ML21008A408

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Byron/Braidwood Stations - Revision 18 to Updated Final Safety Analysis Report, Chapter 11, Radioactive Waste Management
ML21008A408
Person / Time
Site: Byron, Braidwood  Constellation icon.png
Issue date: 12/17/2020
From:
Exelon Generation Co
To:
Office of Nuclear Reactor Regulation, Office of Nuclear Material Safety and Safeguards
Shared Package
ML21008A383 List:
References
RS-20-153
Download: ML21008A408 (214)
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Text

B/B-UFSAR CHAPTER 11.0 - RADIOACTIVE WASTE MANAGEMENT TABLE OF CONTENTS PAGE 11.0 RADIOACTIVE WASTE MANAGEMENT 11.1-1 11.1 SOURCE TERMS 11.1-1 11.1.1 Definition of Radioactive Source Terms 11.1-1 11.1.1.1 Design-Basis Shielding Source Terms 11.1-1 11.1.1.2 Realistic Source Terms 11.1-1 11.1.1.3 Accident Sources 11.1-1 11.1.2 Basis for Radioactive Source Terms 11.1-2 11.1.2.1 Conservative Model for Reactor Coolant Activity 11.1-2 11.1.2.2 Realistic Model for Reactor Coolant Activity 11.1-3 11.1.3 Source Terms for Shielding Design Basis 11.1-4 11.1.4 Source Terms for Component Failure 11.1-5 11.1.5 Source Terms for Radwaste System Components 11.1-5 11.1.6 Sources of In-Plant Airborne Radioactivity 11.1-5 11.1.7 Sources of Radioactive Releases to the Environment 11.1-6 11.1.7.1 Gaseous Releases 11.1-6 11.1.7.2 Liquid Releases 11.1-6 11.1.8 Impact of Uprate on Normal Operation Radiation Source Terms 11.1.9 References 11.1-6 11.2 LIQUID WASTE MANAGEMENT SYSTEMS 11.2-1 11.2.1 Design Bases 11.2-1 11.2.1.1 Safety Design Basis 11.2-1 11.2.1.2 Power Generation Design Basis 11.2-1 11.2.1.3 Expected Radioactive Releases 11.2-2 11.2.1.4 10 CFR 50 Comparison 11.2-2 11.2.1.5 10 CFR 20 Comparison 11.2-2a 11.2.1.6 Component Specifications 11.2-2a 11.2.1.7 Seismic Design and Quality Group 11.2-3 11.2.1.8 Facility and Equipment Design 11.2-3 11.2.1.8.1 Maintenance Operations 11.2-3 11.2.1.8.2 Floor, Wall, and Ceiling Coatings 11.2-3 11.2.1.9 Tank Level Control 11.2-3 11.2.1.10 Prevention of Uncontrolled Releases 11.2-4 11.2.1.11 ETSB-BTP 11-1 Comparison 11.1-5 11.2.2 System Description 11.2-5 11.2.2.1 Steam Generator Blowdown Subsystem 11.2-6 11.2.2.1.1 Normal Operation 11.2-7 11.2.2.1.2 Circulating Water to Secondary System Leakage 11.2-8 11.2.2.1.3 Primary-to-Secondary Leakage Concurrent with Failed Fuel 11.2-8 11.0-i REVISION 9 - DECEMBER 2002

B/B-UFSAR TABLE OF CONTENTS (Cont'd)

PAGE 11.2.2.1.4 Primary-to-Secondary Leakage Not Concurrent with Failed Fuel 11.2-8 11.2.2.1.5 Transient Operating Conditions 11.2-9 11.2.2.2 Nonblowdown Liquid Radwaste Subsystem 11.2-9 11.2.2.2.1 Auxiliary Building Equipment Drain 11.2-10 11.2.2.2.2 Auxiliary Building Floor Drain 11.2-11 11.2.2.2.3 Chemical Waste Drain 11.2-11 11.2.2.2.4 Regeneration Waste Drain 11.2-12 11.2.2.2.5 Laundry Drain 11.2-12 11.2.2.2.6 Turbine Building Equipment Drain 11.2-12 11.2.2.2.7 Turbine Building Floor Drain 11.2-13 11.2.2.2.8 Turbine Building Fire and Oil Sump 11.2-13 11.2.2.2.9 Condensate Polisher Sump 11.2-13 11.2.2.2.10 Waste Treatment System 11.2-13 11.2.2.3 Operating Procedures 11.2-14 11.2.2.4 Performance Tests 11.2-14 11.2.2.5 Control and Instrumentation 11.2-14 11.2.3 Radioactive Releases (Byron) 11.2-15 11.2.3.1 Release Points (Byron) 11.2-15 11.2.3.2 Dilution Factors (Byron) 11.2-15 11.2.3.3 Estimated Annual Average Doses (Byron) 11.2-15 11.2.3 Radioactive Releases (Braidwood) 11.2-16 11.2.3.1 Release Points (Braidwood) 11.2-16 11.2.3.2 Dilution Factors (Braidwood) 11.2-16 11.2.3.3 Estimated Annual Average Doses (Braidwood) 11.2-16 11.2.4 References 11.2-17 11.3 GASEOUS WASTE MANAGEMENT SYSTEMS 11.3-1 11.3.1 Design Bases 11.3-1 11.3.2 System Description 11.3-2 11.3.2.1 System Design 11.3-2 11.3.2.2 Component Design 11.3-4 11.3.2.3 Instrumentation Design 11.3-4 11.3.2.4 Operating Procedure 11.3-5 11.3.2.5 Operations 11.3-5 11.3.2.6 Refueling 11.3-7 11.3.2.7 Auxiliary Services 11.3-7 11.3.2.8 Performance Tests 11.3-7 11.3.3 Radioactive Releases 11.3-8 11.3.3.1 NRC Requirements 11.3-8 11.3.3.2 Westinghouse PWR Experience Releases 11.3-8 11.3.3.3 Expected Gaseous Waste Processing System Releases 11.3-8 11.0-ii REVISION 7 - DECEMBER 1998

B/B-UFSAR TABLE OF CONTENTS (Cont'd)

PAGE 11.3.3.4 Estimated Total Releases 11.3-9 11.3.3.5 Effluent Concentrations and Dilution Factors 11.3-9 11.3.3.6 Release Points of Dilution Factors 11.3-9 11.3.3.7 Estimated Doses from Gaseous Releases 11.3-10 11.3.4 References 11.3-10 11.0-ii (Cont'd) REVISION 2 - DECEMBER 1990

B/B-UFSAR TABLE OF CONTENTS (Cont'd)

PAGE 11.4 SOLID WASTE MANAGEMENT SYSTEM 11.4-1 11.4.1 Design Bases 11.4-1 11.4.1.1 Power Generation Design Bases 11.4-1 11.4.1.2 Safety Design Bases 11.4-1 11.4.1.3 Type of Waste 11.4-2 11.4.1.4 Expected Volumes and Isotopic Compositions 11.4-3 11.4.1.5 ETSB-BTP 11-3 Comparison 11.4-3 11.4.1.6 Comparison of Processing Capacity and Design Basis Waste Volumes (Byron) 11.4-4 11.4.1.6 Comparison of Processing Capacity and Design Basis Waste Volumes (Braidwood) 11.4-5 11.4.1.7 Solid Radwaste System Monitoring 11.4-7 11.4.2 System Description 11.4-7 11.4.2.1 Deleted 11.4-7 11.4.2.2 Deleted 11.4-7 11.4.2.3 Deleted 11.4-7 11.4.2.4 Drum Handling Equipment 11.4-11 11.4.2.5 Smear Test and Label Station 11.4-12 11.4.2.6 Dry Waste Compactor (Byron) 11.4-12 11.4.2.7 Storage Areas 11.4-12 11.4.2.8 Control Room 11.4-13 11.4.2.9 Deleted 11.4-13 11.4.2.10 Deleted 11.4-13 11.4.2.11 Deleted 11.4-13 11.4.2.12 System Interfaces 11.4-13 11.4.2.13 Deleted 11.4-13 11.4.3 Volume Reduction System Description 11.4-14 11.4.4 Polymer/VR Product Drumming Station 11.4-14 11.0-iii REVISION 12 - DECEMBER 2008

B/B-UFSAR TABLE OF CONTENTS (Cont'd)

PAGE 11.5 PROCESS AND EFFLUENT RADIOLOGICAL MONITORING AND SAMPLING SYSTEMS 11.5-1 11.5.1 Design Bases 11.5-1 11.5.1.1 Design Objectives 11.5-1 11.5.1.2 Design Criteria 11.5-3 11.5.2 System Description 11.5-5 11.5.2.1 Instrumentation 11.5-5 11.5.2.2 Airborne Process and Effluent Monitors 11.5-7 11.5.2.2.1 Auxiliary Building Vent Stack Effluent 11.5-7 11.5.2.2.2 Auxiliary Building Plant Areas (for Auxiliary Building Vent Exhausts) 11.5-7 11.5.2.2.3 Pipe Tunnel (for Auxiliary Building Vent Exhausts) 11.5-7 11.5.2.2.4 Fuel-Handling Building Exhaust 11.5-7 11.5.2.2.5 Containment Purge Effluent 11.5-8 11.5.2.2.6 Fuel-Handling Incident in the Fuel Handling Building 11.5-8 11.5.2.2.7 Fuel-Handling Accident in the Containment Building 11.5-8 11.5.2.2.8 Main Control Room Outside Air Intakes A and B 11.5-8 11.5.2.2.9 Main Control Room Turbine Building Air Intakes A and B 11.5-9 11.5.2.2.10 Containment Atmosphere Monitoring 11.5-9 11.5.2.2.11 Miscellaneous Tank Vent Exhaust 11.5-10 11.5.2.2.12 Radwaste Area Vent Exhaust 11.5-10 11.5.2.2.13 SJAE/Gland Steam Exhaust 11.5-10 11.5.2.2.14 Gas Decay Tank Effluent 11.5-10 11.0-iv REVISION 4 - DECEMBER 1992

B/B-UFSAR TABLE OF CONTENTS (Cont'd)

PAGE 11.5.2.2.15 VR Systems Areas and Cubicles Ventilation Exhaust 11.5-11 11.5.2.2.16 TSC Ventilation System 11.5-11 11.5.2.2.17 Miscellaneous Process Monitors 11.5-11 11.5.2.2.18 Auxiliary Building Vent Stack Wide Range Gas Monitor 11.5-11 11.5.2.3 Liquid Effluent Monitors 11.5-11 11.5.2.3.1 Liquid Radwaste Effluent Monitor 11.5-12 11.5.2.3.2 Component Cooling Water Monitors 11.5-12 11.5.2.3.3 Steam Generator Blowdown 11.5-12 11.5.2.3.4 Blowdown Filters 11.5-12 11.5.2.3.5 Gross Failed Fuel Monitor 11.5-12 11.5.2.3.6 Miscellaneous Process Liquid Monitors 11.5-13 11.5.2.3.7 Turbine Building Fire and Oil Sump 11.5-13 11.5.2.3.8 Condensate Cleanup Area Sumps Discharge 11.5-13 11.5.2.4 Sampling 11.5-13 11.5.2.4.1 Process Sampling 11.5-14 11.5.2.4.2 Effluent Sampling 11.5-14 11.5.2.4.3 Representative Sampling 11.5-14 11.5.2.4.4 Analytical Procedures 11.5-14 11.5.2.5 Instrument Inspection, Calibration, and Maintenance 11.5-15 11.5.2.5.1 Calibration 11.5-16 11.5.3 Effluent Monitoring and Sampling 11.5-16 11.5.4 Process Monitoring and Sampling 11.5-16 11.0-v

B/B-UFSAR CHAPTER 11.0 - RADIOACTIVE WASTE MANAGEMENT LIST OF TABLES NUMBER TITLE PAGE 11.1-1 Parameters Used in the Calculation of Design Basis Primary Coolant Activities

- Original and Uprated (***) 11.1-7 11.1-2 Design-Basis Reactor Coolant Fission and Corrosion Product Activity (Original Design) 11.1-10 11.1-3 Parameters Used in the Calculation of Realistic, Operational Basis Primary Coolant Activities 11.1-11 11.1-4 Realistic, Operational Basis Reactor Coolant Fission and Corrosion Product Activities 11.1-13 11.1-5 Maximum Realistic, Operational Basis Waste Gas Decay Tank Activity for Gas Decay Tank Rupture 11.1-15 11.1-6 Realistic Source Terms for Steam Generator Blowdown and Radioactive Drain Streams 11.1-16 11.1-7 Realistic Source Terms for Balance of Plant 11.1-20 11.1-8 Realistic Source Terms for Radwaste System Filters and Demineralizers 11.1-24 11.1-9 Realistic Source Terms for NSSS Filters 11.1-28 11.1-10 Realistic Source Terms for NSSS Demineralizers 11.1-31 11.1-11 Realistic Source Terms for Concentrates and Spent Resin Tanks (Byron) 11.1-33 11.1-11 Realistic Source Terms for High and Low Activity Spent Resin Tanks (Braidwood) 11.1-35 11.1-12 Deleted 11.1-13 Uprated Design-Basis Reactor Coolant Fission And Corrosion Product Activity 11.2-1 Expected Annual Average Releases of Radionuclides in Liquid Effluents 11.2-18 11.2-2 Parameters Used in the GALE-PWR Computer Program (Original & Uprated) - Note 1 11.2-19 11.2-3 Pathways Doses from Liquid Effluents (Byron) 11.2-22 11.2-3 Pathways Doses from Liquid Effluents (Braidwood) 11.2-23 11.2-4 Comparison of Expected Liquid Effluent Concentrations to 10 CFR 20 Limits (Byron) 11.2-24 11.2-4 Comparison of Expected Liquid Effluent Concentrations to 10 CFR 20 Limits (Braidwood) 11.2-25 11.2-5 Liquid Radwaste System Components and Design Parameters Per Station 11.2-26 11.2-6 Design-Basis Annual Average and Maximum Waste Stream Flows (Two Units) 11.2-32 11.0-vi REVISION 9 - DECEMBER 2002

B/B-UFSAR LIST OF TABLES (Cont'd)

NUMBER TITLE PAGE 11.2-7 Design-Basis Process Decontamination Factors 11.2-33 11.2-8 Consumption Factors for the Maximum Exposed Individual 11.2-35 11.2-9 Summary of Tank Level Indication, Annunciators, and Overflows for Tanks Outside of Containment Potentially Containing Radioactive Liquids 11.2-36 11.3-1 Gaseous Waste Processing System Component Data 11.3-11 11.3-2 Gaseous Waste Processing System Instrumentation Design Parameters 11.3-12 11.3-3 Process Parameters and Realistic, Operation Basis Activities in Gaseous Waste System 11.3-15 11.3-4 Assumptions Used in Calculating Expected System Activities 11.3-23 11.3-5 Typical Gaseous Releases From Operating Reactors 11.3-25 11.3-6 Expected Annual Average Release of Airborne Radionuclides 11.3-26 11.3-7 Comparison of Maximum Offsite Airborne Concentrations with 10 CFR 20 Limits (Byron) 11.3-30 11.3-8 Atmospheric Dilution Factors Used in Determining Offsite Doses (Byron) 11.3-31 11.3-9 Byron - Expected Individual Doses from Gaseous Effluents 11.3-32 11.3-7 Comparison of Maximum Offsite Airborne Concentrations with 10 CFR 20 Limits (Braidwood) 11.3-33 11.3-8 Atmospheric Dilution Factors Used in Determining Offsite Doses (Braidwood) 11.3-34 11.3-9 Braidwood - Expected Individual Doses from Gaseous Effluents 11.3-35 11.3-10 Exhaust Stack Airflow Tabulation 11.3-38 11.4-1 Solid Waste Management System Equipment and Storage Design Capacities (Byron) 11.4-52 11.4-2 Expected and Design Basis Annual Volumes of (Units 1 and 2) Solid Waste Management System Output (Byron) 11.4-56 11.4-3 Plant Interfaces with Solid Radwaste System (Byron) 11.4-57 11.4-1 Solid Waste Management System Equipment and Storage Design Capacities (Braidwood) 11.4-64 11.0-vii REVISION 6 - DECEMBER 1996

B/B-UFSAR LIST OF TABLES (Cont'd)

NUMBER TITLE PAGE 11.4-2 Expected and Design Basis Annual Volumes of (Units 1 and 2) Solid Waste Management System Output (Braidwood) 11.4-68 11.4-3 Plant Interface with Solid Radwaste System (Braidwood) 11.4-69 11.5-1 Airborne Process and Effluent Monitors 11.5-17 11.5-2 Process Liquid Monitors 11.5-26 11.5-3 Radiological Analysis Summary of Liquid Process Samples 11.5-30 11.5-4 Radiological Analysis Summary of Gaseous Process Samples 11.5-31 11.5-5 Radiological Analysis Summary of Liquid Effluent Samples 11.5-32 11.5-6 Radiological Analysis Summary of Gaseous Effluent Samples 11.5-33 11.0-viii REVISION 6 - DECEMBER 1996

B/B-UFSAR CHAPTER 11.0 - RADIOACTIVE WASTE MANAGEMENT LIST OF FIGURES NUMBER TITLE 11.2-1 through 11.2-41 Deleted 11.3-1 Deleted 11.3-2 Gaseous Waste Processing System Flow Diagram 11.4-1 Radwaste Disposal System Flow Diagram (Byron) 11.4-1 Radwaste Disposal System Flow Diagram (Braidwood) 11.4-2 Deleted 11.4-3 Deleted 11.4-4 Deleted 11.0-ix REVISION 9 - DECEMBER 2002

B/B-UFSAR CHAPTER 11.0 - RADIOACTIVE WASTE MANAGEMENT DRAWINGS CITED IN THIS CHAPTER*

  • The listed drawings are included as General References only; i.e., refer to the drawings to obtain additional detail or to obtain background information. These drawings are not part of the UFSAR. They are controlled by the Controlled Documents Program.

DRAWING* SUBJECT M-9 General Arrangement Floor Plan At EL. 383-0 Units 1 and 2 M-12 General Arrangement Radwaste/Service Building Units 1 & 2 M-24-1 to -20 General Arrangements, Radiation Shielding Units 1 &

2 M-48-1 Diagram of Waste Disposal 30,000 Gallon Release Tank Units 1 & 2 M-48-2 Diagram of Waste Disposal Steam Generator Blowdown Units 1 & 2 M-48-3A, -3B Diagram of Waste Disposal Blowdown Mixed Bed Demineralizer Units 1 & 2 M-48-4A, -4B Diagram of Waste Disposal Blowdown Monitor Tanks Units 1 & 2 M-48-4C Diagram of Waste Disposal Vacuum Pumps M-48-5A, -5B Diagram of Waste Disposal Steam Generator Blowdown Units 1 & 2 M-48-6A, -6B Diagram of Waste Disposal Auxiliary Building Floor Drains Units 1 & 2 M-48-7 Diagram of Waste Disposal (Liquid) Chemical &

Demineralizer Waste Regen. Drains Units 1 & 2 M-48-8 Diagram of Waste Disposal Laundry Waste Drains Units 1 & 2 M-48-9 Diagram of Waste Disposal Radwaste Evaporator Units 1 & 2 M-48-10 Diagram of Waste Disposal Radwaste Evaporator OA Units 1 & 2 M-48-11, -12 Diagram of Waste Disposal Radwaste Evaporator OB Units 1 & 2 M-48-13 Diagram of Waste Disposal Radwaste Evaporator Units 1 & 2 M-48-14 Diagram of Waste Disposal Radwaste Evaporator OC Units 1 & 2 11.0-x REVISION 9 - DECEMBER 2002

B/B-UFSAR DRAWINGS CITED IN THIS CHAPTER* (Contd)

DRAWING* SUBJECT M-48-15 Diagram of Waste Disposal Radwaste Monitor Tanks Units 1 & 2 M-48-16 Diagram of Waste Disposal Turbine Building Floor Drains Units 1 & 2 M-48-17 Diagram of Waste Disposal Auxiliary Building Equipment Drains Units 1 & 2 M-48-18 Diagram of Waste Disposal Resin Removal Units 1 & 2 M-48-19 Diagram of Miscellaneous Sumps & Pumps Units 1 & 2 M-48-20A, Diagram of Waste Disposal Blowdown Mixed Bed

-20B Demineralizer Units 1 & 2 M-48-21A, Diagram of Waste Disposal Radwaste Mixed Bed

-21B, -21C Demineralizer Units 1 & 2 M-48-22 Diagram of Waste Disposal Turbine Building Equipment Drains Units 1 & 2 M-48-23 Diagram of Radioactive Waste Reprocessing &

Disposal Units 1 & 2 M-48-24 Diagram of Turbine Building Waste Oil Collection System Units 1 & 2 M-48-25 Diagram of Auxiliary Building Waste Oil Collection System Units 1 & 2 M-48-28 Diagram of Auxiliary Building Leak Detection Sumps Units 1 & 2 M-48-29 Diagram of Auxiliary Building Chromated Drain Collection System Units 1 & 2 M-48-30 Diagram of Miscellaneous Sump & Pumps Units 1 & 2 M-38-31 Blowdown Radwaste Mixed Bed Demineralizer Regeneration Skid Units 1 & 2 M-48-32 Diagram of Cement Filling Station Units 1 & 2 M-48-37 Diagram of Turbine Bldg Equipment/Floor Drain Coalescers Units 1 & 2 M-48-38 Diagram of Radwaste Evaporator Ammonia Stripper A Unit 1 & 2 M-48-39 Diagram of Radwaste Evaporator Ammonia Stripper B Unit 1 & 2 M-48-40 Diagram of Radwaste Evaporator Ammonia Stripper C Unit 1 & 2 M-48A Composite Diagram of Liquid Radwaste Treatment Processing Units 1 & 2 11.0-xi REVISION 9 - DECEMBER 2002

B/B-UFSAR DRAWINGS CITED IN THIS CHAPTER* (Contd)

DRAWING* SUBJECT M-64 Diagram of Chemical & Volume Control & Boron Thermal Regeneration Unit 1 M-64A Diagram of Chemical & Volume Control & Boron Thermal Regeneration Unit 1 M-69 Diagram of Radioactive Waste Gas System Units 1 & 2 11.0-xii REVISION 9 - DECEMBER 2002

B/B-UFSAR CHAPTER 11.0 - RADIOACTIVE WASTE MANAGEMENT 11.1 SOURCE TERMS Radioactive source terms are explained in this section.

Radioactive source terms are used in: shielding design, assuring adequacy of ventilation, design of radioactive systems, calculation of expected gaseous and liquid releases from the station, and accident analysis. Source terms are dependent on a number of assumptions; the assumptions depend on the particular application under consideration. To avoid confusion, clear distinction is made between the design-basis shielding source term, the expected source term, and the accident source term.

Operating limits are given in the Technical Specifications and other documents.

The releases of radioactivity and their resulting doses included in this chapter were calculated during plant licensing from assumed values for many parameters. These included coolant activity, iodine partitioning, amount of failed fuel, filter efficiencies, system flow rates, component leak rates, and associated activity for all potentially radioactive water and steam systems. Estimates were made for many individual contributors and then summed to obtain estimates for total annual dose. These values were then compared to appropriate regulatory limits, such as 10 CFR 20 and Appendix I to 10 CFR 50, to show that the plant could be operated, if granted a license, in compliance with these regulations. The NRC reviewed these estimated values and confirmed that the plant could be operated and meet the regulations in their safety evaluation report.

After the NRC issues an operating license, the requirement to meet the applicable radiological dose regulations is demonstrated in the stations annual radiological effluent release report. The values for the report are calculated using the measured total radioactivity releases from all sources and equations and data included in the Offsite Dose Calculation Manual. Only the total values are calculated; there is no requirement to calculate the dose from each of the individual sources listed in this section.

The information on release estimates and offsite doses is maintained in the UFSAR for historical reference and is not intended to be used to establish current operating limits.

The impact of a core power uprate on the radiation source terms at B&B Nuclear Stations is discussed in Section 11.1.8. The original licensed power level was 3411 MWt. The original source term, effluent and shielding analyses were performed at a power level of 3565 MWt. Core power has been uprated twice, first to 3586.6 MWt, then to the Measurement Uncertainty Recapture power uprate core power level of 3645 MWt.

11.1-1 REVISION 15 - DECEMBER 2014

B/B-UFSAR 11.1.1 Definition of Radioactive Source Terms 11.1.1.1 Design-Basis Shielding Source Terms Design-basis shielding source terms or conservative source terms are those source terms used for the design of bulk shielding, for determining in-plant airborne concentrations and the subsequent ventilation adequacy, for determining 40-year integrated doses for the specifications of station equipment, and for determining that the design of the station is such that doses to personnel do not exceed the limits specified in 10 CFR 20 and are as low as reasonably achievable (ALARA). These source terms are described in Subsection 12.2.1.

11.1.1.2 Realistic Source Terms Realistic or operating-basis source terms are those terms which are used for describing the releases from the station to the environment on an average annual basis. Site boundary doses due to releases from the station stack, discharges to the blowdown stream for liquid discharges, and offsite shipment of solid radioactive material are examples of calculations which use these source terms. Realistic source terms are based on realistic models for reactor coolant activity as represented in Tables 11.1-3 and 11.1-4. Calculations pertaining to releases described in Appendix I of 10 CFR 50 follow the source assumptions of Regulatory Guide 1.112, Revision 0, April 1976 and NUREG-0017, April 1976.

11.1.1.3 Accident Sources Accident sources are those sources used in the determination of doses to plant operating personnel and the public during one of the postulated accidents described in the regulatory guides. The design-basis accidents are discussed in Chapter 15.0. The analyses determine that the doses to the population do not exceed the limits specified in 10 CFR 100 for accidents analyzed using TID-14844 and 10 CFR 50.67 for accidents analyzed using alternative source term methodology. Some of the bulk shielding calculations use accident sources. These include the shielding 11.1-1a REVISION 12 - DECEMBER 2008

B/B-UFSAR of the control room and the shielding of piping and components which process radioactive fluids which contain sources from one of the design-basis accidents. These include the components of the RHR, safety injection, and containment spray systems. The accident design conditions for these components are clearly defined in Table 12.3-2. The postulated accidents described in Chapter 15.0 include component failure in which there is a release of contained radionuclides to the environment. The sources for these accidents are referred to as component failure sources and will be referenced in this chapter.

11.1.2 Basis for Radioactive Source Terms Two source term models (a design-basis model and an operational basis realistic model) are presented for shielding design and effluent release analysis. Source terms for shielding design and component failure are based on the same design-basis model for reactor coolant activity but on different assumptions with respect to the operating characteristics of the Waste Processing Systems. The source terms for the effluent release analysis are based on the realistic model for reactor coolant activity as formulated in the draft standard N237 (Reference 1).

Tritium production and fuel operating experience are fully addressed in References 2 (Sections 3 and 4.12) and 3, respectively.

Source terms and models used in the design and evaluation of the Waste Processing Systems are compared to operating plant data where available (Reference 2).

11.1.2.1 Conservative Model for Reactor Coolant Activity Fission Products The parameters used in the calculation of the reactor coolant fission product concentrations for original plant design are summarized in Table 11.1-1 and the concentrations are presented in Table 11.1-2.

The fission products concentrations are computed using the following differential equations:

For parent nuclides in the coolant:

dN wi B' Di Nc ( Ri ) N wi (11.1-1) dt i i Bo tB' For daughter nuclides in the coolant:

dN wi B' DjNc ( Rj ) N wj N wi (11.1-2) dt j j Bo tB' i 11.1-2 REVISION 9 - DECEMBER 2002

B/B-UFSAR Where N = population of nuclides, atoms t = time (sec),

D = cladding defects, as a fraction of rated core thermal power being generated by rods with cladding defects, R = purification flow, coolant system volumes per second, Bo = initial boron concentration (ppm),

B = boron concentration reduction rate by feed and bleed, (ppm/sec),

= removal efficiency of purification cycle for nuclide,

= radioactive decay constant (sec-1), and

= escape rate coefficient for diffusion into coolant (sec-1).

Subscripts:

C = refers to core W = refers to coolant i = refers to parent nuclide j = refers to daughter nuclide.

The fission products are removed by decay, by cleanup in the chemical volume and control system, and by letdown to the boron recycle system.

Corrosion Products The corrosion product activities, which are independent of fuel defect level, are based on measurements at operating reactors (Reference 2). The corrosion product concentrations are given in Table 11.1-2.

11.1.2.2 Realistic Model for Reactor Coolant Activity The range of plant design and operating parameters covered by the referenced standard N237 (Reference 1), together with the corresponding specific plant related parameters, are given in Table 11.1-3. Corrections are made whenever a parameter falls 11.1-3 REVISION 7 - DECEMBER 1998

B/B-UFSAR outside the given range as recommended in Reference 1. The Gaseous Waste Processing System is assumed to strip fission gases from the volume control tank. The overall y parameter, as given in Reference 1 is interpreted as being equivalent to the stripping fractions. A separate value of the stripping fraction for each noble gas isotope is used as indicated in Table 11.1-1.

A stripping efficiency of 40% is used for conservatism. Using this low stripping or separation efficiency in the volume control tank results in a conservative estimation of the reactor coolant system radioactivity.

The amounts of fission gases removed from the reactor coolant in the volume control tank and collected by the gaseous waste processing system are related by the following equations:

CR - CL SE = (11.1-3)

CR - CLeq CR - CL SF = (11.1-4)

CR where SE = stripping efficiency, SF = stripping fraction, CR = gas concentration in the liquid phase entering volume control tank, CL = gas concentration in the liquid phase leaving the volume control tank, and CLeq = gas concentration in the liquid phase leaving the volume control tank, assuming the ratio of the gas concentration in the vapor and liquid phases in the volume control tank follows Henry's Law.

Specific activities in the primary coolant, based on the realistic model, are given in Table 11.1-4.

11.1.3 Source Terms for Shielding Design Basis Liquid Waste Processing System Shielding source terms are supplied for components of the liquid waste processing systems (inside and outside the containment).

These sources are based upon the design-basis coolant activity given in Subsection 11.1.1.1. Source terms for shielding design are given in Subsection 12.2.1.

11.1-4 REVISION 1 - DECEMBER 1989

B/B-UFSAR Gaseous Waste Processing System The gaseous waste processing system consists of two waste-gas compressor packages, six gas decay tanks, and the associated piping, valves and instrumentation. The equipment serves both units. The system is shown in Drawing M-69.

The reactor coolant activities in Table 11.1-2 are used. A stripping efficiency of 100% is assumed. The resulting source terms are given in Table 12.2-28.

11.1.4 Source Terms for Component Failure Liquid Waste Processing System The tanks with the highest isotopic inventories, the recycle holdup tank and the spent resin storage tank, were selected for accident analysis. The inventory used for accident analysis is also the inventory used for shielding design basis for these tanks, thus the sources are found in Subsection 12.2.1. The accident analyses for these tanks are discussed in Subsections 2.3.4, 2.3.5, 2.4.12, 2.4.13.3, and 15.7.3.

Gaseous Waste Processing System The isotopic inventories in one gas decay tank to be used for the gas decay tank rupture accident are given in Table 11.1-5. The inventories are based on the reactor coolant activity in Table 11.1-2 and 100% stripping efficiency in the volume control tank.

The activity is further based on 40 years inventory taking credit for radioactive decay results in equilibrium levels of Kr-85 and all other isotopes within the volume control tank. It is assumed two units are operating simultaneously and decay tanks are switched every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

11.1.5 Source Terms for Radwaste System Components Realistic reactor coolant activities presented in Table 11.1-4 are used as a basis for the expected isotopic inventories of radwaste components for the estimate of average annual curies of radioactive wastes to be shipped offsite. The radioactive inventories are presented in Tables 11.1-6 through 11.1-11. The flow rates and operating times used in the calculation of these inventories are the design-basis parameters for the radwaste system as described in Sections 11.2 and 11.4.

11.1.6 Sources of In-Plant Airborne Radioactivity Sources of in-plant airborne radioactivity for the purpose of evaluating the ventilation systems are discussed in Subsection 12.2.2. Leakage rates are discussed there, and Tables 12.2-46 through 12.2-48 present total liquid iodine concentrations, 11.1-5 REVISION 9 - DECEMBER 2002

B/B-UFSAR number of leakage sources, exhaust air flow rates, and fractions of maximum permissible concentrations for iodine (10 CFR 20 Appendix B). Previous experience of gaseous radioactive in-plant concentrations are cited in Reference 2 for the Robert E. Ginna Plant. Special design features which minimize the possibility of airborne contamination of occupied areas are proper venting of equipment, discussed in Subsection 12.3.1.5, and proper location of valves and instruments, discussed in Subsection 12.3.1.8.

11.1.7 Sources of Radioactive Releases to the Environment 11.1.7.1 Gaseous Releases Gaseous radioactive releases are discussed in Subsection 11.3.3.3. Estimates of the gaseous releases from the plant, which includes gas stripping, blowdown ventilation off-gas, and air ejector exhaust, are presented in Table 11.3-6.

11.1.7.2 Liquid Releases Liquid radioactive releases are discussed in Subsection 11.2.1.3.

Expected annual average releases of radionuclides in liquid effluents are presented in Table 11.2-1. Parameters used in the calculation are presented in Table 11.2-2.

11.1.8 Impact of Uprate on Normal Operation Radiation Source Terms The original licensed power level was 3411 MWt. The original source term, effluent and shielding data/analyses presented in the UFSAR represent a power level of 3565 MWt. As a result of a reactor core power uprate to 3586.6 MWt, the design basis reactor coolant activity was re-calculated at a core power level of 3658.3 MWt which includes a 2% margin for uncertainty. A core power level of 3658.3 MWt bounds the Measurement Uncertainty Recapture power uprate core power level of 3645 MWt including margin for uncertainty. The parameters used in the calculation of the original as well as the uprated reactor coolant concentrations are summarized in Table 11.1-1. The design basis reactor coolant concentrations for the uprated core are presented in Table 11.1-13.

The uprated design basis reactor coolant concentrations are comparable to the original design basis reactor coolant concentrations given to Table 11.1-2. Consequently, the normal operation radiation source terms for downstream process systems described in prior sections, including liquid and gaseous radwaste, remain valid for uprate.

Based on a comparison of original vs power uprate GALE-PWR computer program input parameters presented in Table 11.2-2, and the methodology outlined in NUREG 0017, the maximum expected increase in the realistic reactor coolant source term is limited to the percentage of the uprate relative to the power level used in the original analyses, i.e.; 0.6%. Considering the accuracy and error bounds of the operational data utilized in NUREG 0017 as shown in Table 11.1-3, this small percentage is well within the uncertainty of the existing NUREG 0017 based realistic 11.1-6 REVISION 15 - DECEMBER 2014

B/B-UFSAR reactor coolant isotopic inventory. Consequently, the realistic reactor coolant source terms presented in Table 11.1-4, as well as all of the downstream realistic source terms, remain valid for uprate.

11.1.9 References

1. American National Standard Source Term Specification, N237, March 9, 1976.
2. Source Term Data for Westinghouse Pressurized Water Reactors, WCAP-8253, Amendment 1, July 1975.
3. Operational Experience with Westinghouse Cores, WCAP-8183, June 1, 1977.

11.1-6a REVISION 9 - DECEMBER 2002

B/B-UFSAR TABLE 11.1-1 PARAMETERS USED IN THE CALCULATION OF DESIGN BASIS PRIMARY COOLANT ACTIVITIES - ORIGINAL & UPRATED(***)

1. Ultimate core thermal power, MWt 3565 (3658.3)
2. Cladding defects, as a percent of rated core thermal power being generated by rods with clad defects 1.0
3. Reactor coolant liquid mass, gms 2.42E8 (2.477E8)
4. Reactor coolant full power average temperature,oF 586.2
5. Purification flow rate (normal) *gpm 118.3
6. Effective cation demineralizer flow, *gpm 7.5
7. Volume control tank volumes (stripping efficiency 40%, purge rated rate at which purge gas is introduced in the volume control tank, 0.7 scfm)
a. Vapor, ft3 200
b. Liquid, ft3 200
8. Fission product escape rate coefficients:**

-1

a. Noble gas isotopes, sec 6.5 x 10-8

-1

b. Br, Rb, I and Cs isotopes, sec 1.3 x l0-8
c. Te isotopes, sec-1 1.0 x 10-9
d. Mo isotopes, sec-1 2.0 x 10-9
e. Sr and Ba isotopes, sec-1 1.0 x 10-11

-1

f. Y, La, Ce, Pr isotopes, sec 1.6 x 10-12
  • At reference condition, 130oF and 2300 psig, 1 gpm = 497.3 lb/hr.
    • Escape rate coefficients are based on fuel defect tests performed at the Saxton reactor. Recent experience at plants operating with fuel rod defects has verified the listed escape rate coefficients.
      • Parameters that changed due to uprate are presented in ().

11.1-7 REVISION 9 - DECEMBER 2002

B/B-UFSAR TABLE 11.1-1 (Cont'd)

9. Mixed bed demineralizer decontamination factors:
a. Noble gases and Cs-134, 136, 137, Y-90, 91 and Mo-99 1.0
b. All other isotopes including corrosion 10.0
10. Cation bed demineralized decontamination factor for Cs-134, 137, Y-90, 91 10.0 lla. Volume control tank noble gas stripping fractions Stripping Isotope Fraction Kr-85 2.3 x 10-5 Kr-85m 2.7 x 10-1 Kr-87 6.0 x 10-1 Kr-88 4.3 x 10-1 Xe-131m 1.0 x 10-2 Xe-133 1.6 x 10-2 Xe-133m 3.7 x 10-2 Xe-135 1.8 x 10-1 Xe-135m 8.0 x 10-1 Xe-138 1.0 llb. Partition factor* for iodine in the volume control tank 100.0
12. Boron Concentration and Reduction Rates
a. Bo (initial cycle beginning of life, full power, and with equilibrium xenon), ppm 805
b. Bo (equilibrium cycle), ppm 1080 11.1-8

B/B-UFSAR TABLE 11.1-1 (Cont'd)

13. Pressurizer Volumes
a. Vapor, ft3 720
b. Liquid, ft3 1080
14. Spray line flow*, gpm 1.0
15. Pressurizer Stripping fractions
a. Noble gases 1.0
b. All other elements 0
  • At reference conditions 130 F and 2300 psig, 1 gpm = 497.3 lb/hr.

11.1-9 REVISION 7 - DECEMBER 1998

B/B-UFSAR TABLE 11.1-2 DESIGN-BASIS REACTOR COOLANT FISSION AND CORROSION PRODUCT ACTIVITY (ORIGINAL DESIGN)

ACTIVITY* ACTIVITY*

ISOTOPE (Ci/gram) ISOTOPE (Ci/gram)

H-3 3.5 (maximum) Cs-136 2.8 Br-84 4.3 x 10-2 Cs-137 1.5 Rb-88 3.7 Cs-138 0.98 Rb-89 2.1 x 10-1 Ba-140 4.3 x l0-3 Sr-89 3.3 x 10-3 La-140 1.5 x l0-3 Sr-90 1.7 x 10-4 Ce-144 3.4 x l0-4 Sr-91 1.9 x 10-3 Pr-144 3.4 x l0-4 Sr-92 7.4 x 10-4 Kr-85 8.8 (peak)

Y-90 2.0 x 10-4 Kr-85m 2.1 Y-91 6.1 x 10-3 Kr-87 1.2 Y-92 7.2 x 10-4 Kr-88 3.7 Zr-95 7.0 x 10-4 Xe-131m 1.9 Nb-95 6.9 x 10-4 Xe-133 2.81 x 102 Mo-99 5.3 Xe-133m 18.8 I-131 2.5 Xe-135 6.3 I-132 2.8 Xe-135m 0.4 I-133 4.0 Xe-138 0.7 I-134 0.6 Mn-54** 7.9 x 10-4 I-135 2.2 Mn-56** 3.0 x 10-2 Te-132 0.26 Co-58** 2.6 x 10-2 Te-134 2.9 x 10-2 Co-60** 1.0 x l0-3 Cs-134 2.3 Fe-59** 1.1 x 10-3 Cr-51** 9.5 x 10-4

  • Parameters used in primary coolant activity calculation are listed in Table 11.1-1, at operating temperature.
    • Corrosion product activities are based on activity levels measured at operating reactors.

11.1-10 REVISION 9 - DECEMBER 2002

B/B-UFSAR TABLE 11.1-3 PARAMETERS USED IN THE CALCULATION OF REALISTIC, OPERATIONAL BASIS PRIMARY COOLANT ACTIVITIES NOMINAL RANGE BYRON/

PARAMETER UNITS VALUE MAXIMUM MINIMUM BRAIDWOOD*

Thermal power MWT 3400 3800 3000 3558 Steam flow rate lbs/hr 1.5E+07 1.7E+07 1.3E+07 1.5E+07 Weight of water in lbs 5.5E+05 6.0E+05 5.0E+05 5.3E+05 reactor coolant system Weight of water in all lbs 4.5E+05 5.0E+05 4.0E+05 3.84E+05 steam gen. (full load)

Reactor coolant let- lbs/hr 3.7E+04 4.2E+04 3.2E+04 3.7E+04 down flow (purification)

Reactor coolant let- lbs/hr 500 1000 250 130 down flow (yearly average for boron control)

Steam generator blow- lbs/hr 9000 10,000 8,000 3.0E+04 down flow (total) 11.1-11

B/B-UFSAR TABLE 11.1-3 (Cont'd)

NOMINAL RANGE BYRON/

PARAMETER UNITS VALUE MAXIMUM MINIMUM BRAIDWOOD*

Fraction of radioactivity - 1.0 1.0 0.9 1.0 in blowdown stream which is not returned to the secondary coolant system Flow through the lbs/hr 3700 7500 0.0 3.7E+03 purification system cation demineralizer Ratio of condensate - 0.0 0.01 0.0 0.0 demineralizer flow rate to the total steam flow rate Ratio of the total - 0.0 0.01 0.0 1.0 for amount of noble gases Kr-83m, routed to gaseous radwaste Kr-89, from the purification Xe-137.

system to the total See Table amount of noble gases 11.1-1 routed from the primary for other coolant system to the isotopes.

purification system (not including the boron recovery)

  • Corrections are made whenever a parameter falls outside the given range as recommended in Reference 2.3 11.1-12

B/B-UFSAR TABLE 11.1-4 REALISTIC, OPERATIONAL BASIS REACTOR COOLANT FISSION AND CORROSION PRODUCT ACTIVITIES REACTOR COOLANT REACTOR COOLANT ACTIVITY ACTIVITY ISOTOPE (Ci/gram) ISOTOPE (Ci/gram)

GROUP I - NOBLE GASES GROUP III - CS, RB Kr-83m 2.06E-02 Rb-86 8.87E-05 Kr-85m 9.81E-02 Rb-88 2.17E-01 Kr-85 7.56E-01 Kr-87 6.09E-02 Cs-134 2.60E-02 Kr-88 1.88E-01 Cs-136 1.36E-02 Kr-89 5.60E-03 Cs-137 1.87E-02 Xe-131m 1.13E-01 Xe-133m 1.87E-01 GROUP IV - N - 16 Xe-133 1.63E+01 N-16 4.00E+1 Xe-135m 1.43E-02 Xe-135 3.07E-01 Xe-137 l.0lE-02 GROUP V - TRITIUM Xe-138 4.84E-02 H-3 l.00E+00 GROUP II - HALOGENS Br-83 5.17E-03 Br-84 2.82E-03 Br-85 3.25E-04 I-130 2.23E-03 I-131 2.81E-03 I-132 1.08E-01 I-133 4.00E-01 I-134 5.08E-01 I-135 2.03E-01 11.1-13

B/B-UFSAR TABLE 11.1-4 (Cont'd)

REACTOR COOLANT REACTOR COOLANT ACTIVITY ACTIVITY ISOTOPE (Ci/gram) ISOTOPE (Ci/gram)

GROUP IV - OTHER ISOTOPES GROUP VI - OTHER ISOTOPES (Cont'd)

Cr-51 1.95E-03 Te-129m 1.44E-03 Mn-54 3.18E-04 Te-129 1.73E-03 Fe-55 1.64E-03 Te-131m 2.61E-03 Fe-59 1.03E-03 Te-131 1.19E-03 Co-58 1.64E-02 Te-132 2.79E-02 Co-60 2.05E-03 Ba-137m 1.74E-02 Sr-89 3.60E-04 Ba-140 2.26E-04 Sr-90 1.03E-05 La-140 1.56E-04 Sr-91 6.88E-04 Ce-141 7.19E-05 Y-90 1.24E-06 Ce-143 4.17E-05 Y-91m 3.89E-04 Ce-144 3.39E-05 Y-91 6.57E-05 Pr-143 5.14E-05 Y-93 3.59E-05 Pr-144 3.58E-05 Zr-95 6.16E-05 Np-239 1.24E-03 Nb-95 5.14E-05 Mo-99 8.69E-02 Tc-99m 5.11E-02 Ru-103 4.62E-05 Ru-106 1.03E-05 Rh-103m 4.86E-05 Rh-106 1.09E-05 Te-125m 2.98E-05 Te-127m 2.88E-04 Te-127 8.99E-04 11.1-14

B/B-UFSAR TABLE 11.1-5 MAXIMUM REALISTIC, OPERATIONAL BASIS WASTE GAS DECAY TANK ACTIVITY FOR GAS DECAY TANK RUPTURE*

ISOTOPE ACTIVITIES (Curies)

Kr-85 1140.0 Kr-85m 23.6 Kr-87 14.6 Kr-88 45.2 Xe-131m 27.9 Xe-133 5760.0 Xe-133m 45.0 Xe-135 73.9 Xe-135m 3.4 Xe-138 ll.6

11.1-15

B/B-UFSAR TABLE 11.1-6 REALISTIC SOURCE TERMS FOR STEAM GENERATOR BLOWDOWN AND RADIOACTIVE SOURCE STREAMS REGENERA- REGENERATION AUXILIARY AUXILIARY STEAM TURBINE BLDG. TION WASTE WASTE DRAINS BLDG. BLDG.

GENERATOR TURBINE BLDG. EQUIPMENT CHEMICAL DRAINS WITH WITHOUT EQUIPMENT FLOOR LAUNDRY BLOWDOWN FLOOR DRAINS DRAINS DRAINS SGBD LEAK SGBD LEAK DRAINS DRAINS DRAINS ISOTOPE (Ci/ml) (Ci/ml) (Ci/ml) (Ci/ml) (Ci/ml) (Ci/ml) (Ci/ml) (Ci/ml) (Ci/ml)

H-3 7.400-03 9.915-06 2.000-05 8.000-03 1.190+00 6.346-03 5.000-03 2.007-03 4.000-04 Cr-51 1.443-05 1.893-08 3.900-08 1.560-05 2.272-03 1.212-05 9.750-06 3.871-06 7.800-07 Mn-54 2.353-06 3.147-09 6.360-09 2.544-06 3.777-04 2.014-06 1.590-06 6.375-07 1.272-07 Mn-56 1.214-05 1.481-09 3.280-08 1.312-05 1.778-04 9.481-07 8.200-06 5.903-07 6.560-07 Co-58 1.214-04 1.613-07 3.280-07 1.312-04 1.936-02 1.032-04 8.200-05 3.277-05 6.560-06 Fe-59 7.622-06 1.008-08 2.060-08 8.240-06 1.210-03 6.452-06 5.150-06 2.053-06 4.120-07 Co-60 1.517-05 2.032-08 4.100-08 1.640-05 2.439-03 1.301-05 1.025-05 4.113-06 8.200-07 Br-83 3.826-05 4.363-09 1.034-07 4.136-05 5.236-04 2.792-06 2.585-05 1.741-06 2.068-06 Br-84 2.087-05 5.245-10 5.640-08 2.256-05 6.294-05 3.357-07 1.410-05 2.098-07 1.128-06 Br-85 2.405-06 5.707-12 6.500-09 2.600-06 6.848-07 3.652-09 1.625-06 2.283-09 1.300-07 Rb-88 1.606-03 2.257-08 4.340-06 1.736-03 2.709-03 1.445-05 1.085-03 9.030-06 8.680-05 Rb-89 8.066-08 9.812-13 2.180-10 8.720-08 1.177-07 6.280-10 5.450-08 3.925-10 4.360-09 Sr-89 2.664-06 3.530-09 7.200-09 2.880-06 4.236-04 2.259-06 1.800-06 7.183-07 1.440-07 Y-89m 0.000 3.529-13 0.000 0.000 4.235-08 2.259-10 0.000 7.181-11 0.000 Sr-90 7.622-08 1.021-10 2.060-10 8.240-08 1.226-05 6.537-08 5.150-08 2.067-08 4.120-09 Y-90 9.176-09 2.952-11 2.480-11 9.920-09 3.543-06 1.890-08 5.200-09 4.379-09 4.960-10 Sr-91 5.091-06 2.209-09 1.376-08 5.504-06 2.650-04 1.414-06 3.440-06 7.209-07 2.752-07 Y-91m 0.000 1.290-09 0.000 0.000 1.547-04 8.253-07 0.000 4.114-07 0.000 Y-91 4.862-07 6.757-10 1.314-09 5.256-07 8.108-05 4.324-07 3.285-07 1.354-07 2.628-08 Sr-92 2.879-06 3.699-10 7.780-09 3.112-06 4.439-05 2.367-07 1.945-06 1.472-07 1.556-07 Y-92 2.657-07 4.139-10 7.180-10 2.872-07 4.966-05 2.649-07 1.795-07 1.568-07 1.436-08 Zr-95 4.558-07 6.054-10 1.232-09 4.928-07 7.264-05 3.874-07 3.080-07 1.230-07 2.464-08 Nb-95m 0.000 1.723-12 0.000 0.000 2.068-07 1.103-09 0.000 1.860-10 0.000 Nb-95 3.804-07 5.112-10 1.028-09 4.112-07 6.134-05 3.271-07 2.570-07 1.033-07 2.056-08 Mo-99 6.431-04 7.030-07 1.738-06 6.952-04 8.436-02 4.499-04 4.345-04 1.570-04 3.476-05 Tc-99m 3.781-04 6.075-07 1.022-06 4.088-04 7.289-02 3.888-04 2.555-04 1.260-04 2.044-05 11.1-16

B/B-UFSAR TABLE 11.1-6 (Cont'd)

REGENERA- REGENERATION AUXILIARY AUXILIARY STEAM TURBINE BLDG. TION WASTE WASTE DRAINS BLDG. BLDG.

GENERATOR TURBINE BLDG. EQUIPMENT CHEMICAL DRAINS WITH WITHOUT EQUIPMENT FLOOR LAUNDRY BLOWDOWN FLOOR DRAINS DRAINS DRAINS SGBD LEAK SGBD LEAK DRAINS DRAINS DRAINS ISOTOPE (Ci/ml) (Ci/ml) (Ci/ml) (Ci/ml) (Ci/ml) (Ci/ml) (Ci/ml) (Ci/ml) (Ci/ml)

Tc-99 0.000 5.419-15 0.000 0.000 6.503-10 3.468-12 0.000 5.521-13 0.000 Ru-103 3.419-07 4.514-10 9.240-10 3.696-07 5.417-05 2.889-07 2.310-07 9.201-08 1.848-08 Rh-103m 3.596-07 4.526-10 9.720-10 3.888-07 5.431-05 2.897-07 2.430-07 9.242-08 1.944-08 Ru-106 7.622-08 1.020-10 2.060-10 8.240-08 1.224-05 6.527-08 5.150-08 2.065-08 4.120-09 Rh-106 0.000 1.019-10 0.000 0.000 1.223-05 6.525-08 0.000 2.064-08 0.000 Te-125m 2.205-07 2.925-10 5.960-10 2.384-07 3.510-05 1.872-07 1.490-07 5.949-08 1.192-08 Te-127m 2.131-06 2.841-09 5.760-09 2.304-06 3.409-04 1.818-06 1.440-06 5.763-07 1.152-07 Te-127 6.653-06 4.749-09 1.798-08 7.192-06 5.699-04 3.039-06 4.495-06 1.205-06 3.596-07 Te-129m 1.066-05 1.404-08 2.880-08 1.152-05 1.684-03 8.983-06 7.200-06 2.864-06 5.760-07 Te-129 1.280-05 9.321-09 3.450-08 1.384-05 1.118-03 5.965-06 8.650-06 1.966-06 5.920-07 I-129 0.000 1.398-18 0.000 0.000 1.677-13 8.945-16 0.000 1.493-16 0.000 I-130 1.650-05 8.717-09 4.460-08 1.784-05 1.046-03 5.579-06 1.115-05 2.657-06 8.920-07 Te-131m 1.931-05 1.676-08 5.220-08 2.088-05 2.011-03 1.072-05 1.305-05 4.165-06 1.044-06 Te-131 8.806-06 3.163-09 2.380-08 9.520-06 3.796-04 2.024-06 5.950-06 8.020-07 4.760-07 I-131 2.079-05 2.729-08 5.620-08 2.248-05 3.274-03 1.746-05 1.405-05 5.601-06 1.124-06 Te-132 2.065-04 2.321-07 5.580-07 2.232-04 2.785-02 1.486-04 1.395-04 5.116-05 1.116-05 I-132 7.992-04 3.031-07 2.160-06 8.640-04 3.637-02 1.940-04 5.400-04 7.823-05 4.320-05 I-133 2.960-03 2.180-06 8.000-06 3.200-03 2.617-01 1.395-03 2.000-03 5.822-04 1.600-04 I-134 3.759-03 1.545-07 1.016-05 4.064-03 1.854-02 9.888-05 2.540-03 6.180-05 2.032-04 Cs-134 1.924-04 2.576-07 5.200-07 2.080-04 3.092-02 1.649-04 1.300-04 5.215-05 1.040-05 I-135 1.502-03 4.705-07 4.060-06 1.624-03 5.646-02 3.011-04 1.015-03 1.684-04 8.120-05 Cs-136 1.006-04 1.289-07 2.720-07 1.088-04 1.547-02 8.251-05 6.800-05 2.667-05 5.440-06 Cs-137 1.384-04 1.854-07 3.740-07 1.496-04 2.225-02 1.187-04 9.350-05 3.752-05 7.480-06 Ba-137m 1.288-04 1.734-07 3.480-07 1.392-04 2.081-02 1.110-04 8.700-05 3.509-05 6.960-06 Ba-140 1.672-06 2.141-09 4.520-09 1.808-06 2.569-04 1.370-06 1.130-06 4.431-07 9.040-08 La-140 1.154-06 1.723-09 3.120-09 1.248-06 2.067-04 1.103-06 7.800-07 3.342-07 6.240-08 Ce-141 5.321-07 7.004-10 1.438-09 5.752-07 8.405-05 4.483-07 3.595-07 1.430-07 2.876-08 Ce-143 3.086-07 2.788-10 8.340-10 3.336-07 3.334-05 1.778-07 2.085-07 6.791-08 1.668-08 11.1-17

B/B-UFSAR TABLE 11.1-6 (Cont'd)

REGENERA- REGENERATION AUXILIARY AUXILIARY STEAM TURBINE BLDG. TION WASTE WASTE DRAINS BLDG. BLDG.

GENERATOR TURBINE BLDG. EQUIPMENT CHEMICAL DRAINS WITH WITHOUT EQUIPMENT FLOOR LAUNDRY BLOWDOWN FLOOR DRAINS DRAINS DRAINS SGBD LEAK SGBD LEAK DRAINS DRAINS DRAINS ISOTOPE (Ci/ml) (Ci/ml) (Ci/ml) (Ci/ml) (Ci/ml) (Ci/ml) (Ci/ml) (Ci/ml) (Ci/ml)

Pr-143 3.804-07 5.016-10 1.028-09 4.112-07 6.019-05 3.210-07 2.570-07 1.025-07 2.056-08 Ce-144 2.509-07 3.355-10 6.780-10 2.712-07 4.026-05 2.147-07 1.695-07 6.795-08 1.356-08 Pr-144 2.649-07 3.357-10 7.160-10 2.864-07 4.028-05 2.148-07 1.790-07 6.803-08 1.432-08 Np-239 9.176-06 9.673-09 2.480-08 9.920-06 1.161-03 6.191-06 6.200-06 2.198-06 4.960-07 TOTAL 2.017-02 1.567-05 5.452-05 2.181-02 1.880+00 1.003-02 1.363-02 3.464-03 1.090-03 11.1-18

B/B-UFSAR TABLE 11.1-6 (Cont'd)

ASSUMPTIONS GENERAL: SOURCE TERMS ARE BASED ON THE REALISTIC SOURCE TERMS FROM ANSI N-237 (Table 11.1-4).

1. Steam generator blowdown
a. Assume a 1-gpm primary-to-secondary leak.
b. Assuming blowdown from the leaking steam generator is 90 gpm and the other steam generators are operating at the normal 15-gpm blowdown, the total blowdown is 135 gpm from the leaking unit.
c. From the above assumptions, the activity in the steam generator blowdown is 1/135 of PCA or 7.4 x 10-3 PCA.
2. Turbine building floor drains
a. Assume activity is 1 x 10-5 PCA (based on NUREG/CR-0715, In-Plant Source Term Measurements at Zion Station).
3. Turbine building equipment drains
a. Assume activity is 2 x 10-5 PCA (based on NUREG/CR-0715, In-Plant Source Term Measurements at Zion Station).
4. Chemical drains
a. Assume activity is 8 x 10-3 PCA (based on NUREG/CR-0715, In-Plant Source Term Measurement at Zion Station).
5. Regeneration waste drains
a. Assume activity is 6 x 10-3 PCA under operating conditions other than a steam generator primary to secondary leak condition.
b. Assume activity is 1.2 PCA during a steam generator primary to secondary leak condition.
c. The above assumptions are calculated from flow and source data in this document and equipment parameters by an iterative means.
6. Auxiliary building equipment drains
a. Assume activity is 5 x 10-3 PCA (based on NUREG/CR-0715, In-Plant Source Term Measurement at Zion Station).
7. Auxiliary building floor drains
a. Assume activity is 2 x 10-3 PCA (based on NUREG/CR-0715, In-Plant Source Term Measurement at Zion Station).
8. Laundry drains
a. Assume activity is 4 x 10-4 PCA (based on NUREG/CR-0715, In-Plant Source Term Measurement at Zion Station).

11.1-19 REVISION 2 - DECEMBER 1990

B/B-UFSAR TABLE 11.1-7 REALISTIC SOURCE TERMS FOR BALANCE OF PLANT (1-Year Accumulation as Shipped for 2 Units)

TURBINE BUILDING BLOWDOWN BLOWDOWN TURBINE BUILDING EQUIPMENT DRAIN TURBINE BUILDING BLOWDOWN TURBINE BUILDING DEMINERALIZER DEMINERALIZER EQUIPMENT DRAIN DEMINERALIZER FLOOR DRAIN DEMINER- EQUIPMENT DRAIN PREFILTER AFTERFILTER FILTER AFTERFILTER FILTER ALIZER DEMINERALIZER ISOTOPE (Ci) (Ci) (Ci) (Ci) (Ci) (Ci) (Ci)

H-3 2.802-05 2.802-05 9.010-07 1.802-06 4.505-07 2.802-05 1.502-07 Cr-51 1.926-01 1.926-03 1.374-04 2.748-06 6.869-05 6.754-02 8.648-06 Mn-54 4.228-02 4.228-04 3.135-05 6.269-07 1.567-05 1.191-02 1.571-06 Mn-56 1.245-03 1.245-05 7.894-08 1.579-09 3.947-08 1.370-03 1.447-08 Co-58 1.970+00 1.970-02 1.441-03 2.882-05 7.206-04 5.984-01 7.818-05 Fe-59 1.148-01 1.148-03 8.319-05 1.664-06 4.160-05 3.686-02 4.779-06 Co-60 2.800-01 2.800-03 2.083-04 4.166-06 1.041-04 7.728-02 1.022-05 Br-83 1.449-07 1.449-09 3.965-10 7.930-12 1.982-10 4.034-03 3.982-08 Br-84 7.901-08 7.901-10 4.766-11 9.533-13 2.383-11 4.849-04 1.061-09 Br-85 9.106-09 9.106-11 5.186-13 1.037-14 2.593-13 5.285-06 1.168-12 Rb-88 6.080-06 6.080-07 2.051-09 2.051-09 1.026-09 1.898-02 1.315-08 Rb-89 3.054-10 3.054-11 8.917-14 8.917-14 4.458-14 8.249-07 4.965-13 Sr-89 1.009-08 1.009-10 3.208-10 6.415-12 1.604-10 1.297-02 1.687-06 Y-89m 0.000 0.000 3.207-14 6.415-16 1.604-14 1.297-06 1.687-10 Sr-90 2.886-10 2.886-12 9.281-12 1.856-13 4.641-12 3.887-04 5.144-08 Y-90 3.474-11 3.474-13 2.683-12 5.366-14 1.342-12 2.313-04 3.606-08 Sr-91 1.928-08 1.928-10 2.007-10 4.014-12 1.004-10 2.158-03 8.093-08 Y-91m 0.000 0.000 1.172-10 2.344-12 5.859-11 1.267-03 5.158-08 Y-91 1.841-09 1.841-11 6.140-11 1.228-12 3.070-11 2.537-03 3.320-07 Sr-92 1.090-08 1.090-10 3.361-11 6.723-13 1.681-11 3.420-04 3.803-09 Y-92 1.006-09 1.006-11 3.761-11 7.522-13 1.880-11 3.831-04 9.339-09 Zr-95 7.309-03 7.309-05 5.338-06 1.068-07 2.669-06 2.241-03 2.923-07 Nb-95m 1.207-04 1.207-06 9.272-08 1.854-09 4.636-08 1.987-05 3.279-09 Nb-95 7.181-03 7.181-05 5.342-06 1.068-07 2.671-06 1.960-03 2.602-07 Mo-99 1.714+00 1.714-02 9.719-04 1.944-05 4.860-04 1.555+00 1.538-04 Tc-99m 1.498+00 1.498-02 8.494-04 1.699-05 4.247-04 1.430+00 1.461-04 11.1-20

B/B-UFSAR TABLE 11.1-7 (Cont'd)

TURBINE BUILDING BLOWDOWN BLOWDOWN TURBINE BUILDING EQUIPMENT DRAIN TURBINE BUILDING BLOWDOWN TURBINE BUILDING DEMINERALIZER DEMINERALIZER EQUIPMENT DRAIN DEMINERALIZER FLOOR DRAIN DEMINER- EQUIPMENT DRAIN PREFILTER AFTERFILTER FILTER AFTERFILTER FILTER ALIZER DEMINERALIZER ISOTOPE (Ci) (Ci) (Ci) (Ci) (Ci) (Ci) (Ci)

Tc-99 3.648-07 3.648-09 2.242-10 4.484-12 1.121-10 6.403-08 1.050-11 Ru-103 1.294-09 1.294-11 4.102-11 8.204-13 2.051-11 1.641-03 2.122-07 Rh-103m 1.362-09 1.362-11 4.113-11 8.226-13 2.057-11 1.643-03 2.124-07 Ru-106 2.886-10 2.886-12 9.267-12 1.853-13 4.634-12 3.862-04 5.099-08 Rh-106 0.000 0.000 9.264-12 1.853-13 4.632-12 3.862-04 5.099-08 Te-125m 8.350-12 8.350-12 2.658-11 5.317-13 1.329-11 1.079-03 1.406-07 Te-127m 8.070-09 8.070-11 2.581-10 5.163-12 1.291-10 1.063-02 1.395-06 Te-127 2.519-08 2.519-10 4.316-10 8.632-12 2.158-10 1.245-02 1.458-06 Te-129m 4.035-08 4.035-10 1.275-09 2.551-11 6.377-10 5.066-02 6.525-06 Te-129 4.847-08 4.847-10 8.470-10 1.694-11 4.235-10 3.277-02 4.183-06 I-129 0.000 0.000 1.270-19 2.540-21 6.351-20 2.048-11 3.696-15 I-130 6.248-08 6.248-10 7.921-10 1.584-11 3.961-10 8.979-03 4.100-07 Te-131m 7.313-08 7.313-10 1.523-09 3.046-11 7.614-10 2.485-02 1.880-06 Te-131 3.334-08 3.334-10 2.874-10 5.749-12 1.437-10 4.633-03 3.434-07 I-131 7.873-08 7.873-10 2.480-09 4.959-11 1.240-09 8.878-02 1.072-05 Te-132 7.817-07 7.817-09 2.109-08 4.219-10 1.055-08 5.473-01 5.615-05 I-132 3.026-06 3.026-08 2.754-08 5.509-10 1.377-08 6.231-01 5.811-05 I-133 1.121-05 1.121-07 1.981-07 3.963-09 9.907-08 2.715+00 1.732-04 I-134 1.423-05 1.423-07 1.404-08 2.808-10 7.020-09 1.428-01 5.096-07 Cs-134 7.285-07 7.285-08 2.341-08 2.341-08 1.171-08 8.893-01 6.531-05 I-135 5.688-06 5.688-08 4.276-08 8.551-10 2.138-08 4.415-01 1.196-05 Cs-136 3.811-07 3.811-08 1.172-08 1.172-08 5.858-09 3.894-01 2.670-05 Cs-137 5.240-07 5.240-08 1.685-08 1.685-08 8.425-09 6.416-01 4.717-05 Ba-137m 4.875-07 4.875-09 1.576-08 3.151-10 7.878-09 5.999-01 4.412-05 Ba-140 6.332-09 6.332-11 1.946-10 3.891-12 9.728-11 7.100-03 8.754-07 La-140 4.371-09 4.371-11 1.566-10 3.131-12 7.828-11 6.888-03 8.986-07 Ce-141 2.015-09 2.015-11 6.365-11 1.273-12 3.183-11 2.524-03 3.248-07 Ce-143 1.168-09 1.168-11 2.525-11 5.049-13 1.262-11 4.333-04 2.412-08 11.1-21

B/B-UFSAR TABLE 11.1-7 (Cont'd)

TURBINE BUILDING BLOWDOWN BLOWDOWN TURBINE BUILDING EQUIPMENT DRAIN TURBINE BUILDING BLOWDOWN TURBINE BUILDING DEMINERALIZER DEMINERALIZER EQUIPMENT DRAIN DEMINERALIZER FLOOR DRAIN DEMINER- EQUIPMENT DRAIN PREFILTER AFTERFILTER FILTER AFTERFILTER FILTER ALIZER DEMINERALIZER ISOTOPE (Ci) (Ci) (Ci) (Ci) (Ci) (Ci) (Ci)

Pr-143 1.440-09 1.440-11 4.558-11 9.116-13 2.279-11 1.732-03 2.166-07 Ce-144 9.499-10 9.499-12 3.049-11 6.097-13 1.524-11 1.269-03 1.674-07 Pr-144 1.003-09 1.003-11 3.050-11 6.101-13 1.525-11 1.269-03 1.674-07 Np-239 3.474-08 3.474-10 8.790-10 1.758-11 4.395-10 1.981-02 1.872-06 TOTAL 5.828+00 5.830-02 3.735-03 7.654-05 1.867-03 1.110+01 9.221-04 11.1-22

B/B-UFSAR TABLE 11.1-7 (Cont'd)

ASSUMPTIONS

1. Blowdown demineralizer prefilter.
a. Assume steam generator leakage.
b. Assume two 14-day leakage periods, one per unit per year.
c. The total run time for the prefilter to be contaminated is 28 days per year.
d. DFs given in Table 11.2-7.
2. Blowdown demineralizer afterfilter.
a. As blowdown demineralizer prefilter.
3. Turbine building equipment drain filter.
a. As blowdown demineralizer prefilter.
4. Turbine building equipment drain demineralizer afterfilter.
a. As blowdown demineralizer prefilter.
5. Turbine building floor drain filter.
a. As blowdown demineralizer prefilter.
6. Blowdown demineralizer.
a. Assume 28 days of steam generator leakage per year.
b. Assume that each demineralizer is regenerated every 6 days.
c. DFs given in Table 11.2-7.
7. Turbine building equipment drain demineralizer.
a. As blowdown demineralizer.

11.1-23 REVISION 1 - DECEMBER 1989

B/B-UFSAR TABLE 11.1-8 REALISTIC SOURCE TERMS FOR RADWASTE SYSTEM FILTERS AND DEMINERALIZERS (1-Year Accumulation as Shipped for 2 Units)

AUXILIARY BLDG. AUXILIARY BLDG. RADWASTE CHEMICAL REGENERATION LAUNDRY EQUIPMENT DRAIN FLOOR DRAIN DEMINERALIZER DRAIN WASTE DRAIN RADWASTE DRAIN FILTER FILTER FILTER AFTERFILTER FILTER FILTER DEMINERALIZER ISOTOPE (Ci) (Ci) (Ci) (Ci) (Ci) (Ci) (Ci)

H-3 1.813-05 2.279-04 9.117-05 1.239-03 3.604-04 2.572-06 2.748-05 Cr-51 9.212-04 4.682-02 1.873-02 9.554-06 2.748-02 5.393-01 1.974-06 Mn-54 2.102-04 1.058-02 4.233-03 2.153-06 6.269-03 1.295-01 3.841-07 Mn-56 5.281-07 5.240-05 2.096-05 6.306-09 1.581-05 1.269-05 2.724-10 Co-58 9.664-03 4.880-01 1.952-01 9.943-05 2.882-01 5.856+00 1.868-05 Fe-59 5.579-04 2.824-02 1.130-02 5.758-06 1.664-02 3.338-01 1.122-06 Co-60 1.397-03 7.026-02 2.810-02 1.429-05 4.166-02 8.641-01 2.514-06 Br-83 7.930-09 1.977-07 7.909-08 7.411-12 1.586-07 1.061-07 7.267-09 Br-84 9.533-10 2.383-08 9.533-09 8.914-13 1.907-08 2.499-09 1.244-10 Br-85 1.037-11 2.593-10 1.037-10 9.699-15 2.074-10 8.689-13 1.136-12 Rb-88 4.103-08 1.026-06 4.103-07 3.837-11 8.206-07 4.877-08 2.782-09 Rb-89 1.783-12 4.458-11 1.783-11 1.668-15 3.567-11 1.764-12 1.034-13 Sr-89 6.453-09 8.159-08 3.264-08 5.354-12 1.283-07 2.444-06 3.987-06 Y-89m 6.452-13 8.157-12 3.263-12 5.353-16 1.283-11 2.444-10 3.988-10 Sr-90 1.867-10 2.348-09 9.391-10 1.548-13 3.713-09 7.373-08 1.266-07 Y-90 5.414-11 4.975-10 1.990-10 4.328-14 1.073-09 4.860-08 1.080-07 Sr-91 4.018-09 8.188-08 3.275-08 3.602-12 8.028-08 1.927-07 3.049-08 Y-91m 2.346-09 4.673-08 1.869-08 2.094-12 4.687-08 1.228-07 1.953-08 Y-91 1.235-09 1.538-08 6.154-09 1.023-12 2.456-08 4.799-07 7.896-07 Sr-92 6.723-10 1.672-08 6.689-09 6.280-13 1.345-08 1.017-08 7.333-10 Y-92 7.522-10 1.782-08 7.127-09 6.952-13 1.504-08 2.502-08 2.387-09 Zr-95 3.580-05 1.808-03 7.234-04 3.685-07 1.068-03 2.164-02 6.966-08 Nb-95m 6.218-07 3.090-05 1.236-05 6.338-09 1.854-05 4.051-04 1.041-09 Nb-95 3.582-05 1.802-03 7.206-04 3.666-07 1.068-03 2.217-02 6.441-08 Mo-99 6.511-03 3.618-01 1.447-01 7.027-05 1.944-01 2.217+00 1.996-05 Tc-99m 5.690-03 3.162-01 1.265-01 6.141-05 1.699-01 1.937+00 3.661-05 Tc-99 1.502-09 8.347-08 3.339-08 1.548-11 4.484-08 4.719-07 2.491-11 11.1-24

B/B-UFSAR TABLE 11.1-8 (Cont'd)

AUXILIARY BLDG. AUXILIARY BLDG. RADWASTE CHEMICAL REGENERATION LAUNDRY EQUIPMENT DRAIN FLOOR DRAIN DEMINERALIZER DRAIN WASTE DRAIN RADWASTE DRAIN FILTER FILTER FILTER AFTERFILTER FILTER FILTER DEMINERALIZER ISOTOPE (Ci) (Ci) (Ci) (Ci) (Ci) (Ci) (Ci)

Ru-103 8.251-10 1.045-08 4.181-09 6.848-13 1.641-08 3.085-07 4.952-07 Rh-103m 8.274-10 1.050-08 4.199-09 6.868-13 1.645-08 3.088-07 4.958-07 Ru-106 1.864-10 2.346-09 9.384-10 1.546-13 3.707-09 7.319-08 1.248-07 Rh-106 1.864-10 2.345-09 9.378-10 1.545-13 3.706-09 7.319-08 1.248-07 Te-125m 5.348-10 6.758-09 2.703-09 4.436-13 1.063-08 2.035-07 3.337-07 Te-127m 5.193-09 6.547-08 2.619-08 4.307-12 1.033-07 2.011-06 3.369-06 Te-127 8.665-09 1.369-07 5.477-08 7.425-12 1.726-07 2.166-06 3.380-06 Te-129m 2.566-08 3.254-07 1.301-07 2.130-11 5.102-07 9.509-06 1.510-05 Te-129 1.703-08 2.233-07 8.933-08 1.420-11 3.388-07 6.098-06 9.678-06 I-129 2.569-18 1.696-17 6.783-18 1.655-20 5.081-17 4.466-15 1.444-14 I-130 1.587-08 3.018-07 1.207-07 1.194-10 3.168-07 9.440-07 1.813-07 Te-131m 3.056-08 4.731-07 1.893-07 2.612-11 6.091-07 3.597-06 1.474-06 Te-131 5.769-09 9.110-08 3.644-08 4.944-12 1.150-07 6.571-07 2.692-07 I-131 4.987-08 6.362-07 2.545-07 3.482-10 9.918-07 1.686-05 2.164-05 Te-132 4.239-07 5.811-06 2.324-06 3.557-10 8.438-06 9.327-05 7.866-05 I-132 5.530-07 8.886-06 3.555-06 4.019-09 1.102-05 9.761-05 8.114-05 I-133 3.974-06 6.614-05 2.645-05 2.910-08 7.926-05 3.611-04 1.082-04 I-134 2.808-07 7.020-06 2.808-06 2.254-09 5.616-06 1.278-06 6.581-08 Cs-134 4.710-07 5.924-06 2.370-06 7.249-09 9.365-06 2.166-04 3.694+00 I-135 8.554-07 1.913-05 7.650-06 6.677-09 1.710-05 1.183-04 3.710-06 Cs-136 2.356-07 3.030-06 1.212-06 3.628-09 4.688-06 5.201-03 1.273+00 Cs-137 3.390-07 4.262-06 1.705-06 5.218-09 6.740-06 9.430-03 2.676+00 Ba-137m 3.170-07 3.986-06 1.594-06 2.628-10 6.303-06 8.817-03 2.501+00 Ba-140 3.913-09 5.033-08 2.013-08 3.254-12 7.783-08 3.359-06 1.836-06 La-140 3.151-09 3.796-08 1.518-08 2.597-12 6.262-08 3.443-06 2.008-06 Ce-141 1.280-09 1.624-08 6.497-09 1.063-12 2.546-08 1.243-06 7.504-07 Ce-143 5.068-10 7.714-09 3.086-09 4.319-13 1.010-08 1.321-07 2.860-08 Pr-143 9.168-10 1.164-08 4.657-09 7.611-13 1.823-08 8.308-07 4.632-07 Ce-144 6.133-10 7.719-09 3.088-09 5.086-13 1.219-08 6.396-07 4.090-07 11.1-25

B/B-UFSAR TABLE 11.1-8 (Cont'd)

AUXILIARY BLDG. AUXILIARY BLDG. RADWASTE CHEMICAL REGENERATION LAUNDRY EQUIPMENT DRAIN FLOOR DRAIN DEMINERALIZER DRAIN WASTE DRAIN RADWASTE DRAIN FILTER FILTER FILTER AFTERFILTER FILTER FILTER DEMINERALIZER ISOTOPE (Ci) (Ci) (Ci) (Ci) (Ci) (Ci) (Ci)

Pr-144 6.137-10 7.728-09 3.091-09 5.088-13 1.220-08 6.398-07 4.091-07 Np-239 1.766-08 2.497-07 9.987-08 1.488-11 3.516-07 7.257-06 2.210-06 TOTAL 2.505-02 1.326+00 5.304-01 1.503-03 7.473-01 1.189+01 1.014+01 11.1-26

B/B-UFSAR TABLE 11.1-8 (Cont'd)

ASSUMPTIONS

1. Laundry drain filter.
a. Assume 12 replacements per year based on N. S. Brooks and E. R. Chow, "Cartridge Filtration in Pressurized Water Reactors."
b. DFs are given in Table 11.2-7.
2. Auxiliary building equipment drain filter.
a. As laundry drain filter.
3. Auxiliary building floor drain filter.
a. As laundry drain filter.
4. Radwaste demineralizer afterfilter.
a. As laundry drain filter.
5. Chemical drain filter.
a. As laundry drain filter.
6. Regeneration waste drain filter.
a. As laundry drain filter.
7. Radwaste demineralizer.
a. Assume each demineralizer is regenerated every 8 days.
b. DFs are given in Table 11.2-7.

11.1-27 REVISION 1 - DECEMBER 1989

B/B-UFSAR TABLE 11.1-9 REALISTIC SOURCE TERMS FOR NSSS FILTERS REACTOR SEAL WATER SEAL WATER BRS BRS BRS SPENT FUEL SPENT FUEL COOLANT INJECTION RETURN CONCENTRATES FEED CONDENSATE PIT PIT SKIMMER ISOTOPE (Ci) (Ci) (Ci) (Ci) (Ci) (Ci) (Ci) (Ci)

I 131 4.2 1.8 8.3(-1) 1.2(-1) 2.1(-2) 7.0(-4) - -

I 133 7.1(-1) 2.8(-1) 1.3(-1) 1.9(-2) 3.3(-3) 1.4(-4) - -

RB 86 2.1(-3) 9.1(-4) 4.4(-4) 5.0(-5) 2.9(-5) - - -

CS134 2.2 1.0 4.4(-1) 6.0(-2) 1.0(-1) - - -

CS136 2.1(-1) 1.1(-1) 4.4(-2) 5.0(-3) 3.1(-3) - - -

CS137 1.7 7.4(-1) 3.3(-1) 4.5(-2) 8.3(-2) - - -

CR 51 1.1(-1) 4.5(-2) 2.2(-2) 2.9(-3) 5.1(-4) - 2.3(-1) 5.5(-2)

MN 54 3.5(-2) 1.7(-2) 6.5(-3) 1.0(-3) 5.1(-4) - 4.6(-1) 1.1(-1)

FE 55 2.5(-1) 1.1(-2) 4.4(-2) 7.0(-3) 3.4(-3) - - -

FE 59 7.1(-2) 2.8(-2) 1.3(-2) 1.9(-3) 4.2(-4) - 2.2(-2) 5.5(-3)

CO 58 1.5 6.8(-1) 3.1(-1) 4.0(-2) 1.0(-2) - 4.6(-1) 1.1(-1)

CO 60 3.2(-1) 1.1(-1) 6.6(-2) 9.0(-3) 4.5(-3) - 6.6(-2) 1.7(-2)

SR 87 2.8(-2) 1.1(-2) 6.6(-3) 8.0(-4) 1.7(-4) - - -

SR 90 1.4(-3) 5.7(-4) 2.2(-4) 3.8(-5) 2.4(-5) - - -

BA137M 1.6 6.8(-1) 3.1(-1) 4.2(-2) 7.9(-2) - - -

BA140 7.1(-1) 2.8(-3) 1.3(-3) 1.9(-4) 2.7(-5) - - -

11.1-28

B/B-UFSAR TABLE 11.1-9 (Cont'd)

ASSUMPTIONS

1. ANSI Standard N-237 source terms for reactor coolant are used for the analysis.
2. All isotopes with half-lives less than 1 day are ignored.
3. The filter changeout frequencies are as follows:

VOLUME PER FILTER CHANGES PER FILTER (cm3) YEAR*

A. Reactor coolant 1.11 x 104 3 B. Seal water return 1.11 x 104 1 C. Spent fuel pit 1.11 x 104 1 D. Spent fuel pit skimmer 1.11 x 104 1 E. Seal water injection 1.74 x 103 3 F. Recycle evaporator feed 1.11 x 104 1 G. Recycle evaporator concentrates 1.53 x 103 1 H. Recycle evaporator condensate 1.53 x103 1

4. For filters following demineralizers, the isotopic.

activities are based on 1% of the upstream demineralizer activity distributed on the filter as resin fines.

5. For filters where data exists, the measured contact dose rates are used to estimate the activities. The N-237 activities are scaled to meet the measured dose rate.
6. Primary water filters: reactor coolant, seal water injection, seal water return, and BRS concentrates filters are based on measured contact dose rates.
  • Based on plant data.

11.1-29

B/B-UFSAR TABLE 11.1-9 (Cont'd)

7. Spent fuel pit filters: only the isotopes listed have been measured at plants. Fission products are cleaned up before lifting the head, but corrosion products are released from the spent fuel. The skimmer filter is based on the ratio of measured contact dose rates for the skimmer and spent fuel pit filters.

11.1-30

BYRON-UFSAR TABLE 11.1-10 REALISTIC SOURCE TERMS FOR NSSS DEMINERALIZERS*

MIXED CATION BRS BRS SPENT FUEL BED BED FEED CONDENSATE BTRS PIT ISOTOPE (Ci/cm3) (Ci/cm3) (Ci/cm3) (Ci/cm3) (Ci/cm3) (Ci/cm3)

I 131 1390.0 - 2.4 1.2(-1) 12.7 -

I 133 218.0 - 3.7(-1) 2.4(-2) 2.0 -

RB 86 0.6 0.80 3.3(-3) - - -

CS134 1050.0 142.00 11.2 - - -

CS136 61.0 8.00 3.5(-1) - - -

CS137 818.0 117.00 9.4 - - -

CR 51 33.0 - 5.7(-2) - - 2.70 MN 54 20.0 - 5.8(-2) - - 54.0 FE 55 120.0 - 3.8(-1) - - -

FE 59 27.0 - 4.8(-2) - - 3.0 CO 58 600.0 - 1.2 - - 54.0 CO 60 155.0 - 5.1(-1) - - 8.0 SR 89 10.0 2.00 1.9(-2) - - -

SR 90 0.8 0.01 2.7(-3) - - -

Y 90 - - - - - -

Y 91 - - - - - -

ZR 95 - - - - - -

NB 95 - - - - - -

MO 99 - - - - - -

TO 99M - - - - - -

RU103 - - - - - -

RU106 - - - - - -

BA137M 774.0 105.00 8.8 - - -

BA140 2.0 0.30 3.0(-3) 30.0 30.0 30.0 20.0 70.0 30.0 Value in ft3

  • Multiplier for Ci:

20 - 5.7 x 105 30 - 8.5 x 105 70 - 2.0 x 106 11.1-31 REVISION 14 - DECEMBER 2012

BRAIDWOOD-UFSAR TABLE 11.1-10 REALISTIC SOURCE TERMS FOR NSSS DEMINERALIZERS*

MIXED CATION BRS BRS SPENT FUEL BED BED FEED CONDENSATE BTRS PIT ISOTOPE (Ci/cm3) (Ci/cm3) (Ci/cm3) (Ci/cm3) (Ci/cm3) (Ci/cm3)

I 131 1390.0 - 2.4 1.2(-1) 12.7 -

I 133 218.0 - 3.7(-1) 2.4(-2) 2.0 -

RB 86 0.6 0.80 3.3(-3) - - -

CS134 1050.0 142.00 11.2 - - -

CS136 61.0 8.00 3.5(-1) - - -

CS137 818.0 117.00 9.4 - - -

CR 51 33.0 - 5.7(-2) - - 2.70 MN 54 20.0 - 5.8(-2) - - 54.0 FE 55 120.0 - 3.8(-1) - - -

FE 59 27.0 - 4.8(-2) - - 3.0 CO 58 600.0 - 1.2 - - 54.0 CO 60 155.0 - 5.1(-1) - - 8.0 SR 89 10.0 2.00 1.9(-2) - - -

SR 90 0.8 0.01 2.7(-3) - - -

Y 90 - - - - - -

Y 91 - - - - - -

ZR 95 - - - - - -

NB 95 - - - - - -

MO 99 - - - - - -

TO 99M - - - - - -

RU103 - - - - - -

RU106 - - - - - -

BA137M 774.0 105.00 8.8 - - -

BA140 2.0 0.30 3.0(-3) 35.0 30.0 30.0 20.0 70.0 30.0 Value in ft3

  • Multiplier for Ci:

20 - 5.7 x 105 30 - 8.5 x 105 70 - 2.0 x 106 11.1-31a REVISION 14 - DECEMBER 2012

BYRON-UFSAR TABLE 11.1-10 (Cont'd)

ASSUMPTIONS

1. ANSI Standard N-237 source terms are used for the analysis.
2. All isotopes with half-lives less than 1 day are ignored.
3. The resin changeout frequency is as follows:

VOLUME CHANGES PER 3

DEMINERALIZER (ft per bed) YEAR*

A. Mixed bed 30 2 B. Cation bed 20 1 C. Boron thermal regeneration 70 1 D. Boron recycle evaporator feed 30 1 E. Boron recycle 20 1 condensate F. Spent fuel pit 30 1

4. Mixed bed and cation bed demineralizers: the mixed-bed activities are based on continuous flow through the bed at the nominal letdown rate. The flow through the cation bed is 0.1 of the mixed-bed flow.
5. Boron thermal regeneration demineralizers: the BTR demineralizer activity is based on the estimated flow through 5 BTR beds during continuous load follow operation.
6. Boron recycle system demineralizers: the BRS feed demineralizer activities are based on the estimated volume of primary water processed for boron control. Credit is taken for the mixed-bed demineralizer. The BRS condensate demineralizer activity is based on processing this water at the maximum processing rate.
7. Spent fuel pool demineralizers: only those isotopes that have been measured at plants are listed.
  • Based on plant data.

11.1-32 REVISION 14 - DECEMBER 2012

BRAIDWOOD-UFSAR TABLE 11.1-10 (Cont'd)

ASSUMPTIONS

1. ANSI Standard N-237 source terms are used for the analysis.
2. All isotopes with half-lives less than 1 day are ignored.
3. The resin changeout frequency is as follows:

VOLUME CHANGES PER DEMINERALIZER (ft3 per bed) YEAR*

A. Mixed bed 35 2 B. Cation bed 20 1 C. Boron thermal regeneration 70 1 D. Boron recycle evaporator feed 30 1 E. Boron recycle 20 1 condensate F. Spent fuel pit 30 1

4. Mixed bed and cation bed demineralizers: the mixed-bed activities are based on continuous flow through the bed at the nominal letdown rate. The flow through the cation bed is 0.1 of the mixed-bed flow.
5. Boron thermal regeneration demineralizers: the BTR demineralizer activity is based on the estimated flow through 5 BTR beds during continuous load follow operation.
6. Boron recycle system demineralizers: the BRS feed demineralizer activities are based on the estimated volume of primary water processed for boron control. Credit is taken for the mixed-bed demineralizer. The BRS condensate demineralizer activity is based on processing this water at the maximum processing rate.
7. Spent fuel pool demineralizers: only those isotopes that have been measured at plants are listed.
  • Based on plant data.

11.1-32a REVISION 14 - DECEMBER 2012

BYRON-UFSAR TABLE 11.1-11 REALISTIC SOURCE TERMS FOR CONCENTRATES AND SPENT RESIN TANKS CONCENTRATES HOLDING SPENT RESIN TANK ACTIVITY* TANK ISOTOPE (Ci/tank) (Ci/tank)

Cr-51 3.01 x 10-2 55.29 Mn-54 5.02 x 10-3 55.97 Fe-55 2.48 x 10-2 143.02 Mn-56 7.18 x 10-9 4.80 x 10-4 Co-58 2.56 x 10-1 748.50 Fe-59 1.57 x 10-2 33.89 Co-60 3.19 x 10-2 189.47 Br-83 1.84 x 10-7 1.41 x 10-3 Br-84 1.08 x 10-9 1.70 x 10-4 Br-85 1.05 x l0-13 l.85 x l0-6 Rb-86 2.60 x l0-4 1.03 Rb-88 1.46 x l0-8 6.65 x 10-3 Rb-89 4.75 x l0-13 2.89 x 10-7 Sr-89 2.07 x 10-3 12.67 Y-89m 1.52 x 10-7 4.55 x 10-7 Sr-90 7.50 x 10-5 9.59 X 10-1 Y-90 1.17 x 10-4 8.09 x 10-5 Sr-91 1.26 x l0-6 7.56 x l0-4 Y-91m 8.11 x 10-7 4.45 x 10-4 Y-91 3.38 x 10-3 8.89 x 10-4 Sr-92 1.97 x 10-8 1.20 x 10-4 Y-92 8.12 x 10-8 1.34 x 10-4 Zr-95 2.86 x 10-3 7.84 x 10-4 Nb-95m 5.55 x 10-7 6.97 x 10-6 Nb-95 2.66 x 10-3 6.86 x 10-4 Mo-99 4.13 x 100 5.46 x 10-1 Tc-99m 2.48 x l00 5.01 x 10-1 Tc-99 7.82 x 10-9 2.24 x 10-8 Ru-103 2.30 x 10-3 5.74 x 10-4 Rh-103m 1.78 x 10-4 5.74 x 10-4 Ru-106 1.75 x 10-4 1.35 x 10-4 Rh-106 5.71 x 10-5 1.35 x 10-4 Te-125m 1.55 x 10-3 3.75 x 10-3 Te-127m 1.44 x 10-2 3.71 x 10-3 Te-127 4.51 x 10-2 4.34 x 10-3 Te-129m 7.13 x 10-2 1.77 x 10-2 Te-129 8.83 x 10-2 1.15 x 10-2 I-129 1.84 x 10-11 7.18 x 10-12 I-130 8.71 x l0-6 3.14 x 10-3 Te-131m 1.18 x l0-1 8.68 x 10-3 Te-131 5.66 x 10-2 1.62 x 10-3 11.1-33 REVISION 2 - DECEMBER 1990

BYRON-UFSAR TABLE 11.1-11 (Cont'd)

CONCENTRATES HOLDING SPENT RESIN TANK ACTIVITY* TANK ISOTOPE (Ci/tank) (Ci/tank)

I-131 4.32 x 10-1 1672.22 Te-132 1.31 1.91 x 10-1

-3 I-132 6.31 X 10 2.18 x 10-1 I-133 6.20 x 10-1 263.21 I-134 8.52 x 10-7 5.01 x 10-2 Cs-134 9.72 x 10-2 1313.35 I-135 1.46 x 10-4 1.55 x 10-1 Cs-136 4.31 x 10-1 76.46 Cs-137 7.06 x 10-2 1023.65 Ba-137m 9.91 x 10-2 968.36 Ba-140 1.45 x 10-3 2.51 La-140 8.01 x 10-3 2.41 x 10-3 Ce-141 3.56 x 10-3 8.82 x 10-4 Ce-143 2.01 x 10-3 1.52 x 10-4 Pr-143 2.47 x 10-3 6.06 x 10-4 Ce-144 1.72 x 10-3 4.45 x 10-4 Pr-144 1.85 x 10-4 4.45 x 10-3 Np-239 5.91 x 10-2 6.93 x 10-3

  • Tank has usable volume of 5200 gallons. Waste from radwaste evaporators is 726,000 gal/yr. Waste from boron recycle system is 8000 gal/yr.

11.1-34

BRAIDWOOD-UFSAR TABLE 11.1-11 REALISTIC SOURCE TERMS FOR HIGH AND LOW ACTIVITY SPENT RESIN TANKS HIGH ACTIVITY SPENT LOW ACTIVITY SPENT RESIN RESIN TANK ISOTOPE TANK (Ci/tank) (Ci/tank)

Cr-51 4.29 x 10-2 157.90 Mn-54 7.56 x 10-2 159.90 Fe-55 408.64 Mn-56 8.70 x 10-4 Co-58 3.80 x 10-1 2132.60 Fe-59 2.48 x 10-2 96.78 Co-60 4.91 x 10-2 541.26 Br-83 2.56 x 10-3 Br-84 3.08 x 10-4 Br-85 3.35 x 10-6 Rb-86 2.95 Rb-88 1.21 x 10-2 Rb-89 5.24 x 10-7 Sr-89 8.25 x 10-3 36.20 Y-89m 8.25 x 10-7 Sr-90 2.47 x 10-4 2.74 Y-90 1.47 x 10-4 Sr-91 1.37 x 10-3 Y-91m 8.06 x 10-4 Y-91 1.61 x 10-3 Sr-92 2.17 x 10-4 Y-92 2.43 x 10-4 Zr-95 1.42 x 10-3 Nb-95m 1.26 x 10-5 Nb-95 1.24 x 10-3 Mo-99 9.91 x 10-1 Tc-99m 9.08 x 10-1 Tc-99 4.06 x 10-8 Ru-103 1.04 x 10-3 Ru-103m 1.04 x 10-3 Ru-106 2.45 x 10-4 Rh-106 2.45 x 10-4 Te-125m 6.86 x 10-4 Te-127m 6.73 x 10-3 Te-127 7.87 x 10-3 Te-129m 3.22 x 10-2 Te-129 2.08 x 10-2 I-129 1.30 x 10-11 I-130 5.70 x 10-3 Te-131m 1.75 x 10-2 Te-131 2.94 x 10-3 11.1-35

BRAIDWOOD-UFSAR TABLE 11.1-11 (Cont'd)

HIGH ACTIVITY SPENT LOW ACTIVITY SPENT RESIN RESIN TANK ISOTOPE TANK (Ci/tank) (Ci/tank)

I-131 5.64 x 10-2 4777.69 Te-132 3.47 x 10-1 I-132 3.96 x 10-1 I-133 1.73 749.31 I-134 9.08 x 10-2 Cs-134 2.91 3747.84 I-135 2.81 x 10-1 Cs-136 1.05 216.80 Cs-137 2.11 2921.40 Ba-137m 1.97 2763.64 Ba-140 4.51 x 10-3 7.15 La-140 4.37 x 10-3 Ce-141 1.60 x 10-3 Ce-143 2.75 x 10-4 Pr-143 1.10 x 10-3 Ce-144 8.06 x 10-4 Pr-144 8.06 x 10-4 Np-239 1.26 x 10-2 11.1-36

B/B-UFSAR TABLE 11.1-12 HAS BEEN INTENTIONALLY DELETED.

11.1-37 REVISION 9 - DECEMBER 2002

B/B-UFSAR TABLE 11.1-13 UPRATED DESIGN-BASIS REACTOR COOLANT FISSION AND CORROSION PRODUCT ACTIVITY Activity* Activity*

Nuclide (µCi/gram) Nuclide (µCi/gram)

H-3 3.50E-00 Y-90 3.01E-05 (maximum)

Y-91m 2.42E-03 Kr-83m 4.39E-01 Y-91 3.44E-04 Kr-85m 1.80E-00 Y-92 8.95E-04 Kr-85 7.11E-00 Y-93 3.03E-04 Kr-87 1.15E-00 Zr-95 4.05E-04 Kr-88 3.35E-00 Nb-95 4.06E-04 Kr-89 9.58E-02 Mo-99 5.29E-01 Xe-131m 3.31E-00 Tc-99m 4.88E-01 Xe-133m 3.65E-00 Ru-103 3.61E-04 Xe-133 2.51E+02 Ru-106 1.22E-04 Xe-135m 4.88E-01 Rh-103m 3.57E-04 Xe-135 7.72E-00 Ag-110m 1.18E-03 Xe-137 1.85E-01 Te-125m 4.14E-04 Xe-138 6.63E-01 Te-127m 2.01E-03 Te-127 9.77E-03 Br-83 8.74E-02 Te-129m 6.85E-03 Br-84 4.59E-02 Te-129 1.04E-02 Br-85 5.47E-03 Te-131m 1.73E-02 I-130 3.29E-02 Te-131 1.17E-02 I-131 1.84E-00 Te-132 1.98E-01 I-132 2.43E-00 Te-134 2.95E-02 I-133 3.35E-00 Ba-137m 1.19E-00 I-134 6.04E-01 Ba-140 2.62E-03 I-135 2.09E-00 La-140 7.66E-04 Ce-141 3.99E-04 Rb-86 2.28E-02 Ce-143 3.65E-04 Rb-88 4.21E-00 Ce-144 2.92E-04 Rb-89 1.93E-01 Pr-143 3.84E-04 Cs-134 1.80E-00 Cs-136 2.89E-00 Cr-51** 5.30E-03 Cs-137 1.26E-00 Mn-54** 4.00E-04 Cs-138 1.02E-00 Fe-55** 2.30E-03 Sr-89 2.75E-03 Fe-59** 5.80E-04 Sr-90 1.20E-04 Co-58** 1.50E-02 Sr-91 4.64E-03 Co-60** 1.90E-03 Sr-92 1.12E-03 NOTES:

  • Parameters used in primary coolnt activity calculation are listed in Table 11.1-1, at operating temperature.
    • Corrosion product activities are based activity levels measured at operating reactors.

11.1-38 REVISION 9 - DECEMBER 2002

B/B-UFSAR 11.2 LIQUID WASTE MANAGEMENT SYSTEMS In general, the liquid radwaste system collects, monitors, and recycles or releases, with or without treatment where appropriate, all potentially radioactive liquid wastes produced by the station during normal operation and maintenance, as well as transient conditions. The only exception is that effluent from the treated water system (Byron only), the condensate polisher sump and the turbine building fire and oil sump, because of minimal activity levels, is normally discharged without being processed through the liquid radwaste system. Effluent from these sumps is monitored by radiation monitors that will automatically terminate sump discharge if unacceptable activity is present in the sump effluent. Corrective action can then be initiated to reroute the sump effluents to the appropriate treatment system prior to release.

11.2.1 Design Bases 11.2.1.1 Safety Design Basis The liquid radwaste system is designed so that liquid radwaste discharged from the site will have radioactive nuclide concentrations well within the limits specified in 10 CFR 20 and 10 CFR 50, Appendix I.

Each liquid radwaste processing stream terminates in a monitor tank (see Drawing M-48A). Since the liquid radwaste system operates on a batch basis, this arrangement allows each treated batch to be sampled to assure that the treatment was sufficient.

If the sample indicates that the waste needs further processing, it is recycled either through the same subsystem or through another subsystem providing a different form of treatment. If the treated waste water is not needed for reuse, the water is sent to either release tank (OWX01T or OWX26T) for discharge.

Each batch is sampled prior to discharge from the release tank to verify that its activity level is within limits for discharge.

The actual discharge to the circulating water blowdown line requires manually opening a remotely operated valve with a keylocked switch. The key for the valve lock is controlled by administrative procedures.

11.2.1.2 Power Generation Design Basis The liquid radwaste system is sized to handle maximum expected liquid waste inputs on the basis of both volume and activity as a result of normal operation, including anticipated abnormal occurrences for Units 1 and 2.

The liquid radwaste system is composed of the following two subsystems:

a. the steam generator blowdown subsystem, and
b. the nonblowdown radwaste subsystem.

11.2-1 REVISION 9 - DECEMBER 2002

B/B-UFSAR These subsystems are extensively crosstied to provide a high degree of availability and reliability.

The purpose of the steam generator blowdown subsystem is to maintain the steam generator water chemistry within specified limits.

The liquid radwaste system is designed to permit recycling of plant water. The stations are designed to minimize noncontaminated inputs from leakage of service water, circulating water, and groundwater into the plant floor drain system.

A cost-benefit analysis is not required for the liquid radwaste system. This is because Commonwealth Edison has complied with the Guides on Design Objectives for Light-Water-Cooled Nuclear Power Reactors proposed in the concluding statement of the position of the regulatory staff in Docket RM-50-2 dated February 20, 1974, pp. 25-30.

11.2.1.3 Expected Radioactive Releases Byron and Braidwood Nuclear stations have updated the core power level twice. First to a core power level of 3586.6 MWt, then to the Measurement Uncertainty Recapture uprate power level of 3645 MWt. The original licensed power level was 3411 MWt. The original expected liquid radwaste effluent data presented in the UFSAR is based on a power level of 3565 MWt.

Expected annual average releases of radionuclides from the liquid radwaste system are shown in Table 11.2-1. These releases were determined by using the NUREG 0017/PWR-GALE computer program (References 1 and 2). Both the original as well as the uprated parameters describing the expected normal operation of one unit of the station are listed in Table 11.2-2. These values were used as input to the computer code for the original analyses.

The impact of core uprate on the effluent releases was evaluated based on an assessment of the changes in input parameters.

Core uprate results in a maximum potential increase of 0.6% in the liquid effluent release concentrations previously reported.

Taking into consideration the accuracy and error bounds of the operational data utilized in NUREG 00017, this small percentage change is well within the uncertainty of the calculated results of the original NUREG 0017 based expected liquid effluent concentrations presented in Table 11.2-4 which remain valid for uprate.

For tables 11.2-1 and 11.2-4 (for Braidwood only), actual data has been used to determine the expected tritium (H-3) release and blowdown concentration values.

11.2-2 REVISION 15 - DECEMBER 2014

B/B-UFSAR 11.2.1.4 10 CFR 50 Comparison Conservatively estimated annual average doses to individuals exposed to radioactive liquid effluents are given in Table 11.2-3. As can be seen from the total dose rates from the various exposure pathways, the numerical guidelines set forth in Appendix I to 10 CFR 50 are satisfied. As discussed in Section 11.2.1.3, this assessment and Table 11.2-3 remain valid for uprate.

For Braidwood only, dose calculations using actual release data and compiled in annual effluent release reports, in accordance with the ODCM, indicate that normal liquid effluents, including tritium, are typically within the estimates of Table 11.2-3 and within guidelines of 10 CFR 50 App.I.

11.2.1.5 10 CFR 20 Comparison Table 11.2-4 compares expected liquid effluent concentrations with 10 CFR 20 limits. It can be seen that the expected effluent concentrations are significantly below the specified limits. As discussed in Section 11.2.1.3, this assessment and Table 11.2-4 remain valid for uprate.

For Braidwood only, actual liquid effluent release data compiled in annual effluent release reports, in accordance with the ODCM, indicate that effluents are maintained within the concentration and dose guidelines of 10 CFR 20.

11.2.1.6 Component Specifications Table 11.2-5 gives the design parameters of various radwaste system components.

11.2-2a REVISION 12 - DECEMBER 2008

B/B-UFSAR 11.2.1.7 Seismic Design and Quality Group The structures housing the liquid radwaste system are Safety Category I for the auxiliary building, and Safety Category II for the turbine building and radwaste building. All components (including tanks, pumps, valves, and piping) of the liquid radwaste system containing radioactive wastes are classified as Quality Group D, with the exception of the containment penetration piping out to and including the second isolation valve from the containment sump pump discharge, which is Quality Group B piping and valves (refer to Section 3.2).

11.2.1.8 Facility and Equipment Design The liquid radwaste system is designed to minimize radiation exposure to operating personnel. Normal operations, maintenance, and nonroutine operations are discussed in the following.

11.2.1.8.1 Maintenance Operations Wherever practicable, components of the liquid radwaste systems are segregated to the maximum extent practical. To reduce radiation exposure to maintenance personnel, components are arranged so that access to a low activity component does not necessitate passing near a high activity component. Instruments are located in low dose rate areas wherever practical to minimize the radiation exposure to maintenance personnel.

Valves, where practicable, are located outside of compartments to minimize radiation exposure from tanks or components during valve maintenance. Most radwaste pumps are equipped with mechanical seals to minimize maintenance.

In general, components which may require maintenance are capable of being flushed prior to maintenance.

11.2.1.8.2 Floor, Wall, and Ceiling Coatings In rooms containing radioactive wastes, the floors, and as necessary, the walls and ceilings, are coated with a two-coat water base epoxy paint for ease of decontamination.

11.2.1.9 Tank Level Control Provisions are made to preclude uncontrolled spills due to tank overflows. The following criteria apply to tanks outside the containment building which may contain radioactive fluids:

a. Tank level instrumentation is provided on most radwaste tanks with readout devices in the radwaste control room. A high-level condition on these tanks will be annunciated.
b. Some radwaste tanks overflow to an adjacent sump, as described in Table 11.2-9. Sumps are provided with 11.2-3 REVISION 2 - DECEMBER 1990

B/B-UFSAR duplex or triplex (redundant) pumps as appropriate.

Sumps are level controlled and logic is provided to start and stop pumps automatically.

c. Provisions for tank level indication, level annunciation, and overflows are given in Table 11.2-9 for all tanks outside the containment building containing potentially radioactive liquids.

11.2.1.10 Prevention of Uncontrolled Releases Based on operating experience during normal operations, it is expected that it will be necessary to make controlled releases of contaminated steam and condensate leakage to the environment.

During normal operations, these releases of radioactive liquids to the environment are from the release tank after processing, as needed, by the liquid radwaste system.

As a batch of waste is processed, the effluent is transferred to an appropriate monitor tank (e.g., blowdown monitor tanks, boric acid monitor tanks, and radwaste monitor tanks) for sampling prior to being transferred to the release tanks or being reprocessed. In the release tanks, the liquid is mixed and sampled for activity prior to discharge. The release tanks discharge must pass through either one of two remotely controlled keylocked valves (0WX353 and 0WX896 on Drawing M-48-1) to be released from the station. Limit switches supply status information on the valve position to the operator at the radwaste control panel. A radiation monitor is provided to automatically close the valves on a high radiation signal.

In addition, effluents from the treated water system, the condensate polisher sump and the turbine building fire and oil sump are released to the environment. While normally considered non-radioactive, these effluents can potentially become contaminated, and the sump effluents are monitored by radiation monitors which will halt sump pump operation if unacceptable activity levels are present in sump effluent.

11.2-4 REVISION 9 - DECEMBER 2002

B/B-UFSAR 11.2.1.11 ETSB-BTP 11-1 Comparison The liquid radwaste system is designed to meet the design criteria of the former Effluent Treatment Systems Branch (ETSB),

Branch Technical Position BTP 11-1, Revision 1, and meets the criteria of Regulatory Guide 1.143, as described in Appendix A.

11.2.2 System Description The liquid radwaste system is shared by both units. Unit 1 and Unit 2, however, have separate equipment and floor drain collection sump systems. Process flow diagrams are shown in Drawing M-48A. The systems are depicted in Drawings M-48-1 through M-48-40.

Inputs to the system are separated according to origin and/or concentrations of radioactivity and chemical impurity. Separate collection tanks are provided for each input stream. The waste is routed from the collection tanks to the appropriate processing paths. The system processes the radioactive liquid waste by various combinations of filtration, evaporation (Braidwood only),

and/or demineralization. At Braidwood, vendor radwaste processing systems may utilize filtration, demineralization, chemical and ultraviolet treatment, and/or reverse osmosis to assist in radioactive liquid waste processing and recycling.

Provisions are made to bypass any processing device. The release tanks cannot be bypassed.

After being processed through the various equipment items, the purified effluent can be reused as secondary cycle makeup at Byron, primary cycle makeup at Braidwood, or released to the environment via the circulating water blowdown line.

11.2-5 REVISION 12 - DECEMBER 2008

B/B-UFSAR The liquid radwaste system is designed to handle wastes generated during design-basis operational occurrences. This is accomplished by providing sufficient process capacity within the subsystems and collection and monitor tanks of adequate size.

The liquid radwaste system consists of two crosstied subsystems:

a. steam generator blowdown subsystem, and
b. non-blowdown radwaste subsystem which treats the following waste streams:
1. auxiliary building equipment drains,
2. auxiliary building floor drains,
3. chemical waste drains,
4. regeneration waste drains,
5. laundry (detergent) drains,
6. turbine building equipment and floor drains when contaminated, and
7. condensate polisher sump when unacceptably contaminated.

Expected concentrations of radioactive nuclides in the various input waste streams to the radwaste subsystems are listed in Table 11.1-6. Expected inventories of radioactive nuclides in major components of the liquid waste system are tabulated in Tables 11.1-7 through 11.1-12. Table 11.2-6 lists the annual average and maximum expected daily flows of each waste stream.

The expected activities in Table 11.1-1 correspond to the annual average daily flows. The activities for the maximum daily flows vary significantly. Actual release data are available in the effluent release reports, which are prepared in accordance with the ODCM.

Table 11.2-7 lists the design-basis decontamination factors for the processing components used in the analysis of the systems.

The original steam generator blowdown prefilters were replaced with larger prefilter units. However, the expected average and maximum waste stream flows and the design basis decontamination factors for the steam generator blowdown prefilters were not revised to account for the larger prefilter volume.

11.2.2.1 Steam Generator Blowdown Subsystem The function of the steam generator blowdown subsystem is to maintain steam generator shell side water chemistry within the 11.2-6 REVISION 7 - DECEMBER 1998

B/B-UFSAR specified limits. Continuous blowdown constantly removes impurities from the steam generator. The flow rate is varied as required to maintain the steam generator water chemistry within the required limits.

At Byron, steam generator blowdown may be sent to the condensate polisher sump to improve secondary chemistry when excessive impurities are present that would quickly exhaust steam generator blowdown demineralizers.

For a further description of the steam generator blowdown subsystem, see Subsections 10.4.8 and 10.4.9.3.1.

11.2-6a REVISION 6 - DECEMBER 1996

B/B-UFSAR The components of the steam generator blowdown treatment subsystem include four blowdown prefilters; four blowdown mixed bed demineralizers; four blowdown demineralizer after filters; three blowdown monitor tanks; and associated pumps, valves, and instrumentation.

11.2.2.1.1 Normal Operation Steam generator blowdown is operated in a normal range of 15 to 90 gpm per steam generator, depending on steam generator chemistry requirements. During normal operation, blowdown is pumped from the steam generator blowdown condenser hotwells through the blowdown prefilters, the blowdown mixed-bed demineralizers, and the blowdown after filters to the condensate storage tanks or respective unit hotwell. In the event of high radioactive material in the purified effluent leaving the blowdown mixed-bed demineralizers, the effluent is diverted to the monitoring tanks. Unit 1 and Unit 2 blowdown is normally segregated, as the Unit 1 and Unit 2 condensate storage tanks are normally segregated.

Blowdown from each steam generator is sampled and analyzed at periodic intervals to determine:

a. If the blowdown flow rate requires adjustment to maintain the steam generator water chemistry limits.
b. If leakage condition exists, either at the main condenser or primary to secondary leakage within one or more steam generators so that remedial action can be taken.
c. If the method of processing the blowdown should be changed.

The time interval between samples of the blowdown from each steam generator depends upon operating experience.

The effluent from each blowdown mixed bed demineralizer is directed through a blowdown afterfilter to a header which is valved so that Unit 1 effluent is normally separated from Unit 2 effluent. Conductivity of each effluent stream from the blowdown mixed bed demineralizers is monitored. The processed liquid can be routed to either Unit 1 or Unit 2 condensate storage tanks as 11.2-7 REVISION 6 - DECEMBER 1996

B/B-UFSAR described above or to a monitor tank. The water in the blowdown monitor tanks is normally drained to the turbine building floor drain system. The water may also be used to sluice blowdown demineralizers or to backwash blowdown demineralizer strainers.

In addition to processing steam generator blowdown, the blowdown mixed bed demineralizers can be used for processing turbine building equipment drains, turbine building floor drains, and for the further processing of the purified effluent from the radwaste subsystems via the radwaste and blowdown monitor tanks. This practice is not recommended for normal operation.

Effluent from the blowdown prefilters of each unit can be diverted to each of the three radwaste evaporators, but normally this flowpath is blocked by a spectacle blank flange (Braidwood only).

11.2.2.1.2 Circulating Water to Secondary System Leakage In the event of condenser tube or tube sheet leakage, the blowdown rate may be increased to 360 gpm (180,000 lbs/hr) total per unit to keep the steam generator shell side chemistry within operating limits. The blowdown rate from the four steam generators would be approximately 90 gpm for each steam generator.

11.2.2.1.3 Primary-to-Secondary-Leakage Concurrent with Failed Fuel The radioisotope concentration in the steam generator blowdown is given in Table 12.2-30 and Table 11.1-6. If primary to secondary leakage occurs in only one steam generator, the blowdown rate from nonleaking steam generators remains high enough to maintain chemistry specifications while the blowdown rate from the leaking steam generator may be increased to the design rate of 90 gpm.

11.2.2.1.4 Primary-to-Secondary Leakage Not Concurrent with Failed Fuel The steam generator blowdown during primary-to-secondary leakage not concurrent with failed fuel will be processed as discussed in Subsection 11.2.2.1.3 during transient operating conditions.

11.2-8 REVISION 12 - DECEMBER 2008

B/B-UFSAR 11.2.2.1.5 Transient Operating Conditions Increased blowdown may be used to keep the steam generator water chemistry within specifications.

11.2.2.2 Nonblowdown Liquid Radwaste Subsystem This processing train collects and treats liquid radwastes from sources other than steam generator blowdown. The mode of operation is batchwise. The nonblowdown liquid radwaste subsystem includes the following input sources:

a. auxiliary building equipment drain,
b. auxiliary building floor drain,
c. chemical waste drain,
d. regeneration waste drain,
e. laundry (detergent) drain,
f. turbine building equipment and floor drain (when contaminated),
g. turbine building fire and oil sump (when contaminated)

(Byron only),

h. condensate polisher sump when unacceptably contaminated, and
i. waste treatment system (when contaminated) (Byron only).

Each drain system except the chemical waste, regeneration waste, and laundry drains, has two drain collection tanks. The chemical waste and regeneration waste drains utilize one tank each plus a shared dual purpose chemical/regeneration waste drain tank.

Waste is usually collected in one of two drain tanks. The contents of the other tank may be sampled or processed. Chemical additions to adjust the wastewater pH or filter aids may be added to improve waste processing efficiency.

Oil separators are provided in those sumps that could potentially have oil in the water. A filter is installed downstream of each drain tank pump discharge header, or drain tank effluent is sent to vendor-installed equipment for filtration as needed.

11.2-9 REVISION 17 - DECEMBER 2018

B/B-UFSAR The radwaste evaporator inlet header receives liquid wastes from the previously mentioned drain tanks. The liquid wastes entering the radwaste evaporator inlet header normally bypass the evaporators and are processed by the radwaste demineralizers or by the vendor demineralizers.

At Byron, nonessential service water to the radwaste evaporator skids has been isolated permanently. Blank plates have also been installed in the inlets to the evaporators to prevent liquid wastes from entering.

The radwaste monitor tanks collect radwaste demineralizer effluent. The tanks' contents will be mixed and sampled prior to being transferred to the release tank.

Wastewater may be routed from the radwaste monitor tanks to vendor taps in the radwaste building for additional processing, as needed, and returned to the installed radwaste system for monitored discharge.

Based on this sample and station water balance considerations, the water may be reprocessed or discharged via the release tanks.

See Table 11.2-6 for the design-basis average and maximum waste stream flows for the various inputs that are discussed in the following. Also refer to Table 11.1-6 for the realistic source terms for these inputs.

At Byron, effluent from the condensate polisher sump, from the turbine building floor and equipment drains (collected in the turbine building fire and oil sump) and from the waste treatment system is processed by the radwaste system if the contamination exceeds effluent limits for the sumps. The sump effluent is monitored by radiation monitors to ensure that ODCM limits are maintained.

At Braidwood, effluent from the condensate polisher sump and from the turbine building floor and equipment drains is processed by the radwaste system if contamination levels exceed effluent limits. The turbine building fire and oil sump effluent is monitored by a radiation monitor to ensure that ODCM limits are maintained.

At Braidwood, a Radwaste Storage Tank (RST) is used to store and manage the release of radioactive liquid waste containing elevated concentrations of tritium. Based on waste water tritium concentration, influenced by the time period of the fuel cycle of each unit, discharge of the waste water may be delayed and the waste water stored in the RST. The tanks contents are sampled to determine the degree of processing required prior to transferring the contents to the liquid radwaste release tanks for discharge.

11.2-10 REVISION 15 - DECEMBER 2014

B/B-UFSAR 11.2.2.2.1 Auxiliary Building Equipment Drain Input sources to the auxiliary building equipment drain tanks include the following:

a. auxiliary building equipment drain collection sumps,
b. reactor coolant drain tank, and
c. spent resin tank drains (Braidwood only).

The waste is normally processed through demineralizers.

11.2-10a REVISION 15 - DECEMBER 2014

B/B-UFSAR 11.2.2.2.2 Auxiliary Building Floor Drain Input sources to the floor drain tanks include leakage from pump seals and stuffing boxes, valve stem packing, equipment overflows, and spills. Oil separators are provided in the subsystem's sumps.

Input sources to the auxiliary building floor drain tanks include the following:

a. reactor cavity sumps,
b. containment floor drain sumps,
c. auxiliary building floor drain sumps,
d. fuel handling building floor drain sumps, and
e. radwaste building sump.

The two tanks are sized to accommodate the maximum accumulation of wastes expected in 1 day. The processing flow paths are the same as in the auxiliary building equipment drain.

11.2.2.2.3 Chemical Waste Drain Input sources to the chemical drain tank and the dual purpose chemical/regeneration drain tank include the following:

a. laboratory drains,
b. fuel handling building decontamination sump,
c. samples containing tritiated water and chemicals required for analysis,
d. drumming station sumps,
e. boric acid processing system,
f. primary water storage tank, and
g. any other high-conductivity radioactive drains.

One tank is provided solely for the chemical drains. A second tank is used as a dual purpose chemical/regeneration waste drain tank. These wastes are processed through a demineralizer.

11.2-11 REVISION 6 - DECEMBER 1996

B/B-UFSAR 11.2.2.2.4 Regeneration Waste Drain Input sources to the regeneration waste drain tank and the dual purpose chemical/regeneration waste drain tank include the following:

a. spent resin sluicing drain header,
b. drumming station decanting tank overflows (Byron only),
c. release tanks (regeneration waste drain tank only),

and

d. tendon tunnel sumps (when determined to be a source of radiation contamination into the fire and oil sump).

The blowdown and radwaste mixed bed demineralizers are replaced as often as is required to maintain the demineralizers effluent water quality.

11.2.2.2.5 Laundry Drain The laundry drain tank collects detergent wastes from the radioactive laundry (Braidwood only), personnel decontamination shower and the TSC drains and showers. These waste streams are sent to the release tanks for release or a radwaste demineralizer for further treatment.

11.2.2.2.6 Turbine Building Equipment Drain Secondary system drains are divided into turbine building equipment drain and turbine building floor drain. The turbine building equipment drain system can recover a large amount of condensate grade water for station reuse.

Two turbine building equipment drain tanks receive water from the turbine building equipment drain sumps. Since this drain water is from the secondary system, the water in the turbine building equipment drains are normally uncontaminated or only very slightly contaminated. The water is normally treated in the wastewater treatment plant for discharge. There are also flowpaths from the turbine building equipment drain system to the radwaste demineralizers and to the liquid release tank.

11.2-12 REVISION 10 - DECEMBER 2004

B/B-UFSAR At Byron, in the event of excessive leakage of the primary coolant into the secondary system, the water may be processed in the waste treatment plant and returned to the release tank for discharge. At Braidwood, in the event of excessive leakage of the primary coolant into the secondary system, the contaminated water may be processed through the coalescer/carbon filters and through additional filtration as needed and discharged via the release tanks, but normally this flowpath is blocked by a spectacle blank flange.

11.2.2.2.7 Turbine Building Floor Drain The two turbine building floor drain tanks collect water from the turbine building floor drain sumps, condensate pit sumps, and essential service water sumps. These wastes are normally nonradioactive, except for tritium, and are released to the environment after filtration via the wastewater treatment (TR) system.

11.2.2.2.8 Turbine Building Fire and Oil Sump Turbine building waste water collected in the fire and oil sump, including equipment and floor drain water, is monitored by a radiation monitor. Water from this sump is normally discharged to the waste treatment system for removal of oil and solids and then released to the environment via the circulating water system and blowdown line. However, if unacceptable radioactive contamination is detected, the sump pumps are automatically stopped and the water may be sent to the liquid radwaste treatment system, via the waste treatment system (Byron only).

If the source of radioactive contamination is determined to be one of the tendon tunnel sumps, either tendon tunnel pump discharge can be sent to the regeneration waste drain tank for processing in the radwaste system. The water may be processed by the waste treatment plant and returned to the release tanks for discharge (Byron only).

11.2.2.2.9 Condensate Polisher Sump Water in the condensate polisher sump is monitored by a radiation monitor on the sump discharge. Water from this sump discharge is normally directed to the circulating water system, and then released to the environment via the blowdown line. If a high radiation signal is detected, pump operation is automatically stopped and major condensate polisher inputs into the sump are automatically isolated. If samples confirm that the water is contaminated, the operator may manually change the valve lineup to send the water to the release tank for a monitored discharge.

11.2.2.2.10 Waste Treatment System The input to the waste treatment system is the Turbine Building Fire and Oil Sump (see 11.2.2.2.8). Water processed by the waste treatment system is normally released to the environment via 11.2-13 REVISION 12 - DECEMBER 2008

B/B-UFSAR the circulating water system and blowdown line. If the radiation monitor on the Turbine Building Fire and Oil Sump should fail, an alarm will be annunciated in the radwaste control room, and the contents of the treated water system would be sampled. If the sample contains radioactive contamination, the system's contents would be pumped to the liquid radwaste system.

11.2-13a REVISION 6 - DECEMBER 1996

B/B-UFSAR 11.2.2.3 Operating Procedures If the contents of a monitor tank are to be released, the required radioactivity analysis is performed prior to transferring the material to the release tank. The liquid is then pumped to a release tank where a sample is again taken and the required analysis is performed. Based on this analysis, the discharge rate is determined so that, when mixed with cooling water blowdown discharges, the water leaving the plant has a radioactivity level less than the applicable effluent concentration as stated in the Technical Specifications. A remotely operated valve with a keylocked switch may then be manually opened so that water can be discharged. The key for the valve lock is controlled by administrative procedures. As a further backup, a radiation detector monitors the liquid in the discharge line prior to the point where the liquid is mixed with the cooling water blowdown to the river. Upon detecting an abnormal level of radiation, a valve on the release tank line immediately upstream of the mixing point closes and an alarm signal is relayed to the control room. A composite sample of the cooling water blowdown is analyzed to verify that radioactive releases conform with the requirements of the Technical Specifications. Records are maintained of radioactive wastes discharged to the environment.

11.2.2.4 Performance Tests Liquid wastes may be monitored before and after each processing step on a batch basis. The equipment is therefore subjected to continuous performance testing.

Data on specific isotope decontamination factors are not conclusive. This system was designed using conservative overall decontamination factors. These decontamination factors are based on guidelines from References 2, 4, and 5.

Through system cross-ties, redundancy of equipment, and excess storage capacity, ample provision has been made for equipment maintenance and for reprocessing treated effluents if required.

11.2.2.5 Control and Instrumentation A large portion of the liquid radwaste system is controlled and monitored from the liquid radwaste control panel (LRCP) located in the radwaste control room. Radwaste and blowdown demineralizers and radwaste evaporator control panels and the liquid/solid radwaste interface are also located in the radwaste control room. The solid radwaste handling system control panel is located in the radwaste building.

11.2-14 REVISION 8 - DECEMBER 2000

B/B-UFSAR Some subsystem operations are controlled by automatic sequencers.

Instrumentation on radwaste system tanks includes, as a minimum, a high level detector for LRCP annunciation, a low level detector for pump cutoff, and LRCP level recording. The system instrumentation is shown in detail on Drawings M-48-1 through M-48-40.

11.2-14a REVISION 9 - DECEMBER 2002

BYRON-UFSAR 11.2.3 Radioactive Releases 11.2.3.1 Release Points All liquid radwaste system effluent paths for radioactive nuclides to the environment are suitably processed, monitored, and recycled or discharged via the release tanks in accordance with procedures outlined in Subsection 11.2.2.3. The radioactive waste release line joins the circulating water blowdown line.

Water from the turbine building fire and oil sump, the condensate polisher sump and the treated water system (Subsections 11.2.2.2.8, 11.2.2.2.9 and 11.2.2.2.10), if not unacceptably contaminated, is discharged after suitable treatment into the circulating water flume, and released via the blowdown line.

11.2.3.2 Dilution Factors At 100% capacity factor and design-basis ambient air conditions, blowdown from the circulating water system serving the two units is approximately 23,000 gpm. On an average annual basis, the circulating water blowdown is expected to be approximately 13,000 gpm, or 2.6 x 1013 cm3 per year. The annual radionuclide release and the concentration in the cooling tower blowdown line are given in Table 11.2-4.

Circulating water blowdown enters the Rock River approximately 50 yards downstream of the intake structure, so releases do not become entrained in makeup water. The circulating water blowdown warming line to the river screen house is isolated during releases to prevent entraining radionuclides in the circulating water and essential service water makeup lines.

11.2.3.3 Estimated Annual Average Doses The estimated total annual release of radionuclides in liquid effluents is given in Table 11.2-1. Using an annual dilution volume of 2.6x1013 cm3, the concentration of each nuclide in the cooling tower blowdown line can be determined. This is shown in Table 11.2-4.

Estimated annual average doses to individuals exposed to radioactive liquid effluents were calculated using the methodology of Regulatory Guide 1.109 (Reference 3). Fish consumption, drinking water, and recreational exposure pathways were considered. Annual use factors for these pathways are given in Table 11.2-8.

In order to obtain a conservative estimate of the radiation doses, no radioactive decay or dilution by river water was taken into consideration.

Estimates of doses to the whole body and to different organs are summarized in Table 11.2-3. As explained in Subsection 11.2.1.4, these estimated doses are all within Appendix I to 10 CFR 50 guidelines. Actual release data are available in the effluent release reports, which are prepared in accordance with the ODCM.

11.2-15 REVISION 7 - DECEMBER 1998

BRAIDWOOD-UFSAR 11.2.3 Radioactive Releases 11.2.3.1 Release Points All controlled liquid radwaste system effluent releases of radioactive nuclides to the environment are suitably processed, monitored, and recycled or discharged via the release tanks in accordance with procedures outlined in Subsection 11.2.2.3. The radioactive waste release line joins the cooling pond blowdown line as indicated in Drawing M-48-1. Water from the fire and oil sump, and condensate polisher sump (Subsections 11.2.2.2.8 and 11.2.2.2.9), if not unacceptably contaminated, is discharged, after suitable treatment, into the cooling pond at the circulating water discharge canal, where it mixes with circulating water prior to release via the blowdown line.

Temporary groundwater remediation activities, where contaminated water from the Exelon Pond and surrounding groundwater is pumped into the circulating water blowdown line at Vacuum Breakers 1 and 2, contribute to the inventory of radioactive nuclides released to the environment via the blowdown line. Periodic sampling of the water is used to monitor the radioactivity of the water that is discharged into the blowdown line.

11.2.3.2 Dilution Factors At 100% capacity factor, blowdown from the cooling lake is expected to be 25,000 gpm on an annual average basis, or 4.98 x 1013 cm3 per year. The annual radionuclide release and the concentration in the cooling pond blowdown line are given in Table 11.2-4. Blowdown isotope concentrations were calculated using cooling pond blowdown flow of 12,000 gpm, which is the normally expected blowdown flow rate without the use of blowdown booster pumps.

Cooling pond blowdown enters the Kankakee River approximately 50 yards downstream of the intake structure, so that releases do not become entrained in makeup water.

11.2.3.3 Estimated Annual Average Doses The estimated total annual release of radionuclides in liquid effluents is given in Table 11.2-1. Using an annual dilution volume of 2.4 x 1013 cm3, the concentration of each nuclide in the discharge canal can be determined. This is shown in Table 11.2-4.

Estimated annual average doses to individuals exposed to radioactive liquid effluents were calculated using the methodology of Regulatory Guide 1.109 (Reference 3). Fish consumption, drinking water, and recreational exposure pathways were considered. Annual use factors for these pathways are given in Table 11.2-8.

In order to obtain a conservative estimate of the radiation doses, no radioactive decay or dilution by river water was taken into consideration.

Estimates of doses to the whole body and to different organs are submitted in Table 11.2-3. As explained in Subsection 11.2.1.4, these estimated doses are all within Appendix I to 10 CFR 50 guidelines. Actual release data are available in the effluent release reports, which are prepared in accordance with the ODCM.

11.2-16 REVISION 11 - DECEMBER 2006

B/B-UFSAR 11.2.4 References

1. Regulatory Guide 1.112, "Calculation of Releases of Radioactive Materials in Gaseous and Liquid Effluents from Light Water-Cooled Power Reactors," U.S. Nuclear Regulatory Commission, April 1976.
2. NUREG-0017, "Calculation of Releases of Radioactive Materials in Gaseous and Liquid Effluent from Pressurized Water Reactors (PWR-GALE Code)," Office of Standards Development, U.S. Nuclear Regulatory Commission, April 1976.
3. Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," U.S.

Nuclear Regulatory Commission, Revision 1, October 1977.

4. ANSI Standard N199, "Liquid Radioactive Waste Processing System for Pressurized Water Reactor Plants," American National Standards Institute, Inc., 1976.
5. WASH-1258, "Numerical Guides for Design Objectives and Limiting Conditions for Operation to Meet the Criteria 'Low as Practicable' for Radioactive Material in Light-Water-Cooled Nuclear Power Reactor Effluents," U.S. Atomic Energy Commission, 1973.

11.2-17

B/B-UFSAR TABLE 11.2-1 EXPECTED ANNUAL AVERAGE RELEASES OF RADIONUCLIDES IN LIQUID EFFLUENTS ANNUAL RELEASES TO DISCHARGE CANAL COOLANT CONCENTRATIONS -------------------------------------------------------------------- ADJUSTED DETERGENT TOTAL NUCLIDE HALF-LIFE PRIMARY SECONDARY BORON RS MISC. WASTES SECONDARY TURB BLDG TOTAL LWS TOTAL WASTES (DAYS) (MICRO CI/ML) (MICRO CI/ML) (CURIES) (CURIES) (CURIES) (CURIES) (CURIES) (CI/YR) (CI/YR) (CI/YR)

CORROSION AND ACTIVATION PRODUCTS CR 51 2.78+01 1.90-03 2.51-07 5.36-06 6.13-09 0.00 2.48-06 7.85-06 6.16-05 0.00 6.16-05 MN 54 3.03+02 3.10-04 6.08-08 9.21-07 1.05-09 0.00 6.05-07 1.53-06 1.20-05 1.00-03 1.01-03 FE 55 9.50+02 1.60-03 2.12-07 4.77-06 5.44-09 0.00 2.11-06 6.89-06 5.40-05 0.00 5.40-05 FE 59 4.50+01 1.00-03 1.55-07 2.88-06 3.29-09 0.00 1.54-06 4.42-06 3.47-05 0.00 3.47-05 CO 58 7.13+01 1.60-02 2.15-06 4.67-05 5.34-08 0.00 2.14-05 6.81-05 5.35-04 4.00-03 4.53-03 CO 60 1.92+03 2.00-03 2.73-07 5.97-06 6.81-09 0.00 2.72-06 8.69-06 6.82-05 8.70-03 8.77-03 ZR 95 6.50+01 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 1.40-03 1.40-03 NB 95 3.50+01 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 2.00.03 2.00-03 NP 239 2.35+00 1.20-03 1.23-07 1.82-06 2.32-09 0.00 1.14-06 2.96-06 2.32-05 0.00 2.32-05 FISSION PRODUCTS BR 83 1.00-01 4.80-03 1.26-07 2.11-09 2.69-09 0.00 2.24-06 2.24-06 1.76-05 0.00 1.76-05 RB 86 1.87+01 8.50-05 1.40-08 5.83-06 1.34-08 0.00 1.38-07 5.98-06 4.69-05 0.00 4.69-05 SR 89 5.20+01 3.50-04 6.17-08 1.01-06 1.16-09 0.00 6.13-07 1.63-06 1.28-05 0.00 1.28-05 MO 99 2.79+00 8.40-02 1.19-05 1.42-04 1.76-07 0.00 1.11-04 2.53-04 1.98-03 0.00 1.98-03 TC 99M 2.50-01 4.80-02 2.18-05 1.35-04 1.65-07 0.00 1.58-04 2.94-04 2.31-03 0.00 2.31-03 RU 103 3.96+01 4.50-05 6.21-09 1.29-07 1.48-10 0.00 6.16-08 1.91-07 1.50-06 1.40-04 1.41-04 RU 106 3.67+02 1.00-05 1.52-09 2.97-08 3.39-11 0.00 1.51-08 4.49-08 3.52-07 2.40-03 2.40-03 AG 110M 2.53+02 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 4.40-04 4.40-04 TE 127 3.92-01 8.50-04 1.31-07 8.46-07 1.24-09 0.00 9.37-07 1.78-06 1.40-05 0.00 1.40-05 TE 129M 3.40+01 1.40-03 1.87-07 3.99-06 4.56-09 0.00 1.85-06 5.85-06 4.59-05 0.00 4.59-05 TE 129 4.79-02 1.60-03 5.39-07 2.56-06 2.94-09 0.00 1.30-06 3.86-06 3.03-05 0.00 3.03-05 I 130 5.17-01 2.10-03 1.53-07 2.95-06 1.18-08 0.00 1.09-05 1.38-05 1.09-04 0.00 1.09-04 TE 131M 1.25+00 2.50-03 2.39-07 2.10-06 3.24-09 0.00 2.07-06 4.17-06 3.27-05 0.00 3.27-05 I 131 8.05+00 2.70-01 3.72-05 6.62-03 7.69-06 0.00 3.63-03 1.03-02 8.04-02 6.20-05 8.05-02 TE 132 3.25+00 2.70-02 3.07-06 4.94-05 6.02-08 0.00 2.90-05 7.85-05 6.16-04 0.00 6.16-04 I 132 9.58-02 1.00-01 9.32-06 5.11-05 3.47-07 0.00 1.77-04 2.28-04 1.79-03 0.00 1.79-03 I 133 8.75-01 3.80-01 3.43-05 1.85-03 3.65-06 0.00 2.80-03 4.66-03 3.66-02 0.00 3.66-02 CS 134 7.49+02 2.50-02 4.01-06 1.86-03 4.25-06 0.00 3.99-05 1.91-03 1.50-02 1.30-02 2.80-02 I 135 2.79-01 1.90-01 9.96-06 2.10-05 5.10-07 0.00 5.33-04 5.54-04 4.35-03 0.00 4.35-03 CS 136 1.30+01 1.30-02 1.78-06 8.59-04 1.98-06 0.00 1.75-05 8.79-04 6.89-03 0.00 6.89-03 CS 137 1.10+04 1.80-02 2.67-06 1.34-03 3.06-06 0.00 2.65-05 1.37-03 1.08-02 2.40-02 3.48-02 BA 137M 1.77-03 1.60-02 7.67-06 1.26-03 2.87-06 0.00 2.48-05 1.29-03 1.01-02 0.00 1.01-02 CE 144 2.84+02 3.30-05 6.08-09 9.80-08 1.12-10 0.00 6.05-08 1.59-07 1.24-06 5.20-03 5.20-03 ALL OTHERS 2.53-01 2.02-06 3.69-06 7.27-09 0.00 2.84-06 6.54-06 5.13-05 0.0 5.13-05 TOTAL (EXCEPT TRITIUM) 1.46+00 1.50-04 1.43-02 2.49-05 0.00 7.60-03 2.19-02 1.72-01 6.23-02 2.34-01 TRITIUM RELEASE 300 CURIES PER YEAR (BYRON), 750 CURIES PER YEAR (BRAIDWOOD) 11.2-18 REVISION 12 - DECEMBER 2008

B/B-UFSAR TABLE 11.2-2 PARAMETERS USED IN THE GALE-PWR COMPUTER PROGRAM (ORIGINAL & UPRATED) - NOTE 1

1) Reactor type PWR
2) Thermal power level (MWt) 3565.0 (3586.6)
3) Mass of coolant in the primary system (106 gms) 242 (247.7)
4) Primary system letdown rate (gpm) 75.0
5) Letdown cation demineralizer flow (gpm) 7.5
6) Number of steam generators 4.0
7) Total steam flow (106 lb/hr) 15.0 (16.04)
8) Mass of steam in each steam generator (103 lb) 9.1 (6.039)
9) Mass of liquid in each steam generator (103 lb) 117.0 (114.465)
10) Total mass of secondary coolant (103 lb) 2023.0
11) Steam generator blowdown rate (103 lb/hr) 30.0 The steam generator blowdown is recycled to the condensate system after treatment in the blowdown system. Condensate demineralizers are not used.
12) Condensate demineralizer regeneration time (days) 0.0
13) Fraction of feedwater through the condensate demineralizers 0.0
14) Annual average liquid radwaste dilution flow (103 gpm)

Cooling tower blowdown, Byron 13.0 Cooling lake blowdown, Braidwood 12.0*

15) Shim bleed rate (gpd) 2160.0
16) Decontamination Factors for the shim bleed system:

Iodine - 103, Cesium - 2 x 103, Others - 104 11.2-19 REVISION 10 - DECEMBER 2004

B/B-UFSAR TABLE 11.2-2 (Cont'd)

17) Shim bleed system - Collection time (days) 0.60 Processing time (days) 2.00 Fraction discharged 0.10
18) Equipment drains input (gpd) 2800.0 Fraction of primary coolant activity 0.005
19) Decontamination Factors for Equipment Drains Processing:

Iodine - 105, Cesium - 2 x 104, Others - 106

20) Equipment drains - Collection time (days) 2.30 Processing time (days) 0.15 Fraction discharged 0.10
21) Clean waste input (gpd) 2800.0 Fraction of primary coolant activity 0.002
22) Decontamination Factors for Clean Waste Processing:

Iodine - 105, Cesium - 2 x 104, Others - 106

23) Clean waste - Collection time (days) 2.30 Processing time (days) 0.15 Fraction discharged 0.10
24) Dirty wastes input (gpd) 2800.0 Fraction of primary coolant activity 0.0068
25) Decontamination Factors for Dirty Waste Processing:

Iodine - 105, Cesium - 2 x 104, Others - 106

26) Dirty wastes - Collection time (days) 4.60 Processing time (days) 0.11 Fraction discharged 0.10
27) Blowdown fraction processed 1.00
28) Decontamination Factors for Blowdown Processing:

Iodine - 102, Cesium - 10, Others - 102

29) Blowdown - Collection time (days) 0.03 Processing time (days) 0.03 Fraction discharged 0.10 11.2-20

B/B-UFSAR TABLE 11.2-2 (Cont'd)

30) Condensate demineralizer regenerant flow (gpd) 0.00
31) Decontamination Factors for Regenerant Processing:

Iodine - 1.0, Cesium - 1.0, Others - 1.0

32) Regenerant - Collection time (days) 0.00 Processing time (days) 0.00 Fraction discharged 0.00
33) There is not continuous stripping of full letdown flow.
34) Holdup time for xenon (days) 45.0
35) Holdup time for krypton (days) 45.0
36) Fill time for gas decay tanks (days) 43.0
37) The waste gas system does not have a HEPA filter.
38) The auxiliary building vent system does have a HEPA filter, but it does not have a charcoal filter.
39) Containment volume (106 ft3) 2.9
40) Containment atmosphere cleanup rate (103 cfm) 16.0
41) The containment shutdown purge line has a HEPA filter, but it does not have a charcoal filter.
42) There is no continuous low volume purge of the containment.
43) There is no blowdown tank vent.
44) Fraction of iodine released from the main condenser air ejector ** 1.00**
45) Reciprocal of the detergent waste processing decontamination factor 1.00 11.2-21 REVISION 17 - DECEMBER 2018

B/B-UFSAR TABLE 11.2-2 (Contd)

  • Original design and without the use of CW blowdown booster pumps installed at Braidwood.
    • The Off-Gas filter unit does not provide an Iodine removal mechanism. The iodine removal capability of the Off-Gas system has been evaluated for this condition and the off gas flow bypassing charcoal filter found acceptable, per calculation BRW-99-0468-M (Braidwood) / BYR16-012 (Byron).

Note 1: Parameters that changed due to uprate are presented in

().

11.2-21a REVISION 17 - DECEMBER 2018

BYRON-UFSAR TABLE 11.2-3 PATHWAYS DOSES FROM LIQUID EFFLUENTS (BYRON)

EXPOSURE PATHWAY ORGAN DOSE (mrem/yr/unit)1 Drinking Water Whole Body 7.36 x 10-1 GI-LLI 6.87 x 10-1 Thyroid 3.49 x 10+0 Bone 7.03 x 10-2 Fish Consumption Whole Body 4.54 x 10-1 GI-LLI 7.43 x 10-2 Thyroid 1.03 x 10-1 Bone 3.4 x 10-1 Shoreline Recreation Skin 9.15 x 10-3 Whole Body 7.83 x 10-3 Swimming & Boating Skin 3.38 x l0-4 Whole Body 2.56 x 10-4 1

All activities are assumed to take place in the discharge canal.

No credit is taken for dilution of effluents in the Rock River.

11.2-22

BRAIDWOOD-UFSAR TABLE 11.2-3 PATHWAYS DOSES FROM LIQUID EFFLUENTS (BRAIDWOOD)

EXPOSURE PATHWAY ORGAN DOSE (mrem/yr/unit)2 Drinking Water Whole Body 9.88 x 10-1 GI-LLI 9.22 x 10-1 Thyroid 4.69 x 10+0 Bone 9.44 x 10-2 Fish Consumption Whole Body 6.09 x 10-1 GI-LLI 9.97 x 10-2 Thyroid 1.38 x 10-1 Bone 4.67 x 10-1 Shoreline Recreation Skin 1.23 x 10-2 Whole Body 1.05 x 10-2 Swimming and Boating Skin 4.53 x 10-4 Whole Body 3.42 x 10-4 2

All activities are assumed to take place in the discharge canal. No credit is taken for dilution of effluents in the Kankakee River.

11.2-23

BYRON-UFSAR TABLE 11.2-4 COMPARISON OF EXPECTED LIQUID EFFLUENT CONCENTRATIONS TO 10 CFR 20 LIMITS EXPECTED* BLOWDOWN** 10 CFR 20 RELEASE CONCENTRATION LIMIT***

ISOTOPE (Ci/yr/unit) (ci/ml) (Ci/ml)

H 3 3.00+02 1.16-05 3.00-03 Cr 51 6.20-05 2.39-12 2.00-03 Mn 54 1.00-03 3.86-11 1.00-04 Fe 55 5.40-05 2.08-12 8.00-04 Fe 59 3.50-05 1.35-12 5.00-05 Co 58 4.50-03 1.74-10 9.00-05 Co 60 8.80-03 3.40-10 3.00-05 Br 83 1.80-05 6.59-13 3.00-06 Rb 86 4.70-05 1.81-12 2.00-05 Sr 89 1.30-05 5.02-13 3.00-06 Zr 95 1.40-03 5.40-11 6.00-05 Nb 95 2.00-03 7.72-11 1.00-04 Mo 99 2.00-03 7.72-11 4.00-05 Tc 99m 2.30-03 8.88-11 3.00-03 Ru 103 1.40-04 5.40-12 8.00-05 Ru 106 2.40-03 9.26-11 1.00-05 Ag 110m 4.40-04 1.70-11 3.00-05 Te 127 1.40-05 5.40-13 2.00-04 Te 129m 4.60-05 1.78-12 2.00-05 Te 129 3.00-05 1.16-12 8.00-04 Te 131m 3.30-05 1.27-12 4.00-05 Te 132 6.20-04 2.39-11 2.00-05 I 130 1.10-04 4.24-12 3.00-06 I 131 8.00-02 3.09-09 3.00-07 I 132 1.80-03 6.95-11 8.00-06 I 133 3.70-02 1.43-09 1.00-06 I 135 4.30-03 1.66-10 4.00-06 Cs 134 2.80-02 1.08-09 9.00-06 Cs 136 6.90-03 2.66-10 9.00-05 Cs 137 3.50-02 1.35-09 2.00-05 Ce 144 5.20-03 2.01-10 1.00-05 Np 239 2.30-05 8.88-13 1.00-04 Calculated using the PWR-GALE computer program described in NUREG-0017. The actual data are available in the effluent release reports, which are prepared in accordance with the ODCM.

Annual average cooling tower blowdown = 29.0 cfs.

Limits used in the comparison are those that were in effect at the time of the analysis.

11.2-24 REVISION 7 - DECEMBER 1998

BRAIDWOOD-UFSAR TABLE 11.2-4 COMPARISON OF EXPECTED LIQUID EFFLUENT CONCENTRATIONS TO 10 CFR 20 LIMITS EXPECTED* BLOWDOWN** 10 CFR 20 RELEASE CONCENTRATION LIMIT***

ISOTOPE (Ci/yr/unit) (Ci/ml) (Ci/ml)

H 3 7.50+02 3.88-05 3.00-03 Cr 51 6.20-05 3.21-12 2.00-03 Mn 54 1.00-03 5.18-11 1.00-04 Fe 55 5.40-05 2.80-12 8.00-04 Fe 59 3.50-05 1.81-12 5.00-05 Co 58 4.50-03 2.33-10 9.00-05 Co 60 8.80-03 4.56-10 3.00-05 Br 83 1.80-05 9.33-13 3.00-06 Rb 86 4.70-05 2.44-12 2.00-05 Sr 89 1.30-05 6.74-13 3.00-06 Zr 95 1.40-03 7.25-11 6.00-05 Nb 95 2.00-03 1.04-10 1.00-04 Mo 99 2.00-03 1.04-10 4.00-05 Tc 99m 2.30-03 1.19-10 3.00-03 Ru 103 1.40-04 7.25-12 8.00-05 Ru 106 2.40-03 1.24-10 1.00-05 Ag llOm 4.40-04 2.28-11 3.00-05 Te 127 1.40-05 7.25-13 2.00-04 Te 129m 4.60-05 2.38-12 2.00-05 Te 129 3.00-05 1.55-12 8.00-04 Te 131m 3.30-05 1.71-12 4.00-05 Te 132 6.20-04 3.21-11 2.00-05 I 130 1.10-04 5.70-12 3.00-06 I 131 8.00-02 4.14-09 3.00-07 I 132 1.80-03 9.33-11 8.00-06 I 133 3.70-02 1.92-09 1.00-06 I 135 4.30-03 2.23-10 4.00-06 Cs 134 2.80-02 1.45-09 9.00-06 Cs 136 6.90-03 3.57-10 9.00-05 Cs 137 3.50-02 1.81-09 2.00-05 Ce 144 5.20-03 2.69-10 1.00-05 Np 239 2.30-05 1.19-12 1.00-04 Calculated using the PWR-GALE computer program described in NUREG-0017 (Except H-3. Tritium value is based on actual data.)

The actual data are available in the effluent release reports, which are prepared in accordance with the ODCM.

Annual average cooling lake blowdown = 13.4 cfs per unit.

Original design and without the use of CW blowdown booster pumps installed at Braidwood.

Limits used in the comparison are those that were in effect at the time of the analysis.

11.2-25 REVISION 12 - DECEMBER 2008

B/B-UFSAR TABLE 11.2-5 LIQUID RADWASTE SYSTEM COMPONENTS AND DESIGN PARAMETERS PER STATION DESIGN PRESSURE DESIGN MATERIALS OF EQUIPMENT (psig) TEMP (F) CAPACITY NUMBER CONSTRUCTION I. Blowdown mixed bed 150 110 283 gpm* 4 316-SS demineralizers II. Radwaste mixed bed 150 110 45 gpm 3 316-SS demineralizers III. Cartridge filters:

1. Chemical drain 150 140 130 gpm 1 316-SS
2. Regeneration waste 150 140 130 gpm 1 316-SS drain
  • Hydraulic limit. The kinetic limit will vary based on resin types and water chemistry.

11.2-26 REVISION 11 - DECEMBER 2006

B/B-UFSAR TABLE 11.2-5 (Cont'd)

DESIGN PRESSURE DESIGN MATERIALS OF EQUIPMENT (psig) TEMP (F) CAPACITY NUMBER CONSTRUCTION

3. Blowdown prefilters 250 120 360 gpm 4 Housing shell -

(Byron) 304-SS internal components -

316-SS Blowdown prefilters 150 250 250 gpm 4 Housing shell -

(Braidwood) carbon steel internal components -

304-SS

4. Blowdown 150 140 250 gpm 4 304-SS after-filters
5. Auxiliary Bldg. 150 180 250 gpm 1 304-SS floor drains
6. Auxiliary Bldg. 150 180 250 gpm 1 304-SS equipment drain
7. Turbine Bldg. 150 140 130 gpm 1 304-SS floor drains
8. Turbine Bldg. 150 180 130 gpm 1 304-SS equipment drains
9. Laundry drain 150 180 130 gpm 1 304-SS
10. Radwaste deminer- 150 180 250 gpm 3 304-SS alizer afterfilter 11.2-27 REVISION 8 - DECEMBER 2000

B/B-UFSAR TABLE 11.2-5 (Cont'd)

DESIGN PRESSURE DESIGN MATERIALS OF EQUIPMENT (psig) TEMP (F) CAPACITY NUMBER CONSTRUCTION VI. Tanks:

1. Chemical drain Atmos. 200 6,000 gal 1 304-SS
2. Dual Purpose Chemi- Atmos. 200 10,000 gal 1 304-SS cal/Regeneration waste Drain 11.2-27a REVISION 7 - DECEMBER 1998

B/B-UFSAR TABLE 11.2-5 (Cont'd)

DESIGN PRESSURE DESIGN MATERIALS OF EQUIPMENT (psig) TEMP (F) CAPACITY NUMBER CONSTRUCTION

3. Regeneration waste Atmos. 200 30,000 gal 1 304-SS Drain (Byron) 20,000 gal (Braidwood)
4. Auxiliary Bldg. 50 200 8,000 gal 2 304-SS equipment drain
5. Auxiliary Bldg. Atmos. 150 8,000 gal 2 304-SS floor drain
6. Turbine Bldg. Atmos. 130 12,000 gal 2 C.S.

equipment drain

7. Turbine Bldg. Atmos. 150 12,000 gal 2 C.S.

floor drain

8. Laundry drain Atmos. 200 4,000 gal 1 C.S.
9. Laundry drain Atmos. 130 2,000 gal 2 C.S.

storage

10. Blowdown monitor Atmos. 150 20,000 gal 3 304-SS
11. Radwaste monitor Atmos. 150 20,000 gal 2 304-SS
12. Release Atmos. 150 30,000 gal 2 304-SS 11.2-28 REVISION 7 - DECEMBER 1998

B/B-UFSAR TABLE 11.2-5 (Cont'd)

DESIGN PRESSURE DESIGN MATERIALS OF EQUIPMENT (psig) TEMP (F) CAPACITY NUMBER CONSTRUCTION

13. Concentrates (Byron) Atmos. 250 6,400 gal 1 316L-SS holding
14. Spent Resin (Byron) 125 120 5,000 gal 1 304-SS
15. Low Activity Spent 15 120 6,400 gal 1 316L-SS Resin (Braidwood)
16. High Activity Spent 125 120 5,000 gal 1 304-SS Resin (Braidwood)
17. Radwaste Storage Atmos. 120 500,000 gal 1 304L-SS Tank (Braidwood) 11.2-29 REVISION 13 - DECEMBER 2010

B/B-UFSAR TABLE 11.2-5 (Cont'd)

DISCHARGE MATERIALS OF EQUIPMENT CAPACITY HEAD (ft) NUMBER CONSTRUCTION VII. Pumps:

1. Chemical drain tank 60 gpm 235 2 316-SS
2. Dual purpose chemical/ 60 gpm 235 2 316-SS Regeneration waste drain tank
3. Regeneration waste 60 gpm 235 2 316-SS drain tank
4. Auxiliary Bldg. equip. 60 gpm 235 2 304-SS drain tank
5. Auxiliary Bldg. floor 60 gpm 235 2 304-SS drain tank
6. Turbine Bldg. equip. 90 gpm 235 2 304-SS drain tank
7. Turbine Bldg. floor 90 gpm 235 2 304-SS drain tank
8. Laundry drain tank 30 gpm 200 1 C.S.
9. Laundry drain storage 25 gpm 150 2 C.S.

tank

10. Blowdown monitor tank 350 gpm 175 3 304-SS
11. Radwaste monitor tank 350 gpm 175 2 304-SS 11.2-30

B/B-UFSAR TABLE 11.2-5 (Cont'd)

DISCHARGE MATERIALS OF EQUIPMENT CAPACITY HEAD (ft) NUMBER CONSTRUCTION

12. Release tank 500 gpm 100 2 304-SS
13. Blowdown condenser 180 gpm 1050 4 304-SS
14. Spent resin (Byron) 120 gpm 115 2 ACI CD4MCu-SS
15. Spent resin (Braidwood) 65 gpm 175 2 BUNA N, 316-SS
16. Radwaste Storage 150 gpm 65 1 316-SS Recirculating Pump (Braidwood)
17. Brine Tank Transfer 200 gpm 100 1 316-SS Pump (Braidwood)

NOTE:Radwaste Evaporator Components have been intentionally deleted from this table. Braidwood and Byron stations do not intend to use this equipment.

11.2-31 REVISION 15 - DECEMBER 2014

B/B-UFSAR TABLE 11.2-6 DESIGN-BASIS ANNUAL AVERAGE AND MAXIMUM WASTE STREAM FLOWS (Two Units)

AVERAGE DAILY MAXIMUM DAILY WASTE INPUT SOURCES FLOW (gpd) FLOW (gpd)

Steam generator blowdown 259,200* 604,800**

Auxiliary building equipment 5,600 16,000 drain Auxiliary building floor 5,600 16,000 drain Chemical waste drain 2,100 6,000 Laundry drain 1,400 4,000 Turbine building equipment 4,200 12,000 drain Turbine building floor 4,200 12,000 drain Condensate polisher 25,300 90,700 Turbine building fire and oil 62,000 150,000 sump Waste treatment system 36,300 56,900 Based on average of 28 days primary to secondary leakage (1956 gpm/two units), 28 days condenser to secondary leakage (420 gpm/two units) and 309 days of normal operation (120 gpm/two units).

Based on condenser to secondary leakage of 420 gpm/two units.

11.2-32 REVISION 7 - DECEMBER 1998

B/B-UFSAR TABLE 11.2-7 DESIGN-BASIS PROCESS DECONTAMINATION FACTORS EVAPORATORS CLEAN WASTE BLOWDOWN DISTILLATE FILTERS DEMINER- DEMINER- DEMINER-ELEMENT (A) (B) ALIZERS ALIZERS EVAPORATORS ALIZERS H 1 1 1 1 1 1 Cr 10 1 100 100 104 10 Mn 10 1 100 100 104 10 Fe 10 1 100 100 104 10 Co 10 1 100 100 104 10 Br 1.0 1 100 100 104 10 Kr 1 1 1 1 1 1 Rb 1.0 1 2 10 104 10 Sr 1.0 1 100 100 104 10 Y 1.0 1 100 100 104 10 Zr 10 1 100 100 104 10 Nb 10 1 100 100 104 10 Mo* 10 1 100 100 104 10 Tc* 1.0 1 100 100 104 10 Ru 1.0 1 100 100 104 10 Rh 1.0 1 100 100 104 10 Te 1.0 1 100 100 104 10 I 1.0 1 100 100 103 10 Xe 1 1 1 1 1 1 Cs 1.0 1 2 10 104 10 Ba 1.0 1 100 100 104 10 11.2-33 REVISION 10 - DECEMBER 2004

B/B-UFSAR TABLE 11.2-7 (Cont'd)

EVAPORATORS CLEAN WASTE BLOWDOWN DISTILLATE FILTERS DEMINER- DEMINER- DEMINER-ELEMENT (A) (B) ALIZERS ALIZERS EVAPORATORS ALIZERS La 1.0 1 100 100 l04 10 Ce 1.0 1 100 100 104 10 Pr 1.0 1 100 100 104 10 Np 1.0 1 100 100 104 10 Basis for Decontamination Factors:

1. Filters:

(A) Is used for filter source term calculations only.

(B) Is used for other calculations. (Table 1-3, NUREG-0017, PWR GALE)

2. (A) Radwaste Demineralizers:

(Table 1-3, NUREG-0017, PWR GALE and Table 1 ANSI N199-1976)

(B) Blowdown Demineralizers (Table 1-3, NUREG-0017, PWR GALE)

3. Evaporators:

(Table 1-3, NUREG-0017, PWR GALE and Table 1 ANSI N199-1976)

4. Evaporator Distillate Demineralizers:

(Table 1-3, NUREG-0017, PWR GALE) 11.2-34 REVISION 3 - DECEMBER 1991

B/B-UFSAR TABLE 11.2-8 CONSUMPTION FACTORS FOR THE MAXIMUM EXPOSED INDIVIDUAL PATHWAY CHILD TEEN ADULT UNITS Fruits, vegetables and grains* 520.0 630.0 520.0 kg/yr Leafy vegetables** 26 42 64 kg/yr Milk** 330 400 310 l/yr Meat and poultry** 41 65 110 kg/yr Sport fish** 6.9 15.8 21 kg/yr Drinking water** 508 508 728 l/yr Shoreline activities*** - - 15.0 hr/yr Boating/swimming*** - - 29.0/6.0 hr/yr Inhalation*,** 3700.0 8000.0 8000.0 m3/yr 1400.0 (Infant)

From Regulatory Guide 1.109, Table E-5 (Reference 3).

From Offsite Dose Calculation Manual, Revision 1.2, Table D-10.

From HERMES as used in Zion Station annual and semiannual reports on station radioactive waste, environmental monitoring, and occupational personnel radiation exposure.

11.2-35 REVISION 8 - DECEMBER 2000

B/B-UFSAR TABLE 11.2-9

SUMMARY

OF TANK LEVEL INDICATION, ANNUNCIATORS, AND OVERFLOWS FOR TANKS OUTSIDE OF CONTAINMENT POTENTIALLY CONTAINING RADIOACTIVE LIQUIDS LEVEL INDICATOR AND/OR RECORDER TANK LOCATION ANNUNCIATOR OVERFLOW TO Primary Water Storage Main Control Room* AL, AH, AHH Turbine Building Radwaste Control Panel None Equipment Drains Sump Condensate Storage Main Control Room* AL, AH Turbine Building Radwaste Control Panel None Equipment Drains Makeup Demineralizer Panel AL, AH Sump Turbine Building Equipment Radwaste Control Panel AL, AH None Drain Turbine Building Floor Drain Radwaste Control Panel AL, AH None Chemical Drain Radwaste Control Panel AL, AH None Chemical/Regeneration Waste Radwaste Control Panel AL, AH None Drain Regeneration Waste Drain Radwaste Control Panel AL, AH Auxiliary Building Floor Drain System*

Auxiliary Building Equipment Radwaste Control Panel AL, AH None Drain Auxiliary Building Floor Drain Radwaste Control Panel AL, AH None 11.2-36 REVISION 10 - DECEMBER 2004

B/B-UFSAR TABLE 11.2-9 (Cont'd)

LEVEL INDICATOR AND/OR RECORDER TANK LOCATION ANNUNCIATOR OVERFLOW TO Laundry Drain Radwaste Control Panel AL, AH None Laundry Waste Storage Radwaste Control Panel AL, AH Auxiliary Building Equipment Drains Sump Blowdown Monitor Radwaste Control Panel AL, AH Turbine Building Equipment Drains Sump Radwaste Monitor Radwaste Control Panel AL, AH Auxiliary Building Equipment Drains Sump Release Radwaste Control Panel AL, AH Regeneration Waste Drain Tank or Auxiliary Building Floor Drain System*

Concentrates Holding (Byron) Radwaste Control Panel AL, AH None Spent Resin (Byron) Radwaste Control Panel AL, AH None Decant (Byron) Solid Radwaste Panel AL, AH Regeneration Waste Drain Tank Vacuum Deaerator Catch Radwaste Control Panel AL, AH None High Activity Spent Resin Radwaste Control Panel AHH None (Braidwood) 11.2-37 REVISION 10 - DECEMBER 2004

B/B-UFSAR TABLE 11.2-9 (Cont'd)

LEVEL INDICATOR AND/OR RECORDER TANK LOCATION ANNUNCIATOR OVERFLOW TO Low Activity Spent Resin Radwaste Control Panel AHH None (Braidwood)

Auxiliary Building Borated Radwaste Control Panel AL, AH None Equipment Drain Auxiliary Building Waste Local AH (Radwaste Panel) None Oil Collection Refueling Water Storage Main Control Room* AH, AL, ALL, ALLL Recycle Holdup Tank Volume Control Main Control Room* AH, AL None Local None Recycle Holdup Main Recycle Panel AH, AL None Local None Boric Acid Main Control Room* AH, AL Auxiliary Building Local None Equipment Drains Boric Acid Batching Local AH, AL (Main Control Recycle Holdup Tank Room)

Radwaste Storage Radwaste Control AL, ALL, AH, AHH 3000 gal overflow tank (Braidwood) Panel 11.2-38 REVISION 13 - DECEMBER 2010

B/B-UFSAR TABLE 11.2-9 (Cont'd)

LEVEL INDICATOR AND/OR RECORDER TANK LOCATION ANNUNCIATOR OVERFLOW TO Boric Acid Monitor Boron Recovery Panel Local AH, AL Auxiliary Building None Equipment Drains NOTES:

AL - Alarm Low AH - Alarm High ALL - Alarm Low Low AHH - Alarm High High ALLL - Alarm Low Low Low *General Services Panel 11.2-39

B/B-UFSAR 11.3 GASEOUS WASTE MANAGEMENT SYSTEMS This section describes the capabilities of the plant to collect, process, store, and dispose of gaseous radioactive wastes generated as a result of normal operation including anticipated operation occurrences. Total gaseous releases from the plant for normal operation, including anticipated operational occurrences, and the resulting offsite doses are also included. Design and operating features of the gaseous waste processing system (GWPS) are presented. Appropriate chapters for other systems which may handle radioactive gases are referenced.

11.3.1 Design Bases Radioactive gaseous treatment systems are designed to ensure that the total plant gaseous release is as low as reasonably achievable and meet the requirements of Appendix I of 10 CFR 50. The systems have adequate capacity and redundancy to meet discharge concentration limits of 10 CFR 20 during periods of design-basis fuel leakage. In compliance with General Design Criterion 64 all gaseous effluent discharge paths are monitored for radioactivity.

The GWPS meets the requirements of General Design Criterion 60 by providing long-term holdup capacity, thus precluding the release of radioactive effluents during unfavorable environmental conditions. (See Section 3.1 for a discussion of General Design Criteria.) Component design parameters for the GWPS are given in Tables 11.3-1 and 11.3-2. Design codes and seismic design requirements are also supplied in Chapter 3.0. The protection of plant personnel is considered in component design and system layout. The GWPS is not designed explosion-proof but rather is supplied with instrumentation, particularly hydrogen and oxygen monitors, to preclude the buildup of an explosive mixture.

The gaseous radwaste system meets all of the code criteria specified in Regulatory Guide 1.143. Additional design bases for plant ventilation systems and condenser evacuation system are given in Sections 9.4 and 10.4, respectively.

11.3-1 REVISION 6 - DECEMBER 1996

B/B-UFSAR 11.3.2 System Description 11.3.2.1 System Design The gaseous waste processing system (GWPS) processes hydrogen stripped from the reactor coolant and nitrogen from the closed cover gas system. The components connected to the GWPS are limited to those which contain no air or aerated liquids in order to prevent accumulation of oxygen in the system. Further, the GWPS is maintained at a pressure above atmospheric to avoid intrusion of air. The system is not designed for the addition of oxygen in order to recombine oxygen and hydrogen; therefore, no control functions are associated with the oxygen monitor. Hence, the GWPS will normally not contain oxygen and special design precautions are taken in order to avoid unintentional intrusion of oxygen.

The GWPS has two independent gas analyzing systems. One is a sequencing hydrogen and oxygen monitoring loop (At Byron, the system has a manual switch to select the sample points) which can sample the gas decay tanks and/or the components connected to the GWPS. The other gas analyzing system is an oxygen monitor that samples the waste gas compressor discharge to the inservice gas decay tank. Both gas analyzing systems have independent high oxygen concentration alarms at 2%, which annunciate at the local panel, as well as in the radwaste control room. In addition, each gas analyzing system provides locations at which manual grab samples may be taken.

During normal GWPS operation, the gas analyzers monitor the contents of the inservice gas decay tank and the waste gas compressor discharge for hydrogen and oxygen concentrations. Any high oxygen concentration entering the GWPS will be sensed by the compressor discharge analyzer which will alarm so that corrective actions can be taken before the contents of the gas decay tank exceed the limits for explosive gas mixtures. The sequencing analyzer system can be utilized (At Byron, the selector switch allows selection of sample point) to determine the source of the high oxygen and hydrogen concentrations.

Based on the above, the two analyzer system provides adequate prevention of explosive gas mixtures in the GWPS.

The gaseous waste processing system consists of two waste-gas compressor packages, six gas decay tanks, and the associated piping, valves and instrumentation. The equipment serves both units. The system is shown on the piping and instrumentation diagram Drawing M-69 and the process flow diagram Figure 11.3-2.

Table 11.3-3 gives process parameters for key locations in the system.

The bases used for estimating the process parameters are given in Table 11.3-4.

11.3-2 REVISION 9 - DECEMBER 2002

B/B-UFSAR Gaseous wastes are received from the following: degassing of the reactor coolant and purging of the volume control tank prior to a cold shutdown; displacing of cover gases caused by liquid accumulation in the tanks connected to the vent header; purging of some equipment; sampling and gas analyzer operation; and operating the boron recycle system.

Auxiliary Services The auxiliary services portion of the gaseous waste processing system consists of an automatic gas analyzer and its instrumentation, valves, and tubing; and a nitrogen and a hydrogen supply manifold with the necessary instrumentation, valves, and piping.

The automatic (At Byron, the waste) gas analyzer may be used to determine the quantity of oxygen and hydrogen in the volume control tanks, pressurizer relief tanks, boron recycle holdup tanks, boron recycle evaporators, gas decay tanks, reactor coolant drain tanks, and spent resin storage tank, and provides an alarm on high oxygen concentration.

The nitrogen and hydrogen supply packages are designed to provide a supply of gas to the nuclear steam supply system. Two headers are provided for nitrogen supply: one low pressure for normal operation, which is supplied by a bulk liquid nitrogen tank, and one high pressure consisting of 36 high pressure cylinders for backup. When the operating header is exhausted, an alarm alerts the operator and the backup high pressure header is valved in through a pressure regulator to supply gas.

Low pressure nitrogen is supplied to the following components:

spent resin storage tank, pressurizer relief tank, volume control tank, spray additive tanks, gas decay tanks, radwaste evaporators, hydrogen recombiners, reactor coolant drain tank, recycle holdup tank, and containment electrical penetrations. At Byron, low pressure nitrogen is also supplied to the primary water storage tanks. Makeup nitrogen for the safety injection accumulators during normal operation is supplied from the high pressure backup header.

In addition, there is a truck fill connection in the nitrogen supply header for the direct filling of the safety injection accumulators and the high pressure cylinder backup manifold.

Hydrogen is supplied at pressures between 100 and 125 psig for the volume control tank. The hydrogen system is described in Chapter 10.

The design and material of valves and manifolds are the same as for the main GWPS.

Plant Ventilation Systems Plant ventilation systems are described in Chapter 9.0.

11.3-3 REVISION 11 - DECEMBER 2006

B/B-UFSAR Steam and Power Conversion Systems The main condenser evacuation system and the turbine gland sealing system may be potential sources of gaseous radioactive effluents. These systems are described in Section 10.4.

11.3-3a REVISION 4 - DECEMBER 1992

B/B-UFSAR 11.3.2.2 Component Design GWPS equipment parameters are given in Table 11.3-2. Component ASME Code, seismic design and quality assurance requirements for all components in the GWPS are shown in Table 3.2-1. These design and quality assurance requirements meet the NRC Branch Technical Position ETSB11-1. Source terms for component shielding and failure are provided in Section 11.1. Westinghouse experiences, general practices, and recommendations with respect to controlling occupational radiation exposure are given in Reference 1.

Waste Gas Compressors The two waste gas compressors are provided for the removal of gases discharging to the vent header. One unit is supplied for normal operation and is capable of handling the gas from a holdup tank which is receiving letdown flow at the maximum rate. The second unit is provided for backup during peak load conditions, such as when degassing the reactor coolant, or for service when the first unit is down for maintenance.

The compressors are of the liquid seal rotary type and are provided with mechanical seals.

Gas Decay Tanks Six tanks are provided to hold radioactive waste gases for decay.

The tanks are the vertical cylindrical type and are constructed of carbon steel.

Valves The valves handling gases are carbon steel, Saunders-patent diaphragm type, which minimize stem leakage.

Piping The piping for gaseous waste is carbon steel; all piping joints are welded except where flanged connections are necessary for maintenance.

11.3.2.3 Instrumentation Design The main system instrumentation is described in Table 11.3-2 and shown on Drawing M-69.

11.3-4 REVISION 13 - DECEMBER 2010

B/B-UFSAR The instrumentation readout is located mainly on the waste processing system (WPS) panel in the auxiliary building. Some instruments have local readout at the equipment location.

At Byron, alarms are shown separately on the WPS panel and key alarms are further relayed to one common WPS annunciator on the main control board of the plant. At Braidwood, all alarms are shown separately on the WPS panel and further relayed to one common WPS annunciator on the main control board of the plant.

A multipoint automatic gas analyzer (At Byron, a gas analyzer with manual selector switch) is provided to monitor hydrogen and oxygen concentrations in the GWPS. (At Byron, the sample points in the gaseous waste processing system are manually selected to monitor hydrogen and oxygen concentration in various samples in GWPS.) The analyzer records (At Byron, the analyzer monitors and indicates) the oxygen and hydrogen concentrations and alarms at high levels. In addition, a separate oxygen analyzer is provided between the compressors and the gas decay tanks. The two analyzers provide redundant capability for monitoring oxygen concentration in the gaseous waste processing system to assure that explosive levels of oxygen in hydrogen are avoided.

11.3.2.4 Operating Procedure The equipment installed to reduce radioactive effluents to the minimum practicable level is maintained in good operating order and is operated in accordance with general power plant practices. In order to ensure that these conditions are met, administrative controls are exercised on overall operation of the system; preventive maintenance is performed in accordance with general power plant practices to maintain equipment in peak condition; and experience available from similar plants is used in planning for operation.

Administrative controls are exercised through the use of instructions covering such areas as valve alignment for various operations, equipment operating instructions, and other instructions pertinent to the proper operation of the processing equipment. Operating procedures ensure that proper valve alignments are made, and other operating conditions are satisfied before a release.

Operating procedures and administrative controls incorporate procedures and controls developed at operational PWR plants having similar waste management equipment.

11.3.2.5 Operations Gaseous wastes consist primarily of hydrogen stripped from the reactor coolant during boron recycle and degassing operations and nitrogen from the nitrogen cover gas. The components connected to the vent header are limited to those which contain no air or aerated liquids to prevent the formation of a combustible mixture of hydrogen and oxygen.

11.3-5 REVISION 9 - DECEMBER 2002

B/B-UFSAR Waste gases discharged to the vent header are pumped to a waste gas decay tank by one of the two waste gas compressors.

To compress gas into the gas decay tanks, the auxiliary control panel operator selects two tanks, one to receive gas and one for standby. When the tank in service is pressurized to the control setpoint, flow is automatically switched to the standby tank and an alarm alerts the operator to select a new standby tank.

The contents of the decay tank being filled is sampled automatically by the gas analyzer and an alarm alerts the operator to a high oxygen content. On high oxygen signal, the tank is isolated and operator action is taken to direct flow to the standby tank and to select a new standby tank.

If it should become necessary to transfer gas from one decay tank to another, the tank to be emptied is aligned to the holdup tank return line. The tank to receive gas is opened to the inlet header and the return line pressure regulator setpoint is raised to provide flow. The return line isolation valve is closed and the crossover between the return line and the compressor suction is opened. With this arrangement, gas is transferred by the compressor which is in service.

As the boron recycle systems holdup tanks' liquid is withdrawn for processing by the boric acid recycle system, gas from the gas decay tanks is returned to the holdup tanks. The gas decay tank selected to supply the returning cover gas is aligned with the return header by manually opening the appropriate valve.

Residence time is determined by the activity in the tank and need for volume in the system. A backup supply of gas for the holdup tanks is provided by the nitrogen header.

Before a gas decay tank is discharged to the atmosphere via the plant vent, a gas sample is taken to determine activity concentration of the gas and total activity inventory in the tank.

The sample is taken by inserting a sample vessel into the gas analyzer's vent bypass line. Flow through the sample vessel is established by manually actuating the gas decay tank "manual select" sample station. When sufficient time has elapsed for a volume to be collected, the gas analyzer is returned to its normal alignment and the sample is removed for analysis. Total tank activity inventory is determined from the activity concentration and pressure in the tank.

11.3-6 REVISION 7 - DECEMBER 1998

B/B-UFSAR To release the gas, the appropriate local manual stop valve is opened to the plant vent and the gas discharge modulating valve is opened by operating the valve control switch at the auxiliary control panel. The plant vent activity level is indicated on the panel to aid in setting the valve properly. If a high activity level is detected in the vent during release, the modulating valve closes.

11.3.2.6 Refueling When preparing the plant for a cold shutdown prior to refueling, the reactor coolant is degassed to reduce the hydrogen concentrations. At the start of the degassing operation, the volume control tank gas space contains H2 and traces of fission gases.

Operational procedures and controls direct the activities used to degas the reactor coolant system into the gaseous waste processing system.

Gas evolved from the volume control tank during this operation is pumped by the waste-gas compressors to the gas decay tanks.

Operation of the gaseous side of the gaseous waste processing system is the same during the actual refueling operation as during normal operation.

11.3.2.7 Auxiliary Services During normal operation nitrogen and hydrogen are supplied to primary plant components from their respective systems. Separate headers are provided for each system. The nitrogen system is described in Subsection 11.3.2.1.

The hydrogen system is described in Chapter 10.

11.3.2.8 Performance Tests Initial performance tests are performed to verify the operability of the components, instrumentation and control equipment. See 11.3-7 REVISION 11 - DECEMBER 2006

B/B-UFSAR Chapter 14.0 on preoperational plant testing for further information.

During reactor operation, the system is normally in use at all times and is therefore under continuous surveillance.

11.3.3 Radioactive Releases 11.3.3.1 NRC Requirements The following documents provide regulations and guidelines for radioactive releases:

a. 10 CFR 20, Standards for Protection Against Radiation.
b. Appendix I for 10 CFR 50.

11.3.3.2 Westinghouse PWR Experience Releases Surveys have been performed of gaseous discharges from several Westinghouse PWR plants. The results are presented in Table 11.3-5.

11.3.3.3 Expected Gaseous Waste Processing System Releases Gaseous wastes consist primarily of hydrogen stripped from coolant discharged to Boron Recycle System holdup tanks during boron dilution, nitrogen and hydrogen gases purged from the Chemical Volume Control System volume control tank when degassing the reactor coolant and nitrogen from the Nitrogen cover gas.

The gas decay tank capacity permits sufficient decay time for waste gases to meet discharge limits.

The quantities and isotopic concentration of gases discharged from the gaseous waste processing system and from the volume 11.3-8 REVISION 6 - DECEMBER 1996

B/B-UFSAR reduction system have been estimated. The analysis is based on engineering judgment with respect to the operation of the plant and realistic estimations of the input sources to these two systems.

The associated releases in curies per year per nuclide are given in Table 11.3-6.

11.3.3.4 Estimated Total Releases Byron and Braidwood Nuclear stations have uprated the core power level twice. First to a core power level of 3586.6 MWt, then to the Measurement Uncertainty Recapture uprate power level of 3645 MWt. The original licensed power level was 3411 MWt. The original expected gaseous radwaste effluent data presented in the UFSAR is based on a power level of 3565 MWt.

Estimated annual total releases of radioactive noble gases and particulates were determined by using NUREG 0017 methodology and computer program PWR-GALE. Both the original as well as the uprated parameters describing the normal operation of one unit of the station are listed in Table 11.2-2. These values were used as input to the computer code for the original analyses. The impact of core uprate on the effluent releases was evaluated based on an assessment of the changes in input parameters. Expected releases from routine and shutdown degassing of the primary coolant and from the building ventilation systems are shown in Table 11.3-6.

Core uprate results in a maximum potential increase of 0.6% for long lived isotopes such as Kr 85. Shorter lived isotopes will have reduced releases or only slight increases as compared to the 0.6% increase in power level. The impact of power uprate on iodine releases is limited to a maximum of 0.6%. The other components of gaseous releases (particulates via the building ventilation systems and water activation gases) are not impacted by uprate. All of the incremental tritium production due to power uprate is assumed to be released via the gaseous pathway resulting in an approximate 0.8% increase in tritium releases via the gaseous pathway.

Taking into consideration the accuracy and error bounds of the operational data utilized in NUREG 00017, these small percentage changes are well within the uncertainty of the calculated results of the original NUREG 0017 based maximum offsite airborne concentrations from gaseous radwaste effluents presented in Table 11.3-7.

Actual release data are available in the effluent release reports, which are prepared in accordance with the ODCM.

Expected releases from normal operation of the volume reduction system were determined using the estimated annual production of radioactive wastes and design flow rates and cleanup parameters for this system. Calculated routine releases for the volume reduction system are also included in Table 11.3-6.

11.3-9 REVISION 15 - DECEMBER 2014

B/B-UFSAR 11.3.3.5 Effluent Concentrations and Dilution Factors A comparison of maximum offsite (at site boundary) airborne gaseous effluent concentration with 10 CFR 20 limits is given in Table 11.3-7. The atmospheric dilution factors used for these calculations are given in Table 11.3-8. As discussed in Section 11.3.3.4 above, this comparison and Table 11.3-7 remains valid for uprate.

11.3.3.6 Release Points of Dilution Factors Gaseous radioactive wastes are released to the atmosphere through the two ventilation stacks. Each stack is rectangular and is 13.3 feet by 5.0 feet at the exit point, giving an effective diameter of 9.2 feet per stack. The top of the stack is at elevation 600 feet, and the base elevation is 401 feet. The next tallest structures are the tops of the containments, which are at elevation 599 feet. This qualifies the exhaust vent stacks as mixed-mode release points, since they are 1 foot higher than any surrounding structures.

11.3-9a REVISION 9 - DECEMBER 2002

B/B-UFSAR Effluent Velocity Data Case 1 Case 2 Unit (Refueling) (Normal Plant Operation)

Stack Except Mini-Flow Purge Except Normal Purge Air Flow Exit Velocity Air Flow Exit Velocity (cfm) (fpm) (cfm) (fpm) 1 (Byron) 194,310 2932 151,842 2283 2 (Byron) 189,510 2854 147,042 2204 1 (Braidwood) 192,910 2893 150,442 2263 2 (Braidwood) 189,510 2854 147,042 2204 The expected temperature range of this exhaust gas is from 40F to (in a few cases) 122F. Table 11.3-10 gives a detailed breakdown of the exhaust airflows into each plant vent stack for Cases 1 and 2.

11.3.3.7 Estimated Doses from Gaseous Releases Estimated annual average doses from radionuclides released from the waste gas processing system are given in Table 11.3-9. These doses were calculated using the methodology of Regulatory Guide 1.109 (Reference 3). Site meteorological data and the partially elevated release model were used to calculate the atmospheric dispersion of the effluents. Various exposure pathways were examined. Consumption factors for the ingestion pathways are given in Table 11.2-8. Note that all of these doses are well within the guidelines of Appendix I to 10 CFR 50. As discussed in Section 11.3.3.4 above, this assessment and Table 11.3-9 remain valid for uprate.

11.3.4 References

1. R. J. Lutz, "Design, Inspection, Operation, and Maintenance Aspects of the W NSSS to Maintain Occupational Radiation Exposures," WCAP-8872, April 1977.
2. NUREG-0017, "Calculation of Releases of Radioactive Materials in Gaseous and Liquid Effluents from Pressurized Water Reactors (PWR-GALE Code)," Office of Standards Development, U.S. Nuclear Regulatory Commission, April 1976.
3. Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," U.S.

Nuclear Regulatory Commission, October 1977.

11.3-10 REVISION 9 - DECEMBER 2002

B/B-UFSAR TABLE 11.3-1 GASEOUS WASTE PROCESSING SYSTEM COMPONENT DATA WASTE GAS COMPRESSORS Number 2 Type Liquid seal rotary type Design Flow rate, N2 40 (at 140 F, 2 psig), cfm Design pressure, psig 150 Design temperature, F 180 Normal operating pressure, psig Suction 0.5 - 2.0 Discharge 0 - 110 Normal operating temperature, F 60 - 140 GAS DECAY TANKS Number 6 Volume, each, ft3 600 Design pressure, psig 150 Design temperature, F 180 Normal operating pressure, psig 0 - 125 Normal operating temperature, F 50 - 140 Material of construction Carbon steel 11.3-11

B/B-UFSAR TABLE 11.3-2 GASEOUS WASTE PROCESSING SYSTEM INSTRUMENTATION DESIGN PARAMETERS DESIGN DESIGN INSTRUMENT LOCATION OF PRESSURE TEMP. ALARM CONTROL LOCATION OF NUMBER PRIMARY SENSOR (psig) (F) RANGE SETPOINT SETPOINT READOUT TEMPERATURE INSTRUMENTATION TI-1029 Seal water, compressor No. 1 150 300 30-300F NA NA At Waste Gas (Dial Thermometer) Compressor TI-1034 Seal water, compressor No. 2 150 300 30-300F NA NA At Waste Gas (Dial Thermometer) Compressor PRESSURE INSTRUMENTATION PICA-1025 Vent header Hi, 2.5 psig 3.0 psig WPS panel 100 180 0 - 5 psig (BR) (BR) 2.0 psig (BY) 2.0 psig (BY)

Lo 2.0 psig (BR) 0.5 psig (BY)

PC-1028 (AB) Compressor No. 1 150 180 0 - 150 psig Hi, 100 psig Lo, 30 psig 100 psig WPS panel PC-1035 (AB) Compressor No. 2 150 180 0 - 150 psig Hi, 100 psig Lo, 30 psig 100 psig WPS panel PICA-1036 Waste gas decay tank No. 1 150 180 0 - 150 psig Hi, 95 psig 95 psig WPS panel (BR) 100 psig (BY)

F - Flow R - Radiation P - Pressure I - Indication L - Level C - Control T - Temperature A - Alarm 11.3-12 REVISION 11 - DECEMBER 2006

B/B-UFSAR TABLE 11.3-2 (Cont'd)

DESIGN DESIGN INSTRUMENT LOCATION OF PRESSURE TEMP. ALARM CONTROL LOCATION OF NUMBER PRIMARY SENSOR (psig) (F) RANGE SETPOINT SETPOINT READOUT PICA-1037 Waste gas decay tank No. 2 150 180 0 - 150 psig Hi, 95 psig 95 psig WPS panel (BR)

PICA-1038 Waste gas decay tank No. 3 150 180 0 - 150 psig Hi, 95 psig 95 psig WPS panel (BR) 100 psig (BY)

PICA-1039 Waste gas decay tank No. 4 150 180 0 - 150 psig Hi, 95 psig 95 psig WPS panel (BR) 100 psig (BY)

PI-1047 Nitrogen header 150 180 0 - 25 psig NA NA Local PICA-1052 Waste gas decay tank No. 5 150 180 0 - 150 psig Hi, 95 psig 95 psig WPS panel (BR) 100 psig (BY)

PICA-1053 Waste gas decay tank No. 6 150 180 0 - 150 psig Hi, 95 psig 95 psig WPS panel (BR) 100 psig (BY)

PIA-1065 Hydrogen header 150 180 50 - 150 psig Hi, 130 psig NA WPS panel Lo, 90 psig PIA-1066 Nitrogen header 150 180 50 - 150 psig Hi, 110 psig NA WPS panel Lo, 90 psig 11.3-13 REVISION 10 - DECEMBER 2004

B/B-UFSAR TABLE 11.3-2 (Cont'd)

DESIGN DESIGN INSTRUMENT LOCATION OF PRESSURE TEMP. ALARM CONTROL LOCATION OF NUMBER PRIMARY SENSOR (psig) (F) RANGE SETPOINT SETPOINT READOUT LEVEL INSTRUMENTATION LICA-1030 Waste gas compressor No. 1 150 180 0 - 28 in. Hi, 15 in. (BR) Inches: WPS panel 21 in. (BY) 15, 13 Lo, 1 in. 10, 7, 1 (BR) 21, 15 7, 4, 1 (BY)

LICA-1032 Waste gas compressor No. 2 150 180 0 - 28 in. Hi, 15 in. (BR) Inches: WPS panel 21 in. (BY) 15, 13 Lo, 1 in. 10, 7, 1 (BR) 21, 15 7, 4, 1 (BY)

RADIATION INSTRUMENTATION RICA-014 Plant vent See Section 11.5 GAS ANALYZER Located in separate cubicle in Aux. Bldg.

OAIT-GW8003

/ Oxygen 300 212 0-19.99% 2% (Byron) none Local (Byron)/

/AT-GW8003 O

(Braidwood)

OAR-GW8003

/ Oxygen 300 212 0-5% 2% none Local (Braidwood)

/AIT-GW004 O Oxygen 300 212 0-5% 2% none Local OAIT-GW8000

/ Hydrogen 25 130 0-100% - none Local (Byron)/

/AT-GW8000 O

(Braidwood)

OAR-GW8000

/ Hydrogen 25 130 0-100% - none Local (Braidwood) 11.3-14 REVISION 13 - DECEMBER 2010

B/B-UFSAR TABLE 11.3-3 PROCESS PARAMETERS AND REALISTIC, OPERATION BASIS ACTIVITIES IN GASEOUS WASTE SYSTEM(1)

(CONCENTRATIONS IN C/cm3)

FLOW POS PRESSURE TEMP. RATE NO.(2) LOCATION (psig) (F) (cm3/day) KR83M(4) KR85M(4) KR85 KR87 KR88 1 Unit 1 RCDT Vent 1.5 170 max. 1.14E+6 6.6E-04 1.9E-06 1.0E-04 1.0E-05 1.6E-05 2 Unit 2 RCDT Vent 1.5 170 max. 1.14E+6 6.6E-04 1.9E-06 1.0E-04 1.0E-05 1.6E-05 3 Sampling System VCT Vent Unit 1 1.5 115 0 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 4 Sampling System VCT Vent Unit 2 1.5 115 0 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 5 Vent Boron Recycle Holdup Tank - - 2.18E+7 1.2E-05 2.9E-08 9.5E-05 4.7E-07 3.2E-07 Vent 6 Gas Analyzer 3.5 VAR 0 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 7 Waste Disposal System SRST Vent - - 0 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 (3) 8 BRS Evaporator Unit 1 Vent 1.5 155 3.82E+5 8.1E-04 1.9E-06 1.9E-02 3.2E-05 2.1E-05 (3) 9 BRS Evaporator Unit 2 Vent 1.5 155 3.82E+5 8.1E-04 1.9E-06 1.9E-02 3.2E-05 2.1E-05 10 CVCS VCT Vent Unit 1 1.5 115 0 1.0E-01 8.8E-01 1.6E+01 2.2E-01 1.3E+00 11 CVCS VCT Vent Unit 2 1.5 115 0 1.0E-01 8.8E-01 1.6E+01 2.2E-01 1.3E+00 12 Combination of Normal Letdown 1.5 VAR 2.48E+7 4.5E-04 1.1E-06 7.8E-03 1.5E-05 1.2E-05 GWPS(5) 13 Compressor Recirculation Line 1.5 140 0 4.5E-04 1.1E-06 7.8E-03 1.5E-05 1.2E-05 11.3-15 REVISION 3 - DECEMBER 1991

B/B-UFSAR TABLE 11.3-3 (Cont'd)

FLOW POS PRESSURE TEMP. RATE NO.(2) LOCATION (psig) (F) (cm3/day) KR89 XE131M(4) XE144M(4) XE133 XE135M(4) 14 Compressor Inlet 1.5 VAR 2.48E+7 4.5E-04 1.1E-06 7.8E-03 1.5E-05 1.2E-05 15 Compressor Inlet 0.5 VAR 2.48E+7 4.5E-04 1.1E-06 7.8E-03 1.5E-05 1.2E-05 16 Downstream of Compressor 110 max. 140 2.48E+7 4.5E-04 1.1E-06 7.8E-03 1.5E-05 1.2E-05 17 Compressor Outlet to Gas Decay - - 0 4.5E-04 1.1E-06 7.8E-03 1.5E-05 1.2E-05 Tanks 18 Inlet to Filling Gas Decay Tanks 110 max. 140 2.48E+7 4.5E-04 1.1E-06 7.8E-03 1.5E-05 1.2E-05 19 Line to Gas Decay Tank Header 110 AMB VAR 5.4E-06 3.0E-09 7.8E-03 1.2E-06 2.0E-07 20 Discharge Line 20 AMB VAR 0.0E+00 0.0E+00 7.7E-03 0.0E+00 0.0E+00 21 Discharge Line 1 AMB VAR 0.0E+00 0.0E+00 7.7E-03 0.0E+00 0.0E+00 22 Gas Analyzer 3.5 VAR 0 0.0E+00 0.0E+00 0.0E-00 0.0E+00 0.0E+00 23 From Gas Decay Tanks to Compressor 110 AMB 1.64E+8 5.4E-06 3.0E-09 7.8E-03 1.2E-06 2.0E-07 Inlet 24 From Gas Decay Tanks to BRS 3 AMB 1.64E+8 5.4E-06 3.0E-09 7.8E-03 1.2E-06 2.0E-07 HTs(6)

AMB - Ambient VAR - Variable 11.3-16 REVISION 1 - DECEMBER 1989

B/B-UFSAR TABLE 11.3-3 (Cont'd)

FLOW POS PRESSURE TEMP. RATE NO.(2) LOCATION (psig) (F) (cm3/day) KR89 XE131M(4) XE133M(4) XE133 XE135M(4) 1 Unit 1 RCDT Vent 1.5 170 max. 1.14E+6 6.4E-06 2.1E-05 1.7E+00 3.1E+01 1.1E-01 2 Unit 2 RCDT Vent 1.5 170 max. 1.14E+6 6.4E-06 2.1E-05 1.7E+00 3.1E+01 1.1E-01 3 Sampling System VCT Vent Unit 1 1.5 115 0 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 4 Sampling System VCT Vent Unit 2 1.5 115 0 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 5 Vent Boron Recycle Holdup Tank - - 2.18E+7 9.4E-08 9.9E-06 2.5E-02 8.6E+00 1.6E-03 Vent 6 Gas Analyzer - - 0 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 7 Waste Disposal System SRST Vent - - 0 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 (3) 8 BRS Evaporator Unit 1 Vent 1.5 155 3.82E+5 6.2E-06 1.1E-03 1.7E+00 7.3+02 1.1E-01 (3) 9 BRS Evaporator Unit 2 Vent 1.5 155 3.82E+5 6.2E-06 1.1E-03 1.7E+00 7.3+02 1.1E-01 10 CVCS VCT Vent Unit 1 1.5 115 0 1.0E-03 1.6E+00 2.4E+00 2.2E+02 1.2E-02 11 CVCS VCT Vent Unit 2 1.5 115 0 1.0E-03 1.6E+00 2.4E+00 2.2E+02 1.2E-02 12 Combination of Normal Letdown 1.5 VAR 2.48E+7 3.7E-06 4.6E-04 9.9E-01 3.1E+02 6.4E-02 GWPS(5) 13 Compressor Recirculation Line 1.5 140 0 3.7E-06 4.6E-04 9.9E-01 3.1E+02 6.4E-02 14 Compressor Inlet 1.5 VAR 2.48E+7 3.7E-06 4.6E-04 9.9E-01 3.1E+02 6.4E-02 11.3-17

B/B-UFSAR TABLE 11.3-3 (Cont'd)

FLOW POS PRESSURE TEMP. RATE NO.(2) LOCATION (psig) (F) (cm3/day) KR89 XE131M(4) XE133M(4) XE133 XE135M(4) 15 Compressor Inlet 0.5 VAR 2.48E+7 3.7E-06 4.6E-04 9.9E-01 3.1E+02 6.4E-02 16 Downstream of Compressor 110 max. 140 2.48E+7 3.7E-06 4.6E-04 9.9E-01 3.1E+02 6.4E-02 17 Compressor Outlet to Gas Decay - - 0 3.7E-06 4.6E-04 9.9E-01 3.1E+02 6.4E-02 Tank 18 Inlet to Filling Gas Decay 110 max. 140 2.48E+7 3.7E-06 4.6E-04 9.9E-01 3.1E+02 6.4E-02 Tanks 19 Line to Gas Decay Tank Header 110 AMB VAR 1.2E-09 3.5E-04 1.6E-03 1.8E-02 1.0E-04 20 Discharge Line 20 AMB VAR 0.0E+00 1.0E-05 0.0E+00 6.4E-02 0.0E+00 21 Discharge Line 1 AMB VAR 0.0E+00 1.0E-05 0.0E+00 6.4E-02 0.0E+00 22 Gas Analyzer 2 AMB 0 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 23 From Gas Decay Tank To 110 AMB 1.64E+8 1.2E-09 3.5E-04 1.6E-03 1.8E-02 1.0E-04 Compressor Inlet 24 From Gas Decay Tanks to BRS 3 AMB 1.64E+8 1.2E-09 3.5E-04 1.6E-03 1.8E-02 1.0E-04 Hts(6)

AMB - Ambient VAR - Variable 11.3-18 REVISION 1 - DECEMBER 1989

B/B-UFSAR TABLE 11.3-3 (Cont'd)

FLOW POS PRESSURE TEMP. RATE NO.(2) LOCATION (psig) (F) (cm3/day) XE135 XE137 XE138 I130 I131 1 Unit 1 RCDT Vent 1.5 170 max. 1.14E+6 4.9E+01 1.4E-05 4.1E-01 1.1E-05 1.8E-06 2 Unit 1 RCDT Vent 1.5 170 max. 1.14E+6 4.9E+01 1.4E-05 4.1E-01 1.1E-05 1.8E-06 3 Sampling System VCT Vent Unit 1 1.5 115 0 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 4 Sampling System VCT Vent Unit 2 1.5 115 0 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 5 Boron Recycle Holdup Tank Vent - - 2.18E+7 1.8E+00 2.1E-07 6.2E-03 3.9E-08 5.7E-08 6 Gas Analyzer - - 0 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 7 Waste Disposal System SRST Vent - - 0 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 (3) 8 BRS Evaporator Unit 1 Vent 1.5 1.5 3.82E+5 1.2E+02 1.4E-05 4.1E-01 0.0E+00 0.0E+00 (3) 9 BRS Evaporator Unit 2 Vent 1.5 1.5 3.82E+5 1.2E+02 1.4E-05 4.1E-01 0.0E+00 0.0E+00 10 CVCS VCT Vent Unit 1 1.5 115 0 3.0E+00 2.2E-03 3.7E-02 0.0E+00 0.0E+00 11 CVCS VCT Vent Unit 2 1.5 115 0 3.0E+00 2.2E-03 3.7E-02 0.0E+00 0.0E+00 12 Combination of Normal Letdown to 1.5 VAR 2.48E+7 5.9E+01 8.1E-06 2.4E-01 2.0E-06 3.4E-07 GWPS(5) 13 Compressor Recirculation Line 1.5 140 0 5.9E+01 8.1E-06 2.4E-01 2.0E-06 3.4E-07 14 Compressor Inlet 1.5 VAR 2.48E+7 5.9E+01 8.1E-06 2.4E-01 2.0E-06 3.4E-07 15 Compressor Inlet 0.5 VAR 2.48E+7 5.9E+01 8.1E-06 2.4E-01 2.0E-06 3.4E-07 11.3-19

B/B-UFSAR TABLE 11.3-3 (Cont'd)

FLOW POS PRESSURE TEMP. RATE NO.(2) LOCATION (psig) (F) (cm3/day) XE135 XE137 XE138 I130 I131 16 Downstream of Compressor 110 max. 140 2.48E+7 5.9E+01 8.1E-06 2.4E-01 2.0E-06 3.4E-07 17 Compressor Outlet to Gas Decay - - 0 5.9E+01 8.1E-06 2.4E-01 2.0E-06 3.4E-07 Tanks 18 Inlet to Filling Gas Decay Tanks 110 max. 140 2.48E+7 5.9E+01 8.1E-06 2.4E-01 2.0E-06 3.4E-07 19 Line to Gas Decay Tank Header 110 AMB VAR 3.4E+00 3.3E-09 4.3E-04 1.5E-07 2.3E-07 20 Discharge Line 20 AMB VAR 0.0E+00 0.0E+00 0.0E+00 0.0E+00 1.3E-09 21 Discharge Line 1 AMB VAR 0.0E+00 0.0E+00 0.0E+00 0.0E+00 1.3E-09 22 Gas Analyzer 2 AMB 0 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 23 From Gas Decay Tanks To Compressor 110 AMB 1.64E+8 3.4E+00 3.3E-09 4.3E-04 1.5E-07 2.3E-07 Inlet 24 From Gas Decay Tanks To BRS HTs(6) 3 AMB 1.64E+8 3.4E+00 3.3E-09 4.3E-04 1.5E-07 2.3E-07 AMB - Ambient VAR - Variable 11.3-20 REVISION 1 - DECEMBER 1989

B/B-UFSAR TABLE 11.3-3 (Cont'd)

FLOW POS PRESSURE TEMP. RATE NO.(2) LOCATION (psig) (F) (cm3/day) I132 I133 I134 I135 1 Unit 1 RCDT Vent 1.5 170 max. 1.14E+6 1.6E-07 2.3E-06 4.4E-08 8.4E-07 2 Unit 1 RCDT Vent 1.5 170 max. 1.14E+6 1.6E-07 2.3E-06 4.4E-08 8.4E-07 3 Sampling System VCT Vent Unit 1 1.5 115 0 0.0E+00 0.0E+00 0.0E+00 0.0E+00 4 Sampling System VCT Vent Unit 2 1.5 115 0 0.0E+00 0.0E+00 0.0E+00 0.0E+00 5 Boron Recycle Holdup Tank Vent - - 2.18E+7 2.9E-10 1.2E-08 7.4E-11 2.1E-09 6 Gas Analyzer - - 0 0.0E+00 0.0E+00 0.0E+00 0.0E+00 7 Waste Disposal System SRST Vent - - 0 0.0E+00 0.0E+00 0.0E+00 0.0E+00 (3) 8 BRS Evaporator Unit 1 Vent 1.5 155 3.82E+5 0.0E+00 0.0E+00 0.0E+00 0.0E+00 (3) 9 BRS Evaporator Unit 2 Vent 1.5 155 3.82E+5 0.0E+00 0.0E+00 0.0E+00 0.0E+00 10 CVCS VCT Vent Unit 1 1.5 155 0 0.0E+00 0.0E+00 0.0E+00 0.0E+00 11 CVCS VCT Vent Unit 2 1.5 155 0 0.0E+00 0.0E+00 0.0E+00 0.0E+00 12 Combination of Normal Letdown to 1.5 VAR 2.48E+7 2.8E-08 4.1E-07 7.6E-09 1.5E-07 GWPS(5) 13 Compressor Recirculation Line 1.5 140 0 2.8E-08 4.1E-07 7.6E-09 1.5E-07 14 Compressor Inlet 1.5 VAR 2.48E+7 2.8E-08 4.1E-07 7.6E-09 1.5E-07 15 Compressor Inlet 0.5 VAR 2.48E+7 2.8E-08 4.1E-07 7.6E-09 1.5E-07 11.3-21

B/B-UFSAR TABLE 11.3-3 (Cont'd)

FLOW POS PRESSURE TEMP. RATE NO.(2) LOCATION (psig) (F) (cm3/day) I132 I133 I134 I135 16 Downstream of Compressor 110 max. 140 2.48E+7 2.8E-08 4.1E-07 7.6E-09 1.5E-07 17 Compressor Outlet to Gas Decay - - 0 2.8E-08 4.1E-07 7.6E-09 1.5E-07 Tanks 18 Inlet to Filling Gas Decay Tanks 110 max. 140 2.48E+7 2.8E-08 4.1E-07 7.6E-09 1.5E-07 19 Line to Gas Decay Tank Header 110 AMB VAR 3.9E-10 5.4E-08 4.1E-11 6.1E-09 20 Discharge Line 20 AMB VAR 0.0E+00 0.0E+00 0.0E+00 0.0E+00 21 Discharge Line 1 AMB VAR 0.0E+00 0.0E+00 0.0E+00 0.0E+00 22 Gas Analyzer 2 AMB 0 0.0E+00 0.0E+00 0.0E+00 0.0E+00 23 From Gas Decay Tanks To Compressor 110 AMB 1.64E+8 3.9E-10 5.4E-08 4.1-11 6.1E-09 Inlet (6) 24 From Gas Decay Tanks To BRS HTs 3 AMB 1.64E+8 3.9E-10 5.4E-08 4.1-11 6.1E-09 AMB - Ambient VAR - Variable 11.3-22 REVISION 1 - DECEMBER 1989

B/B-UFSAR TABLE 11.3-3 (Cont'd)

NOTES:

1. This is a synthesis of information from operating reactors.
2. These position numbers correspond to positions marked on Figure 11.3-2.
3. Boron Recycle System (BRS).
4. Metastable (M).
5. Gaseous Waste Processing System (GWPS).
6. Holdup Tank (HT) 11.3-23

B/B-UFSAR TABLE 11.3-4 ASSUMPTIONS USED IN CALCULATING EXPECTED SYSTEM ACTIVITIES A. EXPECTED SYSTEM ACTIVITY

1. The major inputs to the gas system during normal operation are vents on the Boron Recycle System (BRS) holdup tanks (HUT), reactor coolant drain tanks (RCDT) and BRS evaporators. Inputs from the gas analyzer sampling system and CVCS volume control tank are assumed to be negligible.
2. Reactor coolant gaseous activities are based on Regulatory Guide 1.112 as modified to reflect Byron/Braidwood plant parameters.
3. Twenty-five percent of dissolved radiogases in the reactor coolant entering the RCDTs and HUTs leave solution and enter the vapor space.
4. Radioactive decay was assumed while the BRS HUTs, RCDTs and gas decay tanks were filling. No additional decay was assumed in the evaporator.
5. The BRS HUT is assumed to be filled to 80% capacity before processing by the BRS evaporator. The RCDTs are assumed to be filled to 280 gallons before draining.
6. Values for liquid flow rates to the tanks were based on estimates of annual average flows:

BRS HUT flow 1.0 gpm (0.5 gpm per unit)

RCDT flow 300 gpd (per each unit)

BRS Evaporator flow 1.0 gpm (0.5 gpm/evaporator

- from BRS HUTs)

7. The plant capacity factor is 0.8.
8. The iodine partition coefficient in the RCDTs and BRS HUTs was:

Ci / cc in vapor 7.5 X 10 3 Ci / cc in liquid (Based on Regulatory Guide 1.112).

9. The hydrogen concentration in the primary coolant was assumed 35 cc/kg.

11.3-24 REVISION 3 - DECEMBER 1991

B/B-UFSAR TABLE 11.3-4 (Cont'd)

B. ANNUAL RELEASES The following additional assumptions were used in calculating expected annual releases:

1. One refueling per year per unit was assumed, with complete degassing of reactor coolant and also transfer of noble gases and iodines present in the volume control tank vapor space at shutdown to the gaseous waste system. This gaseous activity is released after 60 days decay for this analysis only.
2. Kr-85 release to the environment is based on an entry rate of 0.15 Ci/MWt-yr Kr-85 into the primary coolant. It was assumed that all Kr-85 entering the coolant is eventually released to the environment.
3. From the calculation of system activities, the activity in a single gas decay tank was determined after 60 days decay. It was assumed that one tank was released every 60 days for purposes of this analysis only.

11.3-25 REVISION 3 - DECEMBER 1991

B/B-UFSAR TABLE 11.3-5 TYPICAL GASEOUS RELEASES FROM OPERATING REACTORS NOBLE GASES (103 Ci) 73 74 75 R. E. Ginna 0.576 0.78 1.81 Connecticut Yankee 0.032 0.008 1.81 San Onofre 11.0 1.78 1.07 Surry 1 & 2 0.87 54.4 9.47 H. B. Robinson 2 3.1 0.27 0.707 Point Beach 1 & 2 5.75 9.71 32.1 IODINES (Ci) 73 74 75 R. E. Ginna 0.0006 0.0004 0.0037 Connecticut Yankee 0.0013 0.0001 0.0009 San Onofre 0.42 0.0002 0.0046 Surry 1 & 2 0.042 0.071 0.0456 H. B. Robinson 2 0.296 0.012 0.0115 Point Beach 1 & 2 0.011 0.098 0.0188 11.3-26

B/B-UFSAR TABLE 11.3-6 EXPECTED ANNUAL AVERAGE RELEASE OF AIRBORNE RADIONUCLIDES*, **

GASEOUS RELEASE RATE - CURIES PER YEAR PRIMARY SECONDARY BLOWDOWN AIR COOLANT COOLANT GAS STRIPPING BUILDING VENTILATION VENT EJECTOR NUCLIDE (Ci/g) (Ci/g) SHUTDOWN CONTINUOUS REACTOR AUXILIARY TURBINE OFF-GAS EXHAUST TOTAL KR 83M 2.265-02 6.255-09 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 KR 85M 1.184-01 3.337-08 0.0 0.0 0.0 3.0+00 0.0 0.0 2.0+00 5.0+00 KR 85 1.051-01 2.944-08 5.1+01 5.7+02 7.4+01 2.0+00 0.0 0.0 1.0+00 7.0+02 KR 87 6.474-02 1.726-08 0.0 0.0 0.0 1.0+00 0.0 0.0 0.0 1.0+00 KR 88 2.156-01 5.928-08 0.0 0.0 0.0 5.0+00 0.0 0.0 3.0+00 8.0+00 KR 89 5.399-03 1.512-09 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 XE131M 1.035-01 2.917-08 4.0+00 1.5+01 1.7+01 2.0+00 0.0 0.0 1.0+00 3.9+01 XE133M 2.293-01 6.461-08 0.0 0.0 7.0+00 5.0+00 0.0 0.0 3.0+00 1.5+01 XE133 1.804+01 5.010-06 2.4+01 4.7+01 1.3+03 3.8+02 0.0 0.0 2.4+02 2.0+03 XE135M 1.404-02 3.887-09 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 XE135 3.755-01 1.041-07 0.0 0.0 2.0+00 8.0+00 0.0 0.0 5.0+00 1.5+01 0.0 appearing in the table indicates release is less than 1.0 Ci/yr for noble gas, 0.0001 Ci/yr for I.

For one unit.

KEY: 4.5-03 = 4.5 x 10-3 11.3-27 REVISION 1 - DECEMBER 1989

B/B-UFSAR TABLE 11.3-6 (Cont'd)

GASEOUS RELEASE RATE - CURIES PER YEAR PRIMARY SECONDARY BLOWDOWN AIR COOLANT COOLANT GAS STRIPPING BUILDING VENTILATION VENT EJECTOR NUCLIDE (Ci/g) (Ci/g) SHUTDOWN CONTINUOUS REACTOR AUXILIARY TURBINE OFF-GAS EXHAUST TOTAL XE137 9.719-03 2.700-09 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 XE138 4.751-02 1.296-08 0.0 0.0 0.0 1.0+00 0.0 0.0 0.0 1.0+00 TOTAL NOBLE GASES 2.8+03 I 131 2.795-01 4.215-05 0.0 0.0 1.7-03 4.4-02 2.3-03 0.0 2.8-03 5.1-02 I 133 3.986-01 3.831-05 0.0 0.0 7.7-04 6.3-02 2.1-03 0.0 4.0-03 7.0-02 TRITIUM GASEOUS RELEASE 1000 CURIES/YR 11.3-28 REVISION 1 - DECEMBER 1989

B/B-UFSAR TABLE 11.3-6 (Cont'd)

AIRBORNE PARTICULATE RELEASE RATE - CURIES PER YEAR1 WASTE GAS BUILDING VENTILATION NUCLIDE SYSTEM REACTOR AUXILIARY TOTAL MN 54 4.5-03 6.1-06 1.8-04 4.7-03 FE 59 1.5-03 2.1-06 6.0-05 1.6-03 CO 58 1.5-02 2.1-05 6.0-04 1.6-02 CO 60 7.0-03 9.5-06 2.7-04 7.3-03 SR 89 3.3-04 4.7-07 1.3-05 3.4-04 SR 90 6.0-05 8.4-08 2.4-06 6.2-05 CS134 4.5-03 6.1-06 1.8-04 4.7-03 CS137 7.5-03 1.1-05 3.0-04 7.8-03 In addition to these releases, 25 Ci/yr of argon-41 are released from the containment and 8 Ci/yr of carbon-14 are released from the waste gas processing system. This table was developed taking into account both releases from normal operations and also operational occurrences.

KEY: 4.5-03 = 4.5 x 10-3 11.3-29

B/B-UFSAR TABLE 11.3-6 (Cont'd)

VOLUME REDUCTION SYSTEM* RELEASE RATE (Ci/yr)

Noble Gases:

Xe 131m 5.1-01 Xe 133m 1.2+00 Xe 133 2.1+01 Halogens:

I 131 2.8-03 I 132 3.7-03 I 133 2.1-03 Tritium:

H 3 2.6+01 Particulates:

Cr 51 5.3-08 Fe 55 7.0-07 Co 58 6.0-07 Co 60 9.2-08 Ni 63 7.0-07 Y 91 1.5-09 Mo 99 3.5-07 Tc 99m 2.1-09 Te 132 1.5-07 Cs 134 1.1-05 Cs 136 1.9-07 Cs 137 7.4-07 KEY: 5.1-01 = 5.1x10-1

  • The original estimate included release data for the volume reduction system. This system is no longer used.

11.3-30 REVISION 6 - DECEMBER 1996

BYRON-UFSAR TABLE 11.3-7 COMPARISON OF MAXIMUM OFFSITE AIRBORNE CONCENTRATIONS WITH 10 CFR 20 LIMITS MAXIMUM SITE ANNUAL RELEASE BOUNDARY* 10 CFR 20**

FROM ONE UNIT CONCENTRATION CONCENTRATION ISOTOPE (Ci/yr) (Ci/ml) (Ci/ml)

H 3 1.0+03 3.5-11 2.0-07 C 14 8.0+00 2.8-13 1.0-07 Ar 41 2.5+01 8.8-13 4.0-08 Kr 85m 5.0+00 1.8-13 1.0-07 Kr 85 7.0+02 2.5-11 3.0-07 Kr 87 1.0+00 3.5-14 2.0-08 Kr 88 8.0+00 2.8-13 2.0-08 Xe 131m 4.0+01 1.4-12 4.0-07 Xe 133m 1.6+01 5.6-13 3.0-07 Xe 133 2.0+03 7.0-11 3.0-07 Xe 135 1.5+01 5.3-13 1.0-07 Xe 138 1.0+00 3.5-14 3.0-08 I 131 5.4-02 1.9-15 1.0-10 I 132 3.7-03 1.3-16 3.0-09 I 133 7.2-02 2.5-15 4.0-10 Cr 51 5.3-08 1.9-21 8.0-08 Mn 54 4.7-03 1.7-16 1.0-09 Fe 55 7.0-07 2.5-20 3.0-08 Fe 59 1.6-03 5.6-17 2.0-09 Co 58 1.6-02 5.6-16 2.0-09 Co 60 7.3-03 2.6-16 3.0-10 Ni 63 7.0-07 2.5-20 2.0-09 Sr 89 3.4-04 1.2-17 3.0-10 Sr 90 6.2-05 2.2-18 3.0-11 Y 91 1.5-09 5.3-23 1.0-09 Mo 99 3.5-07 1.2-20 7.0-09 Tc 99m 2.1-09 7.4-23 5.0-07 Te 132 1.5-07 5.3-21 4.0-09 Cs 134 4.7-03 1.7-16 4.0-10 Cs 136 1.9-07 6.7-21 6.0-09 Cs 137 7.8-03 2.7-16 5.0-10 0.26 mi E /Q = 1.11 x 10-6 sec/m3 Limits used are those that were in effect at the time of the analysis.

KEY: 3.5 - 11 = 3.5 x 10-11 11.3-31 REVISION 5 - DECEMBER 1994

BYRON-UFSAR TABLE 11.3-8 ATMOSPHERIC DILUTION FACTORS USED IN DETERMINING OFFSITE DOSES

/Q2 D/Q*

LOCATION (sec/m3) (l/m2)

Nearest site boundary (0.26 mi E) 1.11 - 06 7.86 - 09 Nearest residence (0.30 mi ESE) 7.61 - 07 6.39 - 09 Nearest garden (0.60 mi SW) 1.43 - 07 1.68 - 09 Nearest meat animal (0.60 mi SSE) 2.53 - 07 1.75 - 09 Nearest milk cow (1.50 NE) 1.09 - 07 8.71 - 10 Calculated using the methodology of NRC Regulatory Guide 1.111, Revision 1, July 1977.

KEY: l.ll - 06 = 1.11 x 10-6 11.3-32 REVISION 1 - DECEMBER 1989

BYRON-UFSAR TABLE 11.3-9 BYRON-EXPECTED INDIVIDUAL DOSES FROM GASEOUS EFFLUENTS DOSE RATE (mrem/yr)

TOTAL LOCATION PATHWAY BODY SKIN THYROID BONE LIVER LUNG GI-LLI Nearest Plume 0.023 0.073 Residence (0.3 mi ESE)

Ground Deposition 0.057 0.067 Inhalation Adult 0.030 0.048 0.004 0.030 0.032 0.030 Teen 0.031 0.053 0.005 0.031 0.033 0.031 Child 0.027 0.054 0.007 0.028 0.029 0.027 Infant 0.016 0.040 0.005 0.016 0.017 0.016 Nearest Garden Leafy Vegetables (0.6 mi SW) Adult 0.006 0.028 0.002 0.006 0.006 0.006 Teen 0.004 0.023 0.002 0.004 0.004 0.004 Child 0.005 0.033 0.004 0.005 0.005 0.005 Stored Vegetables Adult 0.083 0.081 0.033 0.084 0.079 0.081 Teen 0.103 0.102 0.057 0.108 0.100 0.101 Child 0.169 0.171 0.138 0.180 0.167 0.167 Nearest Meat Meat Animal Adult 0.019 0.023 0.016 0.019 0.019 0.019 (0.6 mi SSE) Teen 0.013 0.016 0.014 0.013 0.013 0.013 Child 0.017 0.021 0.025 0.017 0.016 0.016 Nearest Milk Cow Milk (1.5 mi NE) Adult 0.027 0.102 0.012 0.027 0.025 0.025 Teen 0.037 0.164 0.024 0.040 0.036 0.035 Child 0.062 0.321 0.059 0.069 0.061 0.060 Infant 0.099 0.730 0.113 0.115 0.099 0.097 11.3-33

BRAIDWOOD-UFSAR TABLE 11.3-7 COMPARISON OF MAXIMUM OFFSITE AIRBORNE CONCENTRATIONS WITH 10 CFR 20 LIMITS MAXIMUM SITE ANNUAL RELEASE BOUNDARY3 10 CFR 20**

FROM ONE UNIT CONCENTRATION CONCENTRATION ISOTOPE (Ci/yr) (Ci/ml) (Ci/ml)

H 3 1.0+03 2.6-11 2.0-07 C 14 8.0+00 2.0-13 1.0-07 Ar 41 2.5+01 6.4-13 4.0-08 Kr 85m 5.0+00 1.3-13 1.0-07 Kr 85 7.0+02 1.8-11 3.0-07 Kr 87 1.0+00 2.6-14 2.0-08 Kr 88 8.0+00 2.1-13 2.0-08 Xe 131m 4.0+01 1.0-12 4.0-07 Xe 133m 1.6+01 4.1-13 3.0-07 Xe 133 2.0+03 5.1-11 3.0-07 Xe 135 1.5+01 3.9-13 1.0-07 Xe 138 1.0+00 2.6-14 3.0-08 I 131 5.4-02 1.4-15 1.0-10 I 132 3.7-03 9.5-17 3.0-09 I 133 7.2-02 1.8-15 4.0-10 Cr 51 5.3-08 1.4-21 8.0-08 Mn 54 4.7-03 1.2-16 1.0-09 Fe 55 7.0-07 1.8-20 3.0-08 Fe 59 1.6-03 4.1-17 2.0-09 Co 58 1.6-02 4.1-16 2.0-09 Co 60 7.3-03 1.9-16 3.0-10 Ni 63 7.0-07 1.8-20 2.0-09 Sr 89 3.4-04 8.7-18 3.0-10 Sr 90 6.2-05 1.6-18 3.0-11 Y 91 1.5-09 3.9-23 1.0-09 Mo 99 3.5-07 9.0-21 7.0-09 Tc 99m 2.1-09 5.4-23 5.0-07 Te 132 1.5-07 3.9-21 4.0-09 Cs 134 4.7-03 1.2-16 4.0-10 Cs 136 1.9-07 4.9-21 6.0-09 Cs 137 7.8-03 2.0-16 5.0-10 0.30 mi NW /Q = 8.10 x 10-7 sec/m3 Limits used are those that were in effect at the time of the analysis.

KEY: 2.6 - 11 = 2.6 x 10-11 11.3-34 REVISION 5 - DECEMBER 1994

BRAIDWOOD-UFSAR TABLE 11.3-8 ATMOSPHERIC DILUTION FACTORS USED IN DETERMINING OFFSITE DOSES

/Q4 D/Q*

LOCATION (sec/m3) (l/m2)

Nearest site boundary (0.30 mi NW) 8.10 - 07 4.36 - 09 Nearest residence (0.30 mi NW) 8.10 - 07 4.36 - 09 Nearest garden (0.30 mi NW) 8.10 - 07 4.36 - 09 Nearest meat animal (1.70 mi NW) 7.73 - 08 4.49 - 10 Nearest milk cow (1.7 mi WSW) 7.79 - 07 3.70 - 10 Nearest milk goat (4.1 mi E) 3.43 - 08 1.49 - 10 Calculated using the methodology of NRC Regulatory Guide 1.111, Revision 1, July 1977.

KEY: 8.10 - 07 = 8.10 x 10-7 11.3-35

BRAIDWOOD-UFSAR TABLE 11.3-9 BRAIDWOOD-EXPECTED INDIVIDUAL DOSES FROM GASEOUS EFFLUENTS DOSE RATE (mrem/yr)

TOTAL LOCATION PATHWAY BODY SKIN THYROID BONE LIVER LUNG GI-LLI Nearest Residence Plume 0.023 0.074 (0.3 mi NW)

Ground Deposition 0.039 0.046 Inhalation Adult 0.035 0.054 0.004 0.035 0.037 0.035 Teen 0.036 0.059 0.005 0.036 0.038 0.036 Child 0.032 0.060 0.007 0.032 0.034 0.032 Infant 0.019 0.044 0.005 0.019 0.020 0.019 Nearest Garden Leafy Vegetables (0.3 mi NW) Adult 0.035 0.090 0.012 0.035 0.034 0.034 Teen 0.025 0.072 0.012 0.025 0.024 0.024 Child 0.031 0.102 0.022 0.031 0.030 0.030 Stored Vegetables Adult 0.498 0.491 0.173 0.500 0.488 0.491 Teen 0.622 0.619 0.298 0.634 0.614 0.616 Child 1.025 1.029 0.727 1.053 1.019 1.018 Nearest Meat Meat Animal Adult 0.006 0.007 0.005 0.006 0.006 0.006 (1.7 mi NW) Teen 0.004 0.005 0.004 0.004 0.004 0.004 Child 0.005 0.006 0.008 0.005 0.005 0.005 11.3-36 REVISION 3 - DECEMBER 1991

BRAIDWOOD-UFSAR TABLE 11.3-9 (Cont'd)

DOSE RATE (mrem/yr)

TOTAL LOCATION PATHWAY BODY SKIN THYROID BONE LIVER LUNG GI-LLI Nearest Milk Cow Milk (1.7 mi WSW) Adult 0.020 0.051 0.008 0.020 0.019 0.019 Teen 0.028 0.081 0.016 0.029 0.027 0.027 Child 0.047 0.155 0.040 0.050 0.047 0.046 Infant 0.075 0.339 0.077 0.082 0.075 0.075 Nearest Milk Goat Milk (4.1 mi E) Adult 0.018 0.032 0.004 0.018 0.017 0.017 Teen 0.024 0.049 0.008 0.026 0.023 0.023 Child 0.039 0.091 0.020 0.043 0.039 0.038 Infant 0.061 0.188 0.038 0.068 0.061 0.060 11.3-37

B/B-UFSAR TABLE 11.3-10 EXHAUST STACK AIRFLOW TABULATION CASE 1 CASE 2 REFUELING EXCEPT NORMAL PLANT MINI-FLOW (cfm) OPERATION (cfm)

UNIT 1 Auxiliary Building Exhaust 135,980 135,980 Laboratory System Exhaust 14,430 (Byron) 14,430 (Byron) 13,030 13,030 (Braidwood) (Braidwood)

Off Gas System Steam Jet Air Ejector 0 32 Gland Steam Condenser Exhaust 0 1,400 (Nominal)

Containment Purge System Mini-Purge Exhaust (3000 CFM) 0 0 Main-Purge Exhaust 43,900 0 194,310 (Byron) 151,842 (Byron) 192,910 150,442 (Braidwood) (Braidwood)

UNIT 2 Auxiliary Building Exhaust 135,980 135,980 Auxiliary Building Filtered Vents 1,000 1,000 Solid Radwaste Area Exhaust 8,630 8,630 Off Gas System Steam Jet Air Ejector 0 32 Gland Steam Condenser Exhaust 0 1,400 (Nominal)

Containment Purge System Mini-Purge Exhaust (3000 CFM) 0 0 Main-Purge Exhaust 43,900 0 189,510 147,042 11.3-38 REVISION 17 - DECEMBER 2018

B/B-UFSAR 11.4 SOLID WASTE MANAGEMENT SYSTEM 11.4.1 Design Bases The solid radwaste system has been designed to receive, concentrate, solidify if required, package, handle, and provide temporary storage facilities for radioactive wet solid wastes generated by Units 1 and 2 prior to offsite shipment and disposal.

The system has provisions for transferring wet solid radwaste to vendor-supplied radwaste system for processing and disposal. The solid waste management system also receives, decontaminates and/or compacts (Byron only), and provides temporary storage facilities for radioactive dry wastes produced during station operation and maintenance prior to offsite shipment and disposal. This system does not normally handle large waste materials such as activated core components.

11.4.1.1 Power Generation Design Bases The solid radwaste system is designed to minimize the volume of solidified waste requiring shipment offsite. The system is designed specifically for a 40-year service life, maximum reliability, minimum maintenance, and minimum exposure to operating and maintenance personnel. The system has the flexibility to handle a wide range of radioactive waste products.

Equipment and storage capacities, as noted in Table 11.4-1, are selected to meet the station's solid waste processing needs in all the operational modes of the station, including anticipated operational occurrences, without impairing the power generation availability of the station. Storage space is designed to accommodate approximately 2 years at the current normal output of packaged waste. This amount of time was selected to allow for some decay of drummed material, startups, trucking strikes, unavailability of burial sites, etc.

11.4.1.2 Safety Design Bases The solid radwaste system is designed to package radioactive solid wastes for offsite shipment and burial in accordance with applicable NRC and DOT regulations including 49 CFR 170-178 and 10 CFR 71.

DOT-approved drums are used for packaging solidified wet solid wastes and for packaging dry solid wastes and spent filter cartridges. Steel liners and high integrity containers (HICs) are used for solidified wet solid wastes and dewatered resin. HICs are used for spent filter cartridges, dry solid wastes, or solidified, wet solid wastes.

System safety is emphasized through redundancy in design of primary components, compartmentalization of equipment layout, remote automatic and/or manual operation, shielding, containment of 11.4-1 REVISION 12 - DECEMBER 2008

B/B-UFSAR possible spills and displaced air, remote decontamination, if required, accurate process monitoring, and interlocking of process controls.

Complete solidification of wastes requiring solidification that is handled by the vendor-supplied radwaste system is ensured by complying with the vendor's process control program.

The solid radwaste system is designed to fail safe upon loss of system power, water, or air supply. System controls are designed to avoid a malfunction or spill due to operator error. The system is designed to keep the containers clean, reducing decontamination and cleaning requirements.

The solid radwaste storage area, the non used volume reduction (VR) system and the non used VR product solidification system are enclosed in a Safety Category II structure. The Byron non used solid radwaste processing equipment is in a Safety Category I structure. The below grade walls are part of the total structural shear wall system and as such are designed to withstand the effects of an earthquake. All piping and components of the system are designed and constructed in accordance with requirements for classification of Quality Group D.

Waste may be sent to an offsite vendor in acceptable DOT containers for processing prior to disposal. The vendor may volume reduce, sort, decontaminate, and process to produce a form acceptable for burial.

To reduce leakage, piping is welded and pump leakoffs are taken to the drain system. Most valves, except for a few specialty valves, are of the plug type designed to minimize leakage.

The design-basis solid radwaste system output volume is shown in Table 11.4-2.

11.4.1.3 Type of Waste The types of wastes handled by the solid radwaste system consist of the following:

a. Expended deep bed demineralizer bead resins typically consisting primarily of a copolymer of styrene and divinylbenzene.
b. Disposable cartridge filter elements typically consisting of epoxy-impregnated cellulose fiber or resin-impregnated glass fiber bonded in stainless steel hardware.

11.4-2 REVISION 9 - DECEMBER 2002

B/B-UFSAR

c. Low-level dry active wastes consisting of air filters; miscellaneous paper, rags, etc., from contaminated areas; contaminated clothing, tools, and equipment parts which cannot be effectively decontaminated; and solid laboratory wastes.
d. Intermediate level dry wastes (e.g., core components) are not solidified, but decontaminated and shipped in special containers.

11.4.1.4 Expected Volumes and Isotopic Compositions Table 11.4-2 indicates the design-basis solid radwaste system output (maximum and expected annual volumes). The radionuclide content of the various types of waste is indicated in Tables 11.1-7 through 11.1-12. These values are the expected values at the time the plants were licensed. Byron and Braidwood Nuclear stations have uprated the core power level twice. First to a core power level of 3586.6 MWt, then to the Measurement Uncertainty Recapture uprate power level of 3645 MWt. The original licensed power level was 3411 MWt. The original expected solid radwaste release data presented in the UFSAR is based on a power level of 3565 MWt.

As uprated does not appreciably change the estimated coolant activity, and maintenance and operational practices remain unaffected by uprate, the calculated specific activity of the solid waste is expected to remain essentially unchanged. The volume of solid waste is also not expected to increase since power uprate does not cause appreciable impact on equipment performance nor does it require drastic changes in system operation. Therefore, power uprate has no significant impact on the calculated solid waste estimates presented in this section.

Actual data from discharged wastes are available in the effluent release reports, which are prepared in accordance with the ODCM.

Dry active waste and all other waste streams are sampled in accordance with 10 CFR 61 to support accurate characterization of the waste. Station and/or corporate procedures are then used to characterize and quantify the waste prior to shipment.

11.4.1.5 ETSB-BTP 11-3 Comparison The solid radwaste system has been designed to meet the design criteria of the Effluent Treatment Systems Branch (ETSB), Branch Technical Position BTP 11-3.

11.4-3 REVISION 15 - DECEMBER 2014

BYRON-UFSAR 11.4.1.6 Comparison of Processing Capacity and Design Basis Waste Volumes The vendor-supplied radwaste system is capable of filling, dewatering, drying, and preparing a liner of spent resin for shipment. Each liner would contain varying amounts of resin based upon the radiation dose being emitted by the material on the resins. Based upon the preparation rate, there is adequate capacity to process the expected waste volume.

Table 11.4-2 gives the following annual expected values of waste to be processed and the resultant number of containers:

Exhausted deep bed resins 1,600 ft3 10 liners or 2,393 drums

  • Sludges and liquids 18,690 ft3 5,140 drums Cartridge filter elements --- 190 drums or 2 liners Total: 7,723 drums or 5,140 drums and 12 liners The number of drums and liners to be processed is based on the volumes of waste as indicated above and on the following drumming efficiencies:

Exhausted deep bed resins 110 to 200 ft3/liner

  • Sludges and liquids 27.5 gal/drum (average)

The actual data are available in the effluent release reports, which are prepared in accordance with the ODCM.

The processing capacity of the solid waste system is adequate to handle the maximum expected volumes of waste. The solid waste system has excess capacity.

  • Sludges and liquids are normally processed by the liquid radwaste system.

11.4-4 REVISION 13 - DECEMBER 2010

BRAIDWOOD-UFSAR 11.4.1.6 Comparison of Processing Capacity and Design Basis Waste Volumes The vendor-supplied radwaste system is capable of filling, dewatering, drying, and preparing a liner of spent resin for shipment. Each liner would contain varying amounts of resin based upon the radiation dose being emitted by the material on the resins. Based upon the preparation rate, there is adequate capacity to process the expected waste volume.

Station operating experience indicates that it requires approximately 1/2 shift, i.e., 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, to remove a filter from its vessel, place it in a cement-lined drum, and transport the drum to the radwaste building for temporary storage and/or further processing.

Filters, after decay, are placed in a vendor-supplied container for disposal. Each container holds up to 150 filter elements.

Operating experience indicates it takes approximately one shift to place 10 to 15 filters in a container. Based upon the aforementioned rate, there is adequate capacity to process the expected number of filters.

Table 11.4-2 gives the following annual expected values of waste to be handled and the resultant number of containers:

Exhausted deep bed resins 1,600 ft3 10 liners

  • Sludges and liquids 18,690 ft3 156 liners or 5140 drums Cartridge filter elements --- 2 liners Total: 168 liners or 12 liners and 5140 drums The number of containers to be processed is based on the volumes of waste as indicated above and on the following drumming efficiencies:
  • Sludges and liquids are normally processed by the liquid radwaste system.

11.4-5 REVISION 13 - DECEMBER 2010

BRAIDWOOD-UFSAR Exhausted deep bed resins 110 to 200 ft3/liner Sludges and liquids 120 ft3/liner Cartridge filter elements 150 filter elements/liner The actual data are available in the effluent release reports, which are prepared in accordance with the ODCM.

The processing capacity of the solid waste system is adequate to handle the maximum expected volumes of waste. The solid waste system has excess capacity.

11.4-6 REVISION 7 - DECEMBER 1998

B/B-UFSAR 11.4.1.7 Solid Radwaste System Monitoring The solid radwaste system monitoring and instrumentation is discussed in Subsection 12.3.4. The design confidence level for each radiation monitoring channel is 95%. The confidence level is based upon equipment reliability and the statistical nature of the measurements. For a further discussion on the confidence levels and the indicated ranges of the monitoring equipment refer to Subsection 12.3.4.

11.4.2 System Description Operation of the solid waste management system is indicated by Figure 11.4-1. Layouts of the packaging, storage, and shipping areas are shown on Drawings M-9 and M-12.

The solid radwaste system is comprised of a number of components or subsystems. They are listed in Table 11.4-1 along with their number, design capacity, and the materials of which they are constructed.

11.4.2.1 Deleted 11.4.2.2 Deleted 11.4.2.3 Deleted 11.4-7 REVISION 9 - DECEMBER 2002

B/B-UFSAR Pages 11.4-8 through 11.4-10 have been deleted intentionally.

11.4-8 through 11.4-10 REVISION 6 - DECEMBER 1996

B/B-UFSAR 11.4.2.4 Drum-Handling Equipment This equipment includes four remotely operated cranes with three of the cranes having television cameras for visual surveillance two drum transfer carts and one cartridge filter transfer vehicle (Braidwood only).

At Byron, the two fixed bridge cranes in the drumming area are used to remotely transport drums to and from the drum transfer carts.

The traveling bridge crane in the storage area is used to transport and position sealed containers in either intermediate or low level storage, retrieve and transport them to trucks for offsite disposal, and load prepared drums onto and remove processed drums from the drum transfer carts. Two electrical circuits are provided for the trolley, bridge, and hoist, one for the high-speed and one for the low-speed motors. This ensures that electrical failure will not prevent remote removal of the crane from a radiation zone or completing the operation in process at time of failure. An adaptor is supplied which can be attached to the grab for righting drums which have come to rest horizontally. A crane target grid system combined with television cameras is provided for accurate remote control positioning. For safety, the container must be raised to the full-up position before high speed operation is possible, and the container cannot be released from the grab while the container is suspended.

At Byron, the remotely operated crane without a television camera is used to lower the drum onto a drum transfer cart. At Braidwood, the remotely operated crane without a television camera is used to remove a drum containing a filter from the cartridge filter transfer vehicle and lower the drum onto a drum transfer cart.

At Byron, the drums are transported through the tunnel connecting the drumming area and the storage area by two drum transfer carts.

At Braidwood, the drums are transported through the tunnel connecting the DAW sorting area and the storage area by two drum transfer carts. Each of the two carts is independently controlled.

The carts may be operated in parallel. Each cart is designed to carry one drum at a time; however, each cart has room to carry two drums if necessary. The carts are a-c powered with heavy duty 3-hp d-c motors and equipped with high and low-speed drives. The carts are equipped with automatic couplers so that a stalled cart in the tunnel may be retrieved by the second cart. Each cart is guided by rails set into the floor. Operation of the carts is semiautomatic.

11.4-11 REVISION 7 - DECEMBER 1998

B/B-UFSAR The cartridge filter transfer vehicle holds one 55-gallon drum.

This vehicle transports drums containing spent filters from the filter area to the filter drop area where the drum is lowered onto a drum transfer cart (Braidwood only).

The spent filter can be placed in a drum on the cartridge filter transfer vehicle (Braidwood only). If the filter dose rate indicates that shielding is required, a drum that contains a precast concrete liner would be used. The filter can be removed and placed into the drum by manual manipulation with reach rods.

Filter drums may be lowered onto the drum transfer cart for transport to the radwaste building.

11.4.2.5 Smear Test and Label Station This portion of the solid waste management system consists of a setdown position for a single drum within an open-topped shielded cubicle provided with side access opening and working tools to accomplish remote labeling, smear testing, and radiation monitoring of all external surfaces of sealed drums prior to offsite disposal.

If a drum is found to be contaminated, it is decontaminated prior to storage. This system is normally not used.

11.4.2.6 Dry Waste Compactor (Byron only)

The dry waste compactor compresses paper, fabrics, plastics, and light metal into 55-gallon drums. An air filtration assembly is provided to maintain control of contaminated particles during compactor operation. Capture of radioactive dust is accomplished by means of a roughing filter and two HEPA filters operating in parallel.

The radioactivity of most of the dry waste is low enough to permit handling by contact. The compactor is designed to meet OSHA standards for safe operation and built to standards for a 40-year expected life of the station. This component is normally not used.

11.4.2.7 Storage Areas Shielded areas are provided for storage of intermediate and low activity containers and compacted dry waste drums per requirements noted in Table 11.4-1. Visual surveillance for the intermediate and low-level storage area is provided by the traveling bridge crane television cameras or other remote cameras. Storage is provided for uncompressible dry solid waste. The storage areas are drained to the radwaste building sump with the exception of the low-level storage area at Braidwood. This bermed area may be used for low activity concentrated liquid waste storage tanks. The drains are sealed to prevent accidental spillage from entering the floor drain system, since the spilled liquid may have high boron concentration.

Radioactive waste may also be stored at an interim storage location away from the processing area while awaiting processing or shipment to a burial site.

11.4-12 REVISION 16 - DECEMBER 2016

B/B-UFSAR Byron Station Dry Active Waste (DAW) may be stored in the DAW building in suitable containers until it is shipped offsite to a disposal facility. If needed, plant equipment and tools that have been packaged in tool or gang boxes can be stored in the DAW facility once they have been packaged in tool or gang boxes.

Braidwood Station Dry Active Waste (DAW) may be stored in the DAW storage facility in suitable shipping containers until its shipped offsite to a disposal facility. If needed, plant equipment and tools that have been packaged in tool or gang boxes can be stored in the DAW facility once they have been packaged in tool or gang boxes. Volumetric liquids are not authorized for storage in the DAW facility. The only incidental liquids allowed in the building will be incidental to the tools and equipment themselves.

11.4-12a REVISION 16 - DECEMBER 2016

B/B-UFSAR 11.4.2.8 Control Room This room houses the equipment which is capable of remote visual monitoring and control of the solid radwaste system. A record board is mounted on the radwaste control room wall to record the location of all containers within the storage area. Container setdown positions are represented by hooks onto which tags are placed. The volume reduction system control panel and the volume reduction product solidification system control panel are also in this area.

At Byron, a liquid/solid interface control panel is provided for transferring waste to the solid radwaste system from the liquid radwaste subsystem for processing.

In the solid radwaste system, compressed air is used as the handling system instrument air. It is at a pressure of 70-100 psig and is used to operate various valves. Service air is used in the solid radwaste system to operate air-driven pumps, vacuums, and other air-driven equipment. Instrument air is used to operate various valves.

11.4.2.9 Deleted 11.4.2.10 Deleted 11.4.2.11 Deleted 11.4.2.12 System Interfaces The expected isotopic radioactivity for the feeds are given in Table 11.1-11. The interface descriptions, line numbers, sizes, design pressures, temperatures, flow rates, expected batch sizes, and expected gross radioisotope concentration are given in Table 11.4-3.

11.4.2.13 Deleted 11.4-13 REVISION 12 - DECEMBER 2008

B/B-UFSAR 11.4.3 Volume Reduction System Description The text for Subsection 11.4.3 has been deleted intentionally.

Byron and Braidwood Stations do not intend to use this equipment.

11.4.4 Polymer/VR Product Drumming Station The text for Subsection 11.4.4 has been deleted intentionally.

Byron and Braidwood Stations do not intend to use this equipment.

11.4-14 REVISION 6 - DECEMBER 1996

B/B-UFSAR Pages 11.4-15 through 11.4-51 have been deleted intentionally.

Pages 11.4-15 through 11.4-51 REVISION 6 - DECEMBER 1996

BYRON-UFSAR TABLE 11.4-1 SOLID WASTE MANAGEMENT SYSTEM EQUIPMENT AND STORAGE DESIGN CAPACITIES PROCESSING EQUIPMENT QUANTITY DESIGN CAPACITY MATERIALS Decanting tank 2 500 gallons 304L SS Decanting pump 2 18 gpm 304L SS Metering pump 4 15 gpm 304L SS Cement storage tank 1 1000 ft3 CS Drum processing unit 2 1 Drum 304L SS Packaging container (drum) - 55 gallons CS Packaging container (liner) - Up to 200 ft3 CS or Polyethylene Dry waste compactor 1 1 Drum CS Traveling bridge crane1 1 9.3 tons CS Fixed bridge crane1 2 1.0 ton CS Drum transfer car2 2 2 drums CS Startup heater 1 395 scfm 304SS/

316L-SS/

347SS Air heater 1 320 scfm 304SS/

316L-SS Gas heater 1 786 scfm 304SS/

316L-SS Fluid bed dryer air blower 1 317 scfm CS Dry waste processor air blower 1 300 scfm CS 11.4-52 REVISION 7 - DECEMBER 1998

BYRON-UFSAR TABLE 11.4-1 (Cont'd)

PROCESSING EQUIPMENT QUANTITY DESIGN CAPACITY MATERIALS Waste feed filter 1 30 gpm 316L-SS FBD inlet air filter 1 320 scfm CS DWP inlet air filter 1 300 scfm CS Gas filter assembly 2 466 scfm CS Recirculating gas filter 1 320 scfm CS Caustic tank 1 1000 gal 304SS Decon tank 1 650 gal 304SS Contaminated oil tank 1 150 gal CS Bed storage and transfer hopper 2 2900 lb 304SS Trash hopper 2 1500 lb CS/Fe Waste liquor storage tank 2 3500 gal 316L-SS Fluid bed dryer 1 0.41 gpm 347SS/

Inconel 625 Dry waste processor 1 83 lb/hr 347SS Trash conveyor 1 --- Rubber/CS Trash elevator 1 20 lb/min CS Waste feed pump 1 120 gph 316L-SS Waste recirc. pump 2 500 gpm 316L-SS Decon. pump 1 50 gpm 304SS Dryer feed pump 1 30 gph 316L-SS Condensate pump 1 22 gpm 316SS Contaminated oil pump 1 14 gpm CS Scrubber preconcentrator recirc. pump 1 20 gpm 316L-SS Caustic additive pump 2 15 gpm 304SS 11.4-53

BYRON-UFSAR TABLE 11.4-1 (Cont'd)

PROCESSING EQUIPMENT QUANTITY DESIGN CAPACITY MATERIALS Scrubber preconcentrator 1 16.8 gpm 316L-SS/

Inconel 625 Secondary scrubber 1 1142 scfm 316L-SS Condenser 1 22 gpm 316SS Metal detector 1 1 Trash Bag Al,Cu Volume reduction system 1 911 scfm 347SS gas/solids separator Trash shredder 1 20 lb/min Fe/CS/CrMo Steel Polymer storage tank 2 3000 gal 304L Promoter additive 1 6 gal 304 storage tank Isolation hopper 1 7.5 ft3 316L-SS Storage hopper 1 80 ft3 304L-SS Drum processing 1 1 drum 304L enclosure Flame arrester 2 --- ---

Volume reduction system 1 250 scfm 304L solidification system gas/solid separator Volume reduction product 1 250 scfm SA285 Gr. C blower Polymer circulating pump 1 15gpm/7.5gpm 316SS Promoter metering pump 1 10oz/min 420SS Roller conveyor 1 30 fpm CS Polymer filter 1 65 gpm 304SS Polymer station vent filter 1 75 scfm 304SS Volume reduction solidi- 1 180 scfm 304L fication system product blower filter 11.4-54

BYRON-UFSAR TABLE 11.4-1 (Cont'd)

NUMBER OF DESIGN CAPACITY STORAGE AREA STORAGE AREAS PER STORAGE AREA Low level 1 500 drums or 30 containers Intermediate level 1 640 drums or 30 containers Dry compacted waste 1 70 drums Dry uncompacted waste 1 90 ft3 Empty drum or container 2 100 drums or 6 containers (total)

NOTES

1. Overhead Crane Operating Speeds High-Speed Low-Speed Bridge 125 fpm 2.5 fpm Trolley 125 fpm 2.5 fpm Drum Grab Hoist 30 fpm 7.5 fpm
2. Drum Transfer Car Operating Speeds High-Speed Low-Speed 100 fpm 10 fpm 11.4-55 REVISION 7 - DECEMBER 1998

BYRON-UFSAR TABLE 11.4-2 EXPECTED AND DESIGN BASIS ANNUAL VOLUMES OF (UNITS 1 AND 2) SOLID WASTE MANAGEMENT SYSTEM OUTPUT*

Solid waste processed by the solid radwaste management system and quantities of processed waste requiring onsite storage or offsite disposal EXPECTED NUMBER OF DESIGN NUMBER OF TYPE OF WASTE VOLUMES CONTAINERS VOLUME CONTAINERS Deep Bed Resin 1,600 ft3 2,393 drums 1,600 ft3 2,393 drums or 10 liners or 10 liners Disposable Filter Elements 75 ft3 190 drums 75 ft3 190 drums or 2 liners or 2 liners Sludges and Liquids*** 16,850 ft3 4,580 drums 18,690 ft3 5,140 drums Dry Active Waste 36,220 ft3 580** drums 36,220 ft3 1,160** drums 73 boxes 73 boxes Total 54,745 ft3 7,743 drums, 56,585 ft3 8,883 drums, 73 boxes 73 boxes or 12 liners, or 12 liners, 5,350 drums 6,490 drums and 73 boxes and 73 boxes

  • The values given are approximate. The actual data are available in the effluent release reports, which are prepared in accordance with the ODCM.
    • Not solidified.
      • Sludges and liquids are normally processed in the liquid radwaste system.

11.4-56 REVISION 7 - DECEMBER 1998

BYRON-UFSAR TABLE 11.4-3 PLANT INTERFACES WITH SOLID RADWASTE SYSTEM ESTIMATED ESTIMATED GROSS INTERFACE NUMBER LINE* LINE EXPECTED TEMPERATURE EXPECTED ESTIMATED RADIOISOTOPE AND DESCRIPTION NUMBER SIZE PRESSURE (°F) FLOW RATE BATCH SIZE CONCENTRATION****

1. Spent Resin OWXX9A 1-1/2 in. 50 psig 90 120 gpm up to 400 gal 370 Ci/cc
2. Evaporator Concentrates OWX143BA 1-1/2 in. 35 psig 130-90 15 gpm 22.5-36.5 gal** 0.05 Ci/cc
3. Flush and Decontamination OWX146BA 1-1/2 in. 52 psig 110 50 gpm 25 gal 0.16 Ci/cc
4. Volume Reduction System***
a. Evaporator concentrates OVR80A 1-1/2 in. 35 psig 190 30 gpm 3500 gal 0.05 Ci/cc
b. Waste oil OVR69A 2 in. 25 psig 150 50 gpm 140 gal low
  • Typical line numbers, for Unit B line numbers the last letter is B.
    • Directly to the drum from a recirculation loop via a metering pump.
      • Byron does not operate the volume reduction system.
        • Based on Table 11.1-11.

Evaporator concentrates are normally processed in the liquid radwaste system.

11.4-57 REVISION 6 - DECEMBER 1996

BYRON-UFSAR TABLE 11.4-3 (Cont'd)

ESTIMATED ESTIMATED GROSS INTERFACE NUMBER LINE* LINE EXPECTED TEMPERATURE EXPECTED ESTIMATED RADIOISOTOPE AND DESCRIPTION NUMBER SIZE PRESSURE (°F) FLOW RATE BATCH SIZE CONCENTRATION****

c. Pump seals/dilution OPW60A 2 in. 50 psig 120 75 gpm continuous Primary water intermittent
d. Decon water supply OPMK7A 2 in. 135 psig 100 100 gpm 600 gal Primary
e. Cooling water supply OWSJ4A 4 in. 140 psig 110 156 gpm continuous 0.0
f. Cooling water return OWSJ6A 3 in. 140 psig 124 156 gpm continuous 0.0
g. Service air supply 2SA67A 1-1/2 in. 115/90 psig 120 78 scfm continuous 0.0
h. Filtered exhaust OVR084B 6 in. 2 in. H2O 175 477 scfm continuous 5.6 x 10-4 Ci/cc
i. Drains OWF69A 3 in. 50 psig 150 50 gpm intermittent 2.7 x 10-2 Ci/cc
j. Decon water return OVR123A 2 in. 50 psig 180 50 gpm 150 gal 0.05 Ci/cc
k. Filter backwash inlet OVR81A 3/4 in. 150 psig 250 50 gpm 50 gal Primary water
l. Filter backwash outlet OVR13A 3/4 in. 150 psig 200 50 gpm 50 gal 0.5 Ci/cc
m. Instrument air OVA210A 1 in. 115 psig 150 82 scfm continuous 0.0
n. Bed storage hopper fill OVR47A 6 in. ambient ambient gravity 50 lb 0.0 3 3
o. Dry active water - - ambient ambient 20 ft /min 7.5 ft Low 11.4-58

BYRON-UFSAR TABLE 11.4-3 (Cont'd)

ESTIMATED ESTIMATED GROSS INTERFACE NUMBER LINE* LINE EXPECTED TEMPERATURE EXPECTED ESTIMATED RADIOISOTOPE AND DESCRIPTION NUMBER SIZE PRESSURE (°F) FLOW RATE BATCH SIZE CONCENTRATION****

9. Volume Reduction System***

Production Solidification System

a. Cooling water supply OWO120A 1-1/2 in. 100 psig 100 10 gpm intermittent 0.0
b. Cooling water return OWO128A 1-1/2 in. 100 psig 100 10 gpm intermittent 0.0
c. Instrument air (polymer) OIA117A 1 in. 115 psig 120 5 scfm intermittent 0.0
d. Instrument air OVR257A 1/2 in. 115 psig 120 58 scfm intermittent 0.0 (equipment)
e. Instrument air OVR255A 1 in. 115 psig 120 58 scfm continuous 0.0 (equipment)
f. Instrument air OVR256A 3/4 in. 115 psig 120 58 scfm intermittent 0.0 (storage hopper)
g. Instrument air (blower) OVR258A 1 in. 115 psig 120 60 scfm intermittent 0.0
h. Drain (drum processing) OVR169A 3 in. 4 psig 180 20 gpm intermittent Low
i. Drain (storage hopper) OVR173A 2 in. 4 psig 180 15 gpm intermittent 8.4 x 10-2 Ci/cc
j. Drain (surge hopper) OVR181A 1-1/2 in. 4 psig 180 5 gpm intermittent 8.4 x 10-2 Ci/cc
k. Polymer filling ------- 2 in. -1 in. H2O ambient 10 scfm continuous 0.0 station vent
l. Blower discharge OVR180A 2-1/2 in. 0.5 psig 120 60 scfm intermittent Low 11.4-59 REVISION 6 - DECEMBER 1996

B/B-UFSAR Pages 11.4-60 through 11.4-63 have been deleted intentionally.

11.4-60 through 11.4-63 REVISION 6 - DECEMBER 1996

BRAIDWOOD-UFSAR TABLE 11.4-1 SOLID WASTE MANAGEMENT SYSTEM EQUIPMENT AND STORAGE DESIGN CAPACITIES PROCESSING EQUIPMENT QUANTITY DESIGN CAPACITY MATERIALS Packaging container - up to 200 ft3 CS or (liner) polyethylene Packaging container (drum) - 55 gal CS Traveling bridge crane1 1 9.3 tons CS Fixed bridge crane1 2 1.0 ton CS Drum transfer car2 2 2 drums CS Cartridge filter transfer vehicle3 1 1 drum CS NOTE: Processing equipment for the volume reduction and radwaste solidification systems has been intentionally deleted from this table. Braidwood station does not intend to use this equipment.

11.4-64 REVISION 12 - DECEMBER 2008

BRAIDWOOD-UFSAR TABLE 11.4-1 (Cont'd)

Page 11.4-65 has been deleted intentionally.

11.4-65 REVISION 9 - DECEMBER 2002

BRAIDWOOD-UFSAR TABLE 11.4-1 (Cont'd)

Page 11.4-66 has been deleted intentionally.

11.4-66 REVISION 9 - DECEMBER 2002

BRAIDWOOD-UFSAR TABLE 11.4-1 (Cont'd)

NUMBER OF DESIGN CAPACITY STORAGE AREA STORAGE AREAS PER STORAGE AREA Low level 1 500 drums or 30 containers Intermediate level 1 640 drums or 30 containers Dry compacted waste 1 70 drums Dry uncompacted waste 1 90 ft3 Empty drum or container 2 100 drums or 6 containers (total)

NOTES

1. Overhead Crane Operating Speeds High-Speed Low-Speed Bridge 125 fpm 2.5 fpm Trolley 125 fpm 2.5 fpm Drum Grab Hoist 30 fpm 7.5 fpm
2. Drum Transfer Car Operating Speeds High-Speed Low-Speed 100 fpm 10 fpm
3. Cartridge Filter Transfer Vehicle Operating Speeds Variable 0 fpm to 250 fpm 11.4-67 REVISION 7 - DECEMBER 1998

BRAIDWOOD-UFSAR TABLE 11.4-2 EXPECTED AND DESIGN BASIS ANNUAL VOLUMES OF (UNITS 1 AND 2) SOLID WASTE MANAGEMENT SYSTEM OUTPUT*

Solid waste processed by the solid radwaste management system and quantities of processed waste requiring onsite storage or offsite disposal EXPECTED NUMBER OF DESIGN NUMBER OF TYPE OF WASTE VOLUMES CONTAINERS VOLUME CONTAINERS Deep Bed Resin 1,600 ft3 10 liners 1,600 ft3 10 liners Disposable Filter Elements 75 ft3 2 liners 75 ft3 2 liners Sludges and Liquids*** 16,850 ft3 141 liners 18,690 ft3 156 liners Dry Active Waste 36,220 ft3 580 drums** 36,220 ft3 1,160 drums**

73 boxes 73 boxes Total 54,745 ft3 153 liners 56,585 ft3 168 liners 580 drums 1,160 drums 73 boxes 73 boxes

  • The values given are approximate. The actual data are available in the effluent release reports, which are prepared in accordance with the ODCM.
    • Not solidified.
      • Sludges and liquids are normally processed in the liquid radwaste system.

11.4-68 REVISION 7 - DECEMBER 1998

BRAIDWOOD-UFSAR TABLE 11.4-3 PLANT INTERFACE WITH SOLID RADWASTE SYSTEM ESTIMATED ESTIMATED GROSS INTERFACE NUMBER LINE* LINE EXPECTED TEMPERATURE EXPECTED ESTIMATED RADIOISOTOPE AND DESCRIPTION NUMBER SIZE PRESSURE (°F) FLOW RATE BATCH SIZE CONCENTRATION**

1. Spent Resin OWX425A 1-1/2 in. 75 psig 90 40 gpm up to 845 gal 1500 Ci/cc
2. Evaporator Concentrates*** OWXZ9D 1-1/2 in. 109 psig 130-190 45 gpm 100 gal 0.05 Ci/cc
3. Resin Flush and Decontamination OWX137A 2 in. 50 psig 120 50 gpm 115 gal 0.16 Ci/cc
4. Pump Seals
a. Evaporator concentrates OWX530AA 1/2 in. 5 psig ambient .25 gpm intermittent Low
b. Spent resin OWX589CA 3/8 in. 90 psig 120 .25 gpm intermittent Primary water
5. Volume Reduction System
a. Waste oil OVR69A 2 in. 25 psig 150 50 gpm 140 gal low
b. Pump seals/dilution water OWMK7A 2 in. 135 psig 100 75 gpm continuous 0.0 intermittent
c. Decon water supply OWMK7A 2 in. 135 psig 100 100 gpm 600 gal 0.0
  • Typical line numbers, for Unit B line numbers the last letter is B.
    • Based on Table 11.1-11.
      • Evaporator concentrates are normally processed in the liquid radwaste system.

Braidwood does not operate the volume reduction system.

11.4-69 REVISION 6 - DECEMBER 1996

BRAIDWOOD-UFSAR TABLE 11.4-3 (Cont'd)

ESTIMATED ESTIMATED GROSS INTERFACE NUMBER LINE* LINE EXPECTED TEMPERATURE EXPECTED ESTIMATED RADIOISOTOPE AND DESCRIPTION NUMBER SIZE PRESSURE (°F) FLOW RATE BATCH SIZE CONCENTRATION**

d. Cooling water supply OWSJ4A 4 in. 140 psig 110 156 gpm continuous 0.0
e. Cooling water supply OWSJ6A 3 in. 140 psig 124 156 gpm continuous 0.0
f. Filtered exhaust OVR084B 4 in. 2 in. H2O 175 477 scfm continuous 5.6x10-4 Ci/cc
g. Drains OWF69A 3 in. 50 psig 150 50 gpm intermittent 2.7x10-2 Ci/cc
h. Decon water supply OVR123A 2 in. 50 psig 180 50 gpm 150 gal 0.05 Ci/cc
i. Filter backwash inlet OVR81A 3/4 in. 150 psig 250 50 gpm 50 gal Primary water
j. Filter backwash outlet OVR13A 3/4 in. 150 psig 200 50 gpm 50 gal 0.5 Ci/cc
k. Instrument air OVR210A 1 in. 115 psig 150 82 scfm continuous 0.0
l. Bed storage hopper fill OVR47A 6 in. ambient ambient gravity 50 lb Low 3 3
m. Dry active waste - - ambient ambient 20 ft /min 7.5 ft Low
6. Volume Reduction System Production Solidification System
a. Cooling water supply OWO348A 1-1/2 in. 100 psig 100 10 gpm intermittent 0.0
b. Cooling water return OWO349A 1-1/2 in. 100 psig 100 10 gpm intermittent 0.0
c. Instrument air (polymer) OIA116A 1 in. 115 psig 120 5 scfm intermittent 0.0 11.4-70 REVISION 6 - DECEMBER 1996

BRAIDWOOD-UFSAR TABLE 11.4-3 (Cont'd)

ESTIMATED ESTIMATED GROSS INTERFACE NUMBER LINE* LINE EXPECTED TEMPERATURE EXPECTED ESTIMATED RADIOISOTOPE AND DESCRIPTION NUMBER SIZE PRESSURE (°F) FLOW RATE BATCH SIZE CONCENTRATION**

d. Instrument air (drum processing) OVR257A 1/2 in. 115 psig 120 58 scfm intermittent 0.0
e. Instrument air (equipment) OVR255A 1 in. 115 psig 120 58 scfm continuous 0.0
f. Air bump (surge hopper) OVR307A 3/8 in. 40 psig 120 58 scfm intermittent 0.0
g. Instrument air (storage hopper) OVR256A 3/4 in. 115 psig 120 58 scfm intermittent 0.0
h. Air bump (storage hopper) OVR310A 3/8 in. 40 psig 120 58 scfm intermittent 0.0
i. Instrument air (blower) OVR258A 1 in. 115 psig 120 60 scfm intermittent 0.0
j. Drain (drum processing) OVR169A 3 in. 4 psig 180 20 gpm intermittent Low
k. Drain (storage hopper) OVR173A 2 in. 4 psig 180 15 gpm intermittent 8.4x10-2 Ci/cc
l. Drain (surge hopper) OVR181A 1-1/2 in. 4 psig 180 5 gpm intermittent 8.4x10-2 Ci/cc
m. Polymer filling station vent ----- 2 in. -1 in. H2O ambient 10 scfm continuous 0.0
n. Blower discharge OVR180A 2-1/2 in. 0.5 psig 120 60 scfm intermittent Low 11.4-71

BRAIDWOOD-UFSAR TABLE 11.4-3 (Cont'd)

ESTIMATED ESTIMATED GROSS INTERFACE NUMBER LINE* LINE EXPECTED TEMPERATURE EXPECTED ESTIMATED RADIOISOTOPE AND DESCRIPTION NUMBER SIZE PRESSURE (°F) FLOW RATE BATCH SIZE CONCENTRATION**

7. Vendor Supplied Mobile Radwaste System
a. Instrument air O1A117A 3/4 in. 115 psig 120 50 scfm continuous 0.0
b. Service air OSAR1A 3/4 in. 115 psig 120 50 scfm continuous 0.0
c. Demineralized water OWMT2A 2 in. 135 psig 100 100 gpm intermittent 0.0
d. Service water supply OWS59A 2 in. 140 psig 96 25 gpm continuous 0.0
e. Service water return OWSX5A 2 in. 140 psig 96 25 gpm continuous 0.0
f. Drain OWX439A 2 in. 100 psig 100 25 gpm continuous 0.16 Ci/cc
g. Vent OVF075A 4 in. 3 psig 175 200 scfm continuous Low 11.4-72

B/B-UFSAR 11.5 PROCESS AND EFFLUENT RADIOLOGICAL MONITORING AND SAMPLING SYSTEMS This section describes the systems that monitor and sample the process and effluent streams in order to control the release of radioactive materials generated as a result of normal operation, anticipated operational occurrences, and during postulated accidents.

11.5.1 Design Bases 11.5.1.1 Design Objectives The process radiological monitoring and sampling system provides measurement, indication, and/or control of radioactivity in those streams which could conceivably be contaminated by radioactive substances.

The effluent radiological monitoring and sampling system provides measurement, indication, and control of radioactivity in those streams which discharge to the environs outside the plant boundaries.

The systems are subdivided into gaseous (airborne) systems, shown in Table 11.5-1, and liquid systems, shown in Table 11.5-2. Both continuous monitoring and sampling with associated laboratory analysis are used for all systems.

The process monitor systems provide operating personnel with radiological measurements within the plant process systems.

The continuous monitors provide a continuous readout of the radiation levels, and they annunciate or generate automatic control of the process streams when a significant increase occurs. By sampling and laboratory analysis, the type of radioactive material and the specific radionuclide present can be determined qualitatively and/or quantitatively.

The effluent monitoring systems provide operating personnel with a continuous readout of the radioactivity levels present in the plant's air exhaust and liquid discharge streams.

The objective of the effluent radiological monitoring system is to sample and monitor each plant effluent discharge path for radioactivity prior to discharge. This is satisfied by the installation of sampling monitors on the following airborne effluent streams and liquid effluent streams:

a. Airborne effluent streams:
1. station vent stacks.

11.5-1

B/B-UFSAR

b. Liquid effluent streams:
1. station blowdown, and
2. liquid radwaste effluent.

The objective of the process radiation monitoring system is to monitor those sections of the plant process to control the release of radioactivity into the effluent streams. This is satisfied by the installation of process gaseous and airborne radiation monitors and liquid process monitors in the following locations:

a. Process gaseous airborne monitors for:
1. auxiliary building ventilation exhausts,
2. fuel handling building ventilation exhausts,
3. radwaste building ventilation exhaust,
4. laundry room ventilation exhaust,
5. lab fume hood exhaust,
6. miscellaneous tank filtered vent exhaust,
7. containment purge effluent,
8. steam jet air ejector/gland steam exhaust, and
9. gas decay tank effluent.
b. Process liquid monitors for:
1. station blowdown,
2. steam generator blowdown,
3. boron thermal regeneration chiller surge tank return,
4. component cooling heat exchanger water outlet,
5. reactor containment fan coolers essential service water outlet,
6. radwaste evaporators condensate return,
7. gross failed fuel monitors, 11.5-2

B/B-UFSAR

8. condensate cleanup area sumps discharge, and
9. turbine building fire and oil sump discharge.

This group of monitors is used for surveillance and control of radioactive substances in gaseous and liquid effluents during normal reactor operations, including anticipated operational occurrences. Accident monitors are discussed separately in the subsequent text, in Subsection 12.3.4 and Section E.30 of Appendix E.

The design and operation characteristics of the process and effluent radiological monitoring and sampling system is based on requirements and guidance in 10 CFR 20, 10 CFR 50, 10 CFR 70, 10 CFR 100 for accidents analyzed using TID-14844 and 10 CFR 50.67 for AST, Regulatory Guides 1.21, 1.97, and 4.15, NUREG-0737, NUREG-0800, ANSI N13.1-1969, and ANSI N13.10-1974.

11.5.1.2 Design Criteria The design of the process and effluent radiological monitoring and sampling system was based on the following:

a. The particulate airborne monitors are beta scintillators, the iodine airborne monitors are gamma scintillators and the noble gas monitors are beta scintillators.
b. Liquid monitors are gamma-responsive scintillation detectors to provide maximum sensitivity to a water medium.
c. Shielding is provided to reduce background and increase sensitivity.
d. Background compensation is provided on selected monitors to increase sensitivity.
e. The gaseous monitor range of detectability is based on actual experience at operating PWRs.
f. The monitors are designed to fail in the interlock mode in the event of loss of power, loss of signal, or operate failure. For OPR31J, OPR32J, OPR33J, and OPR34J, the associated ESF actuation will occur on a 2/2 per train coincidence.
g. All alarms annunciate in the main control room.
h. Monitors readout, alarm, and trend in the main control room.
i. Monitor pumps are initiated locally and in the main control room.

11.5-3 REVISION 12 DECEMBER 2008

B/B-UFSAR

j. Monitor components are readily accessible for maintenance.
k. The monitoring systems are designed for operability within the environmental conditions anticipated. The plant environmental conditions are shown in Table 3.11-2. Instrument locations are shown in Tables 11.5-1 and 11.5-2.
l. Alarm setpoints are adjustable over the range of the instrument, excluding the upper (high) range detector setpoints 0RE-PR031A, C; 0RE-PR032A, C; 0RE-PR033A, C and 0RE-PR034A, C (these setpoints are above the range of the detector, thus eliminating each channel's interlock).
m. The following statements apply to the effluent monitors and samplers for airborne and gaseous radioactivity:
1. They continuously withdraw an isokinetic and representative sample as recommended by ANSI N13.1-1969.
2. The radioparticulates are concentrated on a high-efficiency filter and the radioiodines on an activated charcoal cartridge, which can be changed routinely for laboratory analysis.
3. The radionoble gases are continuously monitored for gross beta activity.
4. Grab sampling capability shall be provided to allow for periodic laboratory analysis.
n. Setpoints and ranges for effluent monitors are established to meet technical specification limits, which encompass 10 CFR 20 (including Table 2 of Appendix B) and 10 CFR 50 Appendix I objectives.

Setpoints for process monitors are established to provide a warning of increased system activity and to initiate corrective action where appropriate. Also, see Subsection 12.3.4 and Section E.30 of Appendix E.

Two independently adjustable radiation setpoints are provided for most monitors. The lower (alert) setpoint normally activates only an alarm, while the upper (high) setpoint activates an alarm and initiates corrective action where appropriate. Alarm and trip functions associated with the various monitors are 11.5-4 REVISION 6 - DECEMBER 1996

B/B-UFSAR listed in Tables 11.5-1 and 11.5-2. The setpoints are under the administrative control of the station manager or his authorized delegate and can be changed if needed within Radioactive Effluent Controls Program limits.

o. All process and effluent monitors are annunciated in the main control room. The radiation monitoring equipment in the main control room will feature an integrated audible (horn) and visual video display unit alarm system. Alarm conditions are automatically logged electronically for reporting and retrieval.

The audible alarm is actuated each time a new alarm message is received. The video display unit provides a color coded indication of low level (failure),

alert-interlock, high, and multi-level diagnostic alarms. The alarm message saved electronically includes the date, time, channel number, and alarm condition.

11.5.2 System Description 11.5.2.1 Instrumentation The process and effluent radiological monitoring and sampling systems monitor radiation levels in various plant operating systems and effluent streams. This includes both liquid and gaseous radiation monitoring.

Continuous Monitoring The system consists of a number of separate and distinct monitors and channels as listed in Tables 11.5-1 and 11.5-2. Each monitor consists of an isokinetic probe or a tap, detector(s) and associated electronics. The continuous sample is piped to a monitor where the sample is monitored for air particulate, gas, and iodine activity, as shown in Tables 11.5-1 and 11.5-2. Data and information from each channel is transmitted to the main control room.

The main control room for each unit contains a video display unit, an operators keyboard, and a work station that communicates with a server in the computer room. The server maintains an hourly record of radiation levels which may be stored on the recorder for historical purposes. When the radiation level for a particular channel is exceeded, the service, setpoint, and intensity level are displayed on the video display unit. In addition, the system alarms to indicate abnormal conditions.

The microprocessor for each monitor is provided with the following features:

11.5-5 REVISION 17 - DECEMBER 2018

B/B-UFSAR

a. monitor on-off switch and instrument available light,
b. high radiation level light, and
c. interlock alert radiation level light.

The operate failure alarm also annunciates in the main control room. This alarm will be initiated by loss of power, loss of signal, or operate failure. The operate failure will also initiate the interlock switching functions. For 0PR31J, 0PR32J, 0PR33J, and 0PR34J (Subsection 11.5.2.2.8) the associated ESF actuation will occur on a 2/2 per train coincidence. Reset action cannot be affected until the failure condition is corrected.

Sample probe locations are shown on HVAC drawings in Section 9.4.

Monitor locations are shown on the drawings referenced in Tables 11.5-1 and 11.5-2 and are also shown and identified on the radiation shielding figures in Section 12.3 (M-24 series drawings Sheets 1 through 20).

For the type of radiation detector and measurement made, see Tables 11.5-1 and 11.5-2.

For most channels which are interlocked with the safety-related systems, redundancy is maintained by using two separate and completely independent channels. In cases where these channels are non-lE, input to the safety-related systems is through non-lE interfacing circuitry located outside the radiation monitoring system cabinets. The redundant channels are designated in Tables 11.5-1 and 11.5-2 under "Remarks".

The range of radioactive concentrations to be monitored is listed in Tables 11.5-1 and 11.5-2 for each detector. The range selected was based on the expected level of radiation for each service.

For alarm and control interlock setpoint values, refer to the "Setpoint" column in Tables 11.5-1 and 11.5-2. Radiation monitors which interlock automatic control functions are designated as such in the remarks column of Tables 11.5-1 and 11.5-2. A reference to the explanatory text section is included.

The radiation monitoring channels employ radioactive check sources. Monitors automatically bypass the interlock function if one is provided upon initiation of the check source test switch.

11.5-6 REVISION 9 - DECEMBER 2002

B/B-UFSAR 11.5.2.2 Airborne Process and Effluent Monitors 11.5.2.2.1 Auxiliary Building Vent Stack Effluent Detectors lRE-PR028A, B, C, D, and E (air particulate, gas low range, iodine, gas high range and background subtraction channels, respectively) and 2RE-PR028A, B, C, D, and E (air particulate, gas low range, iodine, gas high range and background subtraction channels, respectively) monitor station stack effluent from the auxiliary building vent stacks (Units 1 and 2).

Additional features associated with these monitors include:

a. automatic isokinetic sampling system,
b. automatic grab sampling system,
c. tritium sampling system,
d. low/high range gas channels, and
e. background subtraction channel.

11.5.2.2.2 Auxiliary Building Plant Areas (For Auxiliary Building Vent Exhausts)

Detectors 0RE-PR021A, B, C (air particulate, gas, and iodine channels respectively) and 0RE-PR022A, B, C monitor auxiliary building plant areas.

High radiation is annunciated in the main control room.

11.5.2.2.3 Pipe Tunnel (For Auxiliary Building Vent Exhausts)

Detectors lRE-PR021A, B, C (air particulate, gas, and iodine channels respectively) and 2RE-PR021A, B, and C monitor the pipe tunnel.

High radiation is annunciated in the main control room.

Refer to Subsection 9.4.5.1 for description of fans and dampers.

11.5.2.2.4 Fuel-Handling Building Exhaust Detectors 0RE-PR024A, B, C (air particulate, gas, and iodine channels respectively) monitor fuel handling exhaust.

High radiation is annunciated in the main control room.

11.5-7 REVISION 6 - DECEMBER 1996

B/B-UFSAR 11.5.2.2.5 Containment Purge Effluent Detectors lRE-PR001A, B, and C (air particulate, gas and iodine channels respectively) monitor containment effluent for Unit 1, while detectors 2RE-PR001A, B, and C monitor the same for Unit 2.

High radiation is annunciated in the main control room.

11.5.2.2.6 Fuel-Handling Incident in the Fuel Handling Building Two area radiation detectors, 0RE-AR055 and 0RE-AR056, monitor for a postulated fuel-handling incident in the fuel handling building.

Area radiation monitor 0RT-AR055 is interlocked with booster fan 0VAO4CA. Area radiation monitor 0RT-AR056 is interlocked with booster fan 0VA04CB. Upon exceeding the interlock setpoint or as a result of certain monitor failures, a booster fan will automatically start and its associated bypass damper will close with proper VA system alignment.

The channels used for monitoring a postulated fuel-handling incident in the fuel handling building are Class lE.

Refer to Subsection 12.3.4 for further radiation monitor details.

11.5.2.2.7 Fuel-Handling Incident in the Containment Building Two area radiation detectors, lRE-AR011 and lRE-AR012, monitor for postulated fuel-handling incidents in the containment building for Unit 1, while area detectors 2RE-AR011 and 2RE-AR012 monitor the same for Unit 2.

Area radiation monitor lRT-AR011 is interlocked with Train A of the normal containment purge and minipurge isolation valves.

Area radiation monitor lRT-AR012 is interlocked with Train B of the normal containment purge and minipurge isolation valves.

At Byron, the normal containment purge isolation valves are normally closed during fuel movements and at Braidwood these valves are blocked closed.

Refer to Subsections 6.5.1.1.2, 9.4.8, and 9.4.9 for descriptions of the containment building HVAC system.

The channels used for monitoring a postulated fuel-handling incident in the containment building are Class lE.

Refer to Subsection 12.3.4 for further radiation monitor details.

11.5.2.2.8 Main Control Room Outside Air Intakes A and B Detectors 0RE-PR031A, B, and C (air particulate, gas and iodine channels, respectively) and 0RE-PR032A, B, and C monitor main control room outside air intake A. Detectors 0RE-PR033A, B, 11.5-8 REVISION 14 - DECEMBER 2012

B/B-UFSAR and C and 0RE-PR034A, B, and C monitor main control room outside air intake B.

Detectors 0RE-PR031B and 0RE-PR032B are interlocked with the makeup area unit fan 0VC03CA and main control room outside air intake A dampers. Automatically on high radiation, the outside air intake A dampers close, and the fan starts and in turn opens the main control room turbine building air intake A dampers mentioned in Section 6.4 and Subsection 9.4.1.

Detectors 0RE-PR033B and 0RE-PR034B are interlocked with the makeup area unit fan 0VC03CB and main control room outside air intake B dampers. Automatically on high radiation, the outside air intake B dampers close, and the fan starts and in turn opens the main control room turbine building air intake B dampers mentioned in Section 6.4 and Subsection 9.4.1.

11.5.2.2.9 Main Control Room Turbine Building Air Intakes A and B Detectors 0RE-PR035A, B, and C through 0RE-PR038A, B, and C monitor air from the turbine building intakes after it has passed through the makeup air filters.

Detectors 0RE-PR035A, B, and C (air particulate, gas and iodine channels, respectively) and 0RE-PR036A, B, and C monitor the discharge air from the makeup air filter unit A entering the main control room. Detectors 0RE-PR037A, B, and C and 0RE-PR038A, B, and C monitor the discharge air from the makeup filter unit B entering the main control room.

High radiation in the makeup air filter unit (A or B) discharge is annunciated in the main control room.

11.5.2.2.10 Containment Atmosphere Monitoring Detectors lRE-PR011A, B, C, D, and E are used to monitor the Unit 1 containment atmosphere for airborne particulate, gaseous activity low range, iodine, gaseous activity high range and background subtraction, respectively. The detectors also provide leak detection as required by Regulatory Guide 1.45. See subsection 5.2.5.2 for additional information. Identical detectors provide the same function for Unit 2.

Interlocks are provided from the monitor to actuate certain system valves on high radiation to isolate the monitor.

Additionally, monitor purge valves are opened by the interlock to provide a timed purge of any contaminated air from the monitor.

Upon timeout of the purge function, the valves close and the monitor trips. This interlock function is normally bypassed via the bypass/normal control switch located on the containment air sample panel.

The monitor wetted parts are required to maintain pressure boundary integrity during abnormal pressure conditions. The 11.5-9 REVISION 11 - DECEMBER 2006

B/B-UFSAR detector is not required to meet performance requirements for this period.

For post-LOCA monitoring, the samples will be collected manually and analyzed in the laboratory as described in Section E.21 of Appendix E.

High range area type monitors are provided in containment to monitor post-LOCA radiation levels in the containment volume.

These monitors are discussed in Subsection 12.3.4 and Section E.30 of Appendix E.

11.5.2.2.11 Miscellaneous Tank Vent System Exhaust Detectors 0RE-PR025A, B and C (air particulate, gas and iodine channels respectively) monitor the miscellaneous tank vent system exhaust.

High radiation is annunciated in the main control room.

11.5.2.2.12 Radwaste Area Vent Exhaust Detectors 0RE-PR026A, B and C (air particulate, gas and iodine channels respectively) monitor the radwaste area vent exhaust.

The radwaste area vent exhaust is ducted to the auxiliary building vent stack.

The radiation monitor is interlocked with the radwaste building ventilation system supply and exhaust fans 0VW01C, 0VW13C, 0VW03CA, and 0VW03CB. The supply and exhaust fans trip on high radiation.

11.5.2.2.13 SJAE/Gland Steam Exhaust Detectors lRE-PR027 (gas channel) and 2RE-PR027 monitor the off-gas system exhaust. The SJAE/gland steam exhaust monitor features sample conditioning and grab sample collection capability. Sample probe 1(2)RX-PR027 is located in the SJAE/gland steam condenser/hogger exhaust line. An additional sample tap is located in the SJAE exhaust line for 1/2PR27J. The system is normally aligned with the SJAE exhaust sample tap. The SJAE/Gland Steam exhaust is subsequently monitored by probes 1/2PR028A/B in the vent stack. No automatic action is taken on high radiation in the off-gas exhaust stream, as the off-gas vent filter unit 0OG0lS is bypassed under all conditions.

11.5.2.2.14 Gas Decay Tank Effluent Detectors 0RE-PR002A and B (low and high range gas channels, respectively) monitor the radiation level of the gas decay tank discharge to the auxiliary building vent stack. Automatically, on high radiation in the gas decay tank discharge, valve 0GW014 closes.

11.5-10 REVISION 17 - DECEMBER 2018

B/B-UFSAR 11.5.2.2.15 VR System Areas and Cubicles Ventilation Exhaust Detectors 0RE-PR040A, B and C (air particulate, gas and iodine channels respectively) monitor the ventilation exhaust from the volume reduction equipment areas and cubicles.

The radiation monitor is interlocked with the volume reduction ventilation exhaust fans OVW10C and OVW14C, associated bypass, filter inlet and outlet dampers. Automatically on high radiation the bypass dampers close and the fans start to route the exhaust through the filter unit.

Refer to Subsection 9.4.3.3 for a description of the radwaste building ventilation system.

11.5.2.2.16 TSC Ventilation System The TSC ventilation system is provided with a permanently installed isokinetic sample probe 0RX-PR218 in the supply fan exhaust duct. During periods of TSC postaccident occupation, detectors 0RE-PR060A, B and C (air particulate, gas and iodine channels, respectively) will be used to monitor radiation levels in TSC. The monitor has an operating status lamp, two alarm lamps and an alarm horn both locally at the monitor and at a remote panel located in the TSC Health-Physics office. The monitor has a microprocessor which utilizes digital processing techniques to analyze data and control monitor functions.

11.5.2.2.17 Miscellaneous Process Monitors Miscellaneous other monitors shown in Table 11.5-1 monitor the process as indicated.

High radiation is annunciated in the main control room.

11.5.2.2.18 Auxiliary Building Vent Stack Wide Range Gas Monitor Radiation detectors 1RE-PR030A, B and C (low range, mid-range and high range gas channels, respectively) and 2RE-PR030A, B and C for Unit 2 are installed on the auxiliary building vent stacks (final release points). A detailed description of these monitors is included in Appendix E, Item E.30, position 1.

11.5.2.3 Liquid Effluent Monitors 11.5.2.3.1 Liquid Radwaste Effluent Monitor At Byron, detector 0RE-PR00l monitors liquid radwaste effluent from either 30,000-gallon release tank. The release tank discharge valves 0WX353 and 0WX896 close on high radiation. Each release tank has a dedicated sample probe that is aligned to the detector (0RE-PR001) when its tank and pump are preparing for a release.

At Braidwood, detectors 0RE-PR001 and 0RE-PR090 separately monitor liquid radwaste effluent from 30,000 gallon release tanks 11.5-11 REVISION 14 - DECEMBER 2012

B/B-UFSAR 0WX01T and 0WX026T, respectively. The release tank discharge valves 0WX353 and 0WX896 close on a high radiation signal from the radiation monitor of the tank being released.

11.5-11a REVISION 14 - DECEMBER 2012

B/B-UFSAR 11.5.2.3.2 Component Cooling Water Monitors Radiation detectors lRE-PR009, 2RE-PR009, and 0RE-PR009 continuously monitor the component cooling system for leakage of reactor coolant from the reactor coolant system and/or the residual heat removal system.

Detector 1RE-PR009 is interlocked with the component cooling surge tank 1CC0lT vent valve 1CC017, and detector 2RE-PR009 is interlocked with the component cooling surge tank 2CC0lT vent valve 2CC017. Detector 0RE-PR009 is interlocked with both vent valves, 1CC017 and 2CC017.

A high radiation level signal initiates automatic closure of the valve located in the component cooling surge tank vent line to prevent the release of airborne radioactivity.

11.5.2.3.3 Steam Generator Blowdown Detectors lRE-PR008 and 2RE-PR008 monitor steam generator blowdown for Unit 1 and 2 respectively.

Steam generator blowdown sample flow is normally routed through the steam generator blowdown sample panel, 0PS01J, and on to the radiation monitor. Automatically on high radiation, detector lRE-PR008 interlocks to close steam generator blowdown sample valves lPS179A through D to terminate sample flow to the sample panel and radiation monitor. A similar interlock exists between detector 2RE-PR008 and valves 2PS179A through D. Termination of sample flow on high radiation protects personnel in the high level laboratory where the sample panel is located. Subsequent sampling of steam generator blowdown can be accomplished by manually redirecting sample flow to the primary sample room.

Sequential isolation of steam generator blowdown can be used to determine which steam generator may be leaking.

11.5.2.3.4 Blowdown Filters The flow from the blowdown mixed-bed demineralizers is normally sent to the condensate storage tank or respective unit hotwell condenser. Detectors 0RE-PR016 through 19 are interlocked with the blowdown after filter discharge valves 0WX119A through D and blowdown monitor tank inlet valves 0WX058A through D.

Automatically on high radiation, the flow from the blowdown mixed-bed demineralizers is redirected to the blowdown monitor tanks.

11.5.2.3.5 Gross Failed Fuel Monitor Radiation detector lRE-PR006 (and 2RE-PR006 for Unit 2) continuously monitors the CVCS letdown line downstream of the letdown heat exchangers and upstream of the mixed bed demineralizers.

11.5-12 REVISION 6 - DECEMBER 1996

B/B-UFSAR The CVCS is described and the piping and instrument diagram shown in Subsection 9.3.4 and Drawings M-64, M-64A. High radiation alarms are provided in the main control room to alert the operator of an abnormal increase in gross gamma activity in the letdown stream.

Grab sample features are included on the monitor skid for laboratory analysis of primary coolant letdown activity. In addition, process sampling of the letdown line is available at the high radiation sampling system described in Subsection 9.3.2.1 and Appendix E.21.

11.5.2.3.6 Miscellaneous Process Liquid Monitors A high radiation signal from other liquid detectors listed in Table 11.5-2 will be annunciated in the control room.

11.5.2.3.7 Turbine Building Fire and Oil Sump Radiation detector 0RE-PR005 continuously monitors the Turbine Building Fire and Oil Sump liquid radiation levels. The monitor 0RT-PR005 annunciates a high radiation condition on local panel 0PL02J. Automatically on high radiation, pumps 0OD03PA through 0OD03PD are stopped and valve 0OD030 is closed.

11.5.2.3.8 Condensate Cleanup Area Sumps Discharge Radiation detector 0RE-PR041 continuously monitors the water discharged from the condensate cleanup area high and low conductivity sumps to the circulating water system.

On high radiation level, radiation monitor 0RT-PR041 initiates an automatic interlock to trip the condensate cleanup system high conductivity sump pump 0CP04P, the condensate cleanup system low conductivity sump pump 0CP05P and the condensate polishing regeneration process to terminate the discharge flow to the circulating water system. The trip condition is also annunciated at the local condensate polishing system control panel 0CP01J.

Both the sump pumps and the regeneration process are allowed to restart only when the reset switch is actuated after the radiation level has returned to normal.

Additionally, radiation monitor 0RT-PR041 also initiates on high radiation level two local horns, a local strobe light and a local indicating light. The horns and strobe light are reset by an "Alarm Acknowledge" push button, while the indicating light is extinguished only when the radiation level has returned to normal.

11.5.2.4 Sampling Sampling systems are described in Subsections 9.3.2 and 12.3.4.

The following subsections give a description of the procedures, frequencies, and objectives associated with 11.5-13 REVISION 9 - DECEMBER 2002

B/B-UFSAR sampling of plant process and effluent streams for radioactivity.

The sampling program is used in conjunction with the process and effluent radiation monitoring system to assure compliance with applicable regulations.

11.5.2.4.1 Process Sampling The gaseous and liquid process sampling points are identified in Tables 11.5-3 and 11.5-4. The sample frequency, type of analysis, sensitivity and purpose are listed in the tables. The analytical procedures used in the sample analysis are presented in Subsection 11.5.2.4.4. These samples serve to monitor radioactivity levels within various plant systems.

11.5.2.4.2 Effluent Sampling Effluent sampling of all potential radioactive liquid and gaseous effluent paths is conducted on a regular basis in order to verify the adequacy of effluent processing to meet the discharge limits to offsite areas. This effluent sampling program provides the information for the effluent measuring and reporting programs required by 10 CFR 50.36a and 10 CFR 20. The frequency of the periodic sampling and analysis described herein is normal and may be increased if effluent levels approach their limits. Tables 11.5-5 and 11.5-6 summarize the sample and analysis schedules.

11.5.2.4.3 Representative Sampling The pressure head of the fluid, if available, is used for taking samples. If enough pressure head is not available, then sample pumps are used to draw the sample from the process fluid to the detector panels and back to the process.

For obtaining representative samples, isokinetic probes are used for most gaseous samples.

11.5.2.4.4 Analytical Procedures Typically, samples of process and effluent gases and liquids are analyzed in the station laboratory or by an outside laboratory by means of the following techniques:

a. gross alpha/beta counting,
b. gamma spectrometry, and
c. liquid scintillation counting.

Instrumentation which is available in the laboratory for the measurement of radioactivity at the time of initial fuel loading includes the following:

11.5-14 REVISION 8 - DECEMBER 2000

B/B-UFSAR

a. alpha/beta counter,
b. gamma spectrometer, and
c. liquid scintillator.

"Available" instrumentation and counting techniques change as other instruments and techniques become available. For this reason the frequency of sampling and the analysis of samples are generalized here but specifically identified in the station procedures. The following treatment is included as typical of those currently used at Commonwealth Edison Company generating stations.

Gross alpha/beta analysis may be performed directly on unprocessed samples (e.g., air filters) or on processed samples (e.g., evaporated liquid samples). Sample volume, counting geometry, and counting time are chosen to match measurement capability with sample activity. Correction factors for sample-detector geometry, self-absorption and counter resolving time are applied to assure required accuracy.

Liquid effluent samples are prepared for alpha/beta counting by evaporation onto steel planchets.

Gamma analysis may be done on any type of sample (solid or liquid) in the gamma spectrometer.

Tritiated water vapor samples are collected by condensation or adsorption, and the resultant liquid is analyzed by liquid scintillation counting techniques.

Radiochemical separations are used for the routine analysis of SR-89 and SR-90.

Liquid samples are collected in polyethylene bottles to minimize absorption of nuclides onto container walls.

11.5.2.5 Instrument Inspection, Calibration, and Maintenance During reactor operation, daily checks of effluent monitoring system operability are made by observing channel behavior.

Routinely during reactor operation, the detector response is observed with a remotely positioned check source supplied with the monitors. Instrument background count rate is also observed to ensure proper functioning of the monitors. Any detector whose response cannot be verified by observation during normal operation or by using the remotely positioned check source can have its response checked with a portable check source. A record is maintained showing the background radiation level and the detector response.

11.5-15

B/B-UFSAR 11.5.2.5.1 Calibration Calibration of the continuous radiation monitors is done with commercial radionuclide standards that have been standardized using a measurement system traceable to the National Institute of Standards and Technology.

11.5.3 Effluent Monitoring and Sampling In accordance with the requirements of General Design Criterion 64, each effluent discharge path is continuously monitored for radioactive effluents resulting from normal operations, including anticipated operational occurrences and from postulated accidents.

The implementation of the requirements of General Design Criterion 64 concerning monitoring of effluent discharge paths for radioactivity is covered in Subsection 11.5.2. This subsection provides applicable details for gaseous and liquid effluent monitors.

11.5.4 Process Monitoring and Sampling The implementation of the requirements of General Design Criterion 60 concerning automatic closure of isolation valves in gaseous and liquid effluent discharge paths and GDC 63 concerning monitoring of radiation levels in radioactive waste process systems is covered in Subsections 11.5.2 and 11.5.3. These subsections provide applicable details for gaseous and liquid process radiation monitors.

11.5-16 REVISION 8 - DECEMBER 2000

B/B-UFSAR TABLE 11.5-1 AIRBORNE PROCESS AND EFFLUENT MONITORS DETEC- SEISMIC RADIATION TOR PANEL CAT. OF DETECTOR TYPE OF TYPE OF TYPE OF SENSITIVITY RANGE PANEL LOCATION DETEC-NO. SERVICE CHANNEL DETECTOR MEAS. (Ci/cc) (cpm) NO. DWG. NO. TORS SETPOINT* REMARKS 0RE-PR011 Radwaste Air Part. Scint. Gross 10-11-10-5 100-107 0PR11J M-831-6 II Per RP A,B Evap. Gas Scint. Gross 10-6-10-2 100-107 Approved Proc.

Cubicle 0RE-PR012 Recycle Air Part. Scint. Gross 10-11-10-5 100-107 0PR12J M-827-2 II Per RP Evap. Approved Proc.

Cub.

0RE-PR014 Drum Air Part. Scint. Gross 10-11-10-5 100-107 0PR14J M-829-13 II Per RP Station Approved Proc.

0RE-PR015 Laundry Air Part. Scint. Gross 10-11-10-5 100-107 0PR15J M-831-9 II Per RP Room Approved Proc.

0RE-PR013 Gas Air Part. Scint. Gross 10-11-10-5 100-107 0PR13J M-827-2 II Per RP A,B Decay Gas Scint. Gross 10-6-10-2 100-107 Approved Proc.

Tank Cubicle 1RE-PR013 RHR/CS Air Part. Scint. Gross 10-11-10-5 100-107 1PR13J M-827-7 I Per RP A,B Pump 1A Gas Scint. Gross 10-6-10-2 100-107 Approved Proc.

Cubicle

  • Alarm setpoints will be appropriately adjusted as operating experience is gained.

11.5-17 REVISION 7 - DECEMBER 1998

B/B-UFSAR TABLE 11.5-1 (Cont'd)

DETEC- SEISMIC RADIATION TOR PANEL CAT. OF DETECTOR TYPE OF TYPE OF TYPE OF SENSITIVITY RANGE PANEL LOCATION DETEC-NO. SERVICE CHANNEL DETECTOR MEAS. (Ci/cc) (cpm) NO. DWG. NO. TORS SETPOINT* REMARKS 2RE-PR013 RHR/CS Air Part. Scint. Gross 10-11-10-5 100-107 2PR13J M-827-7 I Per RP A,B Pump 2A Gas Scint. Gross 10-6-10-2 100-107 Approved Proc.

Cubicle 1RE-PR014 RHR/CS Air Part. Scint. Gross 10-11-10-5 100-107 1PR14J M-827-7 I Per RP A,B Pump 1B Gas Scint. Gross 10-6-10-2 100-107 Approved Proc.

Cubicle 2RE-PR014 RHR/CS Air Part. Scint. Gross 10-11-10-5 100-107 2PR14J M-827-7 I Per RP A,B Pump 2B Gas Scint. Gross 10-6-10-2 100-107 Approved Proc.

Cubicle 1RE-PR015 RHR Ht. Air Part. Scint. Gross 10-11-10-5 100-107 1PR15J M-829-5 I Per RP A,B Exch. 1A Gas Scint. Gross 10-6-10-2 100-107 Approved Proc.

Cubicle 2RE-PR015 RHR Ht. Air Part. Scint. Gross 10-11-10-5 100-107 2PR15J M-829-5 I Per RP A,B Exch. 2A Gas Scint. Gross 10-6-10-2 100-107 Approved Proc.

Cubicle 1RE-PR016 RHR Ht. Air Part. Scint. Gross 10-11-10-5 100-107 1PR16J M-829-3 I Per RP A,B Exch. 1B Gas Scint. Gross 10-6-10-2 100-107 Approved Proc.

Cubicle 2RE-PR016 RHR Ht. Air Part. Scint. Gross 10-11-10-5 100-107 2PR16J M-829-3 I Per RP A,B Exch. 2B Gas Scint. Gross 10-6-10-2 100-107 Approved Proc.

Cubicle 11.5-18 REVISION 7 - DECEMBER 1998

B/B-UFSAR TABLE 11.5-1 (Cont'd)

DETEC- SEISMIC RADIATION TOR PANEL CAT. OF DETECTOR TYPE OF TYPE OF TYPE OF SENSITIVITY RANGE PANEL LOCATION DETEC-NO. SERVICE CHANNEL DETECTOR MEAS. (Ci/cc) (cpm) NO. DWG. NO. TORS SETPOINT* REMARKS 1RE-PR017 Centrifu- Air Part. Scint. Gross 10-11-10-5 100-107 1PR17J M-828-7 I Per RP A,B gal Charg- Gas Scint. Gross 10-6-10-2 100-107 Approved Proc.

ing Pump 1A Cub.

2RE-PR017 Centrifu- Air Part. Scint. Gross 10-11-10-5 100-107 2PR17J M-828-7 I Per RP A,B gal Charg- Gas Scint. Gross 10-6-10-2 100-107 Approved Proc.

ing Pump 2A Cub.

1RE-PR018 Centrifu- Air Part. Scint. Gross 10-11-10-5 100-107 1PR18J M-827-7 I Per RP A,B gal Charg- Gas Scint. Gross 10-6-10-2 100-107 Approved Proc.

ing Pump 1B Cub.

2RE-PR018 Centrifu- Air Part. Scint. Gross 10-11-10-5 100-107 2PR18J M-827-7 I Per RP A,B gal Charg- Gas Scint. Gross 10-6-10-2 100-107 Approved Proc.

ing Pump 2B Cub.

0RE-PR002 Gas Decay Gas (Low) Scint. Gross 10-6-10-2 100-107 0PR02J M-827-2 II Per Interlock A,B Tank Gas (High) Scint. Gross 10-2-10+2 100-107 ODCM/RETS ref.

Effluent Limits 11.5.2.2.14 0RE-PR003 Lab. Fume Air Part. Scint. Gross 10-11-10-5 100-107 0PR03J M-831-8 II Per RP A,B,C Hood Gas Scint. Gross 10-6-10-2 100-107 Approved Proc.

Exhaust Iodine NaI (I-131) 10-11-10-5 100-107 11.5-19 REVISION 7 - DECEMBER 1998

B/B-UFSAR TABLE 11.5-1 (Cont'd)

DETEC- SEISMIC RADIATION TOR PANEL CAT. OF DETECTOR TYPE OF TYPE OF TYPE OF SENSITIVITY RANGE PANEL LOCATION DETEC-NO. SERVICE CHANNEL DETECTOR MEAS. (Ci/cc) (cpm) NO. DWG. NO. TORS SETPOINT* REMARKS 0RE-PR025 Misc. Air Part. Scint. Gross 10-11-10-5 100-107 0PR25J M-832-34 I Per RP A,B,C Tank Gas Scint. Gross 10-6-10-2 100-107 Approved Proc.

Filter Iodine NaI (I-131) 10-11-10-5 100-107 Vent Effluent 0RE-PR026 Radwaste Air Part. Scint. Gross 10-11-10-5 100-107 0PR26J M-831-6 I Per RP Interlock A,B,C Area Vent Gas Scint. Gross 10-6-10-2 100-107 Approved Proc. ref.

Exhaust Iodine NaI (I-131) 10-11-10-5 100-107 11.5.2.2.12 1RE-PR001 Contain- Air Part. Scint. Gross 10-11-10-5 100-107 1PR01J M-832-26 I Per ODCM/RETS A,B,C ment Gas Scint. Gross 10-6-10-2 100-107 Limits Purge Iodine NaI (I-131) 10-11-10-5 100-107 Effluent 2RE-PR001 Contain- Air Part. Scint. Gross 10-11-10-5 100-107 2PR01J M-832-26 I Per ODCM/RETS A,B,C ment Gas Scint. Gross 10-6-10-2 100-107 Limits Purge Iodine NaI (I-131) 10-11-10-5 100-107 Effluent 1RE-PR011 Contain- Air Part. Scint. Gross 10-11-10-5 100-107 1PR11J M-828-7 II Detect 1gpm Interlock A,B,C,D,E ment Gas (low) Scint. Gross 10-6-10-2 100-107 RCS leak rate ref.

Atmos- Iodine NaI (I-131) 10-11-10-5 100-107 in less 11.5.2.2.10 phere Gas Scint. Gross 10-2-10+2 100-107 than 1 hr or as low as practicable (high)

Gas Scint. Gross 10-6-10-2 100-107 (back-ground) 11.5-20 REVISION 9 - DECEMBER 2002

B/B-UFSAR TABLE 11.5-1 (Cont'd)

DETEC- SEISMIC RADIATION TOR PANEL CAT. OF DETECTOR TYPE OF TYPE OF TYPE OF SENSITIVITY RANGE PANEL LOCATION DETEC-NO. SERVICE CHANNEL DETECTOR MEAS. (Ci/cc) (cpm) NO. DWG. NO. TORS SETPOINT* REMARKS 2RE-PR011 Contain- Air Part. Scint. Gross 10-11-10-5 100-107 2PR11J M-828-7 II Detect Interlock A,B,C,D,E ment Gas (low) Scint. Gross 10-6-10-2 100-107 1gpm RCS Ref.

Atmos Iodine NaI (I-131) 10-11-10-5 100-107 Leak Rate 11.5.2.2.10 phere Gas in less than (high) Scint. Gross 10-2-10+2 100-107 1 hr or as low as practicable Gas (back- Scint. Gross 10-6-10-2 100-107 ground) 1RE-PR028 Aux. Bldg. Air Part. Scint. Gross 10-11-10-5 100-107 1PR28J M-832-34 I Per ODCM/

A,B,C,D,E Vent Stack Gas (low) Scint. Gross 10-6-10-2 100-107 RETS Limits Effluent Iodine NaI (I-131) 10-11-10-5 100-107 Gas (high) Scint. Gross 10-2-10+2 100-107 Gas (back- Scint. Gross 10-6-10-2 100-107 ground) 2RE-PR028 Aux. Bldg. Air Part. Scint. Gross 10-11-10-5 100-107 2PR28J M-832-34 I Per ODCM/

A,B,C,D,E Vent Stack Gas (low) Scint. Gross 10-6-10-2 100-107 RETS Limits Effluent Iodine NaI (I-131) 10-11-10-5 100-107 Gas (high) Scint. Gross 10-2-10+2 100-107 Gas (back- Scint. Gross 10-6-10-2 100-107 ground) 0RE-PR021 Aux. Bldg. Air Part. Scint. Gross 10-11-10-5 100-107 0PR21J M-831-6 I Per RP A,B,C Vent Ex- Gas Scint. Gross 10-6-10-2 100-107 Approved Proc.

haust 0A Iodine NaI (I-131) 10-11-10-5 100-107 11.5-21 REVISION 9 - DECEMBER 2002

B/B-UFSAR TABLE 11.5-1 (Cont'd)

DETEC- SEISMIC RADIATION TOR PANEL CAT. OF DETECTOR TYPE OF TYPE OF TYPE OF SENSITIVITY RANGE PANEL LOCATION DETEC-NO. SERVICE CHANNEL DETECTOR MEAS. (Ci/cc) (cpm) NO. DWG. NO. TORS SETPOINT* REMARKS 0RE-PR022 Aux. Bldg. Air Part. Scint. Gross 10-11-10-5 100-107 0PR22J M-831-6 I Per RP A,B,C Vent Ex- Gas Scint. Gross 10-6-10-2 100-107 Approved Proc.

haust 0B Iodine NaI (I-131) 10-11-10-5 100-107 0RE-PR024 Fuel Air Part. Scint. Gross 10-11-10-5 100-107 0PR24J M-831-6 I Per RP A,B,C Handling Gas Scint. Gross 10-6-10-2 100-107 Approved Proc.

Bldg. Exh. Iodine NaI (I-131) 10-11-10-5 100-107 0RE-PR031 Control Air Part. Scint. Gross 10-11-10-5 100-107 0PR31J M-832-12 I Per RP Redundant A,B,C Room Out- Approved Proc. function with side Air Gas Scint. Gross 10-6-10-2 100-107 2 mR/hr 0RE-PR032A,B,C Intake A Submersion dose Interlock ref.

Iodine NaI (I-131) 10-11-10-5 100-107 Per RP 11.5.2.2.8 Approved Proc.

0RE-PR032 Control Air Part. Scint. Gross 10-11-10-5 100-107 0PR32J M-832-17 I Per RP Redundant A,B,C Room Out- Approved Proc. function with

-6 -2 0 7 side Air Gas Scint. Gross 10 -10 10 -10 2 mR/hr 0RE-PR031A,B,C Intake A Submersion dose Interlock ref.

Iodine NaI (I-131) 10-11-10-5 100-107 Per RP 11.5.2.2.8 Approved Proc.

11.5-22 REVISION 11 - DECEMBER 2006

B/B-UFSAR TABLE 11.5-1 (Cont'd)

DETEC- SEISMIC RADIATION TOR PANEL CAT. OF DETECTOR TYPE OF TYPE OF TYPE OF SENSITIVITY RANGE PANEL LOCATION DETEC-NO. SERVICE CHANNEL DETECTOR MEAS. (Ci/cc) (cpm) NO. DWG. NO. TORS SETPOINT* REMARKS 0RE-PR033 Control Air Part. Scint. Gross 10-11-10-5 100-107 0PR33J M-832-14 I Per RP Redundant A,B,C Room Out- Approved Proc. function with

-6 -2 0 7 side Air Gas Scint. Gross 10 -10 10 -10 <2 mR/hr 0RE-PR034A,B,C Intake B Submersion dose Interlock ref.

Iodine NaI (I-131) 10-11-10-5 100-107 Per RP 11.5.2.2.8 Approved Proc.

0RE-PR034 Control Air Part. Scint. Gross 10-11-10-5 100-107 0PR34J M-832-19 I Per RP Redundant A,B,C Room Out- Approved Proc. function with side Air Gas Scint. Gross 10-6-10-2 100-107 2 mR/hr 0RE-PR033A,B,C Submersion dose Interlock ref.

Iodine NaI (I-131) 10-11-10-5 100-107 Per RP 11.5.2.2.8 Approved Proc 0RE-PR035 Control Air Part. Scint. Gross 10-11-10-5 100-107 0PR35J M-832-12 I Per RP Redundant A,B,C Room Turb. Approved Proc. function with

-6 -2 0 7 Bldg. Gas Scint. Gross 10 -10 10 -10 2 mR/hr 0RE-PR036A,B,C Air In- submersion dose

-11 -5 take A Iodine NaI (I-131) 10 -10 100-107 Per RP Approved Proc.

0RE-PR036 Control Air Part. Scint. Gross 10-11-10-5 100-107 0PR36J M-832-12 I Per RP Redundant A,B,C Room Turb. Approved Proc. function with

-6 -2 0 7 Bldg. Gas Scint. Gross 10 -10 10 -10 2 mR/hr 0RE-PR035A,B,C Air In- submersion dose take A Iodine NaI (I-131) 10-11-10-5 100-107 Per RP Approved Proc.

11.5-23 REVISION 11 - DECEMBER 2006

B/B-UFSAR TABLE 11.5-1 (Cont'd)

DETEC- SEISMIC RADIATION TOR PANEL CAT. OF DETECTOR TYPE OF TYPE OF TYPE OF SENSITIVITY RANGE PANEL LOCATION DETEC-NO. SERVICE CHANNEL DETECTOR MEAS. (Ci/cc) (cpm) NO. DWG. NO. TORS SETPOINT* REMARKS 0RE-PR037 Control Air Part. Scint. Gross 10-11-10-5 100-107 0PR37J M-832-14 I Per RP Redundant A,B,C Room Turb. Approved Proc. function with

-6 -2 0 7 Bldg. Gas Scint. Gross 10 -10 10 -10 <2 mR/hr 0RE-PR038 Air Submersion dose A,B,C Intake B Iodine NaI (I-131) 10-11-10-5 100-107 Per RP Approved Proc.

0RE-PR038 Control Air Part. Scint. Gross 10-11-10-5 100-107 0PR38J M-832-14 I Per RP Redundant A,B,C Room Turb. Approved Proc. function with Bldg. Air Gas Scint. Gross 10-6-10-2 100-107 <2 mR/hr 0RE-PR037 Intake B submersion dose A,B,C Iodine NaI (I-131) 10-11-10-5 100-107 Per RP Approved Proc.

11.5-23a REVISION 11 - DECEMBER 2006

B/B-UFSAR TABLE 11.5-1 (Cont'd)

DETEC- SEISMIC RADIATION TOR PANEL CAT. OF DETECTOR TYPE OF TYPE OF TYPE OF SENSITIVITY RANGE PANEL LOCATION DETEC-NO. SERVICE CHANNEL DETECTOR MEAS. (Ci/cc) (cpm) NO. DWG. NO. TORS SETPOINT* REMARKS 1RE-PR021 Pipe Air Part. Scint. Gross 10-11-10-5 100-107 1PR21J M-831-6 I Per RP A,B,C Tunnel Gas Scint. Gross 10-6-10-2 100-107 Approved Proc.

Iodine NaI (I-131) 10-11-10-5 100-107 2RE-PR021 Pipe Air Part. Scint. Gross 10-11-10-5 100-107 2PR21J M-831-6 I Per RP A,B,C Tunnel Gas Scint. Gross 10-6-10-2 100-107 Approved Proc.

Iodine NaI (I-131) 10-11-10-5 100-107 0RE-PR040 VR System Air Part. Scint. Gross 10-11-10-5 100-107 0PR40J M-844-5 II Per RP Interlock A,B,C Areas & Gas Scint. Gross 10-6-10-2 100-107 Approved Proc. ref.

Cub. Ven- Iodine NaI (I-131) 10-11-10-5 100-107 11.5.2.2.15 tilation Exhaust 1RE-PR027 SJAE/ Gas Scint. Gross 10-6-10-2 100-107 1PR27J M-836-3 II Detect 150 Interlock Gland Stm. gpd ref.

Exhaust Leak Rate 11.5.2.2.13 2RE-PR027 SJAE/ Gas Scint. Gross 10-6-10-2 100-107 2PR27J M-836-19 II Detect 150 Interlock Gland Stm. gpd ref.

Exhaust Leak Rate 11.5.2.2.13 1RE-PR030 Aux. Gas-Low Scint. Gross 10-7-10-1 100-107 1PR30J M-832-34 I Per E-Plan EALS A,B,C Bldg. Gas-Mid CdTe Gross 10-4-102 100-107 Vent Gas-High CdTe Gross 10-1-105 100-107 Stack (WRGM) 11.5-24 REVISION 11 - DECEMBER 2006

B/B-UFSAR TABLE 11.5-1 (Cont'd)

DETEC- SEISMIC RADIATION TOR PANEL CAT. OF DETECTOR TYPE OF TYPE OF TYPE OF SENSITIVITY RANGE PANEL LOCATION DETEC-NO. SERVICE CHANNEL DETECTOR MEAS. (Ci/cc) (cpm) NO. DWG. NO. TORS SETPOINT* REMARKS 2RE-PR030 Aux. Gas-Low Scint. Gross 10-7-10-1 100-107 2PR30J M-832-34 I Per E-Plan EALS A,B,C Bldg. Gas-Mid CdTe Gross 10-4-102 100-107 Vent Gas-High CdTe Gross 10-1-105 100-107 Stack (WRGM) 0RE-PR060 TSC Air Part. Scint. Gross 10-11-10-5 100-107 0PR60J M-850-2 II Per RP A,B,C Vent Gas Scint. Gross 10-6-10-2 100-107 Approved System Iodine NaI (I-131) 10-11-10-5 100-107 Proc.

11.5-25 REVISION 9 - DECEMBER 2002

B/B-UFSAR TABLE 11.5-2 PROCESS LIQUID MONITORS DETEC- SEISMIC RADIATION TOR PANEL CAT. OF DETECTOR TYPE OF TYPE OF TYPE OF SENSITIVITY RANGE PANEL LOCATION DETEC-NO. SERVICE CHANNEL DETECTOR MEAS. (Ci/cc) (cpm) NO. DWG. NO. TORS REMARKS

-6 -2 0 7 0RE-PR001 Liq. Rad- Liquid NaI 10 -10 10 -10 0PR01J M-836-3 II Interlock ref.

waste Eff. 11.5.2.3.1 0RE-PR090 Liq. Rad- Liquid NaI 10-6-10-2 100-107 0PR90J M-836-3 II Interlock ref.

(BWD Only) waste Eff. 11.5.2.3.1 0RE-PR006 Radwaste Liquid NaI 10-6-10-2 100-107 0PR06J M-830-10 II Evap. 0A Cnds. Return 0RE-PR007 Radwaste Liquid NaI 10-6-10-2 100-107 0PR07J M-830-10 II Evap. 0B Cnds. Return 0RE-PR008 Radwaste Liquid NaI 10-6-10-2 100-107 0PR08J M-830-10 II Evap. 0C Cnds. Return 0RE-PR009 CC Ht. Liquid NaI 10-6-10-2 100-107 0PR09J M-828-5 I Interlock ref.

Exch. 0 11.5.2.3.2 Wtr. Outlet 0RE-PR041 Condensate Liquid NaI 10-6-10-2 100-107 0PR41J M-836-15A II Interlock ref.

Polisher 11.5.2.3.8 Conductivity Sump 1RE-PR009 CC Ht. Liquid NaI 10-6-10-2 100-107 1PR09J M-828-5 I Interlock ref.

Exch. 1 11.5.2.3.2 Wtr. Outlet Note: Alarm setpoints are established to provide a warning of increased system activity and ensure agreement with calculational methodology and limits described in the Offsite Dose Calculation Manual.

11.5-26 REVISION 14 - DECEMBER 2012

B/B-UFSAR TABLE 11.5-2 (Cont'd)

DETEC- SEISMIC RADIATION TOR PANEL CAT. OF DETECTOR TYPE OF TYPE OF TYPE OF SENSITIVITY RANGE PANEL LOCATION DETEC-NO. SERVICE CHANNEL DETECTOR MEAS. (Ci/cc) (cpm) NO. DWG. NO. TORS REMARKS 2RE-PR009 CC Ht. Liquid NaI 10-6-10-2 100-107 2PR09J M-828-5 I Interlock ref.

Exch. 2 11.5.2.3.2 Wtr. Outlet 1RE-PR007 Boron Thermal Liquid NaI 10-6-10-2 100-107 1PR07J M-827-7 II Regeneration Chiller Surge Tank Return 2RE-PR007 Boron Thermal Liquid NaI 10-6-10-2 100-107 2PR07J M-827-7 II Regeneration Chiller Surge Tank Return 1RE-PR006 Gross Failed Liquid NaI 10-4-10° 100-107 1PR06J M-829-5 I Fuel (I-135) M-830-4 2RE-PR006 Gross Failed Liquid NaI 10-4-10° 100-107 2PR06J M-829-5 I Fuel (I-135) M-830-6 1RE-PR002 RCFC 1A&1C Liquid NaI 10-6-10-2 100-107 1PR02J M-830-4 I Ess. Service Wtr. Outlet 11.5-27 REVISION 6 - DECEMBER 1996

B/B-UFSAR TABLE 11.5-2 (Cont'd)

DETEC- SEISMIC RADIATION TOR PANEL CAT. OF DETECTOR TYPE OF TYPE OF TYPE OF SENSITIVITY RANGE PANEL LOCATION DETEC-NO. SERVICE CHANNEL DETECTOR MEAS. (Ci/cc) (cpm) NO. DWG. NO. TORS REMARKS 2RE-PR002 RCFC 2A&2C Liquid NaI 10-6-10-2 100-107 2PR02J M-830-6 I Ess. Service Wtr. Outlet 1RE-PR003 RCFC 1B&1D Liquid NaI 10-6-10-2 100-107 1PR03J M-830-4 I Ess. Service Wtr. Outlet 2RE-PR003 RCFC 2B&2D Liquid NaI 10-6-10-2 100-107 2PR03J M-830-6 I Ess. Service Wtr. Outlet 1RE-PR008 Steam Liquid NaI 10-6-10-2 100-107 1PR08J M-831-8 II Interlock ref.

Generator 11.5.2.3.3 Blowdown 2RE-PR008 Steam Liquid NaI 10-6-10-2 100-107 2PR08J M-831-8 II Interlock ref.

Generator 11.5.2.3.3 Blowdown 0RE-PR010 Station Liquid NaI 10-6-10-2 100-107 0PR10J M-834-13 II Blowdown 0RE-PR016 Bldn. After Liquid NaI 10-6-10-2 100-107 0PR16J M-829-7A II Interlock ref.

Filter 0A 11.5.2.3.4 Outlet 0RE-PR017 Bldn. After Liquid NaI 10-6-10-2 100-107 0PR17J M-829-7A II Interlock ref.

Filter 0B 11.5.2.3.4 Outlet 11.5-28 REVISION 6 - DECEMBER 1996

B/B-UFSAR TABLE 11.5-2 (Cont'd)

DETEC- SEISMIC RADIATION TOR PANEL CAT. OF DETECTOR TYPE OF TYPE OF TYPE OF SENSITIVITY RANGE PANEL LOCATION DETEC-NO. SERVICE CHANNEL DETECTOR MEAS. (Ci/cc) (cpm) NO. DWG. NO. TORS REMARKS 0RE-PR018 Bldn. After Liquid NaI 10-6-10-2 100-107 0PR18J M-829-7A II Interlock ref.

Filter 0C 11.5.2.3.4 Outlet 0RE-PR019 Bldn. After Liquid NaI 10-6-10-2 100-107 0PR19J M-829-11A II Interlock ref.

Filter 0D 11.5.2.3.4 Outlet 0RE-PR005 Turb. Bldg. Liquid NaI 10-6-10-2 100-107 0PRO5J M-834-2 II Interlock ref.

Fire and 11.5.2.3.7 Oil Sump 11.5-29 REVISION 6 - DECEMBER 1996

B/B-UFSAR TABLE 11.5-3 RADIOLOGICAL ANALYSIS

SUMMARY

OF LIQUID PROCESS SAMPLES TYPICAL SAMPLE SENSITIVITY SAMPLE DESCRIPTION FREQUENCY ANALYSIS (Ci/ml) PURPOSE

1. Reactor coolant Liquid Daily Gamma isotopic N/A Evaluate reactor water activity Crud Weekly Gamma isotopic N/A Evaluate crud activity Liquid Daily I-131, Dose N/A Evaluate fuel cladding equivalent integrity
2. Condensate storage tank - Unit 1. Weekly Gamma isotopic 10-6 Tank inventory
3. Condensate storage tank - Unit 2. Weekly Gamma isotopic 10-6 Tank inventory
4. Fuel pool filter-demineralizer Inlet and Outlet Periodically Gamma isotopic 10-6 Evaluate system when fuel is Gross 10-6 performance present
  • When sample is available.

Actual frequency is determined by plant needs and operational circumstances per the Technical Specifications.

11.5-30 REVISION 7 - DECEMBER 1998

B/B-UFSAR TABLE 11.5-4 RADIOLOGICAL ANALYSIS

SUMMARY

OF GASEOUS PROCESS SAMPLES TYPICAL SAMPLE SENSITIVITY SAMPLE DESCRIPTION FREQUENCY ANALYSIS (Ci/ml) PURPOSE

1. Containment Periodically Noble gas 10-4 Determine need for atmosphere and prior to Gamma isotopic** 10-11 personnel protection entry* I-131*** 10-12 and effluent I-133*** 10-10 release record Tritium 10-7
  • As determined by plant needs and operational circumstances per the Technical Specifications.
    • On particulate filter.
      • On charcoal cartridge.

11.5-31 REVISION 7 - DECEMBER 1998

B/B-UFSAR TABLE 11.5-5 RADIOLOGICAL ANALYSIS

SUMMARY

OF LIQUID EFFLUENT SAMPLES TYPICAL SAMPLE SENSITIVITY SAMPLE DESCRIPTION FREQUENCY ANALYSIS (Ci/ml) PURPOSE

1. Aux. bldg. floor On request Gamma isotopic 5x10-7 drain tank tritium 10-5
2. Laundry drain On request Gamma isotopic 5x10-7 tank tritium 10-5
3. Liquid release Batch* Gamma isotopic 5 x 10-7 Effluent release record tanks (2) tritium 10-5 Monthly Gamma isotopic 10-5 (noble gas)

Alpha 10-7 Composite of all Quarterly Sr-89/90 5x10-8 release tanks Fe-55 10-6 discharged

4. Circulating water** Weekly Gamma isotopic 5x10-7 Effluent release record I-131 10-6 Monthly Gamma isotopic 10-5 (noble gas)

Tritium 10-5 Gross alpha 10-7 Quarterly Sr-89/90 5x10-8 Fe-55 10-6

  • If tank is to be discharged, analyses will be performed on each batch. If tank is not to be discharged, analyses may be performed.
    • Daily sample collected continuously; composited weekly, monthly, and quarterly.

11.5-32 REVISION 10 - DECEMBER 2004

B/B-UFSAR TABLE 11.5-6 RADIOLOGICAL ANALYSIS

SUMMARY

OF GASEOUS EFFLUENT SAMPLES SAMPLE SENSITIVITY SAMPLE DESCRIPTION FREQUENCY ANALYSIS (Ci/cm3) PURPOSE

1. Aux. Bldg. Vent Stack Weekly Gamma isotopic* 10-11 Effluent release record Unit 1 & Unit 2 I-131** 10-12 I-133 10-10 Monthly Tritium 10-7 Noble Gas 10-4 Quarterly*** Sr-89, Sr-90 10-11 Alpha 10-11
  • On particulate filter.
    • On charcoal cartridge.
      • Performed by off-site vendor.

11.5-33 REVISION 7 - DECEMBER 1998

B/B-UFSAR Figures 11.2-1 through 11.2-41 have been deleted intentionally.

REVISION 9 - DECEMBER 2002

B/B-UFSAR Figure 11.3-1 has been deleted intentionally.

REVISION 9 - DECEMBER 2002

i i

N i

i BYRON/BRAIDWOOD STATIONS g !I i *

REVISION 6 DECEMBER 1996 CARTRIDGE DRY ACTIVE SLUDGES LOW ACTMTY HIGH ACTMTY FILTERS WASTES ANO LIQUIDS SPENT RESIN SPENi RESIN HIGH ACTIVITY SPENT RESIN STORAGE TANK PACKAGE COMPACTOR SPENT RESIN .

STORAGE TANK STORAGE PACKAGE AREA LINER STORAGE AREA 'i MOBILE RADWASTE SYSTEM I AUX. BL.DC.

FLOOR DRAINS MOBILE RADWASTE SYSTEM UNER UNER STORAGE AREA 1

TRUCK TRUCK TRUCK DISPOSAL SITE BRAIDWOOD STATION UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 11.4-1 RADWASTE DISPOSAL SYSTEM FLOW DIAGRAM

REVISION 6 DECEMBER 1996 CARTRIDGE DRY ACTIVE SLUDGES LOW ACTIVITY HIGH ACTIVITY FILTERS WASTES AND LIQUIDS SPENT RESIN SPENT RESIN I

PACKAGE COMPACTOR I

SPENT RESIN

  • STORAGE TANK STORAGE PACKAGE AREA MOBILE MOBILE LINER STORAGE AREA RADWASTE SYSTEM tFLOOR AUX. BLOC.

ORAINS RADWASTE SYSTEM LINER LINER STORAGE AREA TRUCK TRUCK ' TRUCK DISPOSAL SITE BYRON STATION UPDATED FINAL SAFElY ANALYSIS REPORT FIGURE 11.4-1 RADWASTE DISPOSAL SYSTEM FLOW DIAGRAM

B/B-UFSAR Figures 11.4-2 through 11.4-4 have been deleted intentionally.

REVISION 9 - DECEMBER 2002

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