220, Sh. 1 1.2-2 Figure replaced by Drawing M-221, Sh. 1 1.2-3 Figure replaced by Drawing M-222, Sh. 1 1.2-4 Figure replaced by Drawing M-223, Sh. 1 1.2-5 Figure replaced by Drawing M-224, Sh. 1 1.2-6 Figure replaced by Drawing M-225, Sh. 1 1.2-7 Figure replaced by Drawing M-226, Sh. 1 1.2-8 Figure replaced by Drawing M-227, Sh. 1 1.2-9 Figure replaced by Drawing M-230, Sh. 1 1.2-10 Figure replaced by Drawing M-231, Sh. 1 1.2-11 Figure replaced by Drawing M-232, Sh. 1 1.2-12 Figure replaced by Drawing M-233, Sh. 1 1.2-13 Figure replaced by Drawing M-234, Sh. 1 1.2-14 Figure replaced by Drawing M-235, Sh. 1 1.2-15 Figure replaced by Drawing M-236, Sh. 1 1.2-16 Figure replaced by Drawing M-237, Sh. 1 12.-17 Figure replaced by Drawing M-240, Sh. 1 1.2-18 Figure replaced by Drawing M-241, Sh. 1 1.2-19 Figure replaced by Drawing M-242, Sh. 1 1.2-20 Figure replaced by Drawing M-243, Sh. 1 1.2-21 Figure replaced by Drawing M-244, Sh. 1 1.2-22 Figure replaced by Drawing M-245, Sh. 1 1.2-23 Figure replaced by Drawing M-246, Sh. 1 1.2-24 Figure replaced by Drawing M-247, Sh. 1 1.2-25 Figure replaced by Drawing M-248, Sh. 1 1.2-26 Figure replaced by Drawing M-249, Sh. 1 1.2-27 Figure replaced by Drawing M-250, Sh. 1 1.2-28 Figure replaced by Drawing M-251, Sh. 1 1.2-29 Figure replaced by Drawing M-252, Sh. 1 1.2-30 Figure replaced by Drawing M-253, Sh. 1 1.2-31 Figure replaced by Drawing M-254, Sh. 1 1.2-32 Figure replaced by Drawing M-255, Sh. 1 1.2-33 Figure replaced by Drawing M-256, Sh. 1 1.2-34 Figure replaced by Drawing M-257, Sh. 1 1.2-35 Figure replaced by Drawing M-258, Sh. 1 1.2-36 Figure replaced by Drawing M-259, Sh. 1 1.2-37 Figure replaced by Drawing M-260, Sh. 1 1.2-38 Figure replaced by Drawing M-261, Sh. 1 1.2-39 Figure replaced by Drawing M-270, Sh. 1 1.2-40 Figure replaced by Drawing M-271, Sh. 1 1.2-41 Figure replaced by Drawing M-272, Sh. 1 1.2-42 Figure replaced by Drawing M-273, Sh. 1 1.2-43 Figure replaced by Drawing M-274, Sh. 1 1.2-44 Figure replaced by Drawing M-276, Sh. 1 1.2-45 Figure replaced by Drawing M-280, Sh. 1 1.2-46 Figure replaced by Drawing M-281, Sh. 1 1.2-47 Figure replaced by Drawing M-282, Sh. 1 1.2-48 Figure replaced by Drawing M-284, Sh. 1 FSAR Rev. 71 Page 3 of 113
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TABLE OF CONTENTS Chapter 1 Figures 1.2-49 Unit 1 - Heat Balance at Rated Power with 100 x 106 LBm/hr Core Flow 1.2-49-1 Unit 1 - Heat Balance at Rated Power with 108 x 106 LBm/hr Increased Core Flow 1.2-49-2 Unit 2 - Heat Balance at Rated Power with 100 x 106 LBm/hr Core Flow 1.2-49-3 Unit 2 - Heat Balance at Rated Power with 108 x 106 LBm/hr Increased Core Flow 1.2-50 Figure replaced by Drawing M-5200, Sh. 1 1.2-51 Figure replaced by Drawing M-5200, Sh. 2 1.8-1 Piping and Instrument Symbols 1.8-2a Figure replaced by Drawing M-100, Sh. 1 1.8-2b Figure replaced by Drawing M-100, Sh. 2 1.8-2c Figure replaced by Drawing M-100, Sh. 3 1.8-2d Figure replaced by Drawing M-100, Sh. 4 1.8-3 Logic Symbols 1.8-4 Instrument Symbol FSAR Rev. 71 Page 4 of 113
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TABLE OF CONTENTS Chapter 2 2.0 SITE CHARACTERISTICS 2.1 Geography and Demography 2.1.1 Site Location and Description 2.1.2 Exclusion Area Authority and Control 2.1.3 Population Distribution 2.1.4 References 2.2 Nearby Industrial, Transportation, and Military Facilities 2.2.1 Locations and Routes 2.2.2 Descriptions 2.2.3 Evaluation of Potential Accidents 2.2.4 References 2.3 Meteorology 2.3.1 Regional Climatology 2.3.2 Local Meteorology 2.3.3 On-Site Meteorological Measurements Program 2.3.4 Short-Term (Accident) Diffusion Estimates 2.3.5 Long Term (Routine) Diffusion Estimates 2.3.6 References 2.4 Hydrologic Engineering 2.4.1 Hydrologic Description 2.4.2 Floods 2.4.3 Probable Maximum Flood (PMF) on Streams and Rivers 2.4.4 Potential Dam Failures Seismically Induced 2.4.5 Probable Maximum Surge and Seiche Flooding 2.4.6 Probable Maximum Tsunami Flooding 2.4.7 Ice Effects 2.4.8 Cooling Water Canals and Reservoirs 2.4.9 Channel Diversions 2.4.10 Flooding Protection Requirements 2.4.11 Low Water Considerations 2.4.12 Dispersion Dilution and Travel Time of Accidental Releases of Liquid Effluents in Surface Waters 2.4.13 Groundwater 2.4.14 Technical Specification and Emergency Operation Requirements 2.4.15 References 2.5 Geology, Seismology and Geotechnical Engineering 2.5.1 Basic Geologic and Seismic Information 2.5.2 Vibratory Ground Motion 2.5.3 Surface Faulting 2.5.4 Stability of Subsurface Materials and Foundations 2.5.5 Stability of Slopes 2.5.6 References FSAR Rev. 71 Page 5 of 113
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TABLE OF CONTENTS Chapter 2 2.5A U.S. Department of the Interior Report on Investigation of an Earth Disturbance at Wilkes-Barre 2.5B City of Wilkes-Barre Report on an Earth Disturbance 2.5C Boring Logs 2.5C.1 Summary of Field Density Test Results 2.5C.2 Listings of Boring Logs FSAR Rev. 71 Page 6 of 113
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TABLE OF CONTENTS Chapter 2 Tables 2.1-33 Past Population Changes of Counties Within 20 Miles of the Site 2.1-34 Population by Residence for Counties Within 20 Miles of the Site 2.1-35 Population Distribution 2010 0-10 Miles Distance (Miles) 2.1-36 Population Distribution 2010 0-50 Miles Distance (Miles) 2.1-37 Population Distribution 2020 0-10 Miles Distance (Miles) 2.1-38 Population Distribution 2020 0-50 Miles Distance (Miles) 2.1-39 Population Distribution 2000 0-10 Miles Distance (Miles) 2.1-40 Communities Within 10 Miles of the Site, 2000 2.1-41 Population Distribution 2000 0-50 Miles Distance (Miles) 2.1-42 Seasonal Population of Counties in Study Area, 2000 2.1-43 Industries Within 5 Miles of the Site 2.1-44 Population Projections for Berwick, Pennsylvania 2.1-45 Cumulative Populations for 1990 and 2000 2.1-46 Cumulative Populations for 1990, 2000, 2010 and 2020 2.2-1 Pipelines Within 5 Miles of the Site 2.3-1 Hurricanes Within 75 and 150 Nautical Miles of the Susquehanna Site Period of Record 1871 to 1969 2.3-2 Thunderstorm Days for Avoca, Pennsylvania Wilkes-Barre Scranton Airport, Period of Record 1956 to 1974, Values are expressed in Days 2.3-3 Total Number of Days in 5 Years Mixing Heights < 1500 m Wind Speeds < 4.0 sec-1 and No Significant Precipitation For Episodes Lasting at least 2 Days 2.3-5 Mean Monthly Values: Susquehanna Site (1973-1976) 2.3-6 Long Term Average Wind Speed and Prevailing Direction at Wilkes-Barre Scranton Airport, Period of Record: 1956-1974 2.3-7 Average Wind Speed and Prevailing Direction at the Susquehanna Site, Period of Record (1973-1976) 2.3-8 Wind Direction Persistence - Pasquill A (1973-1976) 2.3-9 Wind Direction Persistence - Pasquill B (1973-1976) 2.3-10 Wind Direction Persistence - Pasquill C (1973-1976) 2.3-11 Wind Direction Persistence - Pasquill D (1973-1976) 2.3-12 Wind Direction Persistence - Pasquill E (1973-1976 2.3-13 Wind Direction Persistence - Pasquill F (1973-1976) 2.3-14 Wind Direction Persistence - Pasquill G (1973-1976) 2.3-15 Wind Direction Persistence - Pasquill All (1973-1976) 2.3-16 Wind Direction Persistence - Pasquill E, F, & G (1973-1976) 2.3-17 Long Term Temperature (°F) At Wilkes-Barre -Scranton Airport 2.3-18 Mean Monthly Temperature, Dew Point Temperature and Relative Humidity Wilkes-Barre Scranton Airport Period of Record: 1956-1974 2.3-19 Temperature and Moisture Data for the Susquehanna Site, Period of Record: 1973-1976 2.3-20 Statistics and Diurnal Variation of Meteorological Parameters Data Period: January 1973-1976 2.3-21 Statistics and Diurnal Variation of Meteorological Parameters Data Period: February 1973-1976 2.3-22 Statistics and Diurnal Variation of Meteorological Parameters Data Period: March 1973-1976 FSAR Rev. 71 Page 7 of 113
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TABLE OF CONTENTS Chapter 2 Tables 2.3-23 Statistics and Diurnal Variation of Meteorological Parameters Data Period: April 1973-1976 2.3-24 Statistics and Diurnal Variation of Meteorological Parameters Data Period: May 1973-1976 2.3-25 Statistics and Diurnal Variation of Meteorological Parameters Data Period: June 1973-1976 2.3-26 Statistics and Diurnal Variation of Meteorological Parameters Data Period: July 1973-1976 2.3-27 Statistics and Diurnal Variation of Meteorological Parameters Data Period: August 1973-1976 2.3-28 Statistics and Diurnal Variation of Meteorological Parameters Data Period: September 1973-1976 2.3-29 Statistics and Diurnal Variation of Meteorological Parameters Data Period: October 1973-1976 2.3-30 Statistics and Diurnal Variation of Meteorological Parameters Data Period: November 1973-1976 2.3-31 Statistics and Diurnal Variation of Meteorological Parameters Data Period: December 1973-1976 2.3-32 Statistics and Diurnal Variation of Meteorological Parameters Data Period: January 1973-December 1976 2.3-33 Long Term Monthly Precipitation Data (Liquid Equivalent, In Inches) for Wilkes-Barre Scranton Airport at Avoca, PA 2.3-34 Expected Rainfall by Duration and Recurrence Interval for Vicinity of Susquehanna Site (Ref. 2.3-20) (Inches) 2.3-35 Probable Maximum Precipitation for Varying Rainfall Durations and Areas (Ref. 2.3-
- 21) (Inches) 2.3-36 Precipitation Data for the Susquehanna Site (Inches of Water) (1973-1976) 2.3-37 Frequency Distribution of Precipitation Data Period: January 1973-1976 2.3-38 Frequency Distribution of Precipitation Data Period: February 1973-1976 2.3-39 Frequency Distribution of Precipitation Data Period: March 1973-1976 2.3-40 Frequency Distribution of Precipitation Data Period: April 1973-1976 2.3-41 Frequency Distribution of Precipitation Data Period: May 1973-1976 2.3-42 Frequency Distribution of Precipitation Data Period: June 1973-1976 2.3-43 Frequency Distribution of Precipitation Data Period: July 1973-1976 2.3-44 Frequency Distribution of Precipitation Data Period: August 1973-1976 2.3-45 Frequency Distribution of Precipitation Data Period: September 1973-1976 2.3-46 Frequency Distribution of Precipitation Data Period: October 1973-1976 2.3-47 Frequency Distribution of Precipitation Data Period: November 1973-1976 2.3-48 Frequency Distribution of Precipitation Data Period: December 1973-1976 2.3-49 Frequency Distribution of Precipitation Data Period: January 1973-December 1976 2.3-50 Precipitation Wind Rose January 1973-1976 2.3-51 Precipitation Wind Rose February 1973-1976 2.3-52 Precipitation Wind Rose March 1973-1976 2.3-53 Precipitation Wind Rose April 1973-1976 2.3-54 Precipitation Wind Rose May 1973-1976 2.3-55 Precipitation Wind Rose June 1973-1976 2.3-56 Precipitation Wind Rose July 1973-1976 2.3-57 Precipitation Wind Rose August 1973-1976 FSAR Rev. 71 Page 8 of 113
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TABLE OF CONTENTS Chapter 2 Tables 2.3-58 Precipitation Wind Rose September 1973-1976 2.3-59 Precipitation Wind Rose October 1973-1976 2.3-60 Precipitation Wind Rose November 1973-1976 2.3-61 Precipitation Wind Rose December 1973-1976 2.3-62 Precipitation Wind Rose January 1973-December 1976 2.3-63 Heavy Fog (Visibility 1/4 Mile or Less) at Avoca, PA.
2.3-64 Joint Frequency (%) of Wind Direction, Wind Speed and Stability, Stability Class A 2.3-65 Joint Frequency (%) of Wind Direction, Wind Speed and Stability, Stability Class B 2.3-66 Joint Frequency (%) of Wind Direction, Wind Speed and Stability, Stability Class C 2.3-67 Joint Frequency (%) of Wind Direction, Wind Speed and Stability, Stability Class D 2.3-68 Joint Frequency (%) of Wind Direction, Wind Speed and Stability, Stability Class E 2.3-69 Joint Frequency (%) of Wind Direction, Wind Speed and Stability, Stability Class F 2.3-70 Joint Frequency (%) of Wind Direction, Wind Speed and Stability, Stability Class G 2.3-71 Joint Frequency (%) of Wind Direction, Wind Speed and Stability, All Stability Classes 2.3-72 Mixing Heights (meters) 2.3-73 Heights of Meteorological Sensors 2.3-74 Data Recovery Rates 2.3-75 Joint Wind Frequency Distribution by Stability Class, Lower Wind January 1, 1999 through December 31, 2003 Stability Class: Pasquill A 2.3-76 Joint Wind Frequency Distribution by Stability Class, Lower Wind January 1, 1999 through December 31, 2003 Stability Class: Pasquill B 2.3-77 Joint Wind Frequency Distribution by Stability Class, Lower Wind January 1, 1999 through December 31, 2003, Stability Class: Pasquill C 2.3-78 Joint Wind Frequency Distribution by Stability Class, Lower Wind January 1, 1999 through December 31, 2003, Stability Class: Pasquill D 2.3-79 Joint Wind Frequency Distribution By Stability Class, Lower Wind January 1, 1999 through December 31, 2003, Stability Class: Paquill E 2.3-80 Joint Wind Frequency Distribution By Stability Class, Lower Wind January 1, 1999 through December 31, 2003, Stability Class: Pasquill F 2.3-81 Joint Wind Frequency Distribution by Stability Class, Lower Wind January 1, 1999 through December 31, 2003, Stability Class: Pasquill G 2.3-82 Joint Wind Frequency Distribution by Stability Class Lower Wind January 1, 1999 through December 31, 2003, All Classes 2.3-84 Joint Wind Frequency Distribution by Stability Class, Upper Wind January 1, 1999 through December 31, 2003, Stability Class: Pasquill A 2.3-85 Joint Wind Frequency Distribution by Stability Class, Upper Wind January 1, 1999 through December 31, 2003, Stability Class: Pasquill B 2.3-86 Joint Wind Frequency Distribution by Stability Class, Upper Wind January 1, 1999 through December 31, 2003, Stability Class: Pasquill C 2.3-87 Joint Wind Frequency Distribution by Stability Class, Upper Wind January 1, 1999 through December 31, 2003, Stability Class: Pasquill D 2.3-88 Joint Wind Frequency Distribution by Stability Class, Upper Wind January 1, 1999 through December 31, 2003, Stability Class: Pasquill E 2.3-89 Joint Wind Frequency Distribution by Stability Class, Upper Wind January 1, 1999 through December 31, 2003, Stability Class: Pasquill F 2.3-90 Joint Wind Frequency Distribution by Stability Class, Upper Wind January 1, 1999 through December 31, 2003, Stability Class: Pasquill G FSAR Rev. 71 Page 9 of 113
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TABLE OF CONTENTS Chapter 2 Tables 2.3-91 Joint Wind Frequency Distribution by Stability Class, Upper Wind January 1, 1999 through December 31, 2003, All Classes 2.3-92 Summary of Short-Term X/Q (SEC/M3) Results at 549M EAB 2.3-93 1999 Probability Values for 1 Hour at SSES EAB 2.3-94 2000 Probability Values for 1 Hour at SSES EAB 2.3-95 2001 Probability Values for 1 Hour at SSES EAB 2.3-96 2002 Probability Values for 1 Hour at SSES EAB 2.3-97 2003 Probability Values for 1 Hour at SSES EAB 2.3-98 1999-2003 Probability Values for 1 Hour at SSES EAB 2.3-99 1999 Probability Values for 1 Hour at SSES LPZ 2.3-100 2000 Probability Values for 1 Hour at SSES LPZ 2.3-101 2001 Probability Values for 1 Hour at SSES LPZ 2.3-102 2002 Probability Values for 1 Hour at SSES LPZ 2.3-103 2003 Probability Values for 1 Hour at SSES LPZ 2.3-104 1999-2003 Probability Values for 1 Hour at SSSS LPZ 2.3-105 Summary of Long-Term X/G (SEC/M3) Results at 4827M LPZ 2.3-106 Distances and Terrain/Recirculation Correction Factors for SSES 2003 Land Use Census Locations 2.3-107 1999 Average Relative Concentration (sec/m3) and Disposition (m-2) Estimates at the Site Boundary 2.3-108 2000 Average Relative Concentration (sec/m3) and Deposition (m-2) Estimates at the Site Boundary 2.3-109 2001 Average Relative Concentration (sec/m3) and Deposition (m-2) Estimates at the Site Boundary 2.3-110 2002 Average Relative Concentration (sec/m3) and Deposition (m-2) Estimates at the Site Boundary 2.3-111 2003 Average Relative Concentration (sec/m3) and Deposition (m-2) Estimates at the Site Boundary 2.3-112 1999-2003 Average Relative Concentration (sec/m3) and Deposition (m-2) Estimates at the Site Boundary 2.3-113 1999 Average Relative Concentration (sec/m3) and Deposition (m-2) Estimates at the Exclusion Area Boundary 2.3-114 2000 Average Relative Concentration (sec/m3) and Deposition (m-2) Estimates at the Exclusion Area Boundary 2.3-115 2001 Average Relative Concentration (sec/m3) and Deposition (m-2) Estimates at the Exclusion Area Boundary 2.3-116 2002 Average Relative Concentration (sec/m3) and Deposition (m-2) Estimates at the Exclusion Area Boundary 2.3-117 2003 Average Relative Concentration (sec/m3) and Deposition (m-2) Estimates at the Exclusion Area Boundary 2.3-118 1999-2003 Average Relative Concentration (sec/m3) and Deposition (m-2) Estimates at the Exclusion Area Boundary.
2.3-119 1999 Atmospheric Dispersion Estimates for Nearest Residence and Vegetable Garden 2.3-120 2000 Atmospheric Dispersion Estimates for Nearest Residence and Vegetable Garden 2.3-121 2001 Atmospheric Dispersion Estimates for Nearest Residence and Vegetable Garden FSAR Rev. 71 Page 10 of 113
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TABLE OF CONTENTS Chapter 2 Tables 2.3-122 2002 Atmospheric Dispersion Estimates for Nearest Residence and Vegetable Garden 2.3-123 2003 Atmospheric Dispersion Estimates for Nearest Residence and Vegetable Garden 2.3-124 1999-2003 Atmospheric Dispersion Estimates for Nearest Residence and Vegetable Garden 2.3-125 1999 Atmospheric Dispersion Estimates for Nearest Meat Animal, Dairy Locations and Special Receptors 2.3-126 2000 Atmospheric Dispersion Estimates for Nearest Meat Animal, Dairy Locations and Special Receptors 2.3-127 2001 Atmospheric Dispersion Estimates for Nearest Meat Animal, Dairy Locations and Special Receptors 2.3-128 2002 Atmospheric Dispersion Estimates for Nearest Meat Animal, Dairy Locations and Special Receptors 2.3-129 2003 Atmospheric Dispersion Estimates for Nearest Meat Animal, Dairy Locations and Special Receptors 2.3-130 1999-2003 Atmospheric Dispersion Estimates for Nearest Meat Animal, Dairy Locations and Special Receptors 2.3-131 1999 Atmospheric Dispersion Estimates at Selected Locations 2.3-132 2000 Atmospheric Dispersion Estimates at Selected Locations 2.3-133 2001 Atmospheric Dispersion Estimates at Selected Locations 2.3-134 2002 Atmospheric Dispersion Estimates at Selected Locations 2.3-135 2003 Atmospheric Dispersion Estimates at Selected Locations 2.3-136 1999-2003 Atmospheric Dispersion Estimates at Selected Locations 2.3-137 SSES Relative Concentrations No Decay, Undepleted X/Q (sec/m3) X/Q Accumulation for Ground Average for the Period of 01/01/99 through 12/31/03 2.3-138 SSES Relative Concentrations 2.26-Day Decay, Undepleted X/Q (sec/m3) for Ground Decayed Sector Average for the Period of 01/01/99 through 12/31/03 2.3-139 SSES Relative Concentrations 8-Day Decay, Depleted X/Q (sec/m3) for Ground Decayed Sector Average for the Period of 01/01/99 through 12/31/03 2.3-140 SSES Relative Deposition D/Q (m-2) for the Period of 01/01/99 through 12/31/03 2.3-141 2017-2021 Annual Average Relative Concentration (sec/meter3) and Deposition (1/meter2) Estimates at the Site Boundary 2.3-142 2017-2021 Atmospheric Dispersion Estimates at Selected Locations 2.3-143 2017-2021 Atmospheric Dispersion Estimates at the Nearest Residence within a 5-Mile Radius of SSES by Sector 2.3-144 2017-2021 Atmospheric Dispersion Estimates at the Nearest Garden within a 5-Mile Radius of SSES by Sector 2.3-145 2017-2021 Atmospheric Dispersion Estimates at the Nearest Animal Raised for Meat Consumption within a 5-Mile Radius of SSES by Sector 2.3-146 2017-2021 Atmospheric Dispersion Estimates at all Dairy Locations Near SSES 2.4-1 Existing and Proposed Dams Located in the Susquehanna River Basin (Chemung River Basin) 2.4-2 Minor Upstream Dams and Reservoirs 2.4-3 Water Users 2.4-4 Historic Floods in the Vicinity of the Susquehanna Steam Electric Station.
2.4-5 All-Season 24-Hour Probable Maximum Precipitation FSAR Rev. 71 Page 11 of 113
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TABLE OF CONTENTS Chapter 2 Tables 2.4-6 Probable Maximum Precipitation for Durations Less Than 30 Min.
2.4-7 Peak Runoff Rates from and Maximum Ponding Depths on Roofs of Safety Related Structures for Local All-Season PMP 2.4-8 Adopted 4-Hour Unit Hydrographs and Characteristics.
2.4-9 Susquehanna River Basin Routing Coefficients 2.4-10 Manning "N" Values Computed from 1936 Flood 2.4-11 Susquehanna River Freeze Over at Harrisburg (1870-1955) 2.4-12 Ice Jam Flooding 2.4-13 Summary of Flood Routing Studies - Spray Pond 2.4-14 Results of Wind Wave Computation 2.4-15 Maximum Loadings Resulting from Wind-Wave Activities 2.4-16 Maximum Hydrodynamic Loading Resulting from Earthquake 2.4-18 ESW Cooling Duty on Simultaneous Loss of All Auxiliary Power to Both Units 2.4-21 Regional Hydrogeologic Section (within 20-mile radius of Susquehanna SES) 2.4-22 Water Well Data Within Two Miles of the Station 2.4-23 Spring Data Within Two Miles of the Station 2.4-24 Data for Major Water Wells, Other Than Public Wells, located Between 2 and 10 Miles From the Station 2.4-25 Data for Public Supply Wells Located Between 2 and 20 Miles from the Station 2.4-26 Estimated Groundwater Withdrawal in 1976 Within Two Miles of the Station 2.4-27 Projections of Future Groundwater Withdrawal Within 2 and 20 Miles of the Station 2.4-28 Major Groundwater Withdrawal, and Population Served by Water Supply Companies Within 20-Mile Area 2.4-29 Estimation of Total Groundwater Withdrawal in 1975 Within 20 Mile Radius of the Station 2.4-30 Details of the Construction of Observation Wells at the Susquehanna SES 2.4-31 Groundwater Level Data Taken at Susquehanna SES 1972 through 1975 2.4-32 Groundwater Level Data Taken at Susquehanna SES in 1976 and 1977 2.4-33 Summary of Permeability Tests of Overburden and Upper Bedrock at the Susquehanna SES Performed During Previous Investigations 2.4-34 Summary of Permeability Tests of Overburden and Upper Bedrock at the Susquehanna SES Performed for This Investigation 2.4-35 Radionuclide Content of the Tank Postulated to Rupture - Reactor Water Cleanup (RWCU) Phase Separator Tanks-Susquehanna SES 2.4-36 Groundwater Parameter Values Used for SLUG3D Simulations Accident Analysis for Susquehanna SES 2.4-37 Range of Parameter Values used in Calibrated Numerical Model of Buried Valley Aquifer Northern Side of Susquehanna SES 2.4-38 Estimated Peak Concentration of Radionuclides in Groundwater Resulting from Postulated Rupture of RWCU Phase Separator Tank - Results of Simulations with SLUG3D Model - Susquehanna SES 2.4-39 Estimated Peak Concentration of Radionuclides in Groundwater in Buried Valley Aquifer Resulting from postulated Rupture of RWCU Phase Separator Tank - Results of Simulations with SLUG3D Model - Susquehanna SES 2.5-1 Modified Mercalli Intensity (Damage) Scale (Abridged) 2.5-2 Earthquake list 2.5-3 Unconfined Compressive Strengths of Foundation Rock (Mahantango Formation)
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TABLE OF CONTENTS Chapter 2 Tables 2.5-4 Laboratory Measurements of P-Wave Seismic Velocities on Rock Cores taken from Reactor and Turbine Building Areas 2.5-5 Representative Engineering Properties of Unweathered Foundation Rock for Principal Plant Structures 2.5-6 P-Wave and S-Wave Velocities and Computed Dynamic Moduli, Spray Pond Area 2.5-7 Cross-Hole Seismic Velocities, Reactor Area 2.5-8 Results of Settlement Measurements Taken on ESSW Pumphouse Basemat 2.5-9 Spray Pond Water Level Elevations 2.5-10 Permeabilities Measured in Spray Pond 2.5-11 Permeabilities Measured Near the Railroad Bridge 2.5-12 Circulation Losses in Drill Holes in Spray Pond 2.5-13 Soil Test Results Summary 2.5-14 Spray Pond Summary of Cyclic Consolidated-Undrained Triaxial (CR) Tests 2.5-15 Design Parameters for Spray Pond Liner 2.5-16 Spray Pond, Summary of Liquefaction Analysis 2.5-17 Effect of Varying Standard Relationship of Effective Strain with Damping and Moduli for Profile 2, GWT-665 2.5-18 Spray Pond Factor of Safety as Obtained Using Different Earthquakes 2.5-19 Probable Settlement During Earthquake FSAR Rev. 71 Page 13 of 113
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TABLE OF CONTENTS Chapter 2 Figures 2.1-21 Site Vicinity Map 2.1-22 Site Area Map 2.1-23 Population Distribution 0-10 Miles, 2010 2.1-24 Population Distribution 0-50 Miles, 2010 2.1-25 Population Distribution 0-10 Miles, 2020 2.1-26 Population Distribution 0-50 Miles, 2020 2.1-27 Seasonal Population 0-10 Miles, 2000 2.1-28 Seasonal Population 0-50 Miles, 2000 2.2-1 Major Transportation Routes and Pipelines 2.2-2 Airport and Airline Route Map 2.2-3 Pipeline Break at Elevation 700', Steady State Break Flow 2.2-4 Pipeline Break at Elevation 600', Steady State Break Flow 2.3-1 Tornado Occurrence and Intensity in Susquehanna Region 2.3-2 TP25 Rainfall Intensity - Duration Frequency Curves USDC WB, 1955 2.3-3 Topography Within 5 Miles 2.3-4-1 Maximum Terrain Elevation Versus Distance By Sector 2.3-4-2 Maximum Terrain Elevation Versus Distance By Sector 2.3-4-3 Maximum Terrain Elevation Versus Distance By Sector 2.3-4-4 Maximum Terrain Elevation Versus Distance By Sector 2.3-4-5 Maximum Terrain Elevation Versus Distance By Sector 2.3-4-6 Maximum Terrain Elevation Versus Distance By Sector 2.3-4-7 Maximum Terrain Elevation Versus Distance By Sector 2.3-4-8 Maximum Terrain Elevation Versus Distance By Sector 2.3-5 Schematic of Instrumentation 2.3-6 One Hour Direction Independent X/Q at the EAB (Weighted Average of 1999, 2000, 2001, 2002 and 2003 Calculations) 2.3-7 One Hour Direction Dependent X/Q Values at the EAB (Weighted Average of 1999, 2000, 2001, 2002 and 2003 Calculations) 2.3-8 One Hour Direction Dependent X/Q Values at the LPZ (Weighted Average of 1999, 2000, 2001, 2002 and 2003 Calculations) 2.3-9 One Hour Direction Independent X/Q at the LPZ (Weighted Average of 1999, 2000, 2001, 2002 and 2003 Calculations 2.3-10 Interpolated X/Q Values at the LPZ (Weighted Average of 1999, 2000, 2001, 2002 and 2003 Calculations) 2.4-3 Plant Complete Showing Storm Drain Pipe Layout 2.4-4 Susquehanna River Basin 2.4-5 Stage Discharge Curve at Low Flows 2.4-6 Stage Discharge Curve, Discharge Range 1000-37,000 CFS 2.4-7 Water Users on the Susquehanna River 2.4-8 Stage Discharge Curves at Plant Site 2.4-9 Flood Profiles on the Susquehanna River at the Site 2.4-10 General Site Drainage Plan 2.4-11 Site Drainage Locations A&B 2.4-12 Site Drainage Locations C&D 2.4-13 Site Drainage Locations E&F FSAR Rev. 71 Page 14 of 113
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TABLE OF CONTENTS Chapter 2 Figures 2.4-14 Probable Maximum Precipitation Storm Pattern and Outline of Sub-Basins, Susquehanna River above Wilkes-Barre, Pennsylvania 2.4-15 Probable Maximum Precipitation on Susquehanna River Basin and Probable Maximum Flood Hydrograph at Wilkes-Barre, Pennsylvania 2.4-16 Map of the Susquehanna River, River Miles 150-170 2.4-17 Stage Discharge Curve at Section 2-Berwick Bridge 2.4-18 River and Water Surface Profiles of Susquehanna River in Vicinity of Site 2.4-19 Cross Sections at the Eight River Sections Near the Site 2.4-20 Cross Section of River at the Plant Site 2.4-21 Wind Fetch, Susquehanna River PMF 2.4-22 Tioga Dam and Hammond Dam Reservoir Areas and Sections 2.4-23 Surface Drainage Patterns around the Spray Pond 2.4-24 Spray Pond Inflow and Outflow Hydrograph 2.4-25 Spray Pond Outlet Rating Curves 2.4-26 Spray Pond Elevation Area Storage Capacity Curves 2.4-27 Spray Pond Emergency Spillway Water Surface Profile 2.4-28 Spray Pond Design Spectrum for SSE 2.4-29 Spray Pond Design Spectrum for OBE 2.4-30 Duration Curves of Daily Discharge 2.4-31 Time of Travel, Susquehanna River Shickshinny to Danville 2.4-32 Map of Susquehanna SES Showing Groundwater Contours in September 1977 2.4-33 Hydrogeologic Cross Section from West to East Along Groundwater Flow Path at the Susquehanna SES 2.4-34 Bedrock Geologic Map of Area Within 20 Miles of Susquehanna SES 2.4-35 Major Pleistocene Sand and Gravel Deposits Within 20 Miles of Susquehanna SES 2.4-36 Geologic Map of Area Within Two Miles of the Station 2.4-37 Water Wells Within Two Miles of the Station 2.4-38 Springs Used for Water Supply Within Two Miles of the Station 2.4-39 Major Water Wells Two to Ten Miles from the Station, Excepting Public Supply Wells 2.4-40 Public Supply Wells Two to Twenty Miles from the Station 2.4-41 Map of Susquehanna SES Showing Isopach Contours of Overburden Thickness 2.4-42 Map of Susquehanna SES Showing Top-of-Bedrock Contours 2.4-43 Map of Susquehanna SES Showing Groundwater Contours in April 1977 2.4-44 Log of Boring and Observation Well Construction Details-1200, 1200A 2.4-45 Log of Boring and Observation Well Construction Details-1201 2.4-46 Log of Boring and Observation Well Construction Details-1204 2.4-47 Log of Boring and Observation Well Construction Details-1208 2.4-48 Log of Boring and Observation Well Construction Details-1209A 2.4-49 Log of Boring and Observation Well Construction Details-1210 2.4-50 Map of Susquehanna SES Showing Groundwater Contours in June 1971 2.4-51 Drawdown Curves from Pumping Tests of Observation Wells 1204 and 1210 2.4-52 River Intake Structure 2.4-53 River Discharge Diffuser 2.4-54 Figure replaced by Drawing A-12. Sh. 1 2.4-55 Figure replaced by Drawing FF62005, Sh. 1 2.5-1 Site Location 2.5-2 Regional Physiographic Map FSAR Rev. 71 Page 15 of 113
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TABLE OF CONTENTS Chapter 2 Figures 2.5-3 Regional Geologic Map 2.5-4 Location of Appalachian Basin 2.5-5 Regional Isopach Maps 2.5-6 Stratigraphic Columns 2.5-7 Regional Tectonic Map 2.5-8a Earthquake Epicenters and Tectonic Province Boundaries in the Site Region 2.5-8b Earthquake Epicenters Within 200 Miles of the Site 2.5-9 Bouguer Gravity Anomaly Map 2.5-10 Geologic Map of the Bloomsburg-Berwick Area 2.5-11 Regional Landsat Lineaments 2.5-12 Site Geologic Map 2.5-13 Photograph of Geologic Feature Found in Turbine Building Excavation 2.5-14 Site Vicinity Geologic Column 2.5-15 Geologic Map of Spray Pond Area 2.5-17 Contours on Top of Bedrock Surface 2.5-17a Extent of Rock and Soil Foundations 2.5-18 Geologic Map of Foundation Excavation 2.5-19 Geologic Section Through Foundation Excavations 2.5-20a Photograph of Geologic Features Exposed in Excavations 2.5-20b Photograph of Geologic Features Exposed in Excavations 2.5-20c Photograph of Geologic Features Exposed in Excavations 2.5-20d Photograph of Geologic Features Exposed in Excavations 2.5-20e Photograph of Geologic Features Exposed in Excavations 2.5-20f Photograph of Geologic Features Exposed in Excavations 2.5-20g Photograph of Geologic Features Exposed in Excavations 2.5-21a Site Geologic Cross Sections 2.5-21b Site Geologic Cross Sections 2.5-22 Plot Plan 2.5-22a Plot Plan Details 2.5-23a Log of Borings 2.5-23b Log of Borings 2.5-23c Log of Borings 2.5-23d Log of Borings 2.5-23e Log of Borings 2.5-23f Log of Borings 2.5-23g Log of Borings 2.5-23h Log of Borings 2.5-23i Log of Borings 2.5-23j Log of Borings 2.5-23k Log of Borings 2.5-23l Log of Borings 2.5-23m Log of Borings 2.5-23n Log of Borings 2.5-23o Log of Borings 2.5-23p Log of Borings 2.5-23q Log of Borings 2.5-23r Log of Borings 2.5-23s Log of Borings FSAR Rev. 71 Page 16 of 113
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TABLE OF CONTENTS Chapter 2 Figures 2.5-23t Log of Borings 2.5-24 Final Plant Grades 2.5-25 Tectonic Map of Anthracite Region 2.5-26 Geologic Section of Anthracite Region 2.5-27 Design Response Spectra-Safe Shutdown Earthquake 2.5-28 Design Response Spectra-Operating Basis Earthquake 2.5-29 Geophysical Surveys 2.5-30 Spray Pond-Generalized Cross-Sections 2.5-30a Diesel Generator 'E' Fuel Tank - Generalized Cross-Sections 2.5-31 Spray Pond, Range of Grain Size Curves 2.5-32 Relative Density Related to N Value at ESSW Pumphouse Site 2.5-33 "N" Value Versus Elevation at ESSW Pumphouse Site 2.5-34 Spray Pond, Consolidated Drained Triaxial Test - Mohr Circle Diagram 2.5-35 Spray Pond, Summary of Cyclic Shear Test (CR) Results 2.5-36 Spray Pond, Shear Wave Velocity Design Curves 2.5-37 Location and Limits of Excavation Fill and Backfill for Class 1 Structures 2.5-38 Location of Spray Pond with Contours on Top of Rock and Water Table 2.5-39 Lateral Soil Pressure Diagrams 2.5-40 Spray Pond, Measured and Projected Water Levels 2.5-41 Details of Settlement Pins Cast in ESSW Pumphouse Basemat 2.5-42 Spray Pond, Earthwork Plan 2.5-43 Figure replaced by Drawing C-63, Sh. 1 2.5-44 Spray Pond, Boring and Test Pits Location Plan 2.5-45 Spray Pond, Generalized Cross Sections with Laboratory Test Locations 2.5-46 Spray Pond, Relative Density Related to "N" Value 2.5-47 Spray Pond, Relationship Between Seepage Loss and Maximum Groundwater Elevation 2.5-48 Spray Pond, Soil Profiles Used in Liquefaction Analysis 2.5-49 Spray Pond, Factor of Safety Variation with Groundwater Table and Depth 2.5-50 Spray Pond, Minimum Factor of Safety Against Liquefaction At Selected Locations 2.5-50A Variation Factor of Safety (F.S) vs Change of Damping Ratio 2.5-51 Spray Pond, Comparison of Factors of Safety for Liquefaction for the Design Earthquake and Some Real Earthquakes 2.5-52 Spray Pond, Comparison of Average Cycle Stress As Induced by Design Earthquake and Some Real Earthquakes 2.5-53 Spray Pond, Average Shear Variation with Depth 2.5-54 Spray Pond, Summary of Pore Pressure Buildup 2.5-55 Site Water Table Map (Preconstruction) 2.5-56 Profile of Slope North of Spray Pond 2.5-57 Spray Pond Relationship Between Liner Thickness, Liner Permeability and Seepage Loss 2.5-58 Damping Ratio Versus Shear Strain of Sand in Liquefaction Analysis 2.5-59 Sample Locations of Soil Density Tests 2.5-60 Statistical Analysis of Field Density Test Results 2.5-61 Statistical Analysis of Sand-Cement-Flyash Bedding and Backfill 2.5-62 ESSW Pumphouse Floor Plan El. 685'-6" FSAR Rev. 71 Page 17 of 113
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TABLE OF CONTENTS Chapter 3 3.0 DESIGN OF STRUCTURES, COMPONENTS, EQUIPMENT SYSTEMS 3.1 Conformance with NRC General Design Criteria 3.1.1 Summary Description 3.1.2 Criterion Conformance 3.2 Classification of Structures, Components and Systems 3.2.1 Seismic Classification 3.2.2 System Quality Group Classification 3.2.3 System Safety Classifications 3.2.4 Quality Assurance 3.2.5 Correlation of Safety Classes with Industry Codes 3.3 Wind and Tornado Loadings 3.3.1 Wind Loadings 3.3.2 Tornado Loadings 3.3.3 References 3.4 Water Level (Flood) Design 3.5 Missile Protection 3.5.1 Missile Selection and Description 3.5.2 Systems to be Protected 3.5.3 Barrier Design Procedures 3.5.4 References 3.6 Protection against Dynamic Effects Associated with the Postulated Rupture of Piping 3.6.1 Postulated Piping Failures in Fluid Systems 3.6.2 Determination of Pipe Failure Locations and Dynamic Effects Associated with the Postulated Piping Failure 3.6.3 Definitions 3.6.4 References 3.6A Pipe Break Outside Containment Summary of Analysis and Results 3.7A Seismic Design 3.7a.1 Seismic Input 3.7a.2 Seismic System Analysis 3.7a.3 Seismic Subsystem Analysis 3.7a.4 Seismic Instrumentation 3.7a.5 References 3.7B Seismic Design 3.7b.1 Seismic Input 3.7b.2 Seismic System Analysis 3.7b.3 Seismic Subsystem Analysis 3.7b.4 Seismic Instrumentation FSAR Rev. 71 Page 18 of 113
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TABLE OF CONTENTS Chapter 3 3.7b.5 References 3.8 Design of Category I Structures 3.8.1 Concrete Containment 3.8.2 ASME Class MC Steel Components of the Containment 3.8.3 Containment Internal Structures 3.8.4 Other Seismic Category I Structures 3.8.5 Foundations 3.8A Computer Programs 3.8A.1 D/SAP 3.8A.2 ASHSD 3.8A.3 CECAP 3.8A.4 CE 668 3.8A.5 EASE 3.8A.6 EO119 3.8A.7 EO781 3.8A.8 FINEL 3.8A.9 ME620 3.8A.10 SUPERB 3.8A.11 References 3.8B Concrete, Concrete Materials, Quality Control, and Special Construction Techniques 3.8B.1 Concrete and Concrete Materials - Qualifications 3.8B.2 Concrete and Concrete Materials - Batching, Placing, Curing and Protection 3.8B.3 Concrete and Concrete Materials - Construction Testing 3.8B.4 Concrete Reinforcement Materials - Qualifications 3.8B.5 Concrete Reinforcement Materials - Fabrication 3.8B.6 Concrete Reinforcement Materials - Construction Testing 3.8B.7 Formwork and Construction Joints 3.8C Concrete Unit Masonry, Masonry Materials and Quality Control 3.8C.1 Concrete Unit Masonry and Masonry Materials - Qualifications 3.8C.2 Concrete Unit Masonry and Masonry Materials - Construction and Erection 3.8C.3 Concrete Unit Masonry and Masonry Materials - Construction Testing 3.9 Mechanical Systems and Components 3.9.1 Special Topics for Mechanical Components 3.9.2 Dynamic Testing and Analysis 3.9.3 ASME Code Class 1, 2, and 3 Components, Component Supports, and Core Support Structures 3.9.4 Control Rod Drive System 3.9.5 Reactor Pressure Vessel Internals 3.9.6 In-service Testing of Pumps and Valves 3.9.7 References 3.9A Computer Programs 3.9A.1 ME101 FSAR Rev. 71 Page 19 of 113
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TABLE OF CONTENTS Chapter 3 3.9A.2 ME632 3.9A.3 ME912 3.9A.4 ME913 3.9A.5 References 3.10 Seismic Qualifications of Category I Instrumentation and Electrical Equipment 3.10A Seismic Qualification of Seismic Category I NSSS Instrumentation and Electrical Equipment 3.10a.1 Seismic Qualification Criteria 3.10a.2 Methods and Procedures for Qualifying Electrical Equipment and Instrumentation (Excluding Motors and Valve Mounted Equipment) 3.10a.3 Methods and Procedure of Analysis or Testing of Supports of Electrical Equipment and Instrumentation 3.10a.4 Operating License Review 3.10a.5 Dynamic Analysis By Response Spectrum Method 3.10B Seismic Qualification of Non-NSSS Supplied Seismic Category I Instrumentation 3.10b.1 Seismic Qualification Criteria 3.10b.2 Seismic Category I Equipment Qualification 3.10b.3 Methods and Procedures of Analysis or Testing of Supports of Instrumentation 3.10b.4 Operating License Review 3.10C Seismic Qualification of Non-NSSS Seismic Category I Electrical Equipment 3.10c.1 Seismic Qualification Criteria 3.10c.2 Methods and Procedures for Qualifying Electrical Equipment 3.10c.3 Methods and Procedures of Analysis or Testing of Supports of Electrical Equipment 3.10c.4 Operating License Review 3.11 Environmental Design of Mechanical and Electrical Equipment 3.11.1 Equipment Identification and Environmental Conditions 3.11.2 Qualification Test and Analysis 3.11.3 Qualification Test Results 3.11.4 Loss of Ventilation 3.11.5 Estimated Chemical, Physical, and Radiation Environment 3.11.6 References 3.12 Separation Criteria for Safety-Related Mechanical and Electrical Equipment 3.12.1 Introduction 3.12.2 Mechanical Systems 3.12.3 Electrical Systems and Equipment Separation Criteria FSAR Rev. 71 Page 20 of 113
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TABLE OF CONTENTS Chapter 3 3.13 Compliance with NRC Regulatory Guides 3.13.1 Division 1, Regulatory Guides - Power Reactors 3.14 License Renewal Programs, TLAA and Commitments 3.14.1 Introduction 3.14.2 Aging Management Program (AMP) 3.14.3 Evaluation of Time-Limited Aging Analysis (TLAA) 3.14.4 License Renewal Regulatory Commitments List 3.14.5 Newly Identified Items (10 CFR 54.37 (b))
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TABLE OF CONTENTS Chapter 3 Tables 3.2-1 SSES Design Criteria Summary 3.2-2 Summary of Codes and Standards for Components of Water-Cooled Nuclear Power Units Supplied by AE (ordered prior to July 1, 1971 with the exception of those components located inside the RCPB, and the reactor pressure vessel) 3.2-3 Summary of Codes and Standards for Components of Water-Cooled Nuclear Power Units Supplied by AE (ordered after July 1, 1971) 3.2-4 Code Group Designations - Industry Codes and Standards for Mechanical Components Supplied by the NSSS Vendor 3.2-5 Summary of Safety Class Design Requirements (Minimum) 3.3-1 Wind Loads on Structures 3.3-2 Tornado Wind Protected Systems and Tornado Resistant Enclosures 3.5-4 Tornado-Generated Missile Parameters for All Tornado-Resistant Structures Except the Diesel Generator 'E' Building 3.5-4a Tornado-Generated Missile Parameters for Diesel Generator 'E' Building 3.5-5 Berwick Airport Movement Summary 3.5-6 Plant Target Areas 3.5-7 Calculated Stress for Bonnet-Seal Type Valves 3.5-10 Turbine System Reliability Criteria 3.6-1 High Energy Fluid System Piping 3.6-1a Moderate Energy Fluid System Piping (Located in Safety-Related Structures) 3.6-2 Safety Components in Close Proximity to High Energy Fluid System Piping -
(Requiring Jet Impingement Protection) Primary Containment) 3.6-3 Safety Components in Close Proximity to High Energy Fluid System Piping -
(Requiring Jet Impingement Protection) Reactor Building 3.6-4 Restraint Data 3.6-5 Comparison of PDA and NSC Code 3.6-6a Summary of Stress in High Energy ASME Class 1 Piping - Main Steam Line Inside Containment - Unit 1-Line "A" 3.6-6b Summary of Stress in High Energy ASME Class 1 Piping - Main Steam Line Inside Containment - Unit 1-Line "B" 3.6-6c Summary of Stress in High Energy ASME Class 1 Piping - Main Steam Line Inside Containment - Unit 1-Line "C" 3.6-6d Summary of Stress in High Energy ASME Class 1 Piping - Main Steam Line Inside Containment - Unit 1-Line "D" 3.6-6e Summary of Stress in High Energy ASME Class 1 Piping - Main Steam Line Inside Containment - Unit 2-Line "A" 3.6-6f Summary of Stress in High Energy ASME Class 1 Piping - Main Steam Line Inside Containment - Unit 2-Line "B" 3.6-6g Summary of Stress in High Energy ASME Class 1 Piping - Main Steam Line Inside Containment - Unit 2-Line "C" 3.6-6h Summary of Stress in High Energy ASME Class 1 Piping - Main Steam Line Inside Containment - Unit 2-Line "D" 3.6-7 Summary of Stress in High Energy ASME Class 1 Piping - Feedwater Line Inside Containment-Unit 1 FSAR Rev. 71 Page 22 of 113
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TABLE OF CONTENTS Chapter 3 Tables 3.6-7a Summary of Stress in High Energy ASME Class 1 Piping - Feedwater Line Inside Containment-Unit 2 3.6-8 Summary of Stress in High Energy ASME Class 1 Piping - HPCI Steam Supply Line Inside Containment - Unit 1 3.6-8a Summary of Stress in High Energy ASME Class 1 Piping - HPCI Steam Supply Line Inside Containment - Unit 2 3.6-9 Summary of Stress in High Energy ASME Class 1 Piping - RCIC Steam Supply Line Inside Containment - Unit 1 3.6-9a Summary of Stress in High Energy ASME Class 1 Piping - RCIC Steam Supply Line Inside Containment - Unit 2 3.6-10 Summary of Stress in High Energy ASME Class 1 Piping - Core Spray Line Inside Containment-Unit 1 3.6-10a Summary of Stress in High Energy ASME Class 1 Piping - Core Spray Line Inside Containment-Unit 2 3.6-11 Summary of Stress in High Energy ASME Class 1 Piping - RHR Supply Line Inside Containment - Unit 1 3.6-11a Summary of Stress in High Energy ASME Class 1 Piping - RHR Supply Line Inside Containment - Unit 2 3.6-12a Summary of Stress in High Energy ASME Class 1 Piping - RHR Return Line Inside Containment Unit 1 Loop "A" 3.6-12a.1 Summary of Stress in High Energy ASME Class 1 Piping - Reactor Water Clean Up Line Inside Containment - Unit 1 3.6-12a.2 Summary of Stress in High Energy ASME Class 1 Piping - Reactor Water Clean Up Line Inside Containment - Unit 1 3.6-12a.3 Summary of Stress in High Energy ASME Class 1 Piping - Reactor Water Clean Up Line Inside Containment - Unit 1 3.6-12a.4 Summary of Stress in High Energy ASME Class 1 Piping - Reactor Water Clean Up Line Inside Containment - Unit 2 3.6-12a.5 Summary of Stress in High Energy ASME Class 1 Piping - Reactor Water Clean Up Line Inside Containment - Unit 2 3.6-12a.6 Summary of Stress in High Energy ASME Class 1 Piping - RHR Return Line Inside Containment - Unit 2-Loop "A" 3.6-12a.7 Summary of Stress in High Energy ASME Class 1 Piping - Reactor Water Clean Up Line Inside Containment-Unit 2 3.6-12b Summary of Stress in High Energy ASME Class 1 Piping - RHR Return Line Inside Containment Unit 1 Loop "B" 3.6-12b.1 Summary of Stress in High Energy ASME Class 1 Piping - Head Vent Line Inside Containment-Unit 1 3.6-12b.2 Summary of Stress in High Energy ASME Class 1 Piping - Head Vent Line Inside Containment-Unit 1 3.6-12b.3 Summary of Stress in High Energy ASME Class 1 Piping - RHR Return Line Inside Containment-Unit 2 - Loop "B" 3.6-12b.4 Summary of Stress in High Energy ASME Class 1 Piping - Head Vent Line Inside Containment-Unit 2 3.6-12c Summary of Stress in High Energy ASME Class 1 Piping - Head Spray Line Inside Containment-Unit 1 3.6-12c.1 Summary of Stress in High Energy ASME Class 1 Piping - Head Spray Line Inside Containment-Unit 2 FSAR Rev. 71 Page 23 of 113
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TABLE OF CONTENTS Chapter 3 Tables 3.6-12d.1 Summary of Stress in High Energy ASME Class 1 Piping - Standby Liquid Control Line Inside Containment-Unit 1 3.6-12d.3 Summary of Stress in High Energy ASME Class 1 Piping - Standby Liquid Control Line Inside Containment-Unit 2 3.6-12e.1 Summary of Stress in High Energy ASME Class 1 Piping - MSIV Drain Lines Inside Containment - Unit 1 3.6-12e.2 Summary of Stress in High Energy ASME Class 1 Piping - MSIV Drain Lines Inside Containment - Unit 1 3.6-12e.3 Summary of Stress in High Energy ASME Class 1 Piping - MSIV Drain Lines Inside Containment - Unit 2 3.6-13 High Energy Fluid Systems With and Without Sufficient Capacity to Develop a Jet Stream 3.6-14 Summary of Stress in High Energy ASME Class 1 Piping - Recirculation Piping System - Loop "A" - Unit 1 3.6-15 Summary of Stress in High Energy ASME Class 1 Piping - Recirculation Piping System - Loop "A" -Unit 2 3.6A-1 Comparison of Flow Rates Computed from the Time Dependent Momentum Equation 3.6A-2 Case A - Steam Tunnel Compartment Volumes 3.6A-3 Steam Tunnel Flow Areas Coefficients and L/A 3.6A-4 For Case A & Case B 3.6A-5 Case B - Steam Tunnel Compartment Volumes 3.6A-6 Steam Tunnel Flow Areas Coefficients and L/A 3.7a-1 Critical Damping Ratios for Different Materials 3.7a-3 Number of Dynamic Response Cycles Expected During a Seismic Event 3.7b-1 Amplification Factors for Ground Spectra 3.7b-2 Amplification Factors for Diesel Generator 'E' Building's Ground Spectra 3.7b-3 Damping Values for Non-NSSS Materials (Percent of Critical Damping) 3.7b-4 Damping Values for Diesel Generator 'E' Facility 3.7b-5 Structure Foundation Interaction Coefficients 3.7b-6 Properties of Foundation Media for Containment and ESSW Pumphouse 3.7b-7 Natural Frequencies of Containment Below 33 CPS 3.7b-8 Natural Frequencies of the Reactor and Control Building Below 33 CPS 3.7b-9 ESSW Pumphouse: Frequencies With and Without Eccentricities 3.7b-10 Diesel Generator A-D Building Frequencies With and Without Eccentricities 3.7b-11 Comparisons of Torsional Moments Between Original Design and the Values Computed from the Results of 3-D Stick Model 3.8-1 List of Applicable Codes, Standards, Recommendations, and Specifications 3.8-2 Load Combinations for Primary Containment, Drywell Floor 3.8-2a Load Combinations for Reactor Pedestal 3.8-3 Load Combinations and Allowable Stresses For ASME Class MC Components 3.8-3a Comparison of FSAR and SRP Load Combinations and Allowable Stresses for ASME Class MC Components 3.8-4 Load Combination for the Reactor Shield Wall FSAR Rev. 71 Page 24 of 113
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TABLE OF CONTENTS Chapter 3 Tables 3.8-5 Load Combinations for the Suppression Chamber Columns 3.8-6 Load Combinations for the Drywell Platforms 3.8-7 Load Combination for the Seismic Truss 3.8-8 Load Combinations Applicable to Reactor Building 3.8-9 Load Combinations Applicable to Seismic Category I Structures Other Than Containment, Reactor Building and Diesel Generator 'E' Building 3.8-9a Load Combinations Applicable to Diesel Generator 'E' Building 3.8-10 Load Combinations Applicable to Turbine & Radwaste Building 3.8-11 Concrete Design Compressive Strengths 3.8-12 Allowable Stress Increase Factor for Masonry Structures 3.8A-1 Tabulation of Membrane Stress Resultants From the ASHSD Program 3.8A-2 CECAP and Hand Calculation Comparison - Thermal Gradient 3.8A-3 Comparison of CECAP and Hand Calculation Results - Real Moment 3.8A-4 CECAP and Hand Calculation Comparison - Real Moment and Real Compressive Load 3.8A-5 Comparison of Results for the Rectangular Plate with a Concentrated Load at the Center 3.8A-6 Comparison of Results for the Rectangular Plate with Various Edge Conditions 3.8A-7 Comparison of Stresses for Welding Neck Flange 3.8A-8 Comparison of Stresses for Slip-On Flange 3.8A-9 Comparison of Final Results for Hoop Force, N, and Meridional Moment, M 3.8A-10 Material Properties of the Concrete and Reinforcing Steel Used for FINEL Verification 3.8A-11 Loading History Used for the FINEL Verification 3.8A-12 Comparison of Stress Results 3.8A-13 Comparison of Stress Results 3.8A-14 Comparison of Results 3.8B-1 Minimum Testing Frequencies for Concrete Materials and Concrete (Except for the Diesel Generator 'E' Building) 3.8B-2 Testing Requirements for Concrete Materials Used in the Diesel Generator 'E' Building 3.8B-3 Testing Requirements for Concrete Used in the Diesel Generator 'E' Building 3.9-1 Transients and the Number of Associated Cycles Considered in the Design and Fatigue Analysis of the RPV Assembly and Internal Transients 3.9-2 Introduction/ Index/ Load Combination and Acceptance Criteria for ASME Code Class 1, 2, and 3 NSSS Piping and Equipment 3.9-2a Reactor Pressure Vessel and Shroud Support Assembly 3.9-2b Reactor Internals and Associated Equipment 3.9-2(c) Reactor Water Cleanup Heat Exchangers 3.9-2d ASME Code Class I Main Steam Piping and Pipe Mounted Equipment - Highest Stress Summary - Unit 1 3.9-2d.1 ASME Code Class I Main Steam Piping and Pipe Mounted Equipment - Highest Stress Summary - Unit 2 3.9-2e ASME Code Class I Recirculation Piping and Pipe Mounted Equipment - Highest Stress Summary - Unit 1 FSAR Rev. 71 Page 25 of 113
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TABLE OF CONTENTS Chapter 3 Tables 3.9-2e.1 ASME Code Class I Recirculation Piping and Pipe Mounted Equipment - Highest Stress Summary - Unit 2 3.9-2g Safety/Relief Valves (Main Steam) 3.9-2(h) Main Steam Isolation Valve 3.9-2i Recirculation Pump 3.9-2(j) Reactor Recirculation System Gate Valves, Discharge Structural & Mechanical Loading Criteria 3.9-2L Standby Liquid Control Pump 3.9-2m Standby Liquid Control Tank 3.9-2n (i) RHR Pumps (ii) Core Spray Pumps 3.9-2o RHR Heat Exchanger 3.9-2(p) RWCU Pump 3.9-2q RCIC Turbine 3.9-2(r) RCIC Pump 3.9-2s Reactor Refueling and Servicing Equipment 3.9-2t High Pressure Coolant Injection Pump 3.9-2u Control Rod Drive (Index Tube) 3.9-2v Control Rod Drive Housing 3.9-2w Jet Pumps 3.9-2aa Control Rod Guide Tube Flange 3.9-2ab Incore Housing 3.9-2(ac) Reactor Vessel Support Equipment CRD Housing Support 3.9-2(ae) HPCI Turbine Design Calculations 3.9-2(af) High Density Spent Fuel Racks 3.9-3 NSSS Seismic Category I Active Pumps and Valves 3.9-4 Applicable Thermal Transients 3.9-5 List of Computer Programs Used in BOP Mechanical Systems and Components 3.9-6 Design Loading Combinations For ASME Code Class 1, 2, and 3 Components 3.9-7 Design Criteria for ASME Code Class I Valves 3.9-8 Design Criteria for ASME Code Class 2 and 3 Vessels Designed to NC-3300 and ND-3300 3.9-9 Design Criteria for ASME Code Class 2 Vessels Designed to Alternate Rules of NC-3200 3.9-10 Design Criteria for ASME Code Class 2 and 3 Piping 3.9-11 Design Criteria for ASME Code Class 2 and 3 Pumps 3.9-12 Design Criteria for ASME Code Class 2 and 3 Valves 3.9-14 Design Loading Combinations for Supports for ASME Code Class 1, 2 and 3 Components 3.9-15 Valve Qualification Test Range 3.9-16 Listing of Dynamically Qualified Equipment 3.9-17 Diesel Generator 'A-D' Seismic Test or Analysis Submittal Chart 3.9-18 Summary Comparison - Project Specification -10, "General Project Requirements for A Seismic Design and Analysis of Class 1 Equipment and Equipment Supports" 3.9-20 BOP Piping System Power Ascension Testing 3.9A-1 Comparison Between Sample Problem and Computer Program ME 913 Results 3.9A-2 Comparison of ME912 with ME643 and Analytical Results FSAR Rev. 71 Page 26 of 113
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TABLE OF CONTENTS Chapter 3 Tables 3.10a-1 Essential Electrical Components and Instruments 3.10a-2 Seismic Qualification Test Summary Class IE Control Panels and Local Panels and Racks 3.10a-3 Summary of Sample Seismic Static Analysis For Three Typical Cabinets 3.10a-4 Seismic Design Verification Data Sheet 3.10c-1 Secondary Unit Substations and Power Transformers 3.10c-2 Motor Control Centers 3.10c-3 Battery Monitors and Fuse Boxes 3.10c-4 DC Distribution Panels 3.10c-5 Battery Racks 3.10c-6 Electrical Cable Penetration 3.10c-7 Cable Trays "Safeguard" 3.10c-8 Battery Charger Racks and Cabinets 3.10c-9 Large Induction Motors 4000V 3.10c-10 Panels and Termination Cabinets 3.10c-11 Battery Chargers 3.10c-12 4.16 KV Switchgear 3.10c-13 DC Control and Load Centers 3.10c-14 Instrument AC Transformers 3.10c-15 Automatic Transfer Switches 3.10c-16 Load Isolation Motor-Generator Sets 3.10c-17 Non-NSSS and Non-ACR Relays Required to be Energized 3.10c-18 Inverters and 120V AC Instrument Panels 3.11-1 Normal and Maximum Plant Environmental Conditions 3.11-7 Water Quality 3.12-1 ESF Division Separation 3.12-2 Channel Separation 3.12-3 Main Control Room and Relay Panel Annunciator and Computer Interface Device 3.13-1 Comparison with Regulatory Guide 1.48 3.14-1 License Renewal Commitments 3.14-2 Newly Identified Structures, Systems, and Components (SSC)
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TABLE OF CONTENTS Chapter 3 Figures 3.2-1 Code Classification of Piping Valves 3.2-2 Minimum Instrument Line Classifications 3.5-6 Figure replaced by Drawing A-17, Sh. 1 3.5-7 Figure replaced by Drawing A-21, Sh. 1 3.5-8 Figure replaced by Drawing A-5, Sh. 1 3.5-9 Typical 900# Bonnet Seal Type Valve 3.5-10 Retaining Ring Design for 900# Bonnet-Seal Type Valve 3.6-1A Main Steam Line A 3.6-1B Main Steam Line B 3.6-1C Main Steam Line C 3.6-1D Main Steam Line D 3.6-2 Feedwater System 3.6-3 HPCI Steam Supply 3.6-4 RCIC Steam Supply 3.6-5 Core Spray 3.6-6 RHR Supply 3.6-7 RHR Return Loop A 3.6-8 RHR Return Loop B 3.6-8A.1 Reactor Water Cleanup 3.6-8A.2 Reactor Water Cleanup 3.6-8A.3 Reactor Water Cleanup 3.6-8A.4 Reactor Water Cleanup 3.6-8A.5 Reactor Water Cleanup 3.6-8B Reactor Vessel Head Vent 3.6-8C Head Spray 3.6-8D Standby Liquid Control 3.6-8E MSIV Drains 3.6-10 Typical Pipe Whip Restraints 3.6-11 Pipe Whip Restraint Arrangement to Protect Feedwater Outside Containment Isolation Valves 3.6-11a Main Feedwater Line PIPERUP Mathematical Model 3.6-12 Forcing Functions Model Associated with Pipe Whip Dynamic Analysis 3.6-12a Forcing Functions Model Associated with Pipe Whip Dynamite Analysis 3.6-13 Typical Pipe Whip Restraint Configuration 3.6-14 Recirculation System Postulated Break Locations and Restraint Locations (LOOP A and B Same, Unless Otherwise Specified) 3.6-15 Typical Restraint Force-Deflection Curve 3.6-16 Break Locations and Restraints Analyzed, PDA Verification Program 3.6-17-1 Pipe Break Protection for High Energy Piping in the Reactor Building 3.6-17-2 Pipe Break Protection for High Energy Piping in the Reactor Building 3.6-17-3 Pipe Break Protection for High Energy Piping in the Reactor Building 3.6A-1 Case A MSLB in Reactor Building 3.6A-2 Panel and Platform Locations 3.6A-3 Case A Volume Flows 3.6A-4 Case A Pressure Transient FSAR Rev. 71 Page 28 of 113
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TABLE OF CONTENTS Chapter 3 Figures 3.6A-5 Case B MSLB in Turbine Building 3.6A-6 Case B Volume Flows 3.6A-7 Case B Pressure Transient 3.6A-8 Model for Double-Ended Guillotine MSLB 3.7a-1 Reactor Pressure Vessel and Internal Seismic Model 3.7a-2 Density of Stress Reversals 3.7b-2 Diesel Generator 'E' Building Design Response Spectra Safe Shutdown Earthquake Horizontal Component 3.7b-3 Design Response Spectra Safe Shutdown Earthquake Horizontal Component 3.7b-4 Diesel Generator E Buildings Design Response Spectra Safe Shutdown Earthquake Horizontal Component 3.7b-5 Synthetic Time History Normalized to 1G 3.7b-6 Diesel Generator E Building Horizontal Synthetic Time History Normalized to 0.1G 3.7b-7 Diesel Generator E Building Vertical Synthetic Time History Normalized to 0.1G 3.7b-8 Comparison of Time History Response Spectra and Design Response Spectra 2%
and 5% Damping (0.2-30 CPS) 3.7b-9 Comparison of Time History Response Spectra and Design Response Spectra 3%
and 7% Damping (0.2-30 CPS) 3.7b-10 Comparison of Time History Response Spectra and Design Response Spectra 2%
and 5% Damping (0.2-1.0 CPS) 3.7b-11 Diesel Generator E Building Comparison of Horizontal Time History Response Spectrum and Horizontal Design Response Spectrum 2% Damping 3.7b-12 Diesel Generator E Building Comparison of Horizontal Time History Response Spectrum and Horizontal Design Response Spectrum 5% Damping 3.7b-13 Diesel Generator E Building Comparison of Horizontal Time History Response Spectrum and Horizontal Design Response Spectrum 7% Damping 3.7b-14 Diesel Generator E Building Comparison of Vertical Time History Response Spectrum and Vertical Design Response Spectrum 2% Damping 3.7b-15 Diesel Generator E Building Comparison of Vertical Time History Response Spectrum and Vertical Design Response Spectrum 5% Damping 3.7b-16 Diesel Generator E Building Comparison of Vertical Time History Response Spectrum and Vertical Design Response Spectrum 7% Damping 3.7b-17 Horizontal Seismic Model of Containment With Flexible Base 3.7b-18 Vertical Seismic Model of Containment With Flexible Base 3.7b-19 E-W Seismic Model of Reactor and Control Building 3.7b-20 N-S Seismic Model of Reactor and Control Building 3.7b-21 Vertical Seismic Model of Reactor and Control Building 3.7b-22 Plan View of Reactor and Control Building 3.7b-23 Correlation of Vertical Seismic Model Masspoints of the Physical Structure 3.7b-24 Containment Horizontal Mode Shapes Mode 1 3.7b-25 Containment Horizontal Mode Shapes Mode 2 3.7b-26 Containment Horizontal Mode Shapes Mode 4 3.7b-27 Containment Vertical Mode Shapes Mode 1 3.7b-28 Containment Vertical Mode Shapes Mode 2 3.7b-29 Containment Vertical Mode Shapes Mode 3 FSAR Rev. 71 Page 29 of 113
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TABLE OF CONTENTS Chapter 3 Figures 3.7b-30 Reactor and Control Building E-W Mode Shapes - Mode 1 (Cranes at Points 32 and 33) 3.7b-31 Reactor and Control Building E-W Mode Shapes - Mode 2 3.7b-32 Reactor and Control Building E-W Mode Shapes - Mode 3 (Cranes at Points 32 and 33) 3.7b-33 Reactor and Control Building E-W Mode Shapes - Mode 4 3.7b-34 Reactor and Control Building E-W Mode Shapes, Mode 5 3.7b-35 Reactor and Control Building N-S Mode Shapes - Mode 1 3.7b-36 Reactor and Control Building N-S Mode Shapes - Mode 3 3.7b-37 Reactor and Control Building Vertical Mode Shapes Mode 1 3.7b-38 Reactor and Control Building Vertical Mode Shapes Mode 2 3.7b-39 Reactor and Control Building Vertical Mode Shapes Mode 3 3.7b-40 Containment Horizontal Displacements OBE 3.7b-41 Containment Horizontal Displacements SSE 3.7b-42 Containment Vertical Displacements OBE 3.7b-43 Containment Vertical Displacements SSE 3.7b-44 Containment Horizontal Accelerations OBE 3.7b-45 Containment Horizontal Accelerations SSE 3.7b-46 Containment Vertical Accelerations OBE 3.7b-47 Containment Vertical Accelerations SSE 3.7b-48 Reactor and Control Building E-W Displacements OBE 3.7b-49 Reactor and Control Building E-W Displacements SSE 3.7b-50 Reactor and Control Building N-S Displacements OBE 3.7b-51 Reactor and Control Building N-S Displacements SSE 3.7b-52 Reactor and Control Building Vertical Displacements OBE 3.7b-53 Reactor and Control Building Vertical Displacements SSE 3.7b-54 Reactor and Control Building E-W Accelerations OBE 3.7b-55 Reactor and Control Building E-W Accelerations SSE 3.7b-56 Reactor and Control Building N-S Accelerations OBE 3.7b-57 Reactor and Control Building N-S Accelerations SSE 3.7b-58 Reactor and Control Building Vertical Acceleration OBE 3.7b-59 Reactor and Control Building Vertical Accelerations SSE 3.7b-60 Response Spectrum at RPV Pedestal Horizontal OBE 3.7b-61 Response Spectrum at RPV Pedestal Horizontal SSE 3.7b-62 Response Spectrum at RPV Pedestal Vertical OBE 3.7b-63 Response Spectrum at RPV Pedestal Vertical SSE 3.7b-64 Response Spectrum at Refueling Area E-W OBE 3.7b-65 Response Spectrum at Refueling Area E-W SSE 3.7b-66 Response Spectrum at Refueling Area N-S OBE 3.7b-67 Response Spectrum at Refueling Area N-S SSE 3.7b-68 Response Spectrum at Refueling Area Vertical OBE 3.7b-69 Response Spectrum at Refueling Area Vertical SSE 3.7b-70 Response Spectrum at Top of Pedestal (Diesels A-D) E-W OBE 3.7b-71 Response Spectrum at Top of Pedestal (Diesel E) E-W OBE 3.7b-72 Response Spectrum at Top of Pedestal (Diesels A-D) E-W SSE 3.7b-73 Response Spectrum at Top of Pedestal (Diesel E) E-W SSE 3.7b-74 Response Spectrum at Top of Pedestal (Diesels A-D) N-S OBE 3.7b-75 Response Spectrum at Top of Pedestal (Diesel E) N-S OBE FSAR Rev. 71 Page 30 of 113
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TABLE OF CONTENTS Chapter 3 Figures 3.7b-76 Response Spectrum at Top of Pedestal (Diesels A-D) N-S SSE 3.7b-77 Response Spectrum at Top of Pedestal (Diesel E) N-S SSE 3.7b-78 Response Spectrum at Top of Pedestal (Diesels A-D) Vertical OBE 3.7b-79 Response Spectrum at Top of Pedestal for Diesel E Vertical OBE 3.7b-80 Response Spectrum at Top of Pedestal (Diesels A-D) Vertical-SSE 3.7b-81 Response Spectrum at Top of Pedestal for Diesel E Vertical SSE 3.7b-82 Response Spectrum at Operating Floor of ESSW Pumphouse E-W OBE 3.7b-83 Response Spectrum at Operating Floor of ESSW Pumphouse E-W SSE 3.7b-84 Response Spectrum at Operating Floor of ESSW Pumphouse N-S OBE 3.7b-85 Response Spectrum at Operating Floor of ESSW Pumphouse N-S SSE 3.7b-86 Response Spectrum at Operating Floor of ESSW Pumphouse Vertical OBE 3.7b-87 Response Spectrum at Operating Floor of ESSW Pumphouse Vertical SSE 3.7b-88 Comparison of Design and R.G. 1.60 Response Spectra Horizontal OBE 3.7b-89 Comparison of Design and R.G. 1.60 Response Spectra Horizontal SSE 3.7b-90 Comparison of Design and R.G. 1.60 Response Spectra Vertical OBE 3.7b-91 Comparison of Design and R.G. 1.60 Response Spectra Vertical SSE 3.7b-92 Damping V/S ZPA for Raceway System 3.7b-93 ESSW Pump House 3-D Stick Model 3.7b-94 Diesel Generator 'A-D' Building 3-D Stick Model 3.7b-95 Diesel Generator E Building Seismic Models 3.8-1 Figure replaced by Drawing C-331, Sh. 1 3.8-2 Figure replaced by Drawing C-371, Sh. 1 3.8-3 Figure replaced by Drawing C-1932, Sh. 3 3.8-4 Figure replaced by Drawing C-1932, Sh. 4 3.8-5 Figure replaced by Drawing C-1932, Sh. 5 3.8-9 Primary Containment - Drywell Head Connection 3.8-10 Figure replaced by Drawing C-284, Sh. 1 3.8-11-1 Figure replaced by Drawing C-332, Sh. 1 3.8-11-2 Figure replaced by Drawing C-333, Sh. 1 3.8-12 Figure replaced by Drawing C-281, Sh. 1 3.8-13 Figure replaced by Drawing C-281, Sh. 1 3.8-14 Figure replaced by Drawing C-370, Sh. 1 3.8-15-1 Figure replaced by Drawing C-334, Sh. 1 3.8-15-2 Figure replaced by Drawing C-335, Sh. 1 3.8-15-3 Figure replaced by Drawing C-336, Sh. 1 3.8-15-4 Figure replaced by Drawing C-337, Sh. 1 3.8-15-5 Figure replaced by Drawing C-338, Sh. 1 3.8-16-1 Figure replaced by Drawing C-351, Sh. 1 3.8-16-2 Figure replaced by Drawing C-352, Sh. 1 3.8-16-3 Figure replaced by Drawing C-353, Sh. 1 3.8-16-4 Figure replaced by Drawing C-354, Sh. 1 3.8-16-5 Figure replaced by Drawing C-355, Sh. 1 3.8-16-6 Figure replaced by Drawing C-356, Sh. 1 3.8-16-7 Figure replaced by Drawing C-357, Sh. 1 3.8-16-8 Figure replaced by Drawing C-358, Sh. 1 3.8-16-9 Figure replaced by Drawing C-359, Sh. 1 3.8-16-10 Figure replaced by Drawing C-360, Sh. 1 FSAR Rev. 71 Page 31 of 113
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TABLE OF CONTENTS Chapter 3 Figures 3.8-16-11 Figure replaced by Drawing C-393, Sh. 1 3.8-16-12 Figure replaced by Drawing C-394, Sh. 1 3.8-16-13 Figure replaced by Drawing C-395, Sh. 1 3.8-16-14 Figure replaced by Drawing C-396, Sh. 1 3.8-16-15 Figure replaced by Drawing C-397, Sh. 1 3.8-16-16 Figure replaced by Drawing C-398, Sh. 1 3.8-16-17 Figure replaced by Drawing C-399, Sh. 1 3.8-16-18 Figure replaced by Drawing C-400, Sh. 1 3.8-17 Figure replaced by Drawing C-282, Sh. 1 3.8-18 Figure replaced by Drawing C-285, Sh. 1 3.8-19-1 Figure replaced by Drawing C-288, Sh. 1 3.8-19-2 Figure replaced by Drawing C-287, Sh. 1 3.8-19-3 Figure replaced by Drawing C-283, Sh. 1 3.8-20-1 Suppression Chamber Electrical Penetration Details 3.8-20-2 Drywell Electrical Penetration Details 3.8-21 Figure replaced by Drawing C-286, Sh. 1 3.8-22 Figure replaced by Drawing C-291, Sh. 1 3.8-23 Figure replaced by Drawing C-278, Sh. 1 3.8-24 Containment Wall Temperature Gradients 3.8-25 Containment Wall Analytical Model for Axisymmetric Loads 3.8-26 Drywell Wall Analytical Model for Non-Axisymmetric Missile and Postulated Pipe Rupture Loads 3.8-27 Base Foundation Slab Analytical Model 3.8-28 Equipment Hatch Analytical Model 3.8-29 Structural Acceptance Test - Pressurization Sequence 3.8-30 Structural Acceptance Test - Locations of Deflection Measuring Devices for the Containment 3.8-31 Structural Acceptance Test - Locations of Deflection Measuring Devices for the Equipment Hatch 3.8-32 Figure replaced by Drawing C-384, Sh. 1 3.8-33 Figure replaced by Drawing C-387, Sh. 1 3.8-34 Structural Acceptance Test - Containment Analytical Model 3.8-35 Structural Acceptance Test - Equipment Hatch Analytical Model 3.8-36 Structural Acceptance Test - Comparison of Measured and Predicted Deflections for the Containment 3.8-37 Structural Acceptance Test - Comparison of Measured and Predicted Deflection for the Equipment Hatch 3.8-38 Structural Acceptance Test -Inside Meridional Strain at Mid-height of Suppression Chamber Wall 3.8-39 Structural Acceptance Test - Inside Hoop Strain at Mid-height of Suppression Chamber Wall 3.8-40 Structural Acceptance Test - Outside Meridional Strain at Mid-height of Suppression Chamber Wall 3.8-41 Structural Acceptance Test - Outside Hoop Strain at Mid-height of Suppression Chamber Wall 3.8-42 Structural Acceptance Test - Outside Helical Strain at Mid-height of Suppression Chamber Wall FSAR Rev. 71 Page 32 of 113
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TABLE OF CONTENTS Chapter 3 Figures 3.8-43 Structural Acceptance Test - External Concrete Surface Cracks at Mid-height of Drywell Wall 3.8-44 Drywell Head 3.8-45 Analytical Model of Drywell Head Assembly 3.8-46-1 Figure replaced by Drawing C-348, Sh. 1 3.8-46-2 Figure replaced by Drawing C-349, Sh. 1 3.8-46-3 Figure replaced by Drawing C-350, Sh. 1 3.8-47 Figure replaced by Drawing C-293, Sh. 1 3.8-48 Figure replaced by Drawing C-340, Sh. 1 3.8-49 Figure replaced by Drawing C-341, Sh. 1 3.8-50 Figure replaced by Drawing C-376, Sh. 1 3.8-51-1 Figure replaced by Drawing C-344, Sh. 1 3.8-51-2 Figure replaced by Drawing C-377, Sh. 1 3.8-52 Figure replaced by Drawing C-362, Sh. 1 3.8-53 Figure replaced by Drawing C-363, Sh. 1 3.8-54 Figure replaced by Drawing C-354, Sh. 1 3.8-55 Figure replaced by Drawing C-365, Sh. 1 3.8-56 Figure replaced by Drawing C-367, Sh. 1 3.8-57 Figure replaced by Drawing C-380, Sh. 1 3.8-58 Temperature Gradients for Drywell Floor and Reactor Pedestal 3.8-59 Reactor Shield Wall Temperature Gradients 3.8-60 Drywell Floor Analytical Model 3.8-61 Analytical Model for Reactor Pedestal Above Drywell Floor 3.8-62 Reactor Shield Wall-EASE Program Analytical Model 3.8-63 Reactor Shield Wall-Analytical Model for "FINEL" and "ASHSD" Program 3.8-64 Suppression Chamber Columns - ASHSD Program Analytical Model 3.8-65 Suppression Chamber Columns - Seismic Model 3.8-66 Suppression Chamber Columns - "CE 668" Program Analytical Model 3.8-67 Seismic Truss Analytical Model 3.8-68 Structural Acceptance Test - Comparison of Measured and Predicted Deflections for the Drywell Floor 3.8-69 Figure replaced by Drawing A-11, Sh. 1 3.8-70 Figure replaced by Drawing A-12, Sh. 1 3.8-71 Figure replaced by Drawing A-13, Sh. 1 3.8-72 Figure replaced by Drawing M-203, Sh. 1 3.8-73 Figure replaced by Drawing M-204, Sh. 1 3.8-74 Figure replaced by Drawing A-16, Sh. 1 3.8-75 Figure replaced by Drawing A-17, Sh. 1 3.8-77 Reactor, Control and Turbine Building Sections Looking North 3.8-78 Reactor Building Looking West 3.8-79 Figure replaced by Drawing M-227, Sh. 1 3.8-80 Figure replaced by Drawing M-237, Sh. 1 3.8-81 Figure replaced by Drawing M-260, Sh. 1 3.8-82 Figure replaced by Drawing M-261, Sh. 1 3.8-83 Figure replaced by Drawing M-5200, Sh. 1 3.8-84 Figure replaced by Drawing M-5200, Sh. 2 3.8-85 Figure replaced by Drawing M-284, Sh. 1 3.8-86 Figure replaced by Drawing C-64, Sh. 1 FSAR Rev. 71 Page 33 of 113
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TABLE OF CONTENTS Chapter 3 Figures 3.8-87 Figure replaced by Drawing C-65, Sh. 1 3.8-88 Figure replaced by Drawing C-66, Sh. 1 3.8-89 Figure replaced by Drawing C-67, Sh. 1 3.8-90 Figure replaced by Drawing M-270, Sh. 1 3.8-91 Figure replaced by Drawing M-271, Sh. 1 3.8-92 Figure replaced by Drawing M-272, Sh. 1 3.8-93 Figure replaced by Drawing M-273, Sh. 1 3.8-94 Figure replaced by Drawing M-274, Sh. 1 3.8-95 Figure replaced by Drawing C-795, Sh. 1 3.8A-1 Thin Shell Cylinder 3.8A-2 Layered Cylinder 3.8A-3 General Layout of Cylinder 3.8A-4 Finite Element Model 3.8A-5 Axial Moment 3.8A-6 Cylinder with Hinged Ends 3.8A-7 Finite Element Model 3.8A-8-1 Comparison of Results for Cylindrical Shell Subjected to an Asymmetric Bending 3.8A-8-2 Comparison (Continued) of Results for Cylindrical Shell Subjected to Asymmetric Bending 3.8A-9 Reinforced Concrete Beam 3.8A-10 Reinforced Concrete Beam and CECAP Concrete Element Model 3.8A-11 Beam Cross-Section and Initial Stress Distribution 3.8A-12 Final Thermal Stress Distribution 3.8A-13 Reinforced Concrete Beam and CECAP Concrete Element Model 3.8A-14 Reinforced Concrete Beam and CECAP Concrete Element Model 3.8A-15 Reinforced Concrete Beam and CECAP Model 3.8A-16 Beam Cross-Section and Stress Block 3.8A-17 Plate Geometry, Loading, and Finite Element Mesh for Rectangular Plate with a Concentrated Load at the Center 3.8A-18 Plate Geometry, Loading, and Finite Element Mesh for Rectangular Plate with Various Edge Conditions 3.8A-19 Welding Neck Flange Detail 3.8A-20 Slip-On Flange Detail 3.8A-21 Geometry of Torispherical and Ellipsoidal Heads (Fit to Correspond to Geometry of Ellipsoidal Head in Reference 3.8A-9) 3.8A-22 Measured Thickness Variation in Experimental Head No. 1 (From Reference 3.8A-10, Page 18) 3.8A-23 Thickness Variation in Cylinder No. 1 (From Reference 3.8A-11 Fig. 4) 3.8A-24 Analytical Model with Boundary Conditions 3.8A-25 Plot of Hoop Force and Longitudinal Movement from E0781 Output 3.8A-26 Plot of Stress in the (Hoop) Direction on the Inside Surface ( = 0o) (Ref. 3.8A-12 Page G-14) 3.8A-27 Plot of Stress in the (Hoop) Direction on the Outside Surface ( = 0o) (Ref. 3.8A-12 Page G-11) 3.8A-28 Plot of Stress in the (Longitudinal) Direction on the Inside Surface ( = 0o) (Ref.
3.8A-12 Page G-20)
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TABLE OF CONTENTS Chapter 3 Figures 3.8A-29 Plot of Stress in the (Longitudinal) Direction on the Outside Surface ( = 0o) (Ref.
3.8A-12 Page G-17) 3.8A-30 Plot of Membrane Stress ( = 0o) (Ref. 3.8A-12 Page G-23) 3.8A-31 Dimensions of Cylindrical Water Tank 3.8A-32 Experimental Beam Dimensions 3.8A-33 Reference 3.8A-14 Mesh 3.8A-34 Finel Finite Element Mesh 3.8A-35-1 Regions of Cracking 3.8A-35-2 Regions of Cracking (Cont.)
3.8A-36 Load-Displacement Curves from Finel Verification Using a Simply Supported Beam 3.8A-37 Finite Element Model 3.8A-38 Finite Element Model 3.8A-39 Temperature Distribution 3.8A-40 Schematic of Test Problem 3.8A-41 Finite Element Layout 3.8A-42 Comparison of Results 3.8A-43 Steel Sphere 3.8A-44 Finite Element Model 3.9-1 Transient Pressure Differentials following a Steam Line Break at 105% Rated Steam Flow, 100% Recirculation 3.9-2 Typical Relief Valve Transient 3.9-3 Reactor Vessel Cutaway 3.9-4 Reactor Internals Flow Paths 3.9-5 Fuel Support Pieces 3.9-6 Jet Pump 3.9-7 Pressure Nodes Used for Depressurization Analysis 3.9A-1 Transient Temperature Response 3.10a-1 Typical Vertical Board 3.10a-2 Instrument Rack 3.10a-3 Typical Local Rack 3.10a-4 NEMA Type-12 Enclosure 3.10a-5-1 Cabinet Installation for Seismic and Hydrodynamic Loads- Sample Calculation (Cabinet H12-P608) 3.10a-5-2 Cabinet Installation for Seismic and Hydrodynamic Loads- Sample Calculation (Cabinet H12-P608) 3.10a-5-3 Cabinet Installation for Seismic and Hydrodynamic Loads- Sample Calculation (Cabinet H12-P608) 3.10a-6 Corner Post 3.10a-7 Plan View of Panel 3.10a-8 Barrier With Two End Plates 3.10a-9 Panel Deflections 3.11-1 Figure replaced by Drawing C-1815, Sh. 1 3.11-2 Figure replaced by Drawing C-1815, Sh. 2 3.11-3 Figure replaced by Drawing C-1815, Sh. 3 3.11-4 Figure replaced by Drawing C-1815, Sh. 4 FSAR Rev. 71 Page 35 of 113
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TABLE OF CONTENTS Chapter 3 Figures 3.11-5 Figure replaced by Drawing C-1815, Sh. 5 3.11-6 Figure replaced by Drawing C-1815, Sh. 6 3.11-7 Figure replaced by Drawing C-1815, Sh. 7 3.11-8 Figure replaced by Drawing C-1815, Sh. 8 3.11-9 Figure replaced by Drawing C-1815, Sh. 9 3.11-10 Figure replaced by Drawing C-1815, Sh. 10 3.11-11 Figure replaced by Drawing C-1815, Sh. 11 3.11-12 Figure replaced by Drawing C-1815, Sh. 12 3.13-1 One line diagram illustrating relationship of loads, penetration assemblies, and protective devices for curves presented as Figures 3.13-2A, 3.13-2B & 3.13-3 3.13-2 Figure replaced by Figure 3.13-2A and Figure 3.13-2B 3.13-2A Time-Current Characteristic Curves For Overcurrent Protection Of #10 Copper, Containment Penetrations 3.13-2B Time-Current Characteristic Curves For Overcurrent Protection Of #10 Copper, Containment Penetrations 3.13-3 Relationship Of Loads, Penetration Assemblies & Protective Devices for Curves Presented in Figures 3.13-2, 3.13-3, & 3.18-8 3.13-4 120 Volt AC Control Circuits 3.13-5 125 Volt DC Control Circuits 3.13-6 208/120 Lighting Circuits 3.13-7 React Recir Pump - Max Short Circuit Capability FSAR Rev. 71 Page 36 of 113
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TABLE OF CONTENTS Chapter 4 4.0 REACTOR 4.1 Summary Description 4.1.1 Reactor Vessel 4.1.2 Reactor Internal Components 4.1.3 Reactivity Control Systems 4.1.4 Analysis Techniques 4.1.5 References 4.2 Fuel System Design 4.2.1 Design Bases 4.2.2 General Design Description 4.2.3 Design Evaluations 4.2.4 Testing and Inspection 4.2.5 Operating and Developmental Experience 4.2.6 References 4.3 Nuclear Design 4.3.1 Design Bases 4.3.2 Description 4.3.3 Analytical Methods 4.3.4 Changes 4.3.5 References 4.4 Thermal and Hydraulic Design 4.4.1 Design Basis 4.4.2 Description of Thermal-Hydraulic Design of the Reactor Core 4.4.3 Description of the Thermal and Hydraulic Design of the Reactor Coolant System 4.4.4 Evaluation 4.4.5 Testing and Verification 4.4.6 Instrumentation Requirements 4.5 Reactor Materials 4.5.1 Control Rod System Structural Materials 4.5.2 Reactor Internal Materials 4.5.3 Control Rod Drive Housing Supports 4.6 Functional Design of Reactivity Control Systems 4.6.1 Information for CRDS 4.6.2 Evaluations of the CRDS 4.6.3 Testing and Verification of the CRDs 4.6.4 Information for Combined Performance of Reactivity Systems 4.6.5 Evaluation of Combined Performance 4.6-6 References FSAR Rev. 71 Page 37 of 113
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TABLE OF CONTENTS Chapter 4 - Tables 4.2-14 Fuel Design Characteristics (Nominal) 4.3-1 Reactor Core Characteristics 4.3-4 Typical Core Reactivity Coefficients 4.3-5 Fast Neutron Fluences >1 MEV 54 EFPY Fluence 4.4-1 Typical Thermal and Hydraulic Design Characteristics of the Reactor Core 4.4-2 Typical Void Distribution 4.4-2a Axial Power Distribution Used to Generate Typical Void and Quality Distributions 4.4-3 Typical Flow Quality Distribution 4.4-4 Typical Core Flow Distribution 4.4-6 Uncertainties Considered in MCPR Safety Limit 4.4-7 Bypass Flow Paths 4.4-8 Plant Configuration Data 4.4-9 Lengths of Safety Injection Line NOTE: Additional tables are presented in NEDE 20944/20944-P.
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TABLE OF CONTENTS Chapter 4 - Figures 4.1-2 Steam Dryer Panel 4.1-3 Steam Dryer 4.2-15 Core Cell (ATRIUM'-10 Fuel with Duralife 60C Control Rod) 4.2-15A Core Cell (ATRIUM-10 Fuel with MARATHON Control Rod) 4.2-15B Core Cell (ATRIUM-10 Fuel with Ultra-HD Control Rod) 4.2-15C Core Cell (ATRIUM-10 Fuel with Westinghouse CR 99 Control Rod) 4.2-16A Typical Core Cell (ATRIUM-11 Fuel with GE Hitachi Control Rod) 4.2-16B Typical Core Cell (ATRIUM-11 Fuel with Westinghouse Control Rod) 4.2-17 Fuel Bundle FANP ATRIUM-10 4.2-17-1 Representative ATRIUM-11 Fuel Bundle (Not to Scale) 4.2-18 80 MIL Fuel Channel 4.2-18-1 80 MIL Fuel Channel 4.2-18-2 100 MIL Fuel Channel 4.2-18-3 Advanced Fuel Channel 4.2-18-4 ATRIUM-11 Advanced Fuel Channel 4.2-19 Correct Fuel Assembly Orientation 4.2-20 Control Rod Assembly Original Equipment 4.2-21 Control Rod Assembly Duralife 160-C (D-160C) 4.2-22 Control Rod Assembly Marathon 4.2-23 Control Rod Assembly Westinghouse CR 99 4.3-1 Core Loading Map Typical of Unit 1 4.3-2 Core Loading Map Typical of Unit 2 4.3-3 Uranium Depletion as a Function of Exposure, 40% Voids (Typical) 4.3-4 Plutonium Buildup as a Function of Exposure, 40% Voids (Typical) 4.3-5 Fission Fraction as a Function of Exposure, 40% Voids (Typical) 4.3-6 Delayed Neutron Fraction as a Function of Exposure, 40% Voids (Typical) 4.3-7 Neutron Lifetime as a Functions of Exposure, 40% Voids (Typical) 4.3-8-46 ATRIUMTM -10 Fuel Axial Enrichment (Nominal) Typical Assemblies 4.3-8-47 ATRIUM-11 Fuel Axial Enrichment (Nominal) Typical Assemblies 4.3-9-123 ATRIUM'-10 Fuel Radial Enrichment (Nominal) Typical Lattice A 4.3-9-124 ATRIUM'-10 Fuel Radial Enrichment (Nominal) Typical Lattice B 4.3-9-125 ATRIUM'-10 Fuel Radial Enrichment (Nominal) Typical Lattice C 4.3-9-126 ATRIUM'-10 Fuel Radial Enrichment (Nominal) Typical Lattice D 4.3-9-127 ATRIUM'-10 Fuel Radial Enrichment (Nominal) Typical Lattice E 4.3-9-128 ATRIUM'-10 Fuel Radial Enrichment (Nominal) Typical Lattice F 4.3-9-129 ATRIUM'-10 Fuel Radial Enrichment (Nominal) Typical Lattice G 4.3-9-130 ATRIUM'-10 Fuel Radial Enrichment (Nominal) Typical Lattice H 4.3-9-131 ATRIUM'-10 Fuel Radial Enrichment (Nominal) Typical Lattice I 4.3-9-132 ATRIUM-11 Fuel Radial Enrichment (Nominal) Typical Lattice A 4.3-9-133 ATRIUM-11 Fuel Radial Enrichment (Nominal) Typical Lattice B 4.3-9-134 ATRIUM-11 Fuel Radial Enrichment (Nominal) Typical Lattice C 4.3-9-135 ATRIUM-11 Fuel Radial Enrichment (Nominal) Typical Lattice D 4.3-9-136 ATRIUM-11 Fuel Radial Enrichment (Nominal) Typical Lattice E 4.3-9-137 ATRIUM-11 Fuel Radial Enrichment (Nominal) Typical Lattice F 4.3-9-138 ATRIUM-11 Fuel Radial Enrichment (Nominal) Typical Lattice G 4.3-9-139 ATRIUM-11 Fuel Radial Enrichment (Nominal) Typical Lattice H FSAR Rev. 71 Page 39 of 113
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TABLE OF CONTENTS Chapter 4 - Figures 4.3-9-140 ATRIUM-11 Fuel Radial Enrichment (Nominal) Typical Lattice I 4.3-9-141 ATRIUM-11 Fuel Radial Enrichment (Nominal) Typical Lattice J 4.3-9-142 ATRIUM-11 Fuel Radial Enrichment (Nominal) Typical Lattice K 4.3-9-143 ATRIUM-11 Fuel Radial Enrichment (Nominal) Typical Lattice L 4.3-9-144 ATRIUM-11 Fuel Radial Enrichment (Nominal) Typical Lattice M 4.3-9-145 ATRIUM-11 Fuel Radial Enrichment (Nominal) Typical Lattice N 4.3-9-146 ATRIUM-11 Fuel Radial Enrichment (Nominal) Typical Lattice O 4.3-11-1 FANP ATRIUM 10 Fuel Dominant Lattice Hot-Uncontrolled K-Infinity vs Exposure (Typical) 4.3-11-2 FANP ATRIUM 10 Fuel Dominant Lattice Local Peaking, Unrodded, 40% Voids 0 MWD/MTU (Typical) 4.3-11-3 FANP ATRIUM 10 Fuel Dominant Lattice Local Peaking, Unrodded, 40% Voids 15000 MWD/MTU (Typical) 4.3-11-4 FANP ATRIUM 10 Fuel Dominant Lattice Local Peaking, Unrodded, 40% Voids 40000 MWD/MTU (Typical) 4.3-11-5 FANP ATRIUM 10 Fuel Dominant Lattice Local Peaking, Unrodded, 0% Voids 0 MWD/MTU (Typical) 4.3-11-6 FANP ATRIUM 10 Fuel Dominant Lattice Local Peaking, Unrodded, 80% Voids 0 MWD/MTU (Typical) 4.3-11-7 FANP ATRIUM 10 Fuel Dominant Lattice Maximum Hot-Uncontrolled Local Peaking Factor vs Exposure (Typical) 4.3-11-8 ATRIUM 11 Fuel Dominant Lattice Hot-Uncontrolled K-Infinity vs Exposure (Typical) 4.3-11-9 ATRIUM 11 Fuel Dominant Lattice Local Peaking, Unrodded, 40% Voids 0 MWD/MTU (Typical) 4.3-11-10 ATRIUM 11 Fuel Dominant Lattice Local Peaking, Unrodded, 40% Voids 15000 MWD/MTU (Typical) 4.3-11-11 ATRIUM 11 Fuel Dominant Lattice Local Peaking, Unrodded, 40% Voids 40000 MWD/MTU (Typical) 4.3-11-12 ATRIUM 11 Fuel Dominant Lattice Local Peaking, Unrodded, 0% Voids 0 MWD/MTU (Typical) 4.3-11-13 ATRIUM 11 Fuel Dominant Lattice Local Peaking, Unrodded, 80% Voids 0 MWD/MTU (Typical) 4.3-11-14 ATRIUM 11 Fuel Dominant Lattice Maximum Hot-Uncontrolled Local Peaking Factor vs. Exposure (Typical) 4.3-12 Hot Excess Reactivity vs Exposure (Typical) 4.3-13 Shutdown Margin vs Exposure (Typical) 4.3-14 Vessel Fluence (R,0) Model for Azimuthal Flux Distribution 4.4-1 Schematic of Reactor Assembly Showing the Bypass Flow Paths 4.4-2 Damping Coefficient Versus Decay Ratio (Second Order Systems) 4.4-3 Hydrodynamic and Core Stability Model for Initial Core 4.4-5 Power-Flow Operating Map 4.4-7a 10 Cent Rod Reactivity Step at 51.5% Rated Power (Natural Circulation) 4.4-7b 10 psi Pressure Regulator Setpoint Step at 51.5% Rated Power (Natural Circulation) 4.4-7c 6-9 Inch Level Setpoint Step at 51.5% Rated Power (Natural Circulation) 4.4-8a 10 Cent Rod Reactivity Step at 105% Rated Power and 100% Rated Flow FSAR Rev. 71 Page 40 of 113
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TABLE OF CONTENTS Chapter 4 - Figures 4.4-8b 10 psi Pressure Regulator Setpoint Step at 105% Rated Power and 100% Rated Flow 4.4-8c 6-inch Level Setpoint Step at 105% Rated Power and 100% Rated Flow 4.4-8d 10% Load Demand Step at 105% Rated Power and 100% Rated Flow 4.4-9a 10 Cent Rod Reactivity Step at 68% Rated Power and 51.5% Rated Flow 4.4-9b 10 psi Pressure Regulator Step at 68% Rated Power and 51.5% Rated Flow 4.4-9c 6-inch Water Level Setpoint Step at 60% Rated Power and 51.5% Rated Flow 4.4-9d 10% Load Demand Step at 68% Rated Power and 51.5% Rated Flow 4.6-1 Control Rod to Control Rod Drive Coupling 4.6-2 Control Rod Drive Unit 4.6-3 Control Rod Drive Schematic 4.6-4 Control Rod Drive (Cutaway) 4.6-5a Figured replaced by Drawing M-146, Sh. 1 4.6-5b Figured replaced by Drawing M-147, Sh. 1 4.6-6 Figured replaced by Drawing M1-C12-8, Sh. 1 4.6-7 Control Rod Drive Hydraulic Control Unit 4.6-8 Control Rod Drive Housing Support NOTE: Additional Figures are presented in NEDE 20944/20944-P.
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TABLE OF CONTENTS Chapter 5 5.0 REACTOR COOLANT SYSTEM AND CONNECTED SYSTEMS 5.1 Summary Description 5.1.1 Schematic Flow Diagram 5.1.2 Piping and Instrumentation Diagram 5.1.3 Plan and Elevation Drawings 5.2 Integrity of Reactor Coolant Pressure Boundary 5.2.1 Compliance with Codes and Code Cases 5.2.2 Overpressure Protection 5.2.3 Reactor Coolant Pressure Boundary Materials 5.2.4 In-Service Inspection and Testing of Reactor Coolant Pressure Boundary 5.2.5 Detection of Leakage Through Reactor Coolant Pressure Boundary 5.2.6 References 5.3 Reactor Vessel 5.3.1 Reactor Vessel Materials 5.3.2 Pressure-Temperature Limits 5.3.3 Reactor Vessel Integrity 5.3.4 References 5.4 Component and Subsystem Design 5.4.1 Reactor Recirculation Pumps 5.4.2 Steam Generators (PWR) 5.4.3 Reactor Coolant Piping 5.4.4 Main Steamline Flow Restrictors 5.4.5 Main Steamline Isolation System 5.4.6 Reactor Core Isolation Cooling System 5.4.7 Residual Heat Removal System 5.4.8 Reactor Water Cleanup System 5.4.9 Main Steam Lines and Feedwater Piping 5.4.10 Pressurizer 5.4.11 Pressurizer Relief Discharge System 5.4.12 Valves 5.4.13 Safety and Relief Valves 5.4.14 Component Supports 5.4.15 High Pressure Coolant Injection (HPCI) System 5.4.16 Core Spray (CS) System 5.4-17 Standby Liquid Control (SLC) System 5.4-18 References FSAR Rev. 71 Page 42 of 113
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TABLE OF CONTENTS Chapter 5 - Tables 5.1-1 Design and Performance Characteristics of the Reactor Coolant System and Its Components 5.2-1 Reactor Coolant Pressure Boundary Components Code Case Interpretations 5.2-2 Nuclear System Safety/Relief Set Points Units 1 and 2 5.2-3 Design Temperature, Pressure and Maximum Test Pressure for RCPB Components 5.2-4 Reactor Coolant Pressure Boundary Materials 5.2-5 BWR Water Chemistry 5.2-6 Systems Which May Initiate During Overpressure Event 5.2-7 Water Sample Locations 5.2-8 Summary of Isolation/Alarm of System Monitored and Leak Detection Methods Used 5.2-9 Sequence of Events for MSIV Isolation Closure Unit 1 Typical and Unit 2 Typical 5.2-10 RCPB Components in Compliance with 10CFR50.55(a) (2) (ii) 5.2-11 Identified Leakages into the Drywell Equipment Drain Tank 5.2-12 Unidentified Leakages into the Drywell Floor Drain Sump 5.2-13 Estimated Monitor Responses 5.2-14 RCPB Leak Detection Monitors Inside Primary Containment Drywell 5.3-1a Appendix G Matrix For Susquehanna Unit 1 5.3-1b Appendix H Matrix For Susquehanna SES Unit 1 5.3-2a Appendix G Matrix For Susquehanna SES Unit 2 5.3-2b Appendix H Matrix For Susquehanna SES Unit 2 5.3-3 Reactor Vessel Material Surveillance Program - Withdrawal Schedule 5.4-2 Reactor Water Cleanup System Equipment Design Data 5.4-3 RHR Relief Valve Data 5.4-4 RCPB Component Description FSAR Rev. 71 Page 43 of 113
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TABLE OF CONTENTS Chapter 5 - Figures 5.1-2 Coolant Volumes of the Boiling Water Reactor 5.1-3A-1 Figure replaced by Drawing M-141, Sh. 1 5.1-3A-2 Figure replaced by Drawing M-141, Sh. 2 5.1-3B Figure replaced by Drawing M-142, Sh. 1 5.1-4-1 Reactor Coolant System Plan 5.1-4-2 Reactor Coolant System Elevation 5.1-4-3 Reactor Coolant System Elevation 5.2-2 Simulated Safety/Relief Valve Spring Mode Characteristic Used for Capacity Sizing Analysis 5.2-2A Simulated Safety/Relief Valve Spring Mode Characteristic 5.2-6 Safety Valve Lift Versus Time Characteristic 5.2-7 Schematic of Safety Valve with Auxiliary Actuating Device 5.2-8 Typical BWR Feedwater Cycle 5.2-9 Conductance vs. pH as a Function of Chloride Concentration of Aqueous Solution at 25C 5.2-10 Calculated Leak Rate Versus Crack Length as a Function of Applied Hoop Stress 5.2-11 Axial Through-Wall Crack Length Data Correlation 5.2-12 Region for Spring Safety Mode Nominal Setpoint 5.2-13 Overpressure Protection Analysis (MSIV Closure with High Flux Scram Trip) Typical of Unit 1 5.2-14 Overpressure Protection Analysis (MSIV Closure with High Flux Scram Trip) Typical of Unit 2 5.3-1 Reactor Vessel 5.3-3 Bracket for Holing Surveillance Capsule 5.3-4c Unit 1 Predicted Adjusted Reference Temperature vs. Effective Full Power Years of Operation 5.3-4d Unit 2 Predicted Adjusted Reference Temperature vs. Effective Full Power Years of Operation 5.4-1 Recirculation System Elevation and Isometric 5.4-2b-1 Figure replaced by Drawing M-143, Sh. 1 5.4-2b-2 Figure replaced by Drawing M-143, Sh. 2 5.4-2c Figure replaced by Drawing M1-B31-13, Sh. 3 5.4-3 Recirculation Pump Head, NPSH, Flow and Efficiency Curves 5.4-4a RHR Suction Strainer Details 5.4-4b RHR Suction Strainer Details 5.4-5 Operating Principle of Jet Pump 5.4-6 Core Flooding Capability of Recirculation System 5.4-7 Main Steam Line Flow Restrictor Location 5.4-9a Figure replaced by Drawing M-149, Sh. 1 5.4-9b Figure replaced by Drawing M-150, Sh. 1 5.4-10 Figure replaced by Drawing M1-E51-81, Sh. 1 5.4-13-1 Figure replaced by Drawing M-151, Sh. 1 5.4-13-2 Figure replaced by Drawing M-151, Sh. 2 5.4-13-3 Figure replaced by Drawing M-151, Sh. 3 5.4-13-4 Figure replaced by Drawing M-151, Sh. 4 FSAR Rev. 71 Page 44 of 113
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TABLE OF CONTENTS Chapter 5 - Figures 5.4-14-1 Figure replaced by Drawing M1-E11-3, Sh. 1 5.4-14-2 Figure replaced by Drawing M1-E11-3, Sh. 2 5.4-15A Figure replaced by Drawing M1-G33-16, Sh. 1 5.4-15B Figure replaced by Drawing M1-G33-18, Sh. 1 5.4-16-1 Figure replaced by Drawing M1-144, Sh. 1 5.4-16-2 Figure replaced by Drawing M1-144, Sh. 2 5.4-16-3 Figure replaced by Drawing M1-144, Sh. 3 5.4-18 Figure replaced by Drawing M-145, Sh. 1 FSAR Rev. 71 Page 45 of 113
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TABLE OF CONTENTS Chapter 6 6.0 ENGINEERED SAFETY FEATURES 6.1 Engineered Safety Feature Materials 6.1.1 Metallic Materials 6.1.2 Organic Materials 6.1.3 Post-Accident Chemistry 6.2 Containment Systems 6.2.1 Primary Containment Functional Design 6.2.2 Containment Heat Removal System 6.2.3 Secondary Containment Functional Design 6.2.4 Containment Isolation System 6.2.5 Combustible Gas Control in Containment 6.2.6 Primary Reactor Containment Leakage Rate Testing 6.2.7 References 6.3 Emergency Core Cooling Systems 6.3.1 Design Bases and Summary Description 6.3.2 System Design 6.3.3 ECCS Performance Evaluation 6.3.4 Tests and Inspections 6.3.5 Instrumentation Requirements 6.3.6 NPSHA Margin and Vortex Formation After a Passive Failure in a Water Tight ECCS Pump Room 6.3.7 References 6.4 Habitability Systems 6.4.1 Design Bases 6.4.2 System Design 6.4.3 System Operational Procedures 6.4.4 Design Evaluations 6.4.5 Testing and Inspection 6.4.6 Instrumentation Requirements 6.5 Fission Product Removal and Control Systems 6.5.1 Engineered Safety Feature (ESF) Filter Systems 6.5.2 Containment Spray Systems 6.5.3 Fission Product Control System 6.5.4 Ice Condenser as a Fission Product Cleanup System 6.5.5 References 6.6 Inservice Inspection of Class 2 and 3 Components 6.6.1 Components Subject to Examination 6.6.2 Accessibility 6.6.3 Examination Techniques and Procedures 6.6.4 Inspection Intervals 6.6.5 Examination Categories and Requirements 6.6.6 Evaluation of Examination Results FSAR Rev. 71 Page 46 of 113
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TABLE OF CONTENTS Chapter 6 6.6.7 System Pressure Tests 6.6-8 Augmented Inservice Inspection to Protect Against Postulated Piping Failures 6.6-9 Containment Inspections 6.7 Main Steam Isolation Valve Leakage Isolated Condenser Treatment Method 6.7.1 Design Bases 6.7.2 System Description 6.7.3 System Evaluation 6.7.4 Instrumentation Requirements 6.7.5 Inspection and Testing 6A Subcompartment Differential Pressure Considerations 6B Compartment Differential Pressure Analysis Description 6B.1 FLUD Calculational Procedure 6B.1.1 Equation of State 6B.1.2 Compartment Thermodynamic State 6B.1.3 Compartment Initial Conditions 6B.1.4 Air and Vapor Component Flow Rates 6B.2 Energy Transfer Mechanisms 6B.2.1 Blowdown Energy 6B.2.2 Enthalpy Flow 6B.2.3 Compartment Heat Loads 6B.2.4 Unit Coolers 6B.2.5 Energy Balance 6B.2.6 Blowout Panel Activation 6B.2.7 Energy and Mass Conversion 6B.2.8 Eulerian Integration 6B.3 Thermodynamic Properties of Steam, Water, and Air 6B.4 References FSAR Rev. 71 Page 47 of 113
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TABLE OF CONTENTS Chapter 6 Tables 6.1-1a NSSS Supplied Engineered Safety Features Component Materials 6.1-1b Engineered Safety Features Materials 6.1-2 Containment Components-Coating Schedule 6.1-3 Inventory of Qualified and Unqualified Containment Coatings 6.2-1 Containment Design Parameters 6.2-2 Engineered Safety Systems Inputs and Assumptions for Containment Response Analyses 6.2-3a Initial Plant Conditions for DBA-LOCA Containment Response 6.2-4a Input and Assumptions for the Short-Term DBA-LOCA Analysis 6.2-5a Input and Assumptions for the Long-Term DBA-LOCA Analysis 6.2-6a Containment Performance for DBA-LOCA 6.2-9 RPV Break Flow Data For Recirculation Line Break (102% P / 100% F) 6.2-10 RPV Break Flow Data For Main Steam Line Break (102% P / 100% F) 6.2-11 Core Decay Heat Following LOCA for Containment Analysis 6.2-12 Containment Penetration Data 6.2-12a Data on Instrument Lines Penetrating Containment 6.2-13 Parameters Used for the Evaluation of Combustible Gases in the Containment After a LOCA 6.2-14 Primary Containment Atmosphere Monitoring System (Hydrogen/Oxygen Analyzer)
System Level, Failure Mode and Effect Analysis 6.2-15 Evaluation of Potential Secondary Containment Bypass Leakage Pathways 6.2-17 Information for the SSES Secondary Containment 6.2-19 Type A Test Data 6.2-21 System Venting and Draining for Primary Containment Integrated Leakage Rate Test 6.2-22 Leakage Rate Test List 6.2-23 Initial and Boundary Conditions for Inadvertent Spray Actuation Study 6.2-24 Initial and Boundary Conditions For Drywell- Wetwell Bypass Leakage Study 6.2-25 Blowdown Data and Bypass Leakage 6.2-26 Long-term Blowdown Data for a Recirculation Line Break (Case D) 6.3-1B-2 Event Times for the Highest PCT Case from the TLO Recirculation Line Break Spectrum Analysis 6.3-2B Significant Input Parameters to the Loss-of-Coolant Accident Analysis 6.3-3B-2 Results for Limiting Two Loop Operation Recirculation Line Break 1.0 Deg Pump Suction SF-LPCI Top-Peaked Axial 102% Power (4031 MWt) 80 Mlbs/HR Flow 6.3-3C Recirculation Line Break Results Highest PCT Cases 6.3-5 Single Failures And Available Systems For Susquehanna 6.3-8 HPCI System Design Parameters 6.3-9 Manual Valves in the ECCS 6.3-10 Safety-Related Valves in the Drywell Subject to Spray Impingement 6.4-1 Control Structure Isolation Damper Leakage Characteristics and Closure Times 6.5-1 Engineered Safety Feature Filter System Design Parameters 6.5-2 Engineered Safety Feature Filter Systems Compliance with Recommendations of Regulatory Guide 1.52 6.5-3 Standby Gas Treatment System Failure Mode and Effect Analysis FSAR Rev. 71 Page 48 of 113
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TABLE OF CONTENTS Chapter 6 Tables 6.5-4 Recirculation System Failure Mode and Effect Analysis 6.5-5 List of Materials Used in the Standby Gas Treatment System 6.5-6 List of Materials Used in the Emergency Outside Air Supply System 6.5-7 Zone Volumes and Their Estimated Recirculation Airflow Rates 6A-1(a) Reactor Primary System Blowdown Flow Rates and Fluid Enthalpy-Recirculation Outlet Line Break 6A-1(b) Recirc. Outlet Line Break Blowdown Mass Flux Time History 6A-1(c) Reactor Primary System Blowdown Flow Rates and Fluid Enthalpy - Feedwater Line Break 6A-1(d) Feedwater Line Break Blowdown Mass Flux Time History 6A-2 Head Spray Line Break 6A-3 Susquehanna-Compartment Volumes Used in Reactor Vessel Shield Annulus Subcompartment Analysis 6A-4 Susquehanna-Flow Area and Coefficients Used in Reactor Vessel Shield Annulus Subcompartment Analysis 6A-5 Geometry Node Locations 6A-6 RPV Geometry Node Areas for Recirculation Outlet Line Break 6A-7 RPV Geometry Mode Areas for Feedwater Line Break 6A-8 Reactor Primary System Blowdown Flow Rates And Fluid Enthalpy - Recirculation Outlet Line Break FSAR Rev. 71 Page 49 of 113
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TABLE OF CONTENTS Chapter 6 Figures 6.2-1 Diagram of the Recirculation Line Break Location 6.2-2 Pressure Response for Recirculation Line Break 6.2-3 Temperature Response for Recirculation Line Break 6.2-4 Floor Differential Pressure For Recirculation Line Breaks 6.2-5 Vent Flow for Recirculation Line Break 6.2-6 Containment Pressure Response Long-Term 6.2-7 Drywell Temperature Response - Long-Term 6.2-8 Suppression Pool Temperature Response - Long-Term 6.2-9 RHR Heat Removal Rate 6.2-11 Pressure Response for Main Steamline Break 6.2-12 Temperature Response for Main Steamline Break 6.2-16 Schematic of ECCS Loop 6.2-17 Allowable Leakage Capacity 6.2-18 Vessel Blowdown Rate for Recirculation Line Break 6.2-20 Vessel Blowdown Rate for Main Steamline Break 6.2-24 Secondary Containment Boundary Outline - Unit 1 EL. 645-0 6.2-25 Secondary Containment Boundary Outline - Unit 1 EL. 670-0 6.2-26 Secondary Containment Boundary Outline - Unit 1 EL. 683-0 6.2-27 Secondary Containment Boundary Outline - Unit 1 EL. 719-0 6.2-28 Secondary Containment Boundary Outline - Unit 1 EL. 749-1 6.2-29 Secondary Containment Boundary Outline - Unit 1 EL. 779-1 6.2-30 Secondary Containment Boundary Outline - Unit 1 EL. 818-1 6.2-31 Secondary Containment Boundary Outline - Unit 1 Section A-A 6.2-32 Secondary Containment Boundary Outline - Unit 1 Section B-B 6.2-33 Secondary Containment Boundary Outline - Unit 1 EL. 799-1 6.2-34 Secondary Containment Boundary Outline - Unit 2 EL. 645-0 6.2-35 Secondary Containment Boundary Outline - Unit 2 EL. 670-0 6.2-36 Secondary Containment Boundary Outline - Unit 2 EL. 683-0 6.2-37 Secondary Containment Boundary Outline - Unit 2 EL. 719-0 6.2-38 Secondary Containment Boundary Outline - Unit 2 EL. 749-1 6.2-39 Secondary Containment Boundary Outline - Unit 2 EL. 779-1 6.2-40 Secondary Containment Boundary Outline - Unit 2 EL. 818-1 6.2-41 Secondary Containment Boundary Outline - Unit 2 Section A-A 6.2-42 Secondary Containment Boundary Outline - Unit 2 Section B-B 6.2-43 Secondary Containment Boundary Outline - Unit 2 EL. 799-1 6.2-44 Containment Penetration Details 6.2-44A Containment Penetration Details 6.2-44B Containment Penetration Details 6.2-44C Containment Penetration Details 6.2-44D Containment Penetration Details 6.2-44E Containment Penetration Details 6.2-44F Containment Penetration Details 6.2-44g Containment Penetration Details 6.2-44H Containment Penetration Details 6.2-44i Containment Penetration Details 6.2-44J Containment Penetration Details 6.2-44K Containment Penetration Details 6.2-44L Containment Penetration Details FSAR Rev. 71 Page 50 of 113
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TABLE OF CONTENTS Chapter 6 Figures 6.2-44M Containment Penetration Details 6.2-46 Energy Absorption Rate By the Coolant vs. Time After LOCA 6.2-47 Integrated Energy Absorbed By Coolant vs. Time After LOCA 6.2-52 Reactor Building Ventilation Recirculation and Standby Gas Treatment Systems Zone I and Zone III Isolation 6.2-53 Reactor Building Ventilation Recirculation and Standby Gas Treatment Systems Normal Plant Operation 6.2-54 Reactor Building Ventilation Recirculation and Standby Gas Treatment Systems Zone III Isolation 6.2-55A Figure replaced by Drawing M-157, Sh. 1 6.2.55B Figure replaced by Drawing M-157, Sh. 2 6.2.55C Figure replaced by Drawing M-157, Sh. 3 6.2-56 Drywell to Wetwell Downcomers 6.2-57-1 Vacuum Breaker - DISC/ARM Assembly Unit 1 6.2-57-2 Vacuum Breaker - DISC/ARM Assembly Unit 2 6.2-57a-1 Containment Personnel Lock Door Penetrations 6.2-57a-2 Containment Personnel Lock Door Penetrations 6.2-57a-3 Containment Personnel Lock Penetrations 6.2-58-1 Containment Personnel Lock Door Seals 6.2-58-2 Containment Personnel Lock Door Seals 6.2-59 Personnel Lock Inner Door Tie Downs 6.2-60 Secondary Containment Pressure Transient Post-LOCA 6.2-61 Model for Inadvertent Spray Actuation 6.2-62 Thermal Heat Removal Efficiency of Containment Atmosphere Spray 6.2-63 Drywell Pressure Response For Inadvertent Spray Actuation 6.2-64 Drywell Temperature Response For Inadvertent Spray Actuation 6.2-65 Differential Pressure Experienced Across the Diaphragm Slab During Inadvertent Actuation of the Drywell Spray 6.2-66B RWCU Line Penetration 6.2-66C Suppression Pool Purification Line Penetration 6.2-66F Reactor Building Closed Cooling Water Line Penetration 6.2-66G Reactor Building Control Rod Drive Seismic Island 6.2-66H RBCCW Supply/Return lines at the Reactor Building to Turbine Building Interface 6.2-67 Figure replaced by Drawing M-159, Sh. 1 6.2-70 Long-Term Energy Release Rate for a Recirculation Line Break 6.2-72 TIP Guide Tube Isolation Control 6.3-1A Figure replaced by Drawing M-155, Sh. 1 6.3-1B Figure replaced by Drawing M-156, Sh. 1 6.3-2 Figure replaced by Drawing M1-E41-4, Sh. 1 6.3-3A High Pressure Coolant Injection Pump Speed Characteristics 6.3-4 Figure replaced by Drawing M-152, Sh. 1 6.3-5 Figure replaced by Drawing M1-E21-15, Sh. 1 6.3-77 Pump Characteristic Curves For HPCI Pumps 6.3-79C Low Pressure Core Spray Flow vs. Head Used in LOCA Analysis 6.3-80C RHR (LPCI) Flow vs. Head Characteristics Use in LOCA Analysis 6.3-118 Characteristic Curves for Core Spray Pump 6.3-119 Characteristic Curves for LPCI Pump FSAR Rev. 71 Page 51 of 113
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TABLE OF CONTENTS Chapter 6 Figures 6.3-120 Speed Characteristic Curves for HPCI Pumps - Unit 1 6.3-121 Speed Characteristic Curves for HPCI Pumps - Unit 2 6.3-201 Limiting TLO Recirculation Line Break Upper Plenum Pressure (Lower) 6.3-202 Limiting TLO Recirculation Line Break Total Break Flow Rate 6.3-203 Limiting TLO Recirculation Line Break Core Inlet Flow Rate 6.3-204 Limiting TLO Recirculation Line Break Core Inlet Flow Rate 6.3-205 Limiting TLO Recirculation Line Break Broken Loop Jet Pump Drive Flow Rate 6.3-206 Limiting TLO Recirculation Line Break Ads Flow Rate 6.3-207 Limiting TLO Recirculation Line Break HPCI Flow Rate 6.3-208 Limiting TLO Recirculation Line Break LPCS Flow Rate 6.3-209 Limiting TLO Recirculation Line Break Intact Loop LPCI Flow Rate 6.3-210 Limiting TLO Recirculation Line Break Broken Loop LPCI Flow Rate 6.3-211 Limiting TLO Recirculation Line Break Upper Downcomer Mixture Level 6.3-212 Limiting TLO Recirculation Line Break Lower Downcomer Mixture Level 6.3-213 Limiting TLO Recirculation Line Break Lower Downcomer Liquid Mass 6.3-214 Limiting TLO Recirculation Line Break Upper Plenum Liquid Mass 6.3-215 Limiting TLO Recirculation Line Break Lower Plenum Liquid Mass 6.3-216 Limiting TLO Recirculation Line Break Hot Channel Inlet Flow Rate 6.3-217 Limiting TLO Recirculation Line Break Hot Channel Outlet Flow Rate 6.3-218 Limiting TLO Recirculation Line Break Hot Channel Coolant Temperature At The Limiting Node 6.3-219 Limiting TLO Recirculation Line Break Hot Channel Quality At The Limiting Node 6.3-220 Limiting TLO Recirculation Line Break Hot Channel Heat Transfer Coeff. at The Limiting Node 6.3-221 Limiting TLO Recirculation Line Break Cladding Temperatures 6.4-1A Control Structure Elevation 6.4-1B Control Structure Envelope Plan - El. 697'-0" and 714'-0" 6.4-1C Control Structure Envelope Control Room Floor Plan EL. 729-0 Technical Support Center EL. 741-1 6.4-1D Control Structure Envelope Plan EL. 753-0 & 771-0 6.4-1E Control Structure Envelope Plan EL. 783-0 6.4-2 Control Room Location Intake and Exhaust Location 6A-1(a) Reactor Shield Annulus Arrangement 6A-1(b) RPV Shield Wall and Pedestal 6A-2 RPV Shield Annulus Subcompartment Model Schematic 6A-3a Pressure Transient in Shield Annulus Following a Recirculation Line Break at the Nozzle Safe End 6A-3b Pressure Transient in Shield Annulus Following a Recirculation Line Break at the Nozzle Safe End 6A-3c Pressure Transient in Shield Annulus Following a Recirculation Line Break at the Nozzle Safe End 6A-3d Pressure Transient in Shield Annulus Following a Recirculation Line Break at the Nozzle Safe End 6A-3e Pressure Transient in Shield Annulus Following a Recirculation Line Break at the Nozzle Safe End FSAR Rev. 71 Page 52 of 113
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TABLE OF CONTENTS Chapter 6 Figures 6A-3f Pressure Transient in Shield Annulus Following a Recirculation Line Break at the Nozzle Safe End 6A-3g Pressure Transient in Shield Annulus Following a Feedwater Line Break at the Nozzle Safe End 6A-3h Pressure Transient in Shield Annulus Following a Feedwater Line Break at the Nozzle Safe End 6A-3i Pressure Transient in Shield Annulus Following a Feedwater Line Break at the Nozzle Safe End 6A-3j Pressure Transient in Shield Annulus Following a Feedwater Line Break at the Nozzle Safe End 6A-3k Pressure Transient in Shield Annulus Following a Feedwater Line Break at the Nozzle Safe End 6A-3l Pressure Transient in Shield Annulus Following a Feedwater Line Break at the Nozzle Safe End 6A-4 Drywell Head Arrangement 6A-5 Head Spray Line Break Geometry 6A-6 Pressure Response in the Drywell Head For a Head Spray Line Break 6A-7 Force Transient on Reactor Pressure Vessel Following A Recirculation Line Break at the Nozzle Safe End 6A-8 Force Transient on Reactor Shield Wall Following A Recirculation Line Break at the Nozzle Safe End 6A-9 Resultant Force Transient on RPV Following a Feedwater Line Break at the Nozzle 6A-10 Resultant Force Transient on RPV Following a Feedwater Line Break at the Nozzle 6B-1 Basic FLUD Calculation Flowchart FSAR Rev. 71 Page 53 of 113
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TABLE OF CONTENTS Chapter 7 7.0 INSTRUMENTATION AND CONTROLS 7.1 Introduction 7.1.1 Identification of Safety-Related Systems 7.1.2 Identification of Safety Criteria 7.2 Reactor Trip System-(Reactor Protection System)Instrumentation and Controls 7.2.1 Description 7.2.2 Analysis 7.2.3 Alternate Rod Injection System 7.2.4 ARI Analysis 7.3 Engineered Safety Feature Systems 7.3.1 Description 7.3.2 Analysis 7.3.2a Analysis of ESFAS Supplied with the NSSS 7.3.2b Analysis for Non-NSSS Systems 7.4 Systems Required for Safe Shutdown 7.4.1 Description 7.4.2 Analysis 7.4.3 References 7.5 Safety Related Display Instrumentation (SRDI) 7.5.1a Description 7.5.1b Description of Non-NSSS Safety-Related Displays 7.5.2a Analysis of NSSS Safety-Related Displays 7.5.2b Analysis of Non-NSSS Safety-Related Display Instrumentation 7.6 All Other Instrumentation Systems Required for Safety 7.6.1a Description 7.6.1b Description 7.6.2a Analysis for NSSS - Systems 7.6.2b Analysis for Non-NSSS Systems 7.6.3 References 7.7 Control Systems Not Required for Safety 7.7.1 Description 7.7.2 Analysis 7.7.3 References FSAR Rev. 71 Page 54 of 113
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TABLE OF CONTENTS Chapter 7 Tables 7.1-1 Responsibility 7.1-2 Similarity to Licensed Reactors 7.1-3 Codes and Standards Applicability Matrix 7.1-4 Reactor Protection System Codes and Standards 7.1-5 Primary Containment and Reactor Vessel Isolation Control System Codes and Standards 7.1-6 High Pressure ECCS (HPCI, ADS A, ADS B Network) Codes and Standards 7.1-7 Low Pressure ECCS (CS, RHR Network) Codes and Standards 7.1-8 Process Radiation Monitoring Codes and Standards 7.1-9 Leak Detection System Codes and Standards 7.1-10 Reactor Protection System Sensor Suffix Letters and Division Allocation 7.1-11 Four Division Grouping for Neutron Monitoring System 7.1-12 Emergency Core Cooling System and RCIC Sensor Suffix Letters and Division Allocation 7.2-1 Reactor Protection System Instrumentation Specifications 7.2-2 Channels Required for Functional Performance of RPS 7.2-3 ATWS Recirculation Pump Trip and Alternate Rod Injection Instrumentation Specifications 7.2-4 Channels Required for Functional Performance of ARI 7.3-1 High Pressure Coolant Injection System-Instrument Specifications and Channels 7.3-2 Automatic Depressurization System-Instrument Specifications and Channels 7.3-3 Core Spray System-Instrument Specifications and Channels 7.3-4 Low Pressure Coolant Injection-Instrument Specification and Channels 7.3-5 Primary Containment and Reactor Vessel Isolation Control System Instrumentation Specifications 7.3-13 ESFAS Actuated Equipment Standby Gas Treatment System 7.3-14 ESFAS Actuated Equipment Recirculation System, Reactor Building Isolation Dampers, and Reactor Building Non-Safety Related Equipment 7.3-15 ESFAS Actuated Equipment Control Structure Emergency Outside Air Supply System 7.3-16 ESFAS Actuated Equipment Battery Rooms Exhaust System 7.3-17 General Notes for Tables 7.3-13 Through 7.3-16 7.3-18 Standby Gas Treatment System (SGTS) Failure Mode and Effects Analysis 7.3-19 Reactor Building Recirculation System Failure Mode and Effects Analysis 7.3-20 Failure Mode and Effects Analysis Primary Containment Isolation Control System Fan Non-NSS Systems 7.3-21 Emergency Outside Air Supply System (EOASS) Failure Mode and Effects Analysis 7.3-22 Computer Room Cooling System (CRCS) Failure Mode and Effects Analysis 7.3-23 Control Structure H&V System (CSHVS) Failure Mode and Effects Analysis 7.3-24 Control Structure Chilled Water System (CSCWS) Failure Mode and Effects Analysis 7.3-25 Battery Rooms Exhaust System Failure Mode and Effects Analysis 7.3-26 Control Room Floor Cooling System (CRFCS) Failure Mode and Effects Analysis 7.3-28 Reactor Protection System Response Times 7.3-29 Isolation System Instrumentation Response Time 7.3-30 Emergency Core Cooling System Response Times FSAR Rev. 71 Page 55 of 113
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TABLE OF CONTENTS Chapter 7 Tables 7.4-2 RHRS Shutdown Cooling Bypasses and Interlocks 7.4-3 Remote Shutdown Panel Instrumentation 7.4-4 Alternate Control Structure HVAC Control Panel 7.5-1 Safety Related Display Instrumentation 7.5-2 Safety Related Display Instrumentation-Habitability (Emergency Outside Air System/Control Structure HVAC) 7.5-3 Safety Related Display Instrumentation-Containment and Suppression Pool Instrumentation 7.5-4 Safety Related Display Instrumentation-Standby Gas Treatment System, RX Building Recirculation and Isolation System 7.5-5 Safety Related Display Instrumentation-Emergency Service Water System 7.5-6 Safety Related Display Instrumentation-RHR Service Water System and Spray Pond 7.5-7 Safety Related Display Instrumentation-Containment Instrument Gas System 7.5-7a Safety Related Display Instrumentation Standby Liquid Control System 7.5-8 Bypass Indication System for Non-NSSS Systems 7.6-3 IRM Trips 7.6-4 LPRM System Trips 7.6-5 APRM System Trips 7.6-7 OPRM System Trip 7.6-9 Suppression Pool Temperature Sensor Locations 7.6-10 End-of-Cycle Recirculation Pump Trip System Response Time 7.7-1 CRD Hydraulic System Process Indicators 7.7-2 Refueling Interlock Effectiveness 7.7-3 RBM System Trips 7.7-4 IRM Trips FSAR Rev. 71 Page 56 of 113
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TABLE OF CONTENTS Chapter 7 Figures 7.2-1-1 Figure replaced by Drawing M1-C72-2, Sh. 1 7.2-1-2 Figure replaced by Drawing M1-C72-2, Sh. 2 7.2-1-3 Figure replaced by Drawing M1-C72-2, Sh. 3 7.2-1-4 Figure replaced by Drawing M1-C72-2, Sh. 4 7.2-2 Reactor Protection System Scram Functions 7.2-3 Arrangement of Channels and Logics 7.2-4 Actuators and Actuator Logics 7.2-5 Logic in One Trip System 7.2-6 Relationship Between Neutron Monitoring System and Reactor Protection System 7.2-7 Configuration for Turbine Stop Valve Closure Reactor Trip 7.2-8 Configuration for Main Steamline Isolation Reactor Trip 7.2-9 Block Diagram - RPS Protective Circuit - Electrical Protection Assembly (EPA) 7.2-10 ARI Trip System Logic 7.3-2 Isolation Control System for Main Steamline Isolation Valves 7.3-3 Isolation Control System Using Motor-Operated Valves 7.3-4 Main Steamline Isolation Valve Schematic 7.3-5-1 Initiation Logic - CS, RHR 7.3-5-2 ADS Initiation Logic 7.3-6 Initiation Logic - HPCI, RCIC 7.3-7-1 Figure replaced by Drawing M1-E41-65, Sh. 1 7.3-7-2 Figure replaced by Drawing M1-E41-65, Sh. 2 7.3-7-3 Figure replaced by Drawing M1-E41-65, Sh. 3 7.3-7-4 Figure replaced by Drawing M1-E41-65, Sh. 4 7.3-7-5 Figure replaced by Drawing M1-E41-65, Sh. 5 7.3-8-1 Figure replaced by Drawing M1-B21-92, Sh. 1 7.3-8-2 Figure replaced by Drawing M1-B21-92, Sh. 2 7.3-8-3 Figure replaced by Drawing M1-B21-92, Sh. 3 7.3-8-4 Figure replaced by Drawing M1-B21-92, Sh. 4 7.3-8-5 Figure replaced by Drawing M1-B21-92, Sh. 5 7.3-8-6 Figure replaced by Drawing M1-B21-92, Sh. 6 7.3-9-1 Figure replaced by Drawing M1-E21-3, Sh. 1 7.3-9-2 Figure replaced by Drawing M1-E21-3, Sh. 2 7.3-9-3 Figure replaced by Drawing M1-E21-3, Sh. 3 7.3-10-1 Figure replaced by Drawing M1-E11-51, Sh. 1 7.3-10-2 Figure replaced by Drawing M1-E11-51, Sh. 2 7.3-10-3 Figure replaced by Drawing M1-E11-51, Sh. 3 7.3-10-4 Figure replaced by Drawing M1-E11-51, Sh. 4 7.3-10-5 Figure replaced by Drawing M1-E11-51, Sh. 5 7.3-11-1 Figure replaced by Drawing M1-D12-1, Sh. 1 7.3-11-2 Figure replaced by Drawing M1-D12-1, Sh. 2 7.3-11-3 Figure replaced by Drawing M1-D12-1, Sh. 3 7.3-11-4 Figure replaced by Drawing M1-D12-1, Sh. 4 7.3-11-5 Figure replaced by Drawing M1-D12-1, Sh. 5 7.4-1 Figure replaced by Drawing M-149, Sh. 1 & M-150, Sh. 1 7.4-2-1 Figure replaced by Drawing M1-E51-80, Sh. 1 7.4-2-2 Figure replaced by Drawing M1-E51-80, Sh. 2 FSAR Rev. 71 Page 57 of 113
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TABLE OF CONTENTS Chapter 7 Figures 7.4-2-3 Figure replaced by Drawing M1-E51-80, Sh. 3 7.4-2-4 Figure replaced by Drawing M1-E51-80, Sh. 4 7.4-3 Figure replaced by Drawing M-148, Sh. 1 7.4-4 Figure replaced by Drawing M1-C41-31, Sh. 1 7.5-3 Neutron Flux at Primary Shield 7.6-1 Recirculation Pump Leak Detection Block Diagram 7.6-2 RHR Area Temperature Monitoring System Block Diagram 7.6-3 Vessel Penetrations for Nuclear Instrumentation 7.6-4-1 Figure replaced by Drawing M1-C51-35, Sh. 1 7.6-4-2 Figure replaced by Drawing M1-C51-35, Sh. 2 7.6-5 SRM/IRM Neutron Monitoring Unit 7.6-6 Detector Drive System Schematic 7.6-7-1 Figure replaced by Drawing M1-C51-2, Sh. 1 7.6-7-2 Figure replaced by Drawing M1-C51-2, Sh. 2 7.6-7-3 Figure replaced by Drawing M1-C51-2, Sh. 3 7.6-7-4 Figure replaced by Drawing M1-C51-2, Sh. 4 7.6-7-5 Figure replaced by Drawing M1-C51-2, Sh. 5 7.6-7-6 Figure replaced by Drawing M1-C51-2, Sh. 6 7.6-7-7 Figure replaced by Drawing M1-C51-2, Sh. 7 7.6-8 Functional Block Diagram of SRM Channel 7.6-9 Functional Block Diagram of IRM Channel 7.6-10 Power Range Monitor Detector Assembly Location 7.6-11-1 Refer to Figure 5.4-2A 7.6-11-2 Figure replaced by Drawing M1-B31-13, Sh. 2 7.6-11-3 Figure replaced by Drawing M1-B31-13, Sh. 3 7.6-12 APRM Circuit Arrangement for Reactor Protection System Input 7.6-13 Ranges of Neutron Monitoring System 7.7-1 Water Level Range Definition 7.7-2-1 Control Rod Drive Hydraulic System - FCD 7.7-2-2 Control Rod Drive Hydraulic System - FCD 7.7-2-3 Control Rod Drive Hydraulic System - FCD 7.7-2-4 Control Rod Drive Hydraulic System - FCD 7.7-2-5 Control Rod Drive Hydraulic System - FCD 7.7-2-6 Control Rod Drive Hydraulic System - FCD 7.7-2-7 Control Rod Drive Hydraulic System - FCD 7.7-3-1 Figure replaced by Drawing M1-C12-90, Sh. 4 7.7-3-2 Figure replaced by Drawing M1-C12-110, Sh. 8 7.7-4 Reactor Manual Control System Operation 7.7-5 Reactor Manual Control Self-Test Provisions 7.7-6 Eleven-Wire Position Probe 7.7-7-1 Figure replaced by Drawing M1-B31-189, Sh. 1 7.7-7-2 Figure replaced by Drawing M1-B31-189, Sh. 2 7.7-7-3 Figure replaced by Drawing M1-B31-189, Sh. 3 7.7-7-4 Figure replaced by Drawing M1-B31-189, Sh. 4 FSAR Rev. 71 Page 58 of 113
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TABLE OF CONTENTS Chapter 7 Figures 7.7-7-5 Figure replaced by Drawing M1-B31-189, Sh. 5 7.7-7-6 ATWS Recirculation Pump Trip Logic 7.7-8 Recirculation Flow Control Illustration 7.7-9 Figure replaced by Drawing M1-C32-3, Sh. 1 7.7-10 Detector Drive System Schematic 7.7-11 Figure replaced by Drawing M1-G33-143, Sh. 1 7.7-13 Figure replaced by Drawing A-105, Sh. 1 7.7-13a Control room Panel Safety Related Display Instr. Plant Operator Interface 7.7-14 Traversing In-Core Probe Assembly 7.7-15 Main Turbine Control System Block Diagram 7.7-16 Assignment of LPRM Input to RBM System 7.7-19 Unit 2, Typical RBM Channel Responses, Old Versus New LPRM Assignment (No Failed LPRMS)
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TABLE OF CONTENTS Chapter 8 8.0 ELECTRIC POWER 8.1 Introduction 8.1.1 General 8.1.2 Utility Power Grid and Offsite Power Systems 8.1.3 Onsite Power Systems 8.1.4 Safety Related Loads 8.1.5 Design Bases 8.1.6 Regulatory Guides and IEEE Standards 8.2 Offsite Power System 8.2.1 Description 8.2.2 Analysis 8.2A Reliability Principles and Standards for Planning Bulk Electric Supply System of MAAC Group 8.3 Onsite Power Systems 8.3.1 AC Power Systems 8.3.2 DC Power Systems 8.3.3 Fire Protection for Cable Systems FSAR Rev. 71 Page 60 of 113
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TABLE OF CONTENTS Chapter 8 Tables 8.1-1 Motor Operated Valves With Thermal Overload Continuously Bypassed During Plant Operation 8.1-2 Affiliated and Non-Class 1E Circuits That Connect to Class 1E Power Supplies 8.1-3 Non-Class 1E Annunciator and Computer Interface Devices 8.1-4 Divisional or Affiliated Loads Supplied From Class 1E Channel C or D 4.16 kV Buss 8.1-5 Containment Radiation Monitors Supplied from Class 1E System 8.2-1 Susquehanna Unit #1 & #2 Stability Case List (Summer Light Load Conditions) 8.3-1 Assignment of ESF and Selected Non-ESF Loads to Diesel Generators and ESS Buses 8.3-1a Diesel Generator Loading (Note 1), Diesel Generators A, B, C and D In Service, Unit -
Design Basis Accident; Unit 2-Forced Shutdown 8.3-1b Supplement to Table 8.3-1 8.3-1c Diesel Generator E Loading, Diesel Generator E In Service for A or B or C or D, Unit 1-Design Basis Accident; Unit 2-Forced Shutdown 8.3-2 Diesel Generator Loading, Diesel A Unavailable, Unit 1-Design Basis Accident; Unit 2-Forced Shutdown 8.3-2a Diesel Generator E Loading, Diesel A Unavailable, Diesel Generator E Substituted for Diesel B or C or D, Unit 1-Design Basis Accident; Unit 2-Forced Shutdown 8.3-3 Diesel Generator Loading, Diesel B Unavailable, Unit 1-Design Basis Accident; Unit 2-Forced Shutdown 8.3-3a Diesel Generator Loading E, Diesel B Unavailable, Diesel Generator E Substituted for Diesel A or C or D, Unit 1-Design Basis Accident; Unit 2-Forced Shutdown 8.3-4 Diesel Generator Loading, Diesel C Unavailable, Unit 1-Design Basis Accident; Unit 2-Forced Shutdown 8.3-4a Diesel Generator E Loading, Diesel C Unavailable, Diesel Generator E Substituted for Diesel A or B or D, Unit 1-Design Basis Accident; Unit 2-Forced Shutdown 8.3-5 Diesel Generator Loading, Diesel D Unavailable, Unit 1-Design Basis Accident; Unit 2-Forced Shutdown 8.3-5a Diesel Generator E Loading, Diesel D Unavailable, Diesel Generator E Substituted for Diesel A or B or C, Unit 1-Design Basis Accident; Unit 2-Forced Shutdown 8.3-6A 125 Volt DC Load Cycle 1D610 8.3-6B 125 Volt DC Load Cycle 1D620 8.3-6C 125 Volt DC Load Cycle 1D630 8.3-6D 125 Volt DC Load Cycle 1D640 8.3-6E 125 Volt DC Load Cycle 2D610 8.3-6F 125 Volt DC Load Cycle 2D620 8.3-6G 125 Volt DC Load Cycle 2D630 8.3-6H 125 Volt DC Load Cycle 2D640 8.3-6I 125 Volt DC Load Cycle Channel H 0D597 8.3-6J 125V DC Battery Duty Load Profiles 8.3-7A Unit 1 250V DC Load Cycle Div. I (1D650) 8.3-7B Unit 1 250V DC Load Cycle Div. II (1D660) 8.3-7C Unit 2 250V DC Load Cycle Div. I (2D650) 8.3-7D Unit 2 250V DC Load Cycle Div. II (2D660) 8.3-7E 250V DC Battery Duty Load Profiles 8.3-7F Unit 1 250V DC Load Cycl Div I (1D650) SBO Profile FSAR Rev. 71 Page 61 of 113
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TABLE OF CONTENTS Chapter 8 Tables 8.3-7G Unit 1 250V DC Load Cycl Div II (1D660) SBO Profile 8.3-7H Unit 2 250V DC Load Cycl Div I (2D650) SBO Profile 8.3-7I Unit 2 250V DC Load Cycl Div II (2D660) SBO Profile 8.3-8 24 Volt DC Load Cycle 8.3-9 AC Power Failure Mode Effects Analysis 8.3-10 Routing Table 8.3-16 Diesel Generator Auto Start Circuit Failure Effects Analysis (1) 8.3-17 125V DC Control Power Source for Non-Class 1E 13.8 kV and 4.16 kV Switchgear 8.3-18 125V DC Control Power Source For Non-Class 1E 480V L.C.
8.3-19 125V DC Control Power Source For Class 1E 4.16 kV Switchgear 8.3-20 125V DC Control Power Source For Class 1E 480V LC 8.3-21 Failure Mode and Effect Analysis-125V DC System (4 Channels) 8.3-22 Failure Mode and Effect Analysis-250V DC System (2 Divisions) 8.3-23 Failure Mode and Effect Analysis-24V DC System (2 Divisions) 8.3-24 Common Mode-Common Cause Failure Analysis-Auto Transfer Switch 8.3-25 Separation Methods and Requirements Within Junction Boxes and Field Installed Pull Boxes 8.3-26 Common Mode - Common Cause Failure Analysis - Paragon Auto Transfer Switches FSAR Rev. 71 Page 62 of 113
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TABLE OF CONTENTS Chapter 8 Figures 8.2-1 Figure replaced by Drawing D159760, Sh. 1 8.2-2 Figure replaced by Drawing D159760, Sh. 2 8.2-3 Figure replaced by Drawing D159760, Sh. 3 8.2-4 Figure replaced by Drawing D159760, Sh. 4 8.3-1-1 Figure replaced by Drawing E-1, Sh. 1 8.3-1-2 Figure replaced by Drawing E-1, Sh. 1A 8.3-1-2a Figure replaced by Drawing E-1, Sh. 2 8.3-2 Figure replaced by Drawing E-4, Sh. 2 8.3-2A Preferred Power Supplies to Diesel Generator E Class 1E Power System 8.3-3 Figure replaced by Drawing E-5, Sh. 1 8.3-4 Figure replaced by Drawing E-5, Sh. 2 8.3-4A Figure replaced by Drawing E-5, Sh. 5 8.3-5 Figure replaced by Drawing E-11, Sh. 1 8.3-5A Figure replaced by Drawing E-11, Sh. 11 8.3-6 Figure replaced by Drawing E-13, Sh. 1 8.3-7 Figure replaced by Drawing E-8, Sh. 4 8.3-8 Figure replaced by Drawing E-8, Sh. 8 8.3-9-1 Figure replaced by Drawing E-9, Sh. 54 8.3-9-2 Figure replaced by Drawing E-9, Sh. 55 8.3-10 Figure replaced by Drawing M-260, Sh. 1 8.3-10A Figure replaced by Drawing M-261, Sh. 1 8.3-10B Figure replaced by Drawing M-5200, Sh. 1 8.3-11 Figure replaced by Drawing E-31, Sh. 8 8.3-12 Figure replaced by Drawing E-31, Sh. 9 8.3-13 Single Line Diagram for 480 Volt Swing Bus System 8.3-14 Figure replaced by Drawing FF62396, Sh. 8 8.3-14-1 Figure replaced by Drawing E152-2, Sh. 2 8.3-15 Figure replaced by Drawing E-31, Sh. 5 FSAR Rev. 71 Page 63 of 113
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TABLE OF CONTENTS Chapter 9 9.0 AUXILIARY SYSTEMS 9.1 Fuel Storage and Handling 9.1.1 New Fuel Storage 9.1.2 Spent Fuel Storage 9.1.3 Spent Fuel Pool Cooling and Cleanup System 9.1.4 Fuel Handling System and Reactor Servicing Equipment 9.1.5 Reactor Building Cranes 9.1.6 References 9.2 Water Systems 9.2.1 Service Water System 9.2.2 Reactor Building Closed Cooling Water System 9.2.3 Turbine Building Closed Cooling Water System 9.2.4 Gaseous Radwaste Recombiner Closed Cooling Water System 9.2.5 Emergency Service Water System 9.2.6 RHR Service Water System 9.2.7 Ultimate Heat Sink 9.2.8 Raw Water Treatment System 9.2.9 Makeup Demineralizer System 9.2.10 Condensate Storage and Transfer System 9.2.11 Potable Water and Sanitary Water Systems 9.2.12 Chilled Water Systems 9.2.13 References 9.3 Process Auxiliaries 9.3.1 Compressed Air Systems 9.3.2 Process Sampling System 9.3.3 Equipment and Floor Drainage System 9.3.4 Chemical and Volume Control System 9.3.5 Standby Liquid Control System 9.4 Air Conditioning, Heating, Cooling and Ventilation Systems 9.4.1 Control Room and Control Structure HVAC Systems 9.4.2 Reactor Building Ventilation System 9.4.3 Radwaste Building Ventilation System 9.4.4 Turbine Building Ventilation System 9.4.5 Primary Containment Atmosphere Recirculation and Cooling System 9.4.6 Refueling and Spent Fuel Area Ventilation System 9.4.7 Diesel Generator Buildings Ventilation System 9.4.8 Engineered Safeguard Service Water Pumphouse Ventilation System 9.4.9 Circulating Water Pumphouse and Water Treatment Building HVAC 9.5 Other Auxiliary Systems 9.5.1 Fire Protection System 9.5.2 Communication Systems 9.5.3 Lighting System 9.5.4 Diesel Generator Fuel Oil Storage and Transfer System FSAR Rev. 71 Page 64 of 113
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TABLE OF CONTENTS Chapter 9 9.5.5 Diesel Generator Cooling Water System 9.5.6 Diesel Generator Starting System 9.5.7 Diesel Generator Lubrication System 9.5.8 Diesel Generator Combustion Air Intake and Exhaust System 9.5-9 Hydrogen Water Chemistry (HWC) System 9.5-10 Passive Zinc Injection System 9.5-11 References 9A Analysis for Non-Seismic Spent Fuel Pool Cooling Systems 9B Compliance with NRC Branch Technical Position ASB 9-1 Susquehanna Steam Electric Station Unit 1 Reactor Building Crane FSAR Rev. 71 Page 65 of 113
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TABLE OF CONTENTS Chapter 9 Tables 9.1-1 Spent Fuel Pool Cooling and Cleanup System Component Description 9.1-2 Fuel Servicing Equipment Classification 9.1-2a Original Design Basis - Decay Heat Output Under Normal Fuel Storage Conditions 9.1-2b Original Design Basis - Decay Heat Output Under Normal Fuel Storage Conditions 9.1-2c Original Design Basis - Decay Heat Output Under Full Core Unload Conditions 9.1-2d Original Design Basis - Decay Heat Output Under Full Core Unload Conditions 9.1-2e Updated Design Basis - Decay Heat Output Under Normal Fuel Storage Conditions 9.1-2f Updated Design Basis - Decay Heat Output Under Full Core Unload Conditions 9.1-3 Reactor Vessel Servicing Equipment Classification 9.1-4 Under-Reactor Vessel Servicing Equipment and Tools Classification 9.1-5 Tools and Services Equipment 9.1-6a Unit 1 Reactor Building Crane Failure Modes and Effect Analysis 9.1-6b Unit 2 Reactor Building Crane Failure Modes and Effect Analysis 9.1-7a Load Combinations & Factored Allowable Stress Limits 9.1-7b Load Definitions 9.2-1 List of Coolers Supplied Cooling Water by the Service Water System 9.2-3 Definition of ESW Flows for Units 1 & 2 9.2-4 ESW Cooling Duty Following DBA for Minimum Heat Transfer Case (Loss of Auxiliary Power Followed by a Single Unit LOCA) 9.2-5 ESW Cooling Duty Following DBA for Maximum Water Loss Case (Loss of All Auxiliary Power Followed by a Single Unit LOCA) 9.2-6 Ultimate Heat Sink Components 9.2-7 Spray Pond Design Data 9.2-8 Susquehanna Pond Water Allowances 9.2-9 Minimum Heat Transfer Meteorology - Site Data First of the Two Worst Consecutive Days - August 2, 1975 9.2-10 Maximum Water Loss Meteorology Avoca Airport Data - Hourly Average Data For Worst 30 Days - March 6, 1951 Through April 4, 1951 9.2-12 Summary of Peak Temperature Values and Final Pond Water Inventory 9.2-13 Condensate and Refueling Water Storage Flow Paths 9.2-14 Control Structure Chilled Water System Design Data 9.2-15 Control Structure Chilled Water Systems Failure Mode and Effect Analysis 9.2-16 Turbine Building Chilled Water System Design Data 9.2-17 Reactor Building Chilled Water System Design Data 9.2-18 Radwaste Building Chilled Water System Design Data 9.2-19 Decay Heat Generation Branch Technical Position ASB 9-2 for One Core 9.2-20 Emergency Service Water System Heat Loads (Both Units) (X 106 BTU/HR) 9.2-21 RHR and RHR Service Water System Flow Rates (GPM) Minimum Heat Transfer Case 9.2-21a RHR and RHR Service Water System Flow Rates (GPM) Maximum Heat Transfer Case 9.2-22 Emergency Service Water System Flow Rates (GPM) 9.2-23 Initial Conditions 9.2-27 Size Comparison of Spray Ponds Investigated 9.2-28 Performance Comparison of CANADYS Station and Model Results 9.2-29 Performance Comparison of RANCHO SECO Test Results and Model Results 9.3-1 Instrument Air System Design Parameters (Typical for Units 1 & 2)
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TABLE OF CONTENTS Chapter 9 Tables 9.3-2 Instrument Air System Pneumatically Operated Valves Which Have a Safety Function 9.3-3 Instrument Air Compressors Failure Mode and Effect Analysis 9.3-4 Service Air System Design Parameters (Typical for Units 1 & 2) 9.3-5 Low Pressure Air System Design Parameters (Common to Units 1 & 2) 9.3-6 River Intake Structure Compressed Air System Design Parameters (Common for Units 1 & 2) 9.3-7 List of Instrument Gas Operated Devices 9.3-8 Containment Instrument Gas System Design Parameters (Typical for Units 1 & 2) 9.3-9 Containment Instrument Gas System Failure Mode and Effect Analysis 9.3-10 Equipment and Floor Drainage System Component Description 9.3-11 Standby Liquid Control System Operating Pressure/Temperature Conditions 9.4-1 Ventilation Systems Tests and Inspections 9.4-2 Control Structure HVAC Systems Design Parameters 9.4-3 Reactor Building HVAC Systems Design Parameters 9.4-4 Reactor Building - Safety Related and RCIC Air Cooling System Design Parameters 9.4-5 Reactor Building HVAC Systems Failure Mode and Effect Analysis 9.4-6 Radwaste Building HVAC Systems Design Parameters 9.4-7 Turbine Building HVAC Systems Design Parameters 9.4-8 Unit 1 and 2 Primary Containment Unit Coolers and Ventilation Fans' Design Parameters 9.4-9 Drywell Unit Coolers' and Recirculation Fans' Operating Modes 9.4-10 Primary Containment Atmosphere Recirculation and Cooling System Failure Mode and Effect Analysis 9.4-11 Diesel Generator A, B, C and D Building HVAC Systems Design Parameters 9.4-11A Diesel Generator 'E' Building HVAC System Design Parameters 9.4-11B Diesel Generator 'E' Building Ventilation System Design Temperature Parameters 9.4-12 Diesel Generator Building H&V Failure Mode and Effect Analysis 9.4-13 ESSW Pumphouse HVAC Systems Design Parameters 9.4-14 Engineered Safeguard Service Water Pumphouse H&V Systems Failure Mode and Effect Analysis 9.4-15 Circulating Water Pumphouse HVAC Systems Design Parameters 9.4-16 Control Room and Control Structure HVAC Systems Control Room Floor Cooling Systems Failure Mode and Effect Analysis 9.4-17 Control Room and Control Structure HVAC Systems Computer Room Floor Cooling Systems Failure Mode and Effect Analysis 9.4-18 Control Room and Control Structure HVAC Systems Control Structure H&V Systems Failure Mode and Effect Analysis 9.4-19 Control Room and Control Structure HVAC Systems Emergency Outside Air Supply Systems Failure Mode and Effect Analysis 9.4-20 Control Room and Control Structure HVAC Systems SGTS Equipment Room H&V Systems Failure Mode and Effect Analysis 9.4-21 Control Room and Control Structure HVAC Systems Battery Room Exhaust Systems Failure Mode and Effect Analysis FSAR Rev. 71 Page 67 of 113
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TABLE OF CONTENTS Chapter 9 Tables 9.5-3 Emergency Lighting System in Susquehanna SES 9.5-4 Communication Systems 9A-1 Results of Boiling Spent Fuel Pool Analysis 9B-1 Comparison of Unit 1 Reactor Building Crane Design with BTP ASB 9-1 FSAR Rev. 71 Page 68 of 113
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TABLE OF CONTENTS Chapter 9 Figures 9.1-1 New Fuel Storage 9.1-2 New Fuel Vault Cover Details 9.1-3 Spent Fuel Rack Isometric 9.1-4 Spent Fuel Rack Arrangement 9.1-5 Spent Fuel Rack Detail 9.1-6 Reference Case Fuel Storage Poison Can 9.1-7-1 Figure replaced by Drawing M-153, Sh. 1 9.1-7-2 Figure replaced by Drawing M-153, Sh. 2 9.1-8 Figure replaced by Drawing M-154, Sh. 1 9.1-9 Fuel Preparation Machine 9.1-10 New Fuel Inspection Stand 9.1-11 Channel Bolt Wrench 9.1-12 Channel Handling Tool 9.1-13 Fuel Pool Sipper 9.1-14 Fuel Inspection Fixture 9.1-15 Channel Gauging Fixture 9.1-16 General Purpose Grapple 9.1-18 Figure replaced by Drawing C-1807, Sh. 1 9.1-19 Figure replaced by Drawing C-1807, Sh. 2 9.1-20 Simplified Section of New Fuel Handling Facilities (Section X-X, Figure 9.1-18) 9.1-21 Simplified Section of Refueling Facilities (Section Y-Y, Figure 9.1-18) 9.1-22 Simplified Section of Fuel Shipping Facilities (Section Z-Z, Figure 9.1-19) 9.1-23 Unit 2 Refueling Mast and Grapple Outline 9.1-23-1 Unit 1 Refueling Mast and Grapple Outline 9.1-24 Fuel Transfer Stand 9.1-25 Air Operated General Purpose Grapple BWR 6 9.1-26 New Fuel Channel Up Ender 9.1-27 New Fuel Up Ending Stand 9.1-28 New Fuel Inspection Equipment General Arrangement 9.2-1A-1 Figure replaced by Drawing M-109, Sh. 1 9.2.1A-2 Figure replaced by Drawing M-109, Sh. 2 9.2.1A-3 Figure replaced by Drawing M-109, Sh. 3 9.2-1B Figure replaced by Drawing M-110, Sh. 1 9.2-1C Figure replaced by Drawing M-2110, Sh. 1 9.2-2 Figure replaced by Drawing M-113, Sh. 1 9.2-3 Figure replaced by Drawing M-114, Sh. 1 9.2-4 Figure replaced by Drawing M-131, Sh. 1 9.2-5a Figure replaced by Drawing M-111, Sh. 1 9.2-5b Figure replaced by Drawing M-111, Sh. 2 9.2-5c Figure replaced by Drawing M-111, Sh. 3 9.2-5d Figure replaced by Drawing M-111, Sh. 4 9.2-6 Figure replaced by Drawing M-112, Sh. 1 9.2-7-1 Figure replaced by Drawing M-117, Sh. 1 9.2-7-2 Figure replaced by Drawing M-117, Sh. 2 9.2-7-3 Figure replaced by Drawing M-117, Sh. 3 9.2-7-4 Figure replaced by Drawing M-117, Sh. 4 9.2-7-5 Figure replaced by Drawing M-117, Sh. 5 FSAR Rev. 71 Page 69 of 113
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TABLE OF CONTENTS Chapter 9 Figures 9.2-8-1 Figure replaced by Drawing M-118, Sh. 1 9.2-8-2 Figure replaced by Drawing M-118, Sh. 2 9.2-8-3 Figure replaced by Drawing M-118, Sh. 3 9.2-9 Figure replaced by Drawing M-108, Sh. 1 9.2-10 Sewage Treatment Plant Flowsheet 9.2-11-1 Figure replaced by Drawing M-186, Sh. 1 9.2-11-2 Figure replaced by Drawing M-186, Sh. 3 9.2-12 Figure replaced by Drawing M-188, Sh. 1 9.2-13a Figure replaced by Drawing M-187, Sh. 1 9.2-13b Figure replaced by Drawing M-187, Sh. 2 9.2-14-1 Figure replaced by Drawing M-189, Sh. 1 9.2-14-2 Figure replaced by Drawing M-189, Sh. 2 9.2-14-3 Figure replaced by Drawing M-189, Sh. 3 9.2-14-4 Figure replaced by Drawing M-189, Sh. 4 9.2-15 Drift Loss vs. Wind Speed 9.2-16 Drift Loss vs. Perimeter Distance 9.2-17 Spray Pond Incremental Mass and Energy Flow Schematic 9.2-18 Spray Pond Droplet Trajectory Parameters 9.2-21 Spray Pond Temperature Transient Minimum Heat Transfer Case 9.2-22 Spray Pond Water Inventory Maximum Water Loss Case 9.2-23 Spray Pond Spray Nozzle 9.2-24-1 Spray Pond Plan 9.2-24-2 ESSW Spray Pond Network A1 & B1 Plan, Section & Details 9.2-24-3 ESSW Spray Pond Network A2 & B2 Plan, Section & Details 9.3-1 Figure replaced by Drawing M-125, Sh. 1 9.3-2 Figure replaced by Drawing M-125, Sh. 2 9.3-2A Figure replaced by Drawing M-125, Sh. 6 9.3-3 Figure replaced by Drawing M-125, Sh. 30 9.3-3-4 Figure replaced by Drawing M-2125, Sh. 16 9.3-4 Figure replaced by Drawing M-125, Sh. 5 9.3-5-1 Figure replaced by Drawing M-126, Sh. 1 9.3-5-2 Figure replaced by Drawing M-126, Sh. 2 9.3-6-1 Figure replaced by Drawing M-123, Sh. 1 9.3-6-2 Figure replaced by Drawing M-123, Sh. 2 9.3-6-3 Figure replaced by Drawing M-123, Sh. 3 9.3-6-4 Figure replaced by Drawing M-123, Sh. 4 9.3-6-5 Figure replaced by Drawing M-123, Sh. 5 9.3-6-6 Figure replaced by Drawing M-123, Sh. 6 9.3-6-7 Figure replaced by Drawing M-123, Sh. 7 9.3-6-8 Figure replaced by Drawing M-123, Sh. 8 9.3-6-9 Figure replaced by Drawing M-123, Sh. 9 9.3-6-9A Figure replaced by Drawing M-123, Sh. 12 9.3-6-10 Figure replaced by Drawing M-123, Sh. 10 9.3-6-11 Figure replaced by Drawing M-123, Sh. 11 9.3-6-12 Figure replaced by Drawing M-123, Sh. 13 9.3-10-1 Figure replaced by Drawing M-161, Sh. 1 9.3-10-2 Figure replaced by Drawing M-161, Sh. 2 FSAR Rev. 71 Page 70 of 113
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TABLE OF CONTENTS Chapter 9 Figures 9.3-10-3 Figure replaced by Drawing M-161, Sh. 3 9.3-12 Figure replaced by Drawing M-160, Sh. 1 9.3-12A Figure replaced by Drawing M-160, Sh. 2 9.3-14 Sodium Pentaborate Volume-Concentration Requirements 9.3-15 Saturation Temperature of Sodium Pentaborate Solution 9.4-1-1 Figure replaced by Drawing M-178, Sh. 1 9.4-1-2 Figure replaced by Drawing M-178, Sh. 2 9.4-2-1 Figure replaced by Drawing VC-178, Sh. 1 9.4-2-2 Figure replaced by Drawing VC-178, Sh. 2 9.4-2-3 Figure replaced by Drawing VC-178, Sh. 3 9.4-2-4 Figure replaced by Drawing VC-178, Sh. 4 9.4-4a Figure replaced by Drawing M-176, Sh. 1 9.4-4b Figure replaced by Drawing M-2176, Sh. 1 9.4-5a Figure replaced by Drawing M-175, Sh. 1 9.4-5b Figure replaced by Drawing M-175, Sh. 2 9.4-5c Figure replaced by Drawing M-2175, Sh. 1 9.4-6a Figure replaced by Drawing VC-176, Sh. 1 9.4-6b Figure replaced by Drawing VC-2176, Sh. 1 9.4-7 Figure replaced by Drawing VC-175, Sh. 1 9.4-8 Figure replaced by Drawing VC-175, Sh. 2 9.4-9 Figure replaced by Drawing VC-175, Sh. 3 9.4-10 Figure replaced by Drawing M-179, Sh. 1 9.4-11 Figure replaced by Drawing M-179, Sh. 2 9.4-12 Figure replaced by Drawing VC-179, Sh. 1 9.4-13a Figure replaced by Drawing M-174, Sh. 1 9.4-13b Figure replaced by Drawing M-174, Sh. 2 9.4-14 Figure replaced by Drawing VC-174, Sh. 1 9.4-15 Figure replaced by Drawing M-177, Sh. 1 9.4-16a-1 Figure replaced by Drawing VC-177, Sh. 1 9.4-16a-2 Figure replaced by Drawing VC-177, Sh. 2 9.4-17 Exhaust Registers Refueling Floor 9.4-18 Figure replaced by Drawing VC-182, Sh. 1 9.4-18A Figure replaced by Drawing V-182, Sh. 8 9.4-18B Figure replaced by Drawing V-182, Sh. 8A 9.4-19 Figure replaced by Drawing M-182, Sh. 1 9.4-19A Figure replaced by Drawing M-182, Sh. 2 9.4-20 Figure replaced by Drawing M-173, Sh. 1 9.4-21 Figure replaced by Drawing VC-173, Sh. 1 9.4-22-1 Figure replaced by Drawing V-26-2, Sh. 1 9.4-22-2 Figure replaced by Drawing V-26-3, Sh. 1 9.4-22-3 Figure replaced by Drawing V-26-4, Sh. 1 9.4-22-4 Figure replaced by Drawing V-26-5, Sh. 1 9.4-22-5 Figure replaced by Drawing V-26-6, Sh. 1 9.4-22-6 Figure replaced by Drawing V-26-10, Sh. 1 9.4-22-7 Figure replaced by Drawing V-26-11, Sh. 1 9.4-22-8 Figure replaced by Drawing V-26-12, Sh. 1 9.4-22-9 Figure replaced by Drawing V-26-13, Sh. 1 FSAR Rev. 71 Page 71 of 113
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TABLE OF CONTENTS Chapter 9 Figures 9.4-22-10 Figure replaced by Drawing V-26-14, Sh. 1 9.4-22-11 Figure replaced by Drawing V-26-15, Sh. 1 9.4-22-12 Figure replaced by Drawing V-34-2, Sh. 1 9.4-22-13 Figure replaced by Drawing V-34-3, Sh. 1 9.5-13 Figure replaced by Drawing E-408, Sh. 1 9.5-14 Figure replaced by Drawing E-408, Sh. 2 9.5-15 Figure replaced by Drawing E-409, Sh. 1 9.5-16 Figure replaced by Drawing E-409, Sh. 2 9.5-16A Figure replaced by Drawing E-409, Sh. 3 9.5-16B Figure replaced by Drawing E-409, Sh. 4 9.5-16C Figure replaced by Drawing E-409, Sh. 5 9.5-16D Figure replaced by Drawing E-409, Sh. 6 9.5-16E Figure replaced by Drawing E-409, Sh. 7 9.5-17 Figure replaced by Drawing E-411, Sh. 1 9.5-18 Figure replaced by Drawing E-411, Sh. 2 9.5-19 Figure replaced by Drawing M-120, Sh. 1 9.5-19A Figure replaced by Drawing M-120, Sh. 2 9.5-19B Figure replaced by Drawing M-120, Sh. 3 9.5-20 Figure replaced by Drawing M-134, Sh. 1 9.5-20A Figure replaced by Drawing M-134, Sh. 5 9.5-20B Figure replaced by Drawing M-134, Sh. 6 9.5-20C Figure replaced by Drawing M-134, Sh. 7 9.5-21 Figure replaced by Drawing M30-69, Sh. 1 9.5-22 Figure replaced by Drawing M30-71, Sh. 1 9.5-22A Figure replaced by Drawing FF61604, Sh. 7 9.5-23 Figure replaced by Drawing M-738, Sh. 1 9.5-24 Figure replaced by Drawing FF61604, Sh. 3 9.5-26 Diesel Generator Building Area 44 Plan on El. 677'-0" Intake & Exhaust 9.5-26A Diesel Generator E Building Intake & Exhaust Piping 9.5-26B Diesel Generator E Building Area 81 Plan of El. 656'-6" 9.5-27 Diesel Generator Building 9.5-28 Figure replaced by Drawing C-1006, Sh. 1 9.5-29 Figure replaced by Drawing C-1007, Sh. 1 9.5-29-1 Figure replaced by Drawing C-1007, Sh. 2 9.5-30 Figure replaced by Drawing C-1032, Sh. 1 9.5-30A Figure replaced by Drawing C-5028, Sh. 1 9.5-31 Figure replaced by Drawing EC-1, Sh. 1 9.5-32 Figure replaced by Drawing EC-2, Sh. 1 9.5-33 Figure replaced by Drawing EC-3, Sh. 1 9.5-34 Figure replaced by Drawing EC-4, Sh. 1 9.5-35 Figure replaced by Drawing EC-5, Sh. 1 9.5-36 Figure replaced by Drawing EC-6, Sh. 1 9.5-37 Figure replaced by Drawing EC-7, Sh. 1 9.5-38 Figure replaced by Drawing EC-8, Sh. 1 9.5-39 Figure replaced by Drawing C-46, Sh. 1 9.5-40 Figure replaced by Drawing C-901, Sh. 1 9.5-40A Figure replaced by Drawing C-5012, Sh. 1 FSAR Rev. 71 Page 72 of 113
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TABLE OF CONTENTS Chapter 9 Figures 9.5-41 Figure replaced by Drawing C-904, Sh. 1 9.5-41A Figure replaced by Drawing C-5013, Sh. 1 9.5-42 Figure replaced by Drawing C-905, Sh. 1 9.5-42A Figure replaced by Drawing C-5014, Sh. 1 9.5-42B Figure replaced by Drawing C-5015, Sh. 1 9.5-43-1 Figure replaced by Drawing C-1029, Sh. 1 9.5-43-2 Figure replaced by Drawing C-1029, Sh. 2 9.5-47 Figure replaced by Drawing E-412, Sh. 1 FSAR Rev. 71 Page 73 of 113
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TABLE OF CONTENTS Chapter 10 10.0 STEAM AND POWER CONVERSION SYSTEM 10.1 Summary Description 10.2 Turbine-Generator 10.2.1 Design Bases 10.2.2 Description 10.2.3 Turbine Disk Integrity 10.2.4 Evaluation 10.2.5 References 10.3 Main Steam Supply System 10.3.1 Design Bases 10.3.2 Description 10.3.3 Evaluation 10.3.4 Inspection and Testing Requirements 10.3.5 Water Chemistry (PWR) 10.3.6 Steam and Feedwater System Materials 10.4 Other Features of the Steam and Power Conversion System 10.4.1 Main Condenser 10.4.2 Main Condenser Evacuation System 10.4.3 Steam Seal System 10.4.4 Turbine Bypass System 10.4.5 Circulating Water System 10.4.6 Condensate Cleanup System 10.4.7 Condensate and Feedwater 10.4.8 Steam Generator Blowdown System (PWR) 10.4.9 Auxiliary Feedwater System (PWR) 10.4.10 Extraction Steam and Feedwater Heater Drain and Vent System 10.4.11 Auxiliary Steam System FSAR Rev. 71 Page 74 of 113
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TABLE OF CONTENTS Chapter 10 Tables 10.1-1 Unit 1 - Summary of Typical Design and Performance Characteristics of Power Conversion System 10.1-1a Unit 2 - Summary of Typical Design and Performance Characteristics of Power Conversion System 10.2-1 Turbine Overspeed Protection 10.4-1 Condenser Design Parameters 10.4-3 Circulating Water Quality Design Parameters Used for the Condensate Cleanup 10.4-6 Design Conditions for Feedwater Heaters FSAR Rev. 71 Page 75 of 113
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TABLE OF CONTENTS Chapter 10 Figures 10.1-1a Guaranteed Flow Unit 1 10.1-1b Guaranteed Flow Unit 2 10.1-2a Valves Wide Open (VWO) Unit 1 10.1-2b Valves Wide Open (VWO) Unit 2 10.2-1 Turbine Stop Valve Closure Characteristic 10.2-2 Turbine Control Valve Fast Closure Characteristic 10.2-3 Mechanical Overspeed Trip 10.2-4 Figure replaced by Drawing M2H-54, Sh. 1 10.2-5 Figure replaced by Drawing M2J-101, Sh. 5 10.2-6 Rate Sensitive Power/Load Unbalance Circuit 10.2-11 Figure replaced by Drawing M-133, Sh. 1 10.4-1-1 Figure replaced by Drawing M-101, Sh. 1 10.4-1-1a Figure replaced by Drawing M-2101, Sh. 1 10.4-1-2 Figure replaced by Drawing M-101, Sh. 2 10.4-1-2a Figure replaced by Drawing M-2101, Sh. 2 10.4-1-3 Figure replaced by Drawing M-101, Sh. 3 10.4-1-3a Figure replaced by Drawing M-2101, Sh. 3 10.4-2-1 Figure replaced by Drawing M-116, Sh. 1 10.4-2-2 Figure replaced by Drawing M-116, Sh. 2 10.4-2-3 Figure replaced by Drawing M-116, Sh. 3 10.4-4-1 Figure replaced by Drawing M-105, Sh. 1 10.4-4-2 Figure replaced by Drawing M-105, Sh. 2 10.4-4-3 Figure replaced by Drawing M-105, Sh. 3 10.4-4-4 Figure replaced by Drawing M-105, Sh. 4 10.4-5-1 Figure replaced by Drawing M-106, Sh. 1 10.4-5-2 Figure replaced by Drawing M-106, Sh. 2 10.4-5-2A Figure replaced by Drawing M-2106, Sh. 2 10.4-5-3 Figure replaced by Drawing M-106, Sh. 3 10.4-5-3A Figure replaced by Drawing M-2106, Sh. 3 10.4-5-4 Figure replaced by Drawing M-106, Sh. 4 10.4-5-4A Figure replaced by Drawing M-2106, Sh. 4 10.4-5-5 Figure replaced by Drawing M-106, Sh. 5 10.4-6-1 Figure replaced by Drawing M-102, Sh. 1 10.4-6-1a Figure replaced by Drawing M-2102, Sh. 1 10.4-6-2 Figure replaced by Drawing M-102, Sh. 2 10.4-6-2a Figure replaced by Drawing M-2102, Sh. 2 10.4-6-3 Figure replaced by Drawing M-102, Sh. 3 10.4-6-3a Figure replaced by Drawing M-2102, Sh. 3 10.4-7 Figure replaced by Drawing M-103, Sh. 1 10.4-8 Figure replaced by Drawing M-104, Sh. 1 10.4-9-1 Figure replaced by Drawing M-107, Sh. 1 10.4-9-2 Figure replaced by Drawing M-107, Sh. 2 10.4-9-3 Figure replaced by Drawing M-107, Sh. 3 10.4-9-4 Figure replaced by Drawing M-107, Sh. 4 FSAR Rev. 71 Page 76 of 113
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TABLE OF CONTENTS Chapter 11 11.0 RADIATION WASTE MANAGEMENT 11.1 Source Terms 11.1.1 Fission Products 11.1.2 Activation Products 11.1.3 Tritium 11.1.4 Core Inventory, Fuel Experience and Depressurization Spiking 11.1.5 Process Leakage Sources 11.1.6 Other Releases 11.1.7 References 11.2 Liquid Waste Management Systems 11.2.1 Design Bases 11.2.2 System Descriptions 11.2.3 Radioactive Releases 11.2.4 Estimated Doses 11.3 Gaseous Waste Management Systems 11.3.1 Design Bases 11.3.2 System Descriptions 11.3.3 Radioactive Releases 11.3.4 Estimated Doses 11.3.5 References 11.4 Solid Waste Management System 11.4.1 Design Bases 11.4.2 System Description 11.4.3 References 11.5 Process and Effluent Radiological Monitoring And Sampling Systems 11.5.1 Design Bases 11.5.2 Process and Effluent Radiological Monitoring System Description 11.5.3 Effluent Monitoring and Sampling 11.5.4 Process Monitoring and Sampling 11.6 Low Level Radwaste Holding Facility (LLRWHF) 11.6.1 Design Basis 11.6.2 Low Level Radwaste Holding Facility Description 11.6.3 LLRWHF Waste Description and Capacity 11.6.4 LLRWHF Source Term 11.6.5 Containers 11.6.6 Container Shielding for Transport and Storage 11.6.7 Crane Loading and Unloading System 11.6.8 Health and Safety Requirements 11.6.9 Floor Drain System 11.6.10 LLRWHF HVAC System 11.6.11 Effluent Monitoring 11.6.12 Electrical Systems FSAR Rev. 71 Page 77 of 113
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TABLE OF CONTENTS Chapter 11 11.6.13 Control Panels 11.6.14 Radiation Zoning 11.6.15 Radiation Monitoring System 11.6.16 Shielding 11.6.17 Security 11.6.18 Fire Protection System Operating Description 11.6.19 Exposure to Operating Personnel 11.6.20 Environmental Consequences of Operation of the Low-Level Radioactive Waste Holding Facility 11.6.21 Liner Inspections 11.6.22 Safety Analysis 11.6-23 References 11.7 Independent Spent Fuel Storage Installation (ISFSI) 11.7.1 Design Basis 11.7.2 Dry Storage System Description (NUHOMS System and Holtec System) 11.7.3 ISFSI Source Terms 11.7.4 NUHOMS Dry Shielded Canister (DSC) and Holtec Multi-Purpose Canister (MPC) 11.7.5 NUHOMS Horizontal Storage Module (HSM) and Holtec HI-STORM FW Overpack 11.7.6 Transport Equipment 11.7.7 NUHOMS and Holtec System Operation 11.7.8 Radiological Assessment 11.7.9 Site Specific Evaluations 11.7.10 Heavy Loads 11.7.11 Auxiliary Systems 11.7.12 Dry Fuel Storage Aging Management Program (AMP)
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TABLE OF CONTENTS Chapter 11 Tables 11.1-1 Noble Radiogas Source Terms 11.1-2 Halogen Radioisotopes in Reactor Water and Steam 11.1-3 Other Fission Product Radioisotopes in Reactor Water 11.1-4 Coolant Activation Products in Reactor Water and Steam 11.1-5 Noncoolant Activation Products in Reactor Water 11.1-6 Depressurization Spiking Activity 95th Percentile Cumulative Probability 11.2-1 Expected Daily Inputs and Activities to the Liquid Waste Management System From Two Units 11.2-2 Expected Batched Inputs to the Liquid Radwaste System From the Solid Radwaste System For Normal Operation of Two Units 11.2-3 Liquid Waste Management System Component Description 11.2-4 Liquid Radwaste System Flows (Refer to Fig. 11.2-8) 11.2-5 Expected Radionuclide Activity Inventories of Liquid Radwaste System Components (Curies Per Component))
11.2-6 Design Basis Radionuclide Activity Inventories of Liquid Radwaste System Components (Curies Per Component))
11.2-8 Assumptions and Parameters Used For Evaluation of Radioactive Releases 11.2-9 Expected Radionuclide Activity Concentrations In Reactor Coolant and Main Steam Used For Evaluation of Radioactive Releases 11.2-10 Radwaste System Flow Rates and Stream Activities Used for Evaluation of Radioactive Releases 11.2-11 Expected Holdup Times For Collection, Processing, and Discharge Used for Evaluation of Radioactive Releases 11.2-12 Decontamination Factors Used For Evaluation of Radioactive Releases 11.2-13 Expected Yearly Activity Released From Liquid Radwaste Management Systems Used For Evaluation of Compliance With Appendix I of 10CFR50 (Ci/yr/site) 11.2-14 Calculated Expected Effluent Activity Concentrations for Evaluation of Radioactive Releases to the Susquehanna River 11.2-15 Input Data for Aquatic Dose Calculations 11.2-16 Tanks Outside Primary Containment Which Contain Potentially Radioactive Liquids 11.3-1 Annual Gaseous Releases Per Unit 11.3-2 Assumptions and Parameters Used For Evaluation of Gaseous Releases 11.3-4 Filter Trains Used to Control Gaseous Effluents 11.3-5 Off Gas System Major Equipment Description 11.3-6 Off Gas System Equipment Malfunction Analysis 11.3-7 Input Data For Atmospheric Dose Calculations 11.3-8 Off Gas System Flows (Refer to Fig. 11.3-1) (PPH 1 SCFM) 11.3-10 Comparison of Individual Doses from Expected Gaseous Effluent Releases with 10CFR50, Appendix I Design Objectives 11.3-11 Comparison of Expected Radionuclide Concentrations in the Environment from Routine Atmospheric Releases to 10CFR20 Limits 11.4-1 Inputs to the Solid Radwaste Collection System For Both Units 11.4-2 Dry Solid Waste Amount From Gas, Laundry Drain Filters, and Maintenance Activities 11.4-3 Solid Waste Management System Component Description 11.4-4 Solid Waste Management System Flows (Refer to Fig. 11.4-3)
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TABLE OF CONTENTS Chapter 11 Tables 11.4-5 Expected Inventories of Radioactive Materials in Components of the Solid Radwaste System 11.4-6 Design Inventories of Radioactive Materials in Components of the Solid Waste Management System (Curies) 11.4-9 Expected Inventories Of Radioactive Materials In Waste Shipping Casks 11.4-10 Design Inventories Of Radioactive Materials In Waste Shipping Casks) 11.5-1 Process and Effluent Radiation Monitoring Systems 11.5-2 Radiological Analysis Summary of Routine Effluent Sampling 11.5-3 Composition and Concentration of Nuclides in Routine Effluent Samples 11.6-1 Design Basis Sources and Assumptions Used to Calculate the Off-Site Radiological Consequences Due to a Container Drop from a Transport Vehicle (Reference 11.6-7) 11.6-2 Design Basis Sources and Assumptions Used to Calculate the Off-Site Radiological Consequences Due to Dropping a Heavy Component Onto the Solidified Waste Storage Vault (Reference 11.6-13) 11.6-3 Design Basis Sources and Assumptions Used to Calculate the Off-Site Radiological Consequences Due to an Unspecified Incendiary Event Involving 100% of DAW (Reference 11.6-6) 11.6-4 Design Basis Sources and Assumptions Used to Calculate the Off-Site Radiological Consequences Due to Loss of Off-Site Power to the LLRWHF (Reference 11.6-10) 11.6-5 Design Basis Sources and Assumptions Used to Calculate the Off-Site Radiological Consequences Due to Mobile Shielded Storage Module Without Lid (Reference 11.6-8)
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TABLE OF CONTENTS Chapter 11 Figures 11.1-1 Noble Radiogas Decay Constant Exponent Frequency Histogram 11.1-2 Radiohalogen Decay Constant Exponent Frequency Histogram 11.1-3 Nobel Radiogas Versus I-131 Leakage 11.2-1 Figure replaced by Drawing M-270, Sh. 1 11.2-2 Figure replaced by Drawing M-271, Sh. 1 11.2-3 Figure replaced by Drawing M-272, Sh. 1 11.2-4 Figure replaced by Drawing M-273, Sh. 1 11.2-5 Figure replaced by Drawing M-274, Sh. 1 11.2-6 Figure replaced by Drawing M-220, Sh. 1 11.2-7 Figure replaced by Drawing M-230, Sh. 1 11.2-8 Liquid Radwaste Management System Flow Diagram 11.2-9-1 This Figure has been replaced by Dwg. M-162, Sh. 1 11.2-9-2 This Figure has been replaced by Dwg. M-162, Sh. 2 11.2-9-3 This Figure has been replaced by Dwg. M-162, Sh. 3 11.2-11-1 Figure replaced by Drawing M-163, Sh. 1 11.2-11-2 Figure replaced by Drawing M-163, Sh. 2 11.2-11-3 Figure replaced by Drawing M-163, Sh. 3 11.2-12 Figure replaced by Drawing M-164, Sh. 1 11.2-13 Liquid Waste Management Scheme 11.2-14 Typical Mobile Processing System Flow Diagram 11.3-1 Offgas System Process Flow Diagram 11.3-2A-1 Figure replaced by Drawing M-169, Sh. 1 11.3-2A-2 Figure replaced by Drawing M-169, Sh. 2 11.3-2A-3 Figure replaced by Drawing M-169, Sh. 3 11.3-2A-4 Figure replaced by Drawing M-169, Sh. 4 11.3-2C-1 Figure replaced by Drawing M-2169, Sh. 1 11.3-2C-2 Figure replaced by Drawing M-2169, Sh. 2 11.3-2D-1 Figure replaced by Drawing M-2171, Sh. 1 11.3-2D-2 Figure replaced by Drawing M-2171, Sh. 2 11.3-3-1 Figure replaced by Drawing M-171, Sh. 1 11.3-3-2 Figure replaced by Drawing M-171, Sh. 2 11.3-4 Release Points Locations and Details 11.4-1-1 Figure replaced by Drawing M-166, Sh. 1 11.4-1-2 Figure replaced by Drawing M-166, Sh. 2 11.4-2-1 Figure replaced by Drawing M-167, Sh. 1 11.4-2-2 Figure replaced by Drawing M-167, Sh. 2 11.4-3 Solid Waste Management System Flow Diagram 11.6-1 Figure replaced by Drawing B1P-005, Sh. 1 11.6-2 Figure replaced by Drawing B1N-100, Sh. 1 11.6-3 Shield Bell Assembly FSAR Rev. 71 Page 81 of 113
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TABLE OF CONTENTS Chapter 12 12.0 RADIATION PROTECTION 12.1 Ensuring that Occupational Radiation Exposures Are As Low As Reasonably Achievable (ALARA) 12.1.1 Policy Considerations 12.1.2 Design Considerations 12.1.3 Operational Considerations 12.1.4 References 12.2 Radiation Sources 12.2.1 Contained Sources 12.2.2 Airborne Radioactive Material Sources 12.3 Radiation Protection Design Features 12.3.1 Facility Design Features 12.3.2 Shielding 12.3.3 Ventilation 12.3.4 Area Radiation and Airborne Radioactivity Monitoring Instrumentation 12.3.5 References 12.4 Dose Assessment 12.4.1 Direct Radiation Dose Estimates for Exposures Within the Plant 12.4.2 Airborne Radioactivity Dose Estimates for Exposures Within the Plant 12.4.3 Exposures at Locations Outside Plant Structures 12.4.4 References 12.5 Health Physics Program 12.5.1 Organization 12.5.2 Facilities, Equipment, & Instrumentation 12.5.3 Procedures FSAR Rev. 71 Page 82 of 113
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TABLE OF CONTENTS Chapter 12 Tables 12.2-1 Basic Reactor Data 12.2-2 Core Region Description Used in Calculations to Determine Radial Flux Distribution at Reactor Core Midplane 12.2-3 Material Composition to Determine Radial Flux Distributions at Reactor Core Midplane 12.2-4 Calculated Gamma Ray and Neutron Fluxes at Outside Surface of RPV 12.2-5 Calculated Gamma Ray and Neutron Fluxes at Outside Surface of Primary Shield 12.2-6 Reactor Water Cleanup System N-16 Shielding Source Terms 12.2-7 Reactor Water Cleanup Filter Demineralizer Shielding Source Terms 12.2-8 Reactor Water Cleanup Backwash Receiving Tank Shielding Source Terms 12.2-9A1 Activity (Curies) per Full Core of ATRIUM-11 Fuel 12.2-9A2 Activity (Curies) per Single Assembly of ATRIUM-11 Fuel 12.2-10 Residual Heat Removal System Shielding Source Terms 12.2-11 Steam N-16 Shielding Source Terms for Turbine and Reactor Building Equipment 12.2-12 Fuel Pool System Shielding Source Terms 12.2-13 Fuel Pool Filter Demineralizer Shielding Source Terms 12.2-14 Fuel Pool Water Cleanup Backwash Receiving Tank Shielding Source Terms 12.2-15 Condensate Shielding Source Terms 12.2-16 Condensate Demineralizer Shielding Source Terms 12.2-17 Off-gas Line from SJAE to Recombiner Shielding Source Terms 12.2-18 Off-gas Primary Recombiner Shielding Source Terms 12.2-19 Off-gas Line from Recombiner to Charcoal System Shielding Source Terms 12.2-21 Off-gas Ambient Charcoal Freon Chiller Shielding Source Terms 12.2-22 Off-gas Charcoal Guard Bed Shielding Source Terms 12.2-23 Off-gas Charcoal Beds Shielding Source Terms 12.2-24 Off-gas Post-HEPA Filter Shielding Source Terms 12.2-29 Condensate Storage Tank Source Terms 12.2-30 Estimated Airborne Radioactive Releases Prior to Treatment (Curies/Year) 12.2-31 Estimated Distribution of Airborne Radioactive Releases 12.2-32 Turbine Building Airborne Source Descriptions 12.2-33 Reactor Building Airborne Source Descriptions 12.2-34 Radwaste Building Airborne Source Descriptions 12.2-35 Estimated Airborne Concentrations in the Turbine Building and Fraction of DACs 12.2-36 Estimated Airborne Concentrations in the Reactor Building and Fraction of DACs 12.2-37 Estimated Airborne Concentrations in the Radwaste Building and Fraction of DACs 12.2-38 Turbine Building Shielding Design Radiation Source Description 12.2-39 Reactor Building Shielding Design Radiation Source Description 12.2-40 Radwaste Building Shielding Design Radiation Source Terms 12.2-41 Material Composition of the TIP System Components As Used in Activation Calculations 12.2-42 Traversing Incore Probe Detector Decay Gamma Activities in MEV/Sec of 0.001 g of U-235 12.2-43 Traversing Incore Probe Detector Decay Gamma Activities of Materials in the Detector (Excluding U-235) in Microcuries in the Irradiated Detector 12.2-44 Decay Gamma Activities of Materials in the Cable in Microcuries per Inch of Irradiated Cable.
12.2-46 Condensate Filter Vessel Shielding Source Terms 12.2-47 Condensate Filter Vessel Backwash Shielding Source Terms FSAR Rev. 71 Page 83 of 113
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TABLE OF CONTENTS Chapter 12 Tables 12.2-48 Condensate Filter Vessel Backwash Receiving Tank Shielding Source Terms 12.3-1 Plant Radiation Zone Description 12.3-2 List of Computer Codes Used in Shielding Design Calculations 12.3-7 Area Radiation Monitoring System 12.4-1 Summary of Historical Data Used in Compilation of Exposures Received at Operating Boiling Water Reactors 12.4-2 Occupational Exposures By Job Function for Operating Boiling Water Reactors 12.4-3 Exposure Estimates for the Turbine Building and Control Structure 12.4-4 Exposure Estimates for the Reactor Building 12.4-5 Exposure Estimates for the Radwaste Building 12.4-6 Estimated Exposure for Operators in Residence in Control Rooms 12.4-7 Summary of Routine Operations Exposure Estimate 12.4-8 Estimate of Expected Maintenance Man-hours for Various Types of Equipment 12.4-9 Summary of In-Plant Direct Radiation Exposure Estimates 12.4-10 Estimated Turbine Building Inhalation Exposures Due to Airborne Radioactivity 12.4-11 Estimated Reactor Building Inhalation Exposures Due to Airborne Radioactivity 12.4-12 Estimated Radwaste Building Inhalation Exposures Due to Airborne Radioactivity FSAR Rev. 71 Page 84 of 113
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TABLE OF CONTENTS Chapter 12 Figures 12.3-1 Typical Shielding Arrangement for Liquid Radwaste Filters and Valve Gallery 12.3-2 Typical Shielding Arrangement for Radwaste Demineralizer 12.3-3 Typical Shielding Arrangement for Charcoal and Particulate Filter 12.3-4 Typical Shielding Arrangement for Off-gas Recombiners 12.3-5 Typical Shielding Arrangement for Radwaste Tanks and Pumps 12.3-6 Typical Shielding Arrangement for Radwaste Evaporator 12.3-8 Figure replaced by Drawing A-511, Sh. 1 12.3-9 Figure replaced by Drawing A-512, Sh 1 12.3-10 Figure replaced by Drawing A-513, Sh. 1 12.3-11 Figure replaced by Drawing A-514, Sh. 1 12.3-12 Figure replaced by Drawing A-515, Sh. 1 12.3-13 Figure replaced by Drawing A-516, Sh. 1 12.3-14 Figure replaced by Drawing A-517, Sh. 1 12.3-15 Figure replaced by Drawing A-518, Sh. 1 12.3-16 Figure replaced by Drawing A-519, Sh. 1 12.3-17 Figure replaced by Drawing A-520, Sh. 1 12.3-18 Figure replaced by Drawing A-521, Sh. 1 12.3-19 Figure replaced by Drawing A-522, Sh. 1 12.3-20 Figure replaced by Drawing A-523, Sh. 1 12.3-21 Figure replaced by Drawing A-524, Sh. 1 12.3-22 Figure replaced by Drawing A-525, Sh. 1 12.3-23 Figure replaced by Drawing A-526, Sh. 1 12.3-24 Figure replaced by Drawing A-527, Sh. 1 12.3-25 Figure replaced by Drawing A-528, Sh. 1 12.3-26 Figure replaced by Drawing A-529, Sh. 1 12.3-27 Figure replaced by Drawing A-530, Sh. 1 12.3-28 Figure replaced by Drawing BIN-100 12.3-29 Scaled Isometric of Control Building with Relationship to Containment 12.3-30-1 Figure replaced by Drawing M-137, Sh. 1 12.3-30-2 Figure replaced by Drawing M-137, Sh. 2 12.4-1 Estimated Turbine Shine Dose Rates 12.5-1 Health Physics Organization FSAR Rev. 71 Page 85 of 113
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TABLE OF CONTENTS Chapter 13 13.0 CONDUCT OF OPERATIONS 13.1 Organizational Structure 13.1.1 Management and Technical Support Organization 13.1.2 Operating Organization 13.1.3 Qualification Requirements for Nuclear Plant (On-Site) Personnel 13.2 Training Program 13.2.1 Plant Personnel Training Program 13.2.2 Requalification and Replacement Training 13.3 Emergency Plan 13.4 Review and Audit 13.4.1 Plant Operations Review Committee 13.4.2 Nuclear Safety Review Board 13.4.3 Audit Program 13.4.4 Process Control Program (PCP) 13.4.5 Technical Review and Control 13.5 Plant Procedures 13.5.1 Administrative Procedures 13.5.2 Operating and Maintenance Procedures 13.6 Industrial Security FSAR Rev. 71 Page 86 of 113
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TABLE OF CONTENTS Chapter 13 Tables 13.1-1 Resumes of Key General Office Personnel 13.1-2 Resumes of Key Plant Personnel FSAR Rev. 71 Page 87 of 113
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TABLE OF CONTENTS Chapter 13 Figures 13.1-1 Talen Energy Corporation Management Organization Applicable to Susquehanna SES 13.1-2 Susquehanna Nuclear, LLC, Off-Site Organization 13.1-3 Susquehanna Nuclear, LLC, On-Site Organization 13.5-2 Main Control Room FSAR Rev. 71 Page 88 of 113
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TABLE OF CONTENTS Chapter 14 14.0 INITIAL TEST PROGRAM 14.1 Specific Information to be Included in Preliminary Safety Analysis Reports 14.2 Specific Information to be Included in Final Safety Analysis Report 14.2.1 Summary Of Test Program and Objectives 14.2.2 Organization and Staffing 14.2.3 Test Procedures 14.2.4 Conduct of Test Program 14.2.5 Review, Evaluation, and Approval of Test Results 14.2.6 Test Records 14.2.7 Conformance of Test Programs With Regulatory Guides 14.2.8 Utilization of Reactor Operating and Testing Experience In the Development of The Test Program 14.2.9 Trial Use of Plant Operating and Emergency Procedures 14.2.10 Initial Fuel Loading and Initial Criticality 14.2.11 Test Program Schedule 14.2.12 Individual Test Descriptions 14.3 Power Uprate Test Program 14.3.1 Summary of Power Uprate Test Program and Objectives 14.3.2 Organization and Staffing 14.3.3 Test Procedures FSAR Rev. 71 Page 89 of 113
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TABLE OF CONTENTS Chapter 14 Tables 14.2-1 Preoperational Test Procedures 14.2-2 Acceptance Test Procedures 14.2-3 Startup Test Procedures 14.2-4 Major Test Phase and Test Plateau Schedule - Test Condition Sequence 14.2-5 Control Rod Drive System Startup Tests 14.2-6 Unit 2 Preoperational Test Procedures 14.2-7 Unit 2 Acceptance Test 14.3-1 Power Uprate Test Procedures 14.3-2 Test Plateau and Test Condition Definition FSAR Rev. 71 Page 90 of 113
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TABLE OF CONTENTS Chapter 14 Figures 14.2-1 Integrated Startup Group Organization 14.2-2A Preoperational Test Procedure Standard Format 14.2-2B Startup Test Procedure Standard Format - Unit 1 14.2-2C Startup Test Procedure Standard Format - Unit 2 14.2-3 Initial Test Program Schedule 14.2-4a Unit 1 Preoperational Test Sequence 14.2-4b Unit 2 Preoperational Test Sequence 14.2-5-1 Individual Startup Test Sequence - Unit 1 14.2-5-2 Individual Startup Test Sequence - Unit 1 14.2-5-3 Individual Startup Test Sequence - Unit 2 14.2-5-4 Individual Startup Test Sequence - Unit 2 14.2-6-1 Power Flow Map and Startup Test Conditions 14.2-6-2 Power Flow Map and Power Test Conditions 14.2-7 RCIC Acceptance Criteria Curves For Capacity and Actuation Time FSAR Rev. 71 Page 91 of 113
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TABLE OF CONTENTS Chapter 15 15.0 ACCIDENT ANALYSIS 15.0.1 Analytical Objective 15.0.2 Analytical Categories 15.0.3 Event Evaluation 15.0.4 Nuclear Safety Operational Analysis (NSQA) Relationship 15.0.5 References 15.1 Decrease in Reactor Coolant Temperature 15.1.1 Loss of Feedwater Heating 15.1.2 Feedwater Controller Failure-Maximum Demand 15.1.3 Pressure Regulator Failure - Open 15.1.4 Inadvertent Safety/Relief Valve Opening 15.1.5 Spectrum of Steam System Piping Failures Inside and Outside of Containment In A PWR 15.1.6 Inadvertent RHR Shutdown Cooling Operation 15.1.7 References 15.2 Increase in Reactor Pressure 15.2.1 Pressure Regulator Failure - Closed 15.2.2 Generator Load Rejection 15.2.3 Turbine Trip 15.2.4 MSIV Closures 15.2.5 Loss of Condenser Vacuum 15.2.6 Loss of AC Power 15.2.7 Loss of Feedwater Flow 15.2.8 Feedwater Line Break 15.2.9 Failure of RHR Shutdown Cooling 15.2.10 References 15.3 Decrease in Reactor Coolant System Flow Rate 15.3.1 Recirculation Pump Trip 15.3.2 Recirculation Flow Control Failure - Decreasing Flow 15.3.3 Recirculation Pump Seizure 15.3.4 Recirculation Pump Shaft Break 15.3.5 References 15.4 Reactivity and Power Distribution Anomalies 15.4.1 Rod Withdrawal Error - Low Power 15.4.2 Rod Withdrawal Error-at Power 15.4.3 Control Rod Maloperation (System Malfunction or Operator Error) 15.4.4 Abnormal Startup of Idle Recirculation Pump 15.4.5 Recirculation Flow Control Failure with Increasing Flow 15.4.6 Chemical and Volume Control System Malfunctions 15.4.7 Misplaced Bundle Accident 15.4.8 Spectrum of Rod Ejection Assemblies 15.4.9 Control Rod Drop Accident (CRDA) 15.4.10 References FSAR Rev. 71 Page 92 of 113
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TABLE OF CONTENTS Chapter 15 15.5 Increase in Reactor Coolant Inventory 15.5.1 Inadvertent HPCI Startup 15.5.2 Chemical Volume Control System Malfunction (or Operator Error) 15.5.3 BWR Transients Which Increase Reactor Coolant Inventory 15.5.4 References 15.6 Decrease in Reactor Coolant Inventory 15.6.1 Inadvertent Safety Relief Valve Opening 15.6.2 Instrument Line Break 15.6.3 Steam Generator Tube Failure 15.6.4 Steam System Piping Break Outside Containment 15.6.5 Loss-Of-Coolant Accidents (Resulting From Spectrum of Postulated Piping Breaks Within The Reactor Coolant Pressure Boundary) - Inside Containment 15.6.6 Feedwater Line Break-Outside Containment 15.6.7 References 15.7 Radioactive Release from Subsystems and Components 15.7.1 Gaseous Radwaste System Leak or Failure 15.7.2 Liquid Radwaste System Failure 15.7.3 Postulated Radioactive Releases Due To Liquid Radwaste Tank Failure 15.7.4 Fuel and Equipment Handling Accidents 15.7.5 Spent Fuel Cask Drop Accident 15.7.6 References 15.8 Anticipated Transients Without Scram (ATWS) 15.8.1 Causes, Frequency Classification, Initiating Events, Acceptance Criteria, Mathematical Models, Input Parameters, and Initial Conditions 15.8.2 Inadvertent Control Rod Withdrawal 15.8.3 Loss of Feedwater (LOFW) 15.8.4 Loss of Offsite Power (LOOP) 15.8.5 Loss of Electrical Load 15.8.6 Loss of Condenser Vacuum 15.8.7 Turbine Trip 15.8.8 Closure of Main Steam Line Isolation Valves 15.8.9 Pressure Regulator Failure-Open 15.8.10 Feedwater Controller Failure-Open (FWCFO) 15.8.11 Inadvertent Opening of a S/R Valve 15.8.12 References 15.9 Station Blackout (SBO) 15.9.0 Coping Assessment for the Susquehanna Steam Electric Station During a Station Blackout 15.9.1 References 15A Nuclear Safety Operational Analysis (NOSA) (A System Level/Qualitative Type Plant FMEA) 15A.1 OBJECTIVES 15A.1.1 General Objectives FSAR Rev. 71 Page 93 of 113
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TABLE OF CONTENTS Chapter 15 15A.1.2 Specific Objectives 15A.2 APPROACH TO OPERATIONAL NUCLEAR SAFETY 15A.2.1 General Philosophy 15A.2.2 Specific Philosophy 15A.2.3 Comprehensiveness of the Analysis 15A.2.4 Systematic Approach of the Analysis 15A.2.5 Relationship of Nuclear Safety Operational Analysis to Safety Analyses of Chapter 15 15A.2.6 Relationship Between NSOA and Operational Requirements, Technical Specifications, Design Basis, and SACF Aspects 15A.2.7 Unacceptable Results Criteria 15A.2.8 General Nuclear Safety Operational Criteria 15A.3 METHOD OF ANALYSIS 15A.3.1 General Approach 15A.3.2 BWR Operating States 15A.3.3 Selection of Events for Analysis 15A.3.4 Applicability of Events to Operating States 15A.3.5 Rules for Event Analysis 15A.3.6 Steps in an Operational Analysis 15A.4 DISPLAY OF OPERATIONAL ANALYSIS RESULTS 15A.4.1 General 15A.4.2 Protection Sequence and Safety System Auxiliary Diagrams 15A.5 BASES FOR SELECTING SURVEILLANCE TEST FREQUENCIES 15A.5.1 Normal Surveillance Test Frequencies 15A.5.2 Allowable Repair Times 15A.5.3 Repair Time Rule 15A.6 OPERATIONAL ANALYSES 15A.6.1 Safety System Auxiliaries 15A.6.2 Planned (Normal) Operations 15A.6.3 Anticipated (Expected) Operational Transients 15A.6.4 Abnormal (Unexpected) Operational Transients 15A.6.5 Design Basis (Postulated) Accidents 15A.6.6 Special (Plant Capability) Events 15A.7 REMAINDER OF NSQA 15A.8 CONCLUSIONS 15A.9 LIST OF REFERENCES 15B Accident Dose Model Descriptions 15B.1 OFFSITE DOSE MODEL 15B.1.1 Total Body Gamma Dose 15B.1.2 Thyroid Inhalation Dose 15B.1.3 Beta Skin Dose 15B.2 CONTROL ROOM DOSE MODEL 15B.3 REFERENCES 15C Susquehanna Steam Electric Station Unit 1 Final Safety Analysis Report-Cycle Specific Data 15C.1 Appendix C Contents FSAR Rev. 71 Page 94 of 113
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TABLE OF CONTENTS Chapter 15 15C.1.1 Content Discussion 15C.1.2 References 15D Susquehanna Steam Electric Station Unit 2 Final Safety Analysis Report-Cycle Specific Data 15D.1 Appendix D Contents 15D.1.1 Content Discussion 15D.1.2 References 15E Susquehanna Steam Electric Station Units 1 and 2 Non-Limiting Events FSAR Rev. 71 Page 95 of 113
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TABLE OF CONTENTS Chapter 15 Tables 15.1-1 Sequence or Events for Inadvertent Safety Relief Valve Opening 15.1-2 Safety Relief Valve Opening Event Activity Above Suppression Pool (Curies) 15.1-3 Safety Relief Valve Opening Event Activity Release to Environs (Curies) 15.1-4 Safety Relief Valve Opening Event Radiological Doses (REM-TEDE) 15.1-5 Inadvertent Safety/Relief Valve Openings 15.4-2 Control Rod Drop Accident - Design Basis Analysis-Airborne Activity in Condense (2000 Failed Rods) 15.4-3 Control Rod Drop Accident - Design Basis Analysis-Airborne Activity in Condenser (35 Failed Rods) 15.4-4 Control Rod Drop Accident - Design Basis Analysis- Activity Released to Environs (2000 Failed Rods) 15.4-5 Control Rod Drop Accident - Design Basis Analysis- Activity Released to Environs (35 Failed Rods) 15.4-6 Control Rod Drop Accident - Activity Airborne in Condenser (Realistic Analysis)
(2000 Rods) 15.4-7 Control Rod Drop Accident - Activity Airborne in Condenser (Realistic Analysis)
(35 Rods) 15.4-8 Control Rod Drop Accident - Activity Released to Environs (Realistic Analysis)
(2000 Rods) 15.4-9 Control Rod Drop Accident - Activity Released to Environs (Realistic Analysis)
(35 Rods) 15.4-10 Control Rod Accident Radiological Effects Design Basis Case and Realistic Case 15.4-11 Control Rod Drop Accident - Parameters to be Tabulated for Postulated Accident Analysis 15.6-1 Sequence of Events for Instrument Line Break 15.6-2 Mass Releases-Instrument Line Break 15.6-3 Instrument Line Break Activity Released to the Environment (Curies) 15.6-4 Instrument Line Break Inside Secondary Containment Radiological Consequences 15.6-5 Instrument Line Break Accident - Parameters for Postulated Accident Analysis 15.6-6 Sequence of Events for Steam Line Break Outside Containment 15.6-7 Steam Line Break Accident Activity Released to the Environment (Curies)
(Design Basis Analysis) 15.6-8 Steam Line Break Accident Activity Released to the Environment (Curies)
(Realistic Analysis) 15.6-9 Steam Line Break Outside Containment Radiological Doses (rem) 15.6-10 Steam Line Break Accident - Parameters to be Tabulated for Postulated Accident Analyses 15.6-11 Loss of Coolant Accident - Activity Airborne in Primary Containment (Curies)
(Design Basis Analysis) 15.6-13 Loss of Coolant Accident - Activity Airborne in Reactor Building (Curies) (Design Basis Analysis) 15.6-14 Loss of Coolant Accident - Activity Released to Environment (Curies) (Design Basis Analysis) 15.6-15 Loss of Coolant Accident - Activity Airborne in Primary Containment (Curies)
(Realistic Analysis)
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TABLE OF CONTENTS Chapter 15 Tables 15.6-16 Loss of Coolant Accident - Activity Airborne in Reactor Building (Curies)
(Realistic Analysis) 15.6-17 Loss of Coolant Accident - Activity Released to Environment (Curies) (Realistic Analysis) 15.6-18 Loss-of-Coolant Accident - Summary of Offsite Doses 15.6-21 Loss-of-Coolant Accident - Summary of Control Room Operator Doses (Design Basis Analysis) 15.6-22 Loss-of-Coolant Accident - Parameters for Postulated Accident Analysis 15.6-23 Sequence of Events for Feedwater Line Break Outside Containment 15.6-24 Feedwater Line Break Accident - Parameters for Postulated Accident Analyses 15.6-25 Feedwater Line Break Activity Released to Environment (Curies) 15.6-26 Feedwater Line Break Outside Containment Radiological Doses (rem) 15.7-1 Sequence of Events for Main Condenser Offgas Treatment System Failure 15.7-2 Activity Inventory Stored in Offgas Treatment System Activity Released to the Environs (curies) (Design Basis Analysis) 15.7-3 Activity Inventory Stored in Offgas Treatment System Activity Released to the Environs (curies) (Realistic Analysis) 15.7-4 Main Condenser Offgas Treatment System Failure Radiological Effects 15.7-5 Offgas Treatment System Failure Parameters for Postulated Accident Analysis 15.7-6 Failure of Air Ejector Lines Activity Released to the Environment (curies/sec) 15.7-7 Failure of Steam Jet Air Ejector Lines Radiological Consequences 15.7-8 Failure of Air Ejector Lines Parameters for Postulated Accident Analysis 15.7-9 RWCU Phase Separator Tank Failure - Initial Activity 15.7-9A RWCU Phase Separator Tank Failure Activity Release to Environment 15.7-10 RWCU Phase Separator Tank Failure Radiological Effects 15.7-11 RWCU Phase Separator Tank Failure 15.7-12 Refueling Accidents Activity Airborne in Reactor Building (Curies) (Design Basis Analysis) 15.7-13 Refueling Accidents Activity Released to Environment (Curies)
(Design Basis Analysis) 15.7-14 Refueling Accidents - Activity Airborne in Reactor Building (Realistic Analysis) 15.7-15 Refueling Accidents - Activity Released to Environs (Realistic Analysis) 15.7-16 Refueling Accidents - Radiological Effects 15.7-17 Refueling Accidents - Parameters to be Tabulated for Postulated Accident Analyses 15.7-18 Sequence of Events for SJAE Failure 15.8-1 Input Parameters for ATWS Analysis 15.8-3 Input Operating Conditions for ATWS Analysis 15.8-5 Sequence of Events for MSIV Closure ATWS 15.8-7 Results for MSIV Closure ATWS Event 15.8-9 Sequence of Events for Prego ATWS 15.8-11 Results for Prego ATWS Event 15.9-1 Unit 1 Station Blackout Instrumentation List 15.9-2 Unit 2 Station Blackout Instrumentation List FSAR Rev. 71 Page 97 of 113
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TABLE OF CONTENTS Chapter 15 Tables 15A.2-1 Planned (Normal) Operation Cross-Correlation References 15A.2-2 Anticipated (Expected) Operational Transients Cross-Correlation References 15A.2-3 Abnormal (Unexpected) Operational Transients Cross-Correlation References 15A.2-4 Design Basis (Postulated) Accidents Cross-Correlation References 15A.2-5 Special (Plant Capability) Events Cross-Correlation References 15A.2-6 Plant Event Category: Planned (Normal) Operation Unacceptable Results Criteria 15A.2-7 Plant Event Category: Anticipated (Expected) Operational Transients Unacceptable Results Criteria 15A.2-8 Plant Event Category: Abnormal (Unexpected) Operational Transients Unacceptable Results Criteria 15A.2-9 Plant Event Category: Design Basis (Postulated) Accidents Unacceptable Result Criteria 15A.2-10 Plant Event Category: Special (Plant Capability) Events Unacceptable Results Considerations 15A.3-1 BWR Operating States 15A.6-1 Plant Events Applicable in Each BWR Operating State Planned (Normal)
Operation 15A.6-2 Plant Events Applicable in Each BWR Operating State Anticipated (Expected)
Operational Transients 15A.6-3 Plant Events Applicable in Each BWR Operating State Abnormal (Unexpected)
Operational Transients 15A.6-4 Plant Events Applicable in Each BWR Operating State Design Basis (Postulated)
Accidents 15A.6-5 Plant Events Applicable in Each BWR Operating State Special (Plant Capability)
Events 15.B-1 Control Room Atmospheric Dispersion Factors For Design Basis Accidents - X/Q 15B-2 Physical Data for Isotopes 15B-3 Breathing Rates 15C.0-1 Results Summary of Transient Events Unit 1 (Typical) 15C.0-2 Input Parameters and Initial Conditions for Transients Unit 1 15C.0-3 MCPR Fuel Cladding Integrity Safety Limit (All Fuel) Unit 1 15C.0-4 Unit 1 Minimum MCPR Requirement For Single Loop Operation & 2 Loop Operation 15C.0-5 Average Scram Insertion Times Unit 1 15C.1.1-1 Sequence of Events for Loss of Feedwater Heating Unit 1 15C.1.2-1 Sequence of Events for Feedwater Controller Failure, Maximum Demand Unit 1 (Typical) 15C.1.3-1 Sequence of Events for Pressure Regulator Failure - Open Unit 1 15C.2.2-1 Sequence of Events for Generator Load Rejection Without Bypass and Turbine Trip Without Bypass Unit 1 (Typical) 15C.3.3-1 Pump Seizure Accident from Two Loop Operation Sequence of Events Unit 1 15C.3.3-2 Pump Seizure Accident from Single Loop Operation Sequence of Events Unit 1 15C.4.2-1 Sequence of Events - RWE Drift in Power Range Unit 1 15C.4.5-1 Sequence of Events for Recirculation Flow Controller Failure Unit 1 15C.4.7-1 Unit 1 Sequence of Events for Misloaded Bundle Accident FSAR Rev. 71 Page 98 of 113
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TABLE OF CONTENTS Chapter 15 Tables 15C.4.9-1 Sequence of Events for Control Rod Drop Accident Unit 1 15C.4.9-2 Control Rod Drop Accident Unit 1 (Typical) 15D.0-1 Results Summary of Transient Events Unit 2 (Typical) 15D.0-2 Input Parameters and Initial Conditions for Transients Unit 2 15D.0-3 MCPR Fuel Cladding Integrity Safety Limit (All Fuel) Unit 2 15D.0-4 Unit 2 Minimum MCPR Requirement for Single Loop Operation & Minimum MCPR Requirement for 2 Loop Operation 15D.0-5 Average Scram Insertion Times Unit 2 15D.1.1-1 Sequence of Events for Loss of Feedwater Heating Unit 2 15D.1.2-1 Sequence of Events for Feedwater Controller Failure, Maximum Demand Unit 2 (Typical) 15D.1.3-1 Sequence of Events for Pressure Regulator Failure - Open Unit 2 15D.2.2-1 Sequence of Events for Generator Load Rejection Without Bypass and Turbine Trip Without Bypass Unit 2 (Typical) 15D.3.3-1 Pump Seizure Accident from Two Loop Operation Sequence of Events Unit 2 15D.3.3-2 Pump Seizure Accident from Single Loop Operation Sequence of Events Unit 2 15D.4.2-1 Sequence of Events - RWE Drift in Power Range Unit 2 15D.4.5-1 Sequence of Events for Recirculation Flow Controller Failure Unit 2 15D.4.7-1 Sequence of Events for Misloaded Bundle Accident Unit 2 15D.4.9-1 Sequence of Events for Control Rod Drop Accident Unit 2 15D.4.9-2 Control Rod Drop Accident Unit 2 (Typical) 15E.0-1 Results Summary of Transient Events Units 1 and 2 Non-Limiting Events (Values are for the Initial Cores Only) 15E.0-2 Input Parameters and Initial Conditions for Transients Units 1 and 2 Initial Cycles 15E.1.1-1 Operator Actions When Reactor Scram is Incurred 15E.1.4-1 Sequence of Events for Inadvertent Safety Relief Valve Opening 15E.1-4-2 Safety Relief Valve Opening Event Activity Above Suppression Pool (curies) 15E.1-4-3 Safety Relief Valve Opening Event Activity Released to the Environs (curies) 15E.1-4-4 Safety Relief Valve Opening Event Offsite Radiological Doses (rems) 15E.1.6-1 Sequence of Events for Inadvertent RHR Shutdown Cooling Operation 15E.2.2-1 Sequence of Events for Figure 15E2.2-1 Generator Load Rejection, Bypass On 15E.2.3-1 Sequence of Events for Turbine Trip With Bypass Operable Figure 15E.2.3-1 15E.2.4-1 Sequence of Events for MSIV Closure, Figure 15E.2.4-1 15E.2.5-1 Typical Rates of Decay for Condenser Vacuum 15E.2.5-2 Loss of Condenser Vacuum Sequence of Events for Figure 15E.2.5-1 15E.2.5-3 Trips Signals Associated With Loss of Condenser Vacuum 15E.2.6-1 Loss of Auxiliary Power Sequence of Events for Figure 15E.2.6-1 15E.2.6-2 Loss of All Grid Connections Sequence of Events for Figure 15E.2.6-2 15E.2.7-1 Loss of Feedwater Flow Sequence of Events for Figure 15E.2.7-1 15E.2.9-1 Sequence of Events for Failure of RHR Shutdown Cooling 15E.2.9-2 Input Parameters for Evaluation of Failure of RHR Shutdown Cooling 15E.3.1-1 Sequence of Events for Trip of One Recirculation Pump 15E.3.1-2 Sequence of Events for Trip of Two Recirculation Pumps 15E.4.4-1 Sequence of Events Abnormal Startup of Idle Recirculation Pump for Figure 15E.4.4-1 15E.5.1-1 Sequence of Events for Inadvertent Startup of HPCI FSAR Rev. 71 Page 99 of 113
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TABLE OF CONTENTS Chapter 15 Figures 15.4-1 Leakage Path for Control Rod Drop Accident 15.6-1 Leakage Path for Instrument Line Break 15.6-2 Steam Flow Schematic for Steam Break Outside Containment 15.6-3 Leakage Flow for LOCA 15.6-4 Leakage Path for Feedwater Line Break Outside Containment 15.7-1 Leakage Path for Refueling Accidents 15A.2-1 Possible Inconsistencies in the Selection of Nuclear Safety Operational Requirements 15A.2-2 Methods Used to Derive NSO Requirements System and Sub-System Level Qualitative FMEA and Design Basis Confirmation Audits and Tech. Specs.
15A.4-1 Format for Protection Sequence Diagrams 15A.4-2 Format for Safety System Auxiliary Diagrams 15A.4-3 Format for Commonality of Auxiliary Diagrams 15A.6-1 Safety System Auxiliaries 15A.6-2 Safety System Auxiliaries 15A.6-3 Safety Action Sequences for Planned Operations in State A 15A.6-4 Safety Action Sequences for Planned Operations in State B 15A.6-5 Safety Action Sequences for Planned Operations in State C 15A.6-6 Safety Action Sequences for Planned Operations in State D 15A.6-7 Protection Sequence for Manual or Inadvertent Scram 15A.6-8 Protection Sequence for Loss of Plant Instrument Air System 15A.6-9 Protection Sequence for Inadvertent Start-Up of HPCIs Pump 15A.6-10 Protection Sequences for Inadvertent Start-Up of Idle Recirculation Loop Pump 15A.6-11 Protection Sequence for Recirculation Loop Flow Control Failure - Maximum Demand 15A.6-12 Protection Sequence for Recirculation Loop Flow Control Failure - Decreasing 15A.6-13 Recirculation Loop Pump Trip - One or Both 15A.6-14a Protection Sequences for Isolation of All Main Steamlines 15A.6-14b Protection Sequences for Isolation of the One Main Steamline 15A.6-15 Protection Sequences for Inadvertent Opening of a Safety/Relief Valve 15A.6-16 Protection Sequence for Control Rod Withdrawal Error - Startup and Refueling Operation 15A.6-17 Protection Sequence for Control Rod Withdrawal Error - Power Operation 15A.6-18 Protection Sequences for RHRS - Loss of Shutdown Cooling Failure 15A.6-19 RHRS - Shutdown Cooling Failure - Increased Cooling 15A.6-20 Protection Sequences for Loss of Feedwater Flow 15A.6-21 Protection Sequence for Loss of a Feedwater Heater 15A.6-22 Protection Sequences for Feedwater Controller Failure - Maximum Demand 15A.6-23 Protection Sequences for Pressure Regulator Failure - Open 15A.6-24 Protection Sequence for Pressure Regulator Failure - Closed 15A.6-25 Protection Sequences for Main Turbine Trip with Bypass 15A.6-26 Protection Sequences for Loss of Main Condenser Vacuum 15A.6-27 Protection Sequences for Main Generator Trip with Bypass 15A.6-28 Protection Sequence for Loss of Normal AC Power - Aux Transformer Failure 15A.6-29 Protection Sequences for Loss of Normal AC Power - Grid Connection Loss FSAR Rev. 71 Page 100 of 113
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TABLE OF CONTENTS Chapter 15 Figures 15A.6-30 Protection Sequences Main Generator Trip - Without Bypass 15A.6-31 Protection Sequences Main Turbine Trip - With Bypass Failure 15A.6-32 Protection Sequence for Inadvertent Loading and Operations of Fuel Assembly in Improper Position 15A.6-38 Protection Sequences for Recirculation Loop Pump Seizure 15A.6-39 Protection Sequence for Recirculation Loop Pump Shaft Break 15A.6-40 Protection Sequences for Control Rod Drop Accident 15A.6-41 Protection Sequences for Fuel Handling Accident 15A.6-42 Protection Sequences for Loss-of-Coolant Piping Breaks in RCPB - Inside Containment 15A.6-43 Protection Sequences for Liquid, Steam, Large, Small Piping Breaks Outside Containment 15A.6-46 Protection Sequences for Gaseous Radwaste System Leak or Failure 15A.6-47 Protection Sequence for Off-Gas Treatment System Failure 15A.6-48 Protection Sequence for Liquid Radwaste System Leak or Failure 15A.6-49 Protection Sequence for Liquid Radwaste System Storage Tank Failure 15A.6-50 Protection Sequence for Spend Fuel Cask Drop 15A.6-51 Protection Sequence for Reactor Shutdown - From Anticipated Transient Without Scram 15A.6-52 Protection Sequences for Reactor Shutdown - From Outside Main Control Room 15A.6-53 Protection Sequence for Reactor Shutdown - Without Control Rods 15A.6-54-1 Commonality of Auxiliary Systems - DC Power Systems (125/250 Volts) 15A.6-54-2 Event Identification For Figure 15A.6-54, Page 1 of 2 15A.6-54-3 Event Identification For Figure 15A.6-54, Page 2 of 2 15A.6-55-1 Commonality of Auxiliary Systems - AC Power Systems (120/480/4160 Volts) 15A.6-55-2 Event Identification For Figure 15A.6-55, Page 1 of 2 15A.6-55-3 Event Identification For Figure 15A.6-55, Page 2 of 2 15A.6-56-1 Commonality of Auxiliary Systems - Equipment Area Coding System 15A.6-56-2 Event Identification For Figure 15A.6-56 15A.6-57-1 Commonality of Auxiliary Systems - Plant Service Water System 15A.6-57-2 Event Identification For Figure 15A.6-57 15A.6-58 Commonality of Auxiliary Systems - RHR Service Water System 15A.6-59-1 Commonality of Auxiliary Systems - Suppression Pool Storage 15A.6-59-2 Event Identification For Figure 15A.6-59 15C.1.2-1-1 Susquehanna Feedwater Controller Failure, Maximum Demand, with High Water Level Trip Unit 1 (Typical) 15C.1.2-1-2 Susquehanna Feedwater Controller Failure, Maximum Demand, with High Water Level Trip Unit 1 (Typical) 15C.1.2-1-3 Susquehanna Feedwater Controller Failure, Maximum Demand, with High Water Level Trip Unit 1 (Typical) 15C.1.2-1-4 Susquehanna Feedwater Controller Failure, Maximum Demand, with High Water Level Trip Unit 1 (Typical) 15C.1.3-1 Pressure Regulator Failed Open - Typical of Unit 1 15C.2.2-1-1 Susquehanna Generator Load Reject Without Bypass and Turbine Trip Without Bypass Unit 1 (Typical)
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TABLE OF CONTENTS Chapter 15 Figures 15C.2.2-1-2 Susquehanna Generator Load Reject Without Bypass and Turbine Trip Without Bypass Unit 1 (Typical) 15C.2.2-1-3 Susquehanna Generator Load Reject Without Bypass and Turbine Trip Without Bypass Unit 1 (Typical) 15C.2.2-1-4 Susquehanna Generator Load Reject Without Bypass and Turbine Trip Without Bypass Unit 1 (Typical) 15C.3.3-5 Pump Seizure Accident Two Loop Operation Typical of Unit 1 15C.3.3-6 Pump Seizure Accident Single Loop Operation Typical of Unit 1 15D.1.2-1-1 Susquehanna Feedwater Controller Failure, Maximum Demand, With High Water Level Trip Unit 2 (Typical) 15D.1.2-1-2 Susquehanna Feedwater Controller Failure, Maximum Demand, With High Water Level Trip Unit 2 (Typical) 15D.1.2-1-4 Susquehanna Feedwater Controller Failure, Maximum Demand, With High Water Level Trip Unit 2 (Typical) 15D.1.2-1-5 Susquehanna Feedwater Controller Failure, Maximum Demand, With High Water Level Trip Unit 2 (Typical) 15D.1.3-1 Pressure Regulator Failed Open - Typical of Unit 2 15D.2.2-1-1 Susquehanna Generator Load Reject Without Bypass and Turbine Trip Without Bypass Unit 2 (Typical) 15D.2.2-1-2 Susquehanna Generator Load Reject Without Bypass and Turbine Trip Without Bypass Unit 2 (Typical) 15D.2.2-1-4 Susquehanna Generator Load Reject Without Bypass and Turbine Trip Without Bypass Unit 2 (Typical) 15D.2.2-1-5 Susquehanna Generator Load Reject Without Bypass and Turbine Trip Without Bypass Unit 2 (Typical) 15D.3.3-5 Pump Seizure Accident Two Loop Operation Typical of Unit 2 15D.3.3-6 Pump Seizure Accident Single Loop Operation Typical of Unit 2 15E.0-1 Typical Power/Flow Map 15E.0-2 Scram Position and Reactivity Characteristics 15E.2.2-1 Susquehanna Generator Load Rejection, With Bypass On 15E.2.3-1 Turbine Trip, Trip Scram, Bypass and RPT On 15E.2.4-1 Three-Second Closure of All MSIVs With Position Switch Scram Trip 15E.2.5-1 Loss of Condenser Vacuum at 2 Inches Per Second 15E.2.6-1 Loss of Auxiliary Power Transformer 15E.2.6-2 Loss of All Grid Connections 15E.2.7-1 Loss of All Feedwater Flow 15E.2.7-2 Loss of Feedwater Core Power, Heat Flux and Core Flow 15E.2.7-3 Loss of Feedwater, Feedwater Flow Steam Flow and RCIC Flow 15E.2.9-1-1 ADS/RHR Cooling Loops 15E.2.9-1-2 Notes for Figure 15E.2.9-1-1 15E.2.9-1-3 Notes for Figure 15E.2.9-1-1 15E.2.9-2 Summary of Paths Available to Achieve Cold Shutdown 15E.2.9-3 Vessel Temperature and Pressure Versus Time (Activity C1 or C2) 15E.2.9-4 Suppression Pool Temperature Versus Time (90 Service Water Temperature)
Capacity C1 or C2 15E.2.9-5 Activity C1 Alternate Shutdown Cooling Path Utilizing RHR Loop B FSAR Rev. 71 Page 102 of 113
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TABLE OF CONTENTS Chapter 15 Figures 15E.2.9-6 Activity C2 Alternate Shutdown Cooling Path Utilizing RHR Loop A 15E.3.1-1 Trip of One Recirculation Pump Motor 15E.3.1-2 Trip of Both Recirculation Pump Motors 15E.4.4-1 Startup of Idle Recirculation Loop Pump 15E.5.1-1 Inadvertent Startup of HPCI FSAR Rev. 71 Page 103 of 113
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TABLE OF CONTENTS Chapter 16 16.0 TECHNICAL SPECIFICATIONS 16.1 Preliminary Technical Specifications 16.2 Proposed Final Technical Specifications 16.3 Technical Requirements Manuals FSAR Rev. 71 Page 104 of 113
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TABLE OF CONTENTS Chapter 17 17.0 QUALITY ASSURANCE 17.1 Quality Assurance During Design and Construction 17.2 Quality Assurance During the Operations Phase 17.2.0 Introduction 17.2.1 Organization 17.2.2 Quality Assurance Program 17.2.3 Design Control 17.2.4 Procurement Document Control 17.2.5 Instructions, Procedures, and Drawings 17.2.6 Document Control 17.2.7 Control of Purchased Material, Equipment, and Services 17.2.8 Identification and Control of Materials, Parts, and Components 17.2.9 Control of Special Processes 17.2.10 Inspection 17.2.11 Test Control 17.2.12 Control of Measuring and Test Equipment 17.2.13 Handling, Storage, and Shipping 17.2.14 Inspection, Test, and Operating Status 17.2.15 Nonconforming Materials, Parts, or Components 17.2.16 Corrective Action 17.2.17 Quality Assurance Records 17.2.18 Audits FSAR Rev. 71 Page 105 of 113
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TABLE OF CONTENTS Chapter 17 Tables 17.2-1 Quality Assurance Program Description Compliance Matrix 17.2-2 Operational Policy Statement Cross Reference Matrix with 10CFR50 Appendix B Criteria FSAR Rev. 71 Page 106 of 113
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TABLE OF CONTENTS Chapter 17 Figures 17.2-1 Hierarchy of Operational Quality Assurance Documents 17.2-2 Talen Energy Corporation Management Organization Applicable to Susquehanna SES 17.2-3 Susquehanna Nuclear, LLC Management Organization 17.2-4 Nuclear Oversight Organization FSAR Rev. 71 Page 107 of 113
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TABLE OF CONTENTS Chapter 18 18.0 RESPONSES TO TMI RELATED REQUIREMENTS 18.0 Organization 18.1 Response to Requirements in NUREG 0737 18.1.1 Shift Technical Advisor (I.A.1.1) 18.1.2 Shift Supervisor Responsibilities (I.A.1.2) 18.1.3 Shift Manning (I.A.1.3) 18.1.4 Immediate Upgrading Of Reactor Operator and Senior Reactor Operator Training and Qualifications (I.A.2.1) 18.1.5 Administration of Training Programs (I.A.2.3) 18.1-6 Revise Scope And Criteria for Licensing Examinations (I.A.3.1) 18.1.7 Evaluation Of Organization and Management (I.B.1.2) 18.1.8 Short-Term Accident and Procedure Review (I.C.1) 18.1-9 Shift Relief and Turnover Procedures (I.C.2) 18.1.10 Shift Supervisor Responsibility (I.C.3) 18.1.11 Control Room Access (I.C.4) 18.1.12 Feedback Of Operating Experience (I.C.5) 18.1.13 Verify Correct Performance of Operating Activities (I.C.6) 18.1.14 NSSS Vendor Review of Procedures (I.C.7) 18.1.15 Pilot Monitoring of Selected Emergency Procedures for Near Term Operating Licenses (I.C.8) 18.1.16 Control Room Design Review (I.D.1) 18.1.17 Plant Safety Parameter Display System (I.D.2) 18.1.18 Training During Low-Power Testing (I.G.1) 18.1.19 Reactor Coolant System Vents (II.B.1) 18.1.20 Plant Shielding (II.B.2) 18.1.21 Post-Accident Sampling (II.B.3) 18.1.22 Training For Mitigating Core Damage (II.B.4) 18.1.23 Relief and Safety Valve Test Requirements (II.D.1) 18.1.24 Safety/Relief Valve Position Indication (II.D.3) 18.1.25 Auxiliary Feedwater System Evaluation (II.E.1.1) 18.1.26 Auxiliary Feedwater System Initiation And Flow (II.E.1.2) 18.1.27 Emergency Power for Pressurizer Heaters (II.E.3.1) 18.1.28 Dedicated Hydrogen Penetrations (II.E.4.1) 18.1.29 Containment Isolation Dependability (II.E.4.2) 18.1.30 Accident-Monitoring Instrumentation (II.F.1) 18.1.31 Instrument for Detection of Inadequate Core Cooling (II.F.2) 18.1.32 Emergency Power for Pressurizer Equipment (II.G.1) 18.1.33 Review ESF Valves (II.K.1.5) 18.1.34 Operability Status (II.K.1.10) 18.1.35 Trip Pressurizer Low-Level Coincident Signal Bistables (II.K.1.17) 18.1.36 Operator Training for Prompt Manual Reactor Trip (II.K.1.20) 18.1.37 Automatic Safety Grade Anticipatory Reactor Trip (II.K.1.21) 18.1.38 Auxiliary Heat Removal System Procedures (II.K.1.22) 18.1.39 Reactor Vessel Level Procedures (II.K.1.23) 18.1.40 Commission Orders On Babcock and Wilcox Plants (II.K.2) 18.1.41 Automatic Power-Operated Relief Valve Isolation System (II.K.3.1)
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TABLE OF CONTENTS Chapter 18 18.1.42 Report On Power-Operated Relief Valve Failures (II.K.3.2) 18.1.43 Reporting Safety/Relief Valve Failures and Challenges (II.K.3.3) 18.1.44 Automatic Trip of Reactor Coolant Pumps During A LOCA (II.K.3.5) 18.1.45 Evaluation of Power-Operated Relief Valve Opening Probability (II.K.3.7) 18.1.46 Proportional Integral Derivative Controller Modification (II.K.3.9) 18.1.47 Proposed Anticipatory Trip Modification (II.K.3.10) 18.1.48 Power-Operated Relief Valve Failure Rate (II.K.3.11) 18.1.49 Anticipatory Reactor Trip on Turbine Trip (II.K.3.12) 18.1.50 Separation Of High Pressure Coolant Injection and Reactor Core Isolation Cooling System Initiation Levels (II.K.3.13) 18.1.51 Modify Break-Detection Logic to Prevent Spurious Isolation of High Pressure Coolant Injection and Reactor Core Isolation Cooling (II.K.3.15) 18.1.52 Reduction of Challenges and Failures of Relief Valves (II.K.3.16) 18.1.53 Report On Outages Of Emergency Core Cooling Systems (II.K.3.17) 18.1.54 Modification of Automatic Depressurization System Logic (II.K.3.18) 18.1.55 Restart of Core Spray And Low Pressure Coolant Injection Systems (II.K.3.21) 18.1.56 Automatic Switchover of Reactor Core Isolation Cooling System Suction (II.K.3.22) 18.1.57 Confirm Adequacy of Space Cooling For High Pressure Coolant Injection and Reactor Core Isolation Cooling Systems (II.K.3.24) 18.1.58 Effect of Loss of Alternating-Current Power on Recirculation Pump Seals (II.K.3.25) 18.1.59 Provide A Common Reference Level for Vessel Level Instrumentation (II.K.3.27) 18.1.60 Verify Qualification of Accumulators on Automatic Depressurization System Valves (II.K.3.28) 18.1.61 Revised Small-Break Loss of Coolant Accident Methods (II.K.3.30) 18.1.62 Plant-Specific Calculations To Show Compliance with 10CFR Part 50.46 (II.K.3.31) 18.1.63 Evaluation of Anticipated Transients with Single Failure To Verify No Fuel Cladding Failure (II.K.3.44) 18.1.64 Evaluation of Depressurization With Other Than The Automatic Depressurization System (II.K.3.45) 18.1.65 Michelsen Concerns (II.K.3.46) 18.1.66 Emergency Preparedness - Short Term (III.A.1.1) 18.1.67 Upgrade Emergency Support Facilities (III.A.1.2) 18.1.68 Emergency Preparedness - Long Term (III.A.2) 18.1.69 Integrity Of Systems Outside Containment Likely To Contain Radioactive Material (III.D.1.1) 18.1.70 Inplant Iodine Radiation Monitoring (III.D.3.3) 18.1.71 Control Room Habitability Requirements (III.D.3.4) 18.1.72 References 18.2 Response to Requirements in NUREG 0694 18.2.1 Shift Technical Advisor (I.A.1.1) 18.2.2 Shift Supervisor Administrative Duties (I.A.1.2) 18.2.3 Shift Manning (I.A.1.3)
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TABLE OF CONTENTS Chapter 18 18.2.4 Immediate Upgrading Of Operator And Senior Operator Training And Qualification (I.A.2.1) 18.2.5 Revise Scope And Criteria For Licensing Examinations (I.A.3.1) 18.2.6 Evaluation Of Organization And Management Improvements Of Near-Term Operating License Applicants (I.B.1.2) 18.2.7 Short-Term Accident Analysis And Procedure Revision (I.C.1) 18.2.8 Shift Relief And Turnover Procedures (I.C.2) 18.2.9 Shift Supervisor Responsibilities (I.C.3) 18.2.10 Control Room Access (I.C.4) 18.2.11 Procedures For Feedback Of Operating Experience To Plant Staff (I.C.5) 18.2.12 NSSS Vendor Review Of Procedures (I.C.7) 18.2.13 Pilot Monitoring Of Selected Emergency Procedures Near-Term Operating License Applicants (I.C.8) 18.2.14 Control Room Design (I.D.1) 18.2.15 Training During Low Power Testing (I.G.1) 18.2.16 Reactor Coolant System Vents (II.B.1) 18.2.17 Plant Shielding (II.B.2) 18.2.18 Post-Accident Sampling (II.B.3) 18.2.19 Training For Mitigating Core Damage (II.B.4) 18.2.20 Relief And Safety Valve Test Requirements (II.D.1) 18.2.21 Relief And Safety Valve Position Indication (II.D.3) 18.2.22 Containment Isolation Dependability (II.E.4.2) 18.2.23 Additional Accident Monitoring Instrumentation (II.F.1) 18.2.24 Inadequate Core Cooling Instruments (II.F.2) 18.2.25 Assurance Of Proper ESF Functioning (II.K.1.5) 18.2-26 Safety Related System Operability Status (II.K.1.10) 18.2.27 Trip Pressurizer Low-Level Coincident Signal Bistables (II.K.1.17) 18.2.28 Operator Training For Prompt Manual Reactor Trip (II.K.1.20) 18.2.29 Automatic Safety Grade Anticipatory Trip (II.K.1.21) 18.2.30 Auxiliary Heat Removal Systems Operating Procedures (II.K.1.22) 18.2.31 Reactor Level Instrumentation (II.K.1.23) 18.2.32 Commission Orders On Babcock And Wilcox Plants (II.K.2) 18.2.33 Reporting Requirements For Safety/Relief Valve Failures Or Challenges (II.K.3.3) 18.2.34 Proportional Integral Derivative Controller (II.K.3.9) 18.2.35 Anticipatory Reactor Trip Modification (II.K.3.10) 18.2.36 Power Operated Relief Valve Failure Rate (II.K.3.11) 18.2.37 Anticipatory Reactor Trip on Turbine Trip (II.K.3.12) 18.2.38 Emergency Preparedness-Short Term (II.A.1.1) 18.2.39 Upgrade Emergency Support Facilities (III.A.1.2) 18.2.40 Primary Coolant Sources Outside Containment (III.D.1.1) 18.2.41 Inplant Radiation Monitoring (III.D.3.3) 18.2.42 Control Room Habitability (III.D.3.4)
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TABLE OF CONTENTS Chapter 18 Tables 18.1-1 Interim Required Shift Staffing 18.1-2 Initial Core Isotopic Inventory 18.1-3 Post Accident Radiation Zone Classification 18.1-4 Vital Areas 18.1-5 Principal Dose Rate Contributors in Plant Area 18.1-8 Training Criteria for Mitigating Core Damage 18.1-9 Mitigating Core Damage Course Outline 18.1-10 Containment Isolation Actuation Provision 18.1-11 Essential/Non-Essential Penetration Classification Basis 18.1-12 Actuation/Isolation Signal Codes and Corresponding Actuating Switches 18.1-13 Meteorological Information 18.1-17 Information Required for Control Room Habitability Evaluation 18.1-18 Possible ICC Detection Devices 18.2-1 Testing Program Outline FSAR Rev. 71 Page 111 of 113
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TABLE OF CONTENTS Chapter 18 Figures 18.1-1 Radiation Levels for the Site Plan 18.1-2 Radiation Levels for the Site Plan Elevations 646'-0," 645'0," and 656'-0" 18.1-3 Radiation Levels for Elevations 670'-0" and 676'-0" 18.1-4 Radiation Levels for Elevations 683'-0," 699'-0," 714'-0," and 716'-3" 18.1-5 Radiation Levels for Elevations 719'-1," 729'-0," and 741-1 18.1-6 Radiation Levels for Elevations 749'-1," 754'-0," 762'-0," 771'-0," and 783'-0" 18.1-7 Radiation Levels for Elevations 779'-1," 799'-1," and 806'-0" 18.1-8 Radiation Levels for Elevations 818'-1" and 872'-4 1/2" 18.1-12 Typical HPCI RCIC Steamline Break Detection Logic 18.1-13 Typical Reactor Water Level Display 18.1-14 Downcomer Water Level History 18.1-15 Water Level as an Indicator of Core Overheating 18.1-16 Cladding Temperature Sensitivity to Core Recovery Time FSAR Rev. 71 Page 112 of 113
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TABLE OF CONTENTS Chapter - Responses to NRC Questions NOTE 1: 040, 281, and 441 questions concerning fire protection may be found in the FPRR NOTE 2: Any 040 questions which contain "X10" in the question numbers were initiated by the Oak Ridge National Laboratories Branch No. Branch Title 005 Auxiliary System 010 Auxiliary Systems 021 Containment Systems 032 Instrumentation and Control Systems 040 Power Systems 110 Mechanical Engineering 112 Mechanical Engineering 121 Materials Engineering Branch-Materials Integrity Section 123 Structural and Geosciences Branch 130 Structural Engineering 211 Reactor Systems 221 Analysis Branch-Reactor Analysis Section 222 Analysis Branch-System Analysis Section 230 Core Performance Branch 231 Core Performance Branch-Reactor Fuels Section 232 Core Performance Branch-Reactor Physics Section 260 Quality Assurance Branch 281 Chemical Engineering Branch 312 Accident Analysis 313 Accident Analysis Branch-Emergency Planning 321 Effluent Treatment Systems 331 Radiological Assessment 361 Geosciences Branch-Seismology Geology Section 362 Geosciences Branch-Foundation Engineering Section 371 Hydrology-Meteorology Branch-Hydrology Section 372 Hydrology-Meteorology Branch-Meteorology Section 400 Project Management 410 Licensee Qualification Branch 421 Quality Assurance-Operations 422 Licensee Qualification Branch 423 Quality Assurance Branch-Initial Test Program 440 Operator Licensing 441 Operator Licensing Branch-Training 442 Operator Licensing Branch-Procedures 500 Security FSAR Rev. 71 Page 113 of 113