ML13004A065
| ML13004A065 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood  |
| Issue date: | 12/14/2012 |
| From: | Exelon Generation Co |
| To: | Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation |
| References | |
| RS-12-221 | |
| Download: ML13004A065 (212) | |
Text
B/B-UFSAR 11.0-i REVISION 9 - DECEMBER 2002 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 Shi elding 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 Mod el for React or 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 I n-Plant Airborne R adioactivity 11.1-5 11.1.7 Sources of Radio active 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 No rmal 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 Un controlled Releases 11.2-4 11.2.1.11 ETSB-BTP 11-1 Comparison 11.1-5 11.2.2 System D escription 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 Sec ondary System Leakage 11.2-8 11.2.2.1.3 Primary-to-Secon dary Leakage Concurrent with Failed Fuel 11.2-8
B/B-UFSAR 11.0-ii REVISION 7 - DECEMBER 1998 TABLE OF CONTENTS (Cont'd)
PAGE 11.2.2.1.4 Primary-to-Sec ondary 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 D escription 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 Gaseo us Waste Processing System Releases 11.3-8
B/B-UFSAR 11.0-ii (Cont'd)
REVISION 2 - DECEMBER 1990 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
B/B-UFSAR 11.0-iii REVISION 12 - DECEMBER 2008 TABLE OF CONTENTS (Cont'd)
PAGE 11.4 SOLID WASTE MA NAGEMENT 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 Proces sing 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 D escription 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
B/B-UFSAR 11.0-iv REVISION 4 - DECEMBER 1992 TABLE OF CONTENTS (Cont'd)
PAGE 11.5 PROCESS AND EFFL UENT 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 D escription 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 Bu ilding Vent Stack Effluent 11.5-7 11.5.2.2.2 Auxiliary Buil ding Plant Areas (for Auxiliary Building Vent Exhausts) 11.5-7 11.5.2.2.3 Pipe Tunnel (f or 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-Handlin g 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 Miscel laneous 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
B/B-UFSAR 11.0-v 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 Miscel laneous Process Monitors 11.5-11 11.5.2.2.18 Auxiliary Bu ilding 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 Ins pection, 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 Monitori ng and Sampling 11.5-16
B/B-UFSAR 11.0-vi REVISION 9 - DECEMBER 2002 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 Rea ctor Coolant Fission and Corrosion Product Activity (Original Design) 11.1-10 11.1-3 Parameters Used in the Calculation of Realistic, Opera tional Basis Primary Coolant Activities 11.1-11 11.1-4 Realistic, Ope rational Basis Reactor Coolant Fission and Corrosion Product Activities 11.1-13 11.1-5 Maximum Realisti c, Operational Basis Waste Gas Decay Tank Activity for Gas Decay Tank Rupture 11.1-15 11.1-6 Realistic Sour ce Terms for Steam Generator Blowdo wn and Radioactive Drain Streams 11.1-16 11.1-7 Realistic Source Terms for Balance of Plant 11.1-20 11.1-8 Realistic Sour ce Terms for Radwaste System Filters and Demineralizers 11.1-24 11.1-9 Realistic Source Ter ms for NSSS Filters 11.1-28 11.1-10 Realistic So urce Terms for NSSS Demineralizers 11.1-31 11.1-11 Realistic Source Terms for C oncentrates and Spent Resin Tanks (Byron) 11.1-33 11.1-11 Realistic Sour ce 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 Pr oduct Activity 11.2-1 Expected Annual Average Releases of Radionuclides in Liquid Effluents 11.2-18 11.2-2 Parameters U sed in the GALE-PWR Computer Program (Original & Uprated) - Note 1 11.2-19 11.2-3 Pathways Doses f rom Liquid Effluents (Byron) 11.2-22 11.2-3 Pathways Doses f rom Liquid Effluents (Braidwood) 11.2-23 11.2-4 Comparison of Expected Liqui d Effluent Concentrations to 10 CFR 20 Limits (Byron) 11.2-24 11.2-4 Comparison of Expected Liqui d 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 A nnual Average and Maximum Waste Stream Flows (Two Units) 11.2-32
B/B-UFSAR 11.0-vii REVISION 6 - DECEMBER 1996 LIST OF TABL ES (Cont'd)
NUMBER TITLE PAGE 11.2-7 Design-Basis P rocess Decontamination Factors 11.2-33 11.2-8 Consumption Fa ctors for the Maximum Exposed Individual 11.2-35 11.2-9 Summary of T ank Level Indicati on, Annunciators, and Overflows for Tanks Outside of Containment Poten tially Containing Radioactive Liquids 11.2-36 11.3-1 Gaseous Wast e Processing System Component Data 11.3-11 11.3-2 Gaseous Wast e Processing System Instrumentation Design Parameters 11.3-12 11.3-3 Process Paramete rs 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 Gase ous 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 Mana gement Syste m 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 Interfac es with Solid Radwaste System (Byron) 11.4-57 11.4-1 Solid Waste Mana gement Syste m Equipment and Storage Design Capacities (Braidwood) 11.4-64
B/B-UFSAR 11.0-viii REVISION 6 - DECEMBER 1996 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 B/B-UFSAR 11.0-ix REVISION 9 - DECEMBER 2002 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 B/B-UFSAR 11.0-x REVISION 9 - DECEMBER 2002 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 B/B-UFSAR 11.0-xi REVISION 9 - DECEMBER 2002 DRAWINGS CITED IN TH IS CHAPTER* (Cont'd)
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 Sum ps & Pumps Units 1 & 2 M-48-20A,
-20B Diagram of Waste Disposal Blowdown Mixed Bed Demineralizer Units 1 & 2 M-48-21A, -21B, -21C Diagram of Waste Disposal Radwaste Mixed Bed Demineralizer Units 1 & 2 M-48-22 Diagram of Waste Disposal Turbine Building Equipment Drains Units 1 & 2 M-48-23 Diagram of Radioactive W aste Reprocessing &
Disposal Units 1 & 2 M-48-24 Diagram of Turbine Build ing Waste Oil Collection System Units 1 & 2 M-48-25 Diagram of Auxiliary Bui lding Waste Oil Collection System Units 1 & 2 M-48-28 Diagram of Auxiliary Building Leak D etection Sumps Units 1 & 2 M-48-29 Diagram of Auxil iary 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 Turbi ne Bldg Equipm ent/Floor Drain Coalescers Units 1 & 2 M-48-38 Diagram of Radwaste Evap orator Ammonia Stripper "A" Unit 1 & 2 M-48-39 Diagram of Radwaste Evap orator Ammonia Stripper "B" Unit 1 & 2 M-48-40 Diagram of Radwaste Evap orator Ammonia Stripper "C" Unit 1 & 2 M-48A Composite Diagram of L iquid Radwaste Treatment Processing Units 1 & 2
B/B-UFSAR 11.0-xii REVISION 9 - DECEMBER 2002 DRAWINGS CITED IN TH IS CHAPTER* (Cont'd)
DRAWING* SUBJECT M-64 Diagram of Chemical & Vo lume Control
& Boron Thermal Regenera tion Unit 1 M-64A Diagram of Chemical & Vo lume Control
& Boron Thermal Regenera tion Unit 1 M-69 Diagram of Radioacti ve Waste Gas Sys tem Units 1 & 2
B/B-UFSAR 11.1-1 REVISION 9 - DECEMBER 2002 CHAPTER 11.0 -
RADIOACTIVE WASTE MANAGEMENT 11.1 SOURCE TERMS Radioactive source ter ms are explained in this section.
Radioactive source terms are used in: shielding design, assuring adequacy of ventilation, design of radioacti ve systems, calculation of expected gaseous and liquid releases from the station, and accident analysis. Source term s are dependent on a number of assumptions; the assumptio ns depend on the particular application under consideration.
To avoid confusion, clear distinction is made between the design-basis s hielding source term, the expected source term, and the accident source term.
Operating limits are given in the Technical Sp ecifications and other documents.
The releases of radioa ctivity and their resu lting doses included in this chapter were calculated during p lant licensing from assumed values for many parameters. T hese included coolant activity, iodine partitioning, amount of failed fuel, filter efficiencies, system flow rate s, component l eak rates, and associated activity for all potentially radi oactive water and steam systems. Estima tes were made for many individual contributors and then su mmed 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 g ranted a license, in compliance with these regulations. The NRC reviewed these estimated values and confirmed that the plant co uld be operated and meet the regulations in th eir safety evaluation report.
After the NRC issues an operating license, the requirement to meet the applicable radiological dos e regulations is demonstrated in the stations annu al radiological ef fluent release report. The values for the r eport are calculated u sing the m easured total radioactivity releases from all sources and equations and data included in the Offsite Dose Calculation Manua
- l. Only the total values are calcu lated; there is no requirement to calculate the dose from each of the individual sources listed in this section.
The information on rel ease estimates a nd offsite doses is maintained in the UFSAR for hi storical referen ce and is not intended to be used to establish current operating limits.
The impact of a core pow er uprate on the rad iation source terms at B&B Nuclear S tations is discu ssed in Section 11.1.8. The original licensed power level was 3411 MWt. The original source term, effluent and shiel ding analyses were per formed at a power level of 3565 MWt. The uprate power level is 3586.6 MWt.
B/B-UFSAR 11.1-1a REVISION 12 - DECEMBER 2008 11.1.1 Definition of Ra dioactive Source Terms 11.1.1.1 Design-Basis S hielding Source Terms
Design-basis shielding source terms or conservative source terms are those source terms u sed for the design of bulk shielding, for determining in-plant a irborne 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 do ses to personnel do not exceed the limits sp ecified 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 sou rce terms are those terms which are used for describing the rele ases from the station to the environment on an average annual basis. Site bo undary doses due to releases from the station stack, disc harges to the blowdown stream for liquid di scharges, and offsite shipment of solid radioactive material are examples of calculati ons which use these source terms. R ealistic source terms are based on realistic models for reactor c oolant activity as r epresented in Tables 11.1-3 and 11.1-4.
Calculations pertaining to releases described in Appendix I of 10 CFR 50 follow the so urce assumptions of Regulatory Guide 1.112, Revision 0, April 19 76 and NUREG-0017, April 1976.
11.1.1.3 Accident Sources Accident sources are those sources used in the d etermination of doses to plant operating per sonnel and the pub lic during one of the postulated accidents des cribed in the regulatory guides. The design-basis accidents are discussed in Chapter 15.0. The analyses determine that the doses to the popul ation do not exceed the limits specified in 10 CFR 100 f or accidents analyzed using TID-14844 and 10 CFR 50.67 f or accidents analyzed using alternative source term methodology. Some of the bulk shielding calculations use accident source
- s. These include the shielding
B/B-UFSAR 11.1-2 REVISION 9 - DECEMBER 2002 of the control room and the shielding of piping and components which process radioactive fluids which contain s ources from one of the design-basis ac cidents. These include the components of the RHR, safety injectio n, and containment s pray systems. The accident design condit ions for these c omponents are clearly defined in Table 12.3-2. The po stulated 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 acci dents are referred to as component failure sources and will be refe renced in this chapter.
11.1.2 Basis for Radi oactive Source Terms Two source term models (a design-basis model and an operational basis realistic model) a re presented for shi elding design and effluent release analysis. Source terms for shi elding design and component failure are based on t he same design-b asis model for reactor coolant activi ty but on different assumptions with respect to the o perating characteristics of the Waste Processing Systems. The source t erms for the e ffluent release analysis are based on the realistic model for reactor coolant activity as formulated in the draft standard N237 (Reference 1).
Tritium production a nd fuel operating ex perience 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 com pared to operating plant data where available (Reference 2).
11.1.2.1 Conservative Model for Reactor C oolant Activity Fission Products The parameters used in t he calculation of the reactor coolant fission product concentr ations for original plant design are summarized in Table 11.1
-1 and the concentra tions are presented in Table 11.1-2.
The fission products concentrations are computed using the following differ ential equations:
For parent nuclides in the coolant:
wi o i i c i wi N)'tB B'B R (N D dt dN i++= (11.1-1) For daughter nuclide s in the coolant:
wi i wj o j j c j wi N N)'tB B'B R (N D dt dN j+++= (11.1-2)
B/B-UFSAR 11.1-3 REVISION 7 - DECEMBER 1998 Where N = population of nuclides, atoms t = time (sec),
D = cladding defects, as a fraction of rated core thermal power being ge nerated by rods with cladding defects, R = purification flow, coo lant system volumes per second, B o = initial boron co ncentration (ppm), B = boron concentrat ion 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 da ughter nuclide. The fission products are removed by decay, by cleanup in the chemical volume and cont rol system, and by let down to the boron recycle system.
Corrosion Products The corrosion product ac tivities, which are in dependent of fuel defect level, are based on measurements at operating reactors (Reference 2). The co rrosion product concentr ations are given in Table 11.1-2.
11.1.2.2 Realistic Model for Reactor Coolant Activity The range of plant design and op erating parameters c overed by the referenced standard N237 (Refe rence 1), together with the corresponding specific p lant related paramet ers, are given in Table 11.1-3. C orrections are made when ever a parameter falls
B/B-UFSAR 11.1-4 REVISION 1 - DECEMBER 1989 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 e quivalent to the stripping fractions. A separate value of the st ripping fraction for each noble gas isoto pe is used as indicated in Table 11.1-1.
A stripping efficiency of 40% is used for conservatism. Using this low stripping or separation eff iciency in the volume control tank results in a co nservative estimation of the reactor coolant system radioactivity.
The amounts of fission g ases removed from the reactor coolant in the volume control t ank and collected by the gaseous waste processing system are related by the following equations:
C - C C - C = SE L R L R eq (11.1-3) C C - C = SF R L R (11.1-4) where SE = stripping efficiency, SF = stripping fraction, C R = gas concentration in the liquid phase entering volume control tank, C L = gas concentration in the liquid phase leaving the volume control tank, and C Leq = gas concentration in the liquid phase leaving the volume control tan k, assuming the ratio of the gas concentration in the vapor and liquid phases in the volume c ontrol tank follows Henry's Law.
Specific activities in t he primary coolant, based on the realistic model, are g iven in Table 11.1-4.
11.1.3 Source Terms for Shielding Design Basis Liquid Waste P rocessing System Shielding source terms are suppl ied 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 S ubsection 12.2.1.
B/B-UFSAR 11.1-5 REVISION 9 - DECEMBER 2002 Gaseous Waste Pr ocessing System The gaseous waste processing s ystem consists of two waste-gas compressor packages, six gas dec ay 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 a re used. A stripping efficiency of 100% is assumed.
The result ing source terms are given in Table 12.2-28.
11.1.4 Source Terms f or Component Failure Liquid Waste P rocessing System The tanks with the h ighest isotopic inve ntories, the recycle holdup tank and the spent resin storage tank, were selected for accident analysis. The inventory used for a ccident analysis is also the inventory u sed 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 Pr ocessing System The isotopic inventories in one gas decay tank to be used for the gas decay tank rupture a ccident are given in T able 11.1-5. The inventories are based on the reactor coolant activity in Table 11.1-2 and 100% stripping efficiency in the vo lume control tank.
The activity is further based on 40 years inve ntory taking credit for radioactive decay re sults in equilibrium l evels of Kr-85 and all other isotopes within the volume control t ank. It is assumed two units are operat ing simultaneously a nd 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 acti vities presented in Table 11.1-4 are used as a basis for the expected isotopic inventories of radwaste components for the estimate of aver age annual curies of radioactive wastes to be shipped offsite. T he radioactive inventories are presented in Tables 11.1-6 thr ough 11.1-11. The flow rates and operating times u sed in the calcu lation of these inventories are the design-basis parameters for the radwaste system as described in S ections 11.2 and 11.4.
11.1.6 Sources of In-Plant Airborne Radioactivity Sources of in-plant airb orne radioactivity f or the purpose of evaluating the v entilation systems are discussed in Subsection 12.2.2. Leakage rates are discussed the re, and Tables 12.2-46 through 12.2-48 present total liquid iod ine concentrations, B/B-UFSAR 11.1-6 REVISION 9 - DECEMBER 2002 number of leakage sour ces, exhaust a ir flow rates, and fractions of maximum permissib le concentrations for iodine (10 CFR 20 Appendix B). Previous e xperience of gaseous radioactive in-plant concentrations are cited in Reference 2 for the Robert E. Ginna Plant. Special design f eatures which minimize t he possibility of airborne contamination of occupi ed areas are proper venting of equipment, discussed in Subsection 12.3.1.5, and proper location of valves and instruments, dis cussed in Subsec tion 12.3.1.8.
11.1.7 Sources of R adioactive Releases to the Environment 11.1.7.1 Gaseous Releases Gaseous radioactive re leases are discussed in Subsection 11.3.3.3. Estimates of the gaseous releases from the plant, which includes gas stripping, blowdo wn ventilation off-gas, and air ejector exhaust, are pre sented in Table 11.3-6.
11.1.7.2 Liquid Releases Liquid radioactive relea ses are discussed in S ubsection 11.2.1.3.
Expected annual average releases of radionuc lides 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 Norm al Operation R adiation Source Terms The original licensed po wer level was 3411 M Wt. The original source term, eff luent 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 is re-calcu lated at a core power level of 3658.3 MWt which includes a 2%
margin for unc ertainty. The parameters used in the calculation of the original as well as t he uprated reactor coolant concentr ations are summarize d 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 react or coolant concentrations are comparable to the original d esign basis reactor coolant concentrations given to Table 11.1-2. C onsequently, the normal operation radiation source terms for downstream process systems described in prior sections, including liquid and gaseous radwaste, remain val id for uprate.
Based on a comparison of original vs power uprate GALE-PWR computer program input parameters pr esented in Table 11.2-2, and the methodology outlined in NUREG 0017, the ma ximum 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%. Consi dering 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 t he existing NUREG 00 17 based realistic B/B-UFSAR 11.1-6a REVISION 9 - DECEMBER 2002 reactor coolant isotopic inventory. Consequen tly, the realistic reactor coolant source t erms presented in Ta ble 11.1-4, as well as all of the downstre am realistic source te rms, remain valid for uprate. 11.1.9 References
- 1. American National Standard S ource Term Speci fication, N237, March 9, 1976.
- 2. Source Term Data for Westinghouse Pres surized Water Reactors, WCAP-8253, Amendment 1, July 1975.
- 3. Operational Expe rience with Westinghou se Cores, WCAP-8183, June 1, 1977.
B/B-UFSAR 11.2-1 REVISION 9 - DECEMBER 2002 11.2 LIQUID WASTE MANAGEMENT SYSTEMS In general, the liquid radwaste system colle cts, monitors, and recycles or releases, with or without tr eatment where appropriate, all potentially r adioactive liquid wastes produced by the station d uring normal ope ration and maint enance, as well as transient conditions. The on ly exception is that effluent from the treated water system (Byron only), the condensate polisher sump and the turbine buildi ng fire and oil sump, because of minimal activity le vels, is normally discha rged without being processed through the liquid r adwaste system.
Effluent from these sumps is monit ored by radiation monitors that will automatically terminate sump discharge if un acceptable activity is present in the sump effluent.
Corrective act ion can then be initiated to reroute the sum p effluents to t he appropriate treatment system pri or 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 wil l have radio active nuclide concentrations well within the limits sp ecified in 10 CFR 20 and 10 CFR 50, Appendix I.
Each liquid radwaste processing stream termi nates in a monitor tank (see Drawing M-48A). S ince the liquid radwaste system operates on a batch basi s, this arrangement al lows each treated batch to be sampled to a ssure that the treatment was sufficient.
If the sample in dicates that the waste needs fur ther processing, it is recycled eithe r through the same subsystem or through another subsystem prov iding a different form of treatment. If the treated waste water is not needed for re use, the water is sent to either r elease tank (OWX01T or OWX26 T) for discharge.
Each batch is sampled prior to discharge from the release tank to verify that its activity level is within lim its for discharge.
The actual discharge to the circulating water blowdown line requires manually opening a re motely operated valve with a keylocked switch. The key f or the valve loc k is controlled by administrative procedures.
11.2.1.2 Power Genera tion Design Basis The liquid radwaste system is sized to handle maximum expected liquid waste inputs on t he basis of both volume and activity as a result of normal operation, in cluding anticipated abnormal occurrences for Units 1 and 2.
The liquid radwaste system is composed of th e following two subsystems:
- a. the steam generator blowdown subsystem, and
- b. the nonblowdown radwaste subsystem.
B/B-UFSAR 11.2-2 REVISION 12 - DECEMBER 2008 These subsystems are extensively crosstied to provide a high degree of availabili ty and reliability.
The purpose of the s team generator blo wdown subsystem is to maintain the steam generator w ater chemistry within specified limits. The liquid radwaste system is de signed to permit recycling of plant water. The stations are designed to minimize noncontaminated inputs f rom leakage of service water, circulating water, and groundwat er into the plant fl oor drain system.
A cost-benefit a nalysis is not r equired for the liquid radwaste system. This is because Commonw ealth Edison has complied with the Guides on Design Objectives for Ligh t-Water-Cooled Nuclear Power Reactors p roposed in the concluding st atement of the position of the regulatory staff in Docket RM-50-2 dated February 20, 1974, pp. 25-30.
11.2.1.3 Expected Radio active Releases Byron and Braidwood Nucl ear stations have upra ted the core power level to 3586.6 MWt. The origin al licensed power level was 3411 MWt. The original expected liquid rad waste 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 t he uprated parameters describing the expected normal op eration of one unit of the station are listed in Table 11.
2-2. These values were used as input to the c omputer code for the original analyses.
The impact of core uprate on t he effluent releas es was evaluated based on an assessment of the changes in input parameters.
Core uprate results in a maximum potential inc rease of 0.6% in the liquid effluent re lease concentrations p reviously reported.
Taking into consideration the accuracy and e rror bounds of the operational data utilized in NUREG 00017, th is 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 whi ch remain valid for uprate. For tables 11.2-1 and 11.2-4 (for Braidwood only
), actual data has been used to determine the e xpected tritium (H-3) release and blowdown concent ration values.
B/B-UFSAR 11.2-2a REVISION 12 - DECEMBER 2008 11.2.1.4 10 CFR 50 Comparison Conservatively estimat ed annual average dose s to individuals exposed to radioactive liquid effluents are given in Table 11.2-3. As can be s een from the total d ose rates from the various exposure pathway s, the numerical gui delines set forth in Appendix I to 10 CFR 50 are sati sfied. As discu ssed in Section 11.2.1.3, this assessm ent and Table 11.2-3 remain valid for uprate.
For Braidwood only, dose calculations using actu al release data and compiled in annu al 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 compare s expected liquid ef fluent concentrations with 10 CFR 20 limits.
It can be seen that the expected effluent concentrations are signi ficantly below the spe cified limits. As discussed in Section 11.2.1.3, this assessme nt and Table 11.2-4 remain valid for uprate.
For Braidwood only, actual liquid effluent r elease data compiled in annual effluent release rep orts, 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 t he design parameters of various radwaste system components.
B/B-UFSAR 11.2-3 REVISION 2 - DECEMBER 1990 11.2.1.7 Seismic Design a nd Quality Group The structures housing t he liquid radwaste system are Safety Category I for the auxil iary building, a nd Safety Category II for the turbine building and radwaste building. All components (including tanks, pumps, valve s, and piping) of the liquid radwaste system containi ng radioactive wastes are classified as Quality Group D, with the ex ception of the containment penetration piping out to and including the second isolation valve from the c ontainment 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 de signed to minimi ze radiation exposure to operating personnel. No rmal operations, maintenance, and nonroutine operati ons are discussed in the following.
11.2.1.8.1 Maintenance Operations Wherever practicable, components of the liquid r adwaste systems are segregated to the maximum extent pra ctical. To reduce radiation exposure to maintena nce personnel, components are arranged so that access to a low activity component does not necessitate passing near a high activity compo nent. Instruments are located in low dose rate areas wherever practical to minimize the radiation exposure to maintenance personnel.
Valves, where practicabl e, are located outside of co mpartments to minimize radiation exposure from tan ks or components during valve maintenance. Most r adwaste pumps are eq uipped with mechanical seals to minimize maintenance.
In general, components which may require maintenance are capable of being flushed pri or to maintenance.
11.2.1.8.2 Floor, Wall, and Ceiling Coatings In rooms containing radioactive wastes, the floors, and as necessary, the w alls and ceilings, are coated with a two-coat water base epoxy pai nt 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 w hich may contain r adioactive fluids:
- a. Tank level instrumenta tion is provided on most radwaste tanks with readout devices in the radwaste control room. A high-level conditio n on these tanks will be annunciated.
- b. Some radwaste ta nks overflow to an a djacent sump, as described in Table 11.2-
- 9. Sumps ar e provided with
B/B-UFSAR 11.2-4 REVISION 9 - DECEMBER 2002 duplex or triplex (redun dant) pumps as a ppropriate.
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 du ring normal oper ations, it is expected that it will be necessary to make controlle d releases of contaminated steam and condensate leakage to the environment.
During normal operations, these releases of radioactive liquids to the environment are from the rele ase tank after processing, as needed, by the liqui d radwaste system.
As a batch of waste is processed, the effluent is transferred to an appropriate m onitor tank (e.g., blowd own 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 p rior to discharge.
The release tanks discharge must pass thro ugh either one of tw o remotely controlled keylocked valves (0WX353 and 0 WX896 on Drawing M 1) to be released from the station. Li mit switches supply status information on the valve position to the operator at the radwaste control panel. A radi ation monitor is provided to automatically close the valves on a hi gh radiation signal.
In addition, eff luents from the treated water system, the condensate polisher sump and the turbine building fire and oil sump are released to the environ ment. While n ormally considered non-radioactive, these effluents can potentially become contaminated, and the sump efflu ents are monitored by radiation monitors which will halt sump pump operation if unacceptable activity levels are pres ent in sump effluent.
B/B-UFSAR 11.2-5 REVISION 12 - DECEMBER 2008 11.2.1.11 ETSB-BTP 11-1 Comparison The liquid radwaste system is designed to meet the design criteria of the former E ffluent Treatment Syst ems Branch (ETSB), Branch Technical Position BTP 11
-1, Revision 1, and meets the criteria of Regulatory G uide 1.143, as descr ibed in Appendix A.
11.2.2 System Description The liquid radwaste syst em is shared by both units. Unit 1 and Unit 2, however, hav e separate equipment and floor drain collection sump system
- s. Process flow d iagrams are shown in Drawing M-48A. The systems are depicted in Drawings M-48-1 through M-48-40.
Inputs to the system are separat ed according to origin and/or concentrations of radi oactivity and chemical impurity. Separate collection tanks are provided for each input stream.
The waste is routed from the c ollection tanks to the a ppropriate processing paths. The system pro cesses the radioactive liquid waste by various combinations of filtration, evaporation (Braidwood only), and/or demineralizatio
- n. At Braidwood, vendor radwaste processing systems m ay utilize filtration, demineralization, chemical and ultraviolet treatment, and/or reverse osmosis to assist in radioactive liquid waste proce ssing and recycling.
Provisions are made to b ypass any processing d evice. The release tanks cannot be bypassed.
After being processed th rough the various eq uipment 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 circulat ing water bl owdown line.
B/B-UFSAR 11.2-6 REVISION 7 - DECEMBER 1998 The liquid radwaste system is de signed to handle wastes generated during design-basis op erational occurren ces. This is accomplished by providing sufficient process capacity within the subsystems and c ollection and monitor tanks of adequate size.
The liquid radwaste syst em consists of two c rosstied subsystems:
- a. steam generator blowdown subsystem, and
- b. non-blowdown radwaste subsystem which treats the following waste streams:
- 1. auxiliary buildi ng equipment drains, 2. auxiliary building floor drains, 3. chemical waste drains,
- 4. regeneration waste drains, 5. laundry (det ergent) drains, 6. turbine building equipme nt and floor drains when contaminated, and
- 7. condensate polisher sump when unacceptably contaminated.
Expected concentrations of radioactive nucli des in the various input waste streams to t he radwaste subsystems are listed in Table 11.1-6. E xpected inventories of r adioactive 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 expe cted daily flows of each waste stream.
The expected activities in Table 11.1-1 corres pond 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 acco rdance with the ODCM.
Table 11.2-7 lists t he design-basis decontam ination factors for the processing components used in the analys is of the systems.
The original steam g enerator blowdown pr efilters were replaced with larger prefilter units. However, the expected average and maximum waste stream flo ws and the design basis decontamination factors for the steam generator blowdown pre filters were not revised to account for the larger prefilter volume.
11.2.2.1 Steam Generator Blowdown Subsystem The function of the steam genera tor blowdown sub system is to maintain steam generator shell side water chem istry within the
B/B-UFSAR 11.2-6a REVISION 6 - DECEMBER 1996 specified limits. Continuou s blowdown constantly removes impurities from the steam generator. The flow rate is varied as required to maintain the steam g enerator water c hemistry within the required limits.
At Byron, steam generator blowdo wn may be sent to the condensate polisher sump to improve secondary chemistry when excessive impurities are prese nt that would quickly ex haust steam generator blowdown demineralizers.
For a further descript ion of the steam generator blowdown subsystem, see Subse ctions 10.4.8 and 10.4.9.3.1.
B/B-UFSAR 11.2-7 REVISION 6 - DECEMBER 1996 The components of th e steam generator blowdown treatment subsystem include fo ur blowdown prefilters; four blowdown mixed bed demineralizers; four blowdown demineralizer after filters; three blowdown monit or tanks; and associated pumps, valves, and instrumentation.
11.2.2.1.1 Normal Operation Steam generator blowdown is operated in a norm al range of 15 to 90 gpm per steam generator, depending on steam generator chemistry requirements.
During normal opera tion, blowdown is pumped from the steam generator blowdown con denser hotwells through the blowdown prefilters, the b lowdown 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 e ffluent leaving the blowdown mixed-bed demineralizer s, the effluent is diverted to the monitoring tanks.
Unit 1 and Unit 2 blo wdown is normally segregated, as the Unit 1 and Unit 2 con densate 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 requ ires adjustment to maintain the steam generator water chemistry limits.
- b. If leakage condition e xists, 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 up on operating experience.
The effluent from ea ch blowdown mixed bed demineralizer is directed through a blowdown afte rfilter to a header which is valved so that Unit 1 ef fluent is normally sep arated from Unit 2 effluent. Conductivity of each effluent stream from the blowdown mixed bed demineralizers is moni tored. The processe d liquid can be routed to either Unit 1 or Unit 2 condensate storage tanks as
B/B-UFSAR 11.2-8 REVISION 12 - DECEMBER 2008 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 u sed to sluice blowdown demineralizers or to b ackwash blowdown demineralizer strainers.
In addition to process ing steam generator blowdown, the blowdown mixed bed demineralizers can be used for processing turbine building equipment drain s, turbine building fl oor drains, and for the further processing of the purified effluent from the radwaste subsystems via the r adwaste and blowdown mon itor tanks. This practice is not recommended for normal operation.
Effluent from the blowdown pre filters of each unit can be diverted to each of the three ra dwaste evaporators, but normally this flowpath is blocked by a sp ectacle blank flange (Braidwood only).
11.2.2.1.2 Circulating Water to Secondary S ystem Leakage In the event of condenser tube or tu be 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-Lea kage Concurrent with Failed Fuel The radioisotope concent ration in the steam ge nerator blowdown is given in Table 12.2-30 and Table 11.1-6. If primary to secondary leakage occurs in only one steam generat or, the blowdown rate from nonleaking steam generators remains high enough to maintain chemistry specifications while the blowdown ra te from the leaking steam generator may be increased to the desi gn rate of 90 gpm.
11.2.2.1.4 Primary-to-Secondary Leakage Not Concurrent with Failed Fuel The steam generator blowdown d uring 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.
B/B-UFSAR 11.2-9 REVISION 10 - DECEMBER 2004 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 Liqu id Radwaste Subsystem This processing train co llects and treats li quid radwastes from sources other than steam generator blowd own. The mode of operation is batchwi se. The nonblow down liquid radwaste subsystem includes the following input sources:
- a. auxiliary buildi ng equipment drain, b. auxiliary building floor drain, c. chemical waste drain,
- d. regeneration waste drain, e. laundry (det ergent) 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 contami nated) (Byron only). Each drain system except the c hemical waste, reg eneration waste, and laundry drains, has two drain co llection tanks. The chemical waste and regeneration w aste drains utilize one tank each plus a shared dual purpose chemical/reg eneration waste drain tank.
Waste is usually collected in one of two drain tanks. The contents of the other tank may be sampled or processed. The sample is taken from the recirculation line.
Chemical additions to adjust the wastewater pH or filter aids may be added to improve waste proces sing efficiency.
Oil separators are provi ded in those sumps t hat could potentially have oil in the water.
A filter is installe d downstream of each drain tank pump discharge header, or drain tank effluent is sent to vendor-installed eq uipment for filtration as needed.
B/B-UFSAR 11.2-10 REVISION 10 - DECEMBER 2004 The radwaste evaporator inlet header receive s liquid wastes from the previously mentioned dra in tanks. The liq uid wastes entering the radwaste evapora tor inlet header n ormally bypass the evaporators and are proc essed by the radwaste demineralizers or by the vendor demineralizers.
At Byron, nonessential service water to the radwaste evaporator skids has been isolated permanently. Blank plat es have also been installed in the inlets to the evaporators to prevent liquid wastes from entering.
The radwaste monitor tanks collect rad waste 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 rad waste building for add itional processing, as needed, and retur ned to the installed radwaste system for monitored discharge.
Based on this sample and stati on water balance considerations, the water may be reproce ssed or discharg ed via the rel ease tanks.
See Table 11.2-6 for the design-basis average and maximum waste stream flows for the v arious 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 p olisher sump, from the turbine building floor a nd equipment drains (collected in the turbine building fire and oil su mp) and from the waste treatment system is processed by t he 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 f rom the condensate pol isher sump and from the turbine building flo or and equipment drains is processed by the radwaste system if contamination lev els exceed effluent limits. The turbine building fire and oil sump effluent is monitored by a radiation monitor to ensure that ODCM limits are maintained.
11.2.2.2.1 Auxiliary Buil ding Equipment Drain Input sources to the a uxiliary building equi pment 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 pr ocessed through demineralizers.
B/B-UFSAR 11.2-11 REVISION 6 - DECEMBER 1996 11.2.2.2.2 Auxiliary Building Floor Drain Input sources to the floor dra in tanks include l eakage from pump seals and stuffing boxes, va lve stem pac king, equipment overflows, and spill
- s. Oil separators a re provided in the subsystem's sumps.
Input sources to the a uxiliary building floor drain tanks include the following:
- a. reactor cavity sumps, b. containment fl oor drain sumps, c. auxiliary buildi ng floor drain sumps, d. fuel handling building floor dra in sumps, and
- e. radwaste building sump.
The two tanks are sized to accommodate the m aximum accumulation of wastes expected in 1 day. The processing flow paths are the same as in the a uxiliary building equipment drain.
11.2.2.2.3 Chemical Waste Drain Input sources to the chemical dr ain tank and the dual purpose chemical/regeneratio n drain tank include the following:
- a. laboratory drains, b. fuel handling buildi ng decontamination sump, c. samples containing triti ated water and chemicals required for analysis,
- d. drumming station sumps, e. boric acid p rocessing system, f. primary water storage tank, and
- g. any other high-condu ctivity radioactive drains.
One tank is provided solely for the chemical dra ins. A second tank is used as a du al purpose chemica l/regeneration waste drain tank. These wastes are processed through a demineralizer.
B/B-UFSAR 11.2-12 REVISION 10 - DECEMBER 2004 11.2.2.2.4 Regeneration Waste Drain Input sources to the regeneration waste drain tank and the dual purpose chemical/regen eration waste drain tank include the following:
- a. spent resin sluicing drain header, b. drumming station decanti ng tank overflows (Byron only), c. release tanks (r egeneration waste dr ain tank only), and d. tendon tunnel su mps (when determined to be a source of radiation contaminati on into the fire and oil sump). The blowdown and radwaste mixed bed demineralizers are replaced as often as is required to maintain the demi neralizers effluent water quality.
11.2.2.2.5 Laundry Drain
The laundry drain tank collects detergent wastes from the radioactive laundry (Braidwood o nly), personnel decontamination shower and the T SC drains and showers.
These waste streams are sent to the release tanks for release or a r adwaste demineralizer for further treatment.
11.2.2.2.6 Turbine Buildi ng Equipment Drain Secondary system drains are di vided into turbine building equipment drain and turb ine building floor d rain. The turbine building equipment drain system can recover a large amount of condensate grade water f or station reuse.
Two turbine building equ ipment drain tan ks receive water from the turbine building equipme nt drain sumps. Sin ce 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 p lant for discharge.
There are also flowpaths from the tur bine building equipment drain system to the radwaste demineralizers and to the liquid release tank.
B/B-UFSAR 11.2-13 REVISION 12 - DECEMBER 2008 At Byron, in the event of ex cessive leakage of the primary coolant into the seconda ry system, the water may be processed in the waste treatment plant and re turned to the re lease tank for discharge. At Braidwo od, in the event of excessive leakage of the primary coolant into the sec ondary system, the contaminated water may be process ed through the coale scer/carbon filters and through additional fil tration 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 flo or drain tanks col lect water from the turbine building floor d rain sumps, condensate pit sumps, and essential service wa ter sumps. These wa stes 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 Buildi ng Fire and Oil Sump Turbine building was te water collect ed in the fire and oil sump, including equipment and floor drain water, is monitored by a radiation monitor. Water from this sump is norm ally discharged to the waste tre atment system for removal of oil and solids and then released to the environment via the circulating water system and blowdown line.
However, if unacce ptable radioactive contamination is detected, the sump pumps ar e automatically stopped and the water may be sent to the liquid radwaste treatment system, via the waste treatment syst em (Byron only).
If the source of radio active contamination is determined to be one of the tendon tunnel sumps, either tendon tunnel pump discharge can be sent to the reg eneration waste drain tank for processing in the radwaste system.
The water may be processed by the waste treatment plant and re turned to the re lease tanks for discharge (Byron only).
11.2.2.2.9 Condensate Polisher Sump Water in the condensate polisher sump is monit ored by a radiation monitor on the sump disc harge. Water from this sump discharge is normally directed to the circula ting water sys tem, and then released to the environm ent via the blowdown line. If a high radiation signal is detected, pu mp operation is automatically stopped and major conden sate polisher inputs into the sump are automatically isolated.
If samples confirm th at the water is contaminated, the oper ator may manua lly change the valve lineup to send the water to the relea se tank for a monitored discharge.
11.2.2.2.10 Waste Treatment System The input to the waste treatment system is the T urbine Building Fire and Oil Sump (see 11.2.2.2.8). Water p rocessed by the waste treatment system is normally rel eased to the environment via
B/B-UFSAR 11.2-13a REVISION 6 - DECEMBER 1996 the circulating wate r system and blowdown li ne. If the radiation monitor on the Turbi ne 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 radioact ive contamination, t he system's contents would be pumped to the liquid radwas te system.
B/B-UFSAR 11.2-14 REVISION 8 - DECEMBER 2000 11.2.2.3 Operating Procedures If the contents of a monitor tank are to be released, the required radioactivity analysis is perfo rmed prior to transferring the material to t he release tank. The liquid is then pumped to a release tank wh ere a sample is again taken and the required analysis is performed. Based on this analysis, the discharge rate is de termined so that, wh en mixed with cooling water blowdown discharge s, 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 admi nistrative pro cedures. As a further backup, a radiation detector mon itors 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 radi ation, 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 requ irements of th e Technical Specifications. Recor ds are maintained of radioactive wastes discharged to the environment.
11.2.2.4 Performance Tests Liquid wastes may be m onitored before and af ter each processing step on a batch basis. The equipment is the refore subjected to continuous per formance testing.
Data on specific isotope decon tamination factors are not conclusive. This system was d esigned using cons ervative overall decontamination factors.
These decontamination factors are based on guidelines from R eferences 2, 4, and 5.
Through system cross-t ies, 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 t he liquid radwas te system is con trolled and monitored from the liq uid radwaste control panel (LRCP) located in the radwaste cont rol room. Radwa ste and blowdown demineralizers and radwaste evaporator c ontrol panels and the liquid/solid radwaste interface are also loc ated in the radwaste control room. The solid radwaste handling system control panel is located in the radwaste building.
B/B-UFSAR 11.2-14a REVISION 9 - DECEMBER 2002 Some subsystem operations are controlled by au tomatic sequencers.
Instrumentation on rad waste system tanks inc ludes, as a minimum, a high level det ector for LRCP annun ciation, a low level detector for pump cutoff, and LRCP le vel recording.
The system instrumentation is sho wn in detail on Drawin gs M-48-1 through M-48-40.
BYRON-UFSAR 11.2-15 REVISION 7 - DECEMBER 1998 11.2.3 Radioactive Releases 11.2.3.1 Release Points All liquid radwaste sy stem effluent paths for radioactive nuclides to the enviro nment are suitably pro cessed, monitored, and recycled or discha rged via the relea se tanks in accordance with procedures outlin ed in Subsection 11.2.2.
- 3. The radioactive waste release line joins the c irculating water b lowdown line.
Water from the turbi ne 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 dischar ged after suitable t reatment into the circulating water flume, and r eleased via th e blowdown line.
11.2.3.2 Dilution Factors
At 100% capacity factor and design-basis ambie nt 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 blowdo wn is expected to be approximately 13,000 gpm, or 2.6 x 10 13 cm 3 per year. The a nnual radionuclide release and the concentration in the cooling tower blowdown line are given in Table 11.2-4.
Circulating water blowdo wn enters the Rock R iver approximately 50 yards downstream of the intake structure, so releases do not become entrained in makeup water. The circula ting water blowdown warming line to the ri ver screen house is isolated during releases to prevent entr aining radionuclides in the circulating water and essential serv ice water makeup lines.
11.2.3.3 Estimated Annual Average Doses The estimated total annu al release of ra dionuclides in liquid effluents is given in Table 11.2
-1. Using an annual dilution volume of 2.6x10 13 cm 3 , the concentration of each nuclide in the cooling tower blowdown l ine can be determined.
This is shown in Table 11.2-4.
Estimated annual average doses to individuals exposed to radioactive liquid eff luents were calc ulated using the methodology of Regulat ory Guide 1.109 (R eference 3). Fish consumption, drinking water, and recreationa l exposure pathways were considered. Annual use fac tors for these p athways are given in Table 11.2-8.
In order to obtain a conservative estimate of the radiation doses, no radioactive decay or dilution by r iver water was taken into consideration.
Estimates of doses to the whole body and to diff erent organs are summarized in Table 11.2
-3. As explained in Subsection 11.2.1.4, these estimated doses are all within Appendi x I to 10 CFR 50 guidelines. Actual release data are available in the effluent release reports, which a re prepared in accorda nce with the ODCM.
BRAIDWOOD-UFSAR 11.2-16 REVISION 11 - DECEMBER 2006 11.2.3 Radioactive Releases 11.2.3.1 Release Points All controlled liquid ra dwaste system ef fluent releases of radioactive nuclides to the environm ent are suitably proce ssed, monitored, and recycled or discharged via t he release tanks in accordance w ith procedures outlined in Subsection 11.2.2.3. The radioactive waste release line joins the cooling pond blowdown line as in dicated in Drawing M 1. Water from the fire and oil sump, and con densate polisher s ump (Subsections 11.2.2.2.8 and 1 1.2.2.2.9), if not unacc eptably contaminated, is discharged, after suitable treat ment, into the c ooling 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 a nd surrounding groundwat er is pumped into the circulating water blowdown line at Vacuum Breake rs 1 and 2, contribute to the inventory of radioactive nuclides released to th e environment via the blowdown line. Periodic sampl ing of the water is used to monitor the radioactivity of the wat er that is dis charged into the blowdown line.
11.2.3.2 Dilution Factors
At 100% capacity factor, blo wdown from the cooling lake is expected to be 25,000 gpm on an annual aver age basis, or 4.98 x 10 13 cm 3 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 co oling pond blowdown flow of 12,000 gpm, which is the normally expected bl owdown flow rate without the use of blowdown booster pumps.
Cooling pond blowdown en ters the Kankakee River approximately 50 yards downstream of the intake structu re, so that releases do not become entrained in makeup water.
11.2.3.3 Estimated Annual Average Doses The estimated total annual release of radionucli des in liquid effluents is given in Table 11.2-1.
Using an annual dilution volume of 2.4 x 10 13 cm 3 , 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 expose d to radioactive liquid effluents were calculated using the methodology of Re gulatory Guide 1.109 (Reference 3). Fi sh consumption, drinking water, and recreational exposure pathways were consi dered. Annual use facto rs for these pathways are given in Table 11.2-8.
In order to obtain a conservative es timate of the radiation doses, no radioactive decay or dil ution by river water was taken into consideration.
Estimates of doses to the whole body and to diff erent organs are submitted in Table 11.2-3. As explained in Subsection 11.2.1.
4, these estimated doses are all within App endix I to 10 CFR 50 g uidelines. Actual release data are available in the effluent r elease reports, which are prepared in accordance with the ODCM.
B/B-UFSAR 11.2-17 11.2.4 References
- 1. Regulatory Guide 1.112, "Calculati on of Releases of Radioactive Materials in Gaseous and Liquid Effluents from Light Water-Cooled Power Rea ctors," U.S. Nuclear R egulatory Commission, April 1976.
- 2. NUREG-0017, "Calcu lation of Releases of Radioactive Materials in Gaseous and Liqui d Effluent from Pres surized Water Reactors (PWR-GALE Code)," Office of Stan dards Development, U.S. Nuclear Regulatory Commissio n, April 1976.
- 3. Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for t he Purpose of Evaluating Compliance with 10 CFR Part 50, A ppendix I," U.S.
Nuclear Regulatory C ommission, Revision 1, October 1977.
- 4. ANSI Standard N199, "Liquid Radioactive Waste Processing System for Press urized Water Rea ctor Plants," Am erican National Standards Institute, Inc., 1976.
- 5. WASH-1258, "Numeri cal Guides for D esign Objectives and Limiting Conditions for Operation to Meet the Criteria 'Low as Practicable' for Radioactive Material in Light-Water-Cooled Nuclear Power Reactor Ef fluents," U.S. Atomic Energy Commission, 1973.
B/B-UFSAR 11.2-18 REVISION 12 - DECEMBER 2008 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 (DAYS) PRIMARY (MICRO CI/ML) SECONDARY (MICRO CI/ML) BORON RS (CURIES) MISC. WASTES (CURIES) SECONDARY (CURIES) TURB BLDG (CURIES) TOTAL LWS (CURIES) TOTAL (CI/YR) WASTES (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)
B/B-UFSAR
11.2-19 REVISION 10 - DECEMBER 2004 TABLE 11.2-2 PARAMETERS USED IN THE GALE-PWR COMPUTER PROGRAM (ORIGINAL & UPRA TED) - NOTE 1
- 1) Reactor type PWR 2) Thermal power level (MWt) 3565.0 (3586.6) 3) Mass of coolant in the primary system (10 6 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 (10 6 lb/hr) 15.0 (16.04) 8) Mass of steam in each steam generator (10 3 lb) 9.1 (6.039) 9) Mass of liquid in ea ch steam generator (10 3 lb) 117.0 (114.465) 10) Total mass of se condary coolant (10 3 lb) 2023.0
- 11) Steam generator blowdown rate (10 3 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 (10 3 gpm)
Cooling tower blowdown, Byron 13.0 Cooling lake blowdown, Braidwood 12.0*
Iodine - 10 3 , Cesium - 2 x 10 3 , Others - 10 4
B/B-UFSAR 11.2-20 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 - 10 5 , Cesium - 2 x 10 4 , Others - 10 6 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 - 10 5 , Cesium - 2 x 10 4 , Others - 10 6 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 - 10 5 , Cesium - 2 x 10 4 , Others - 10 6 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 - 10 2 , Cesium - 10, Others - 10 2 29) Blowdown - Collection time (days) 0.03 Processing time (days) 0.03 Fraction discharged 0.10 B/B-UFSAR 11.2-21 REVISION 10 - DECEMBER 2004 TABLE 11.2-2 (Cont'd)
- 30) Condensate demineralizer regenerant flow (gpd) 0.00
- 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 d oes 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 (10 6 ft 3) 2.9 40) Containment atmosphe re cleanup rate (10 3 cfm) 16.0
- 41) The containment shut down 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 rel eased from the main condenser air ejector **
0.10** 45) Reciprocal of the dete rgent waste processing decontamination factor 1.00 B/B-UFSAR 11.2-21a REVISION 10 - DECEMBER 2004 TABLE 11.2-2 (Cont'd)
____________________
_______________
- Original design and wi thout the use of CW blowdown booster pumps installed at Braidwood.
-0468-M revision 0.
Note 1: Parameters t hat changed due to uprat e are presented in
().
BYRON-UFSAR 11.2-22 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 assum ed to take place in the discharge canal.
No credit is tak en for dilution of e ffluents in the Rock River.
BRAIDWOOD-UFSAR 11.2-23 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 a ssumed to take pla ce in the discharge canal. No credit is taken for dilution of effluents in the Kankakee River.
BYRON-UFSAR 11.2-24 REVISION 7 - DECEMBER 1998 TABLE 11.2-4 COMPARISON OF EX PECTED LIQUID EFFLUE NT CONCENTRATIONS TO 10 CFR 20 LIMITS
- Calculated using the PWR-GAL E computer progr am described in NUREG-0017. The actual data are available in the effluent release reports, which are prepared in a ccordance with the ODCM. ** Annual average cooli ng tower blowdow n = 29.0 cfs.
- Limits used in the com parison are those that were in effect at the time of the analysis.
EXPECTED* BLOWDOWN**10 CFR 20 RELEASE CONCENTRATION LIMIT***
ISOTOPE (Ci/yr/unit)
(µci/ml) (µCi/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 8.88-131.00-04 BRAIDWOOD-UFSAR 11.2-25 REVISION 12 - DECEMBER 2008 TABLE 11.2-4 COMPARISON OF EX PECTED LIQUID EFFLUE NT CONCENTRATIONS TO 10 CFR 20 LIMITS
EXPECTED* BLOWDOWN** 10 CFR 20 RELEASE CONCENTRATION LIMIT***
ISOTOPE (Ci/yr/unit)
(µCi/ml) (µCi/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-GAL E computer progr am described in NUREG-0017 (Except H-3.
Tritium value is based on actual data.)
The actual data are av ailable in the eff luent release reports, which are prepared in accordance with the ODCM.
- Annual average cooling lake blowdown = 1 3.4 cfs per unit.
Original design and with out the use of CW blow down booster pumps installed at Braidwood.
- Limits used in the com parison are those that were in effect at the time of the analysis.
B/B-UFSAR
11.2-26 RE VISION 11 - DECEMBER 2006 TABLE 11.2-5 LIQUID RADWASTE SYSTEM C OMPONENTS 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 wi ll vary based on resin types and water chemistry.
B/B-UFSAR
11.2-27 R
EVISION 8 - DECEMBER 2000 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
after-filters 150 140 250 gpm 4 304-SS 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
B/B-UFSAR
11.2-27a
REVISION 7 - DECEMBER 1998 TABLE 11.2-5 (Cont'd)
DESIGN PRESSURE DESIGN MATERIALS OF EQUIPMENT (psig)
TEMP (°F) CAPACITY NUMBERCONSTRUCTION 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
B/B-UFSAR
11.2-28
REVISION 7 -
DECEMBER 1998 TABLE 11.2-5 (Cont'd)
DESIGN PRESSURE DESIGN MATERIALS OF EQUIPMENT (psig)
TEMP (°F) CAPACITY NUMBERCONSTRUCTION
- 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 B/B-UFSAR
11.
2-29 REVISION 13
- DECEMBER 2010 TABLE 11.2-5 (Cont'd)
DESIGN PRESSURE DESIGN MATERIALS OF EQUIPMENT (psig)
TEMP (°F) CAPACITY NUMBERCONSTRUCTION
- 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 Tank (Braidwood)
Atmos. 120 500,000 gal 1 304L-SS
B/B-UFSAR 11.2-30 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 B/B-UFSAR
11.2-3 1
REVISION 13 - DECEMBER 2010 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)
NOTE: Radwaste Evaporator Componen ts have been intentional ly deleted from this tab le. Braidwood and Byron stations do not intend to use this equipment.
B/B-UFSAR 11.2-32 REVISION 7 - DECEMBER 1998 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 uni ts) and 309 days of normal operation (120 gpm/two units).
- Based on condenser to secondary leakage of 420 gpm/two units.
B/B-UFSAR 11.2-33 REVISION 10 - DECEMBER 2004 TABLE 11.2-7
DESIGN-BASIS PROCESS D ECONTAMINATION FACTORS
EVAPORATORS CLEAN WASTEBLOWDOWN DISTILLATE FILTERS DEMINER- DEMINER- DEMINER- ELEMENT (A) (B) ALIZERS ALIZERS EVAPORATORS ALIZERS H 1 1 1 1 1 1 Cr 10 1 100 100 10 4 10 Mn 10 1 100 100 10 4 10 Fe 10 1 100 100 10 4 10 Co 10 1 100 100 10 4 10 Br 1.0 1 100 100 10 4 10 Kr 1 1 1 1 1 1
Rb 1.0 1 2 10 10 4 10 Sr 1.0 1 100 100 10 4 10 Y 1.0 1 100 100 10 4 10 Zr 10 1 100 100 10 4 10 Nb 10 1 100 100 10 4 10 Mo* 10 1 100 100 10 4 10 Tc* 1.0 1 100 100 10 4 10 Ru 1.0 1 100 100 10 4 10 Rh 1.0 1 100 100 10 4 10 Te 1.0 1 100 100 10 4 10 I 1.0 1 100 100 10 3 10 Xe 1 1 1 1 1 1
Cs 1.0 1 2 10 10 4 10 Ba 1.0 1 100 100 10 4 10 B/B-UFSAR 11.2-34 REVISION 3 - DECEMBER 1991 TABLE 11.2-7 (Cont'd)
EVAPORATORS CLEAN WASTEBLOWDOWN DISTILLATE FILTERS DEMINER- DEMINER- DEMINER- ELEMENT (A) (B) ALIZERS ALIZERS EVAPORATORS ALIZERS La 1.0 1 100 100 l0 4 10 Ce 1.0 1 100 100 10 4 10 Pr 1.0 1 100 100 10 4 10 Np 1.0 1 100 100 10 4 10
Basis for Decontamination Factors
- 1. Filters: (A) Is used for fi lter source term calculations only. (B) Is used for other calculations. (Ta ble 1-3, NUREG-0017, PWR GALE) 2. (A) Radwaste Demineralizers: (Table 1-3, NUREG-0017, PWR GA LE 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 Disti llate Demineralizers: (Table 1-3, NUREG-0017, PWR GALE)
B/B-UFSAR 11.2-35 REVISION 8 - DECEMBER 2000 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 m 3/yr 1400.0 (Infant)
- From Regulatory Guide 1.109, Table E
-5 (Reference 3).
- From Offsite Dose Calc ulation Manual, Revision 1.2, Table D-10.
- From HERMES as used in Zion Station annu al and semiannual reports on station radio active waste, environmental monitoring, and occupa tional personnel r adiation exposure.
B/B-UFSAR
11.2-36 REVISI ON 10 - DECEMBER 2004 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
B/B-UFSAR
11.2-37 RE VISION 10 - DECEMBER 2004 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)
B/B-UFSAR
11.2-38 RE VISION 13 - DECEMBER 2010 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
B/B-UFSAR 11.2-39 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
B/B-UFSAR 11.3-1 REVISION 6 - DECEMBER 1996 11.3 GASEOUS WASTE MANAGEMENT SYSTEMS This section describes the capabilities of t he plant to collect, process, store, and dispose of g aseous radioactive wastes generated as a resul t of normal operation including anticipated operation occurrences.
Total gaseous releases from the plant for normal operation, incl uding anticipated oper ational occurrences, and the resulting offs ite doses are also inc luded. Design and operating features of the gaseous waste processing system (GWPS) are presented. Appropriate chapters for other syste ms which may handle radioacti ve gases are referenced.
11.3.1 Design Bases Radioactive gaseous treatmen t 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 capaci ty and redundancy to meet discharge concentration limits of 10 CFR 20 during periods of design-basis fuel leakage. In comp liance with General Design Criterion 64 all gaseous effluent discharge paths are monitored for radioactivity.
The GWPS meets the requi rements of Gener al Design Criterion 60 by providing long-term hold up capacity, thus pr ecluding the release of radioactive efflu ents during unfavora ble 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. D esign codes and seismic design requirements are also su pplied 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 instrument ation, particularly hy drogen and oxygen monitors, to preclude the buil dup of an explosive mixture.
The gaseous radwaste system meets all of the code criteria specified in Regulatory Guide 1.143. Additi onal design bases for plant ventilation systems and co ndenser evacuation system are given in Sections 9.4 and 10.4, respectively.
B/B-UFSAR 11.3-2 REVISION 9 - DECEMBER 2002 11.3.2 System Description 11.3.2.1 System Design The gaseous waste processing sys tem (GWPS) proce sses hydrogen stripped from the reactor cool ant and nitrogen from the closed cover gas system.
The components conn ected to the GWPS are limited to those which contain no air or aer ated liquids in order to prevent accumulation of oxygen in the system. Further, the GWPS is maintained at a pressure above a tmospheric to avoid intrusion of air. T he system is not designe d for the addition of oxygen in order to rec ombine oxygen and hydrog en; therefore, no control functions are as sociated with the oxygen monitor. Hence, the GWPS will normally n ot contain oxygen and special design precautions are taken in order to avoid unin tentional intrusion of oxygen.
The GWPS has two independent gas analyzing systems. One is a sequencing hydrogen and oxygen monitoring lo op (At Byron, the system has a manual switch to se lect the sample points) which can sample the gas decay tanks and/or the co mponents connected to the GWPS. The other gas analyzing system is an ox ygen monitor that samples the waste gas compressor discharge to the inservice gas decay tank. Both ga s 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 whic h manual grab samples may be taken.
During normal GWPS o peration, the gas analyzers monitor the contents of the inservice gas decay tank and the waste gas compressor discharge for hydrogen and oxygen concent rations. Any high oxygen concentration entering the GWPS will be sensed by the compressor discharge a nalyzer which will alarm so that corrective actions can be taken b efore the contents of the gas decay tank exceed the limits fo r 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 hydr ogen concentrations.
Based on the above, the two analyzer system provides adequate prevention of ex plosive gas mixtures in the GWPS.
The gaseous waste processing s ystem consists of two waste-gas compressor packages, six gas dec ay tanks, and the associated piping, valves and instrumentation. The equipment serves both units. The system is shown on t he piping and instrumentation diagram Drawing M-69 and the process flow diagram Figure 11.3-2.
Table 11.3-3 gives pro cess parameters for key locations in the system. The bases used for est imating the process pa rameters are given in Table 11.3-4.
B/B-UFSAR 11.3-3 REVISION 11 - DECEMBER 2006 Gaseous wastes are recei ved from the following:
degassing of the reactor coolant and purging of the volume control tank prior to a cold shutdown; d isplacing of cover g ases caused by liquid accumulation in the ta nks connected to the vent header; purging of some equipment; s ampling and gas anal yzer operation; and operating the bo ron recycle system.
Auxiliary Services The auxiliary services portion of the ga seous waste processing system consists of an automatic gas an alyzer and its instrumentation, valves, and tubing; and a nit rogen and a hydrogen supply manifold with the necessary instr umentation, valves, and piping. The automatic (At Byron, the was te) gas analyzer may be used to determine the quantity of oxygen and hydrogen in the volume control tanks, pressuriz er relief tanks, boron recycle holdup tanks, boron rec ycle evaporators, gas decay tanks, reactor coolant drain tanks, and spent resin storage tank, and provides an alarm on high oxy gen concentration.
The nitrogen and hydrogen supply pac kages are designed to provide a supply of gas to the nuclear steam supply system. Two headers are provided for nitrogen supply:
one low p ressure for normal operation, which is supp lied by a bu lk liquid nitrog en tank, and one high pressure consisting of 36 high pressure cylinders for backup. When the oper ating header is exhaus ted, an alarm alerts the operator and the backup high pressure header is valved in through a pressu re regulator to supply gas.
Low pressure nitrogen is supplied to the followi ng components:
spent resin storage tank, pressurizer relief tan k, volume control tank, spray additive t anks, gas decay tanks, radwaste evaporators, hydrogen recombiners, re actor coolant drain tank, recycle holdup tank, and containment electrical penetrations. At Byron, low pressure nitrogen is also suppli ed to the primary water storage tanks. Makeup nitrogen for the safety injec tion accumulators during normal op eration is supplied from the high pressure backup header. In addition, there is a truck fill conne ction in the nitrogen supply header for the direct filling of the safety injection accumulators and the high pres sure cylinder ba ckup manifold.
Hydrogen is supplied at pressures between 100 and 125 psig for the volume control ta nk. The hydro gen system is described in Chapter 10.
The design and m aterial of valves and ma nifolds are the same as for the main GWPS.
Plant Ventilation Systems Plant ventilation systems ar e described in Chapter 9.0.
B/B-UFSAR 11.3-3a REVISION 4 - DECEMBER 1992 Steam and Power Conv ersion Systems The main condenser evacuation sy stem and the turbine gland sealing system may be potential sources of g aseous radioactive effluents. These systems ar e described in S ection 10.4.
B/B-UFSAR 11.3-4 REVISION 13 - DECEMBER 2010 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 quali ty 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 recommen dations with respect to controlling occup ational radiation ex posure are given in Reference 1.
Waste Gas Compressors The two waste gas compre ssors are provided f or 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 pe ak load conditions, such as when deg assing the reactor coola nt, or for ser vice when the first unit is down for maintenance.
The compressors are of t he liquid seal r otary type and are provided with mechan ical seals.
Gas Decay Tanks Six tanks are provided to hold radioacti ve waste gases for decay.
The tanks are the vertical cyl indrical 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 carb on steel; all piping joints are welded except wh ere flanged connections are necessary for maintenance.
11.3.2.3 Instrumentation Design The main system instrume ntation is described in Table 11.3-2 and shown on Drawing M-69.
B/B-UFSAR 11.3-5 REVISION 9 - DECEMBER 2002 The instrumentation readout is l ocated mainly on the waste processing system (W PS) panel in the aux iliary building. Some instruments have local readout at the eq uipment location.
At Byron, alarms are shown sep arately on the W PS panel and key alarms are further relayed to one common WPS annunciator on the main control board of the plan
- t. At Braidwood, all alarms are shown separately on the WPS panel and further relayed to one common WPS annun ciator on the main con trol board of the plant.
A multipoint automat ic gas analyzer (At Byron, a gas analyzer with manual selector s witch) is provided to monitor hydrogen and oxygen concentration s in the GWPS. (At Byro n, the sample points in the gaseous w aste processing system are manua lly selected to monitor hydrogen and oxy gen concentration in v arious samples in GWPS.) The analyzer rec ords (At Byron, the an alyzer monitors and indicates) the oxygen and hydrogen concentrati ons and alarms at high levels. In addition, a sep arate oxygen analyzer is provided between the compressors and the gas decay tanks. The two analyzers provide redundant ca pability for mon itoring oxygen concentration in the gaseous was te processing sy stem to assure that explosive level s of oxygen in hyd rogen are avoided.
11.3.2.4 Operating Procedure The equipment installed to reduce radioactiv e effluents to the minimum practicable level is maintained in g ood operating order and is operated in a ccordance with gen eral power plant practices. In order to ensure that these conditions are met, administrative controls are exercised on overall operation of the system; preventive mai ntenance is performed in accordance with general power plant pr actices to maintain equipment in peak condition; and e xperience available from similar plants is used in planning for operation.
Administrative controls are exercised th rough the use of instructions covering such areas as valve alignment for various operations, equipment operating instruct ions, and other instructions pertinent to the proper operati on of the processing equipment. Operatin g procedures ensure that proper valve alignments are m ade, and other operating conditions are satisfied before a release.
Operating procedures and admin istrative contro ls incorporate procedures and c ontrols developed at o perational PWR plants having similar w aste management equipment.
11.3.2.5 Operations Gaseous wastes consist p rimarily of hydrogen stripped from the reactor coolant duri ng boron recycle and deg assing operations and nitrogen from the nitrogen cover gas. The com ponents connected to the vent head er are limited to those which co ntain no air or aerated liquids to preve nt the formation of a combustible mixture of hydrogen and oxygen.
B/B-UFSAR 11.3-6 REVISION 7 - DECEMBER 1998 Waste gases discharged to the vent header are pumped to a waste gas decay tank by one of the two waste g as compressors.
To compress gas into t he gas decay tanks, the auxiliary control panel operator selec ts two tanks, one to rec eive gas and one for standby. When the tank in service is pressu rized to the control setpoint, flow is au tomatically switched to the standby tank and an alarm alerts the op erator to select a new standby tank.
The contents of the decay ta nk being fil led is sampled automatically by the gas analyzer and an alarm alert s the operator to a high oxygen content. On hi gh oxygen signal, the tank is isolated and operator action is taken to direct flow to the standby tank and to sele ct a new standby tank.
If it should become ne cessary to transfer gas from one decay tank to another, the tank to be emptied is aligne d to the holdup tank return line. The tank to receive gas is opened to t he inlet header and the r eturn line pressure regu lator 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 arrangemen t, gas is transferred by the compressor whi ch is in service.
As the boron rec ycle systems holdup tank s' liquid is withdrawn for processing by the bo ric acid recycle system, gas from the gas decay tanks is retur ned to the holdu p tanks. The gas decay tank selected to supply the returning cover gas is aligned with the return header by manua lly opening the appropriate valve.
Residence time is dete rmined by the activity in the tank and need for volume in the system. A bac kup 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 ta ken to det ermine 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 l ine. Flow through t he sample ve ssel is established by manually actuating the gas de cay tank "manual select" sample station.
When sufficient time has elapsed for a volume to be collect ed, the gas analyzer is returned to its normal alignment and the sample is removed f or analysis. Total tank activity invent ory is determined from the activity concentration and pres sure in the tank.
B/B-UFSAR 11.3-7 REVISION 11 - DECEMBER 2006 To release the gas, the appropriate local manual stop valve is opened to the plant vent and the gas discharge m odulating valve is opened by operati ng the valve control swi tch 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 du ring 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 degassi ng operation, the volume control tank gas space contains H 2 and traces of fission gases.
Operational procedures and controls direct the activities used to degas the reactor coolant sy stem into the gaseous waste processing system.
Gas evolved from the v olume 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 w aste processing system is the same during th e actual refueli ng operation as during normal operation.
11.3.2.7 Auxiliary Services
During normal operat ion nitrogen and hydroge n are supplied to primary plant components from their respective s ystems. Separate headers are provided f or each system. The nitrogen system is described in Sub section 11.3.2.1.
The hydrogen system is described in Chapter 10.
11.3.2.8 Performance Tests Initial performance tests are performed to ver ify the operability of the component s, instrumentation and c ontrol equipment. See
B/B-UFSAR 11.3-8 REVISION 6 - DECEMBER 1996 Chapter 14.0 on preo perational plant t esting for further information.
During reactor operation, the system is norm ally in use at all times and is the refore under continu ous 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, Sta ndards for Protect ion Against Radiation.
- b. Appendix I for 10 CFR 50.
11.3.3.2 Westinghouse P WR Experience Releases Surveys have been pe rformed of gaseous disch arges from several Westinghouse PWR plants. The results are pres ented 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 h oldup tanks during boron dilution, nitrog en and hydrogen ga ses purged from the Chemical Volume Control System volume control ta nk when degassing the reactor coolant and nitrogen fro m the Nitrogen cover gas.
The gas decay tank cap acity permits sufficient decay time for waste gases to meet discharge limits.
The quantities and iso topic concentration of gases discharged from the gaseous waste processing system and from the volume
B/B-UFSAR 11.3-9 REVISION 9 - DECEMBER 2002 reduction system have been estimated. The analy sis is based on engineering judgment with respect to the operation of the plant and realistic estimations of the input s ources to these two systems.
The associated releases in curies per year p er nuclide are given in Table 11.3-6.
11.3.3.4 Estimated Total Releases
Byron and Braidwood Nucl ear Stations have upra ted the core power level to 3586.6 MWt. The origin al 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 radioacti ve noble gases and particulates were dete rmined by using NUREG 0017 methodology and computer program PWR-GALE. Both the original as well as the uprated parameters descr ibing the normal operati on of one unit of the station are listed in Table 11.2-2. These values were used as input to the computer co de for the ori ginal analyses.
The impact of core uprate on th e effluent relea ses was evaluated based on an assessment of the changes in i nput parameters.
Expected releases from routine and shutdown degass ing of the prima ry coolant and from the building ventilation sy stems are shown in Table 11.3-6.
Core uprate results in a maximum potential incre ase of 0.6% for long lived isotopes su ch as Kr 85. Shorter li ved isotopes will have reduced releases or only slight increases as compared to the 0.6% increase in power l evel. 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 gas es) are not impacted by uprate. All of t he incremental tritium production due to power uprate is assumed to be released v ia the gaseo us pathway resulting in an approx imate 0.8% increase in tritium releases via the gaseous pathway.
Taking into consideration the accuracy and e rror bounds of the operational data utilized in NUR EG 00017, these small percentage changes are well within the uncertainty of the calculated results of the original NURE G 0017 based maximum offsite airborne concentrations from gase ous radwaste effluents presented in Table 11.3-7. Actual release data are avai lable in the effluent release reports, which are prepared in accordance with the ODCM.
Expected releases from normal op eration of the v olume reduction system were determined using the estimated ann ual production of radioactive wastes and d esign flow rates and cleanup parameters for this system. Calculated rou tine releases for the volume reduction system are also included in Table 11.3-6.
B/B-UFSAR 11.3-9a REVISION 9 - DECEMBER 2002 11.3.3.5 Effluent Concentrati ons and Dilution Factors A comparison of maxi mum offsite (at site boundary) airborne gaseous effluent concent ration with 10 CFR 20 limits is given in Table 11.3-7. The a tmospheric dilution fact ors used for these calculations are given in Table 11.3-8.
As discussed in Section 11.3.3.4 above, this c omparison 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 recta ngular and is 13.3 feet by 5.0 feet at the e xit point, giving an effective diameter of 9.2 feet p er stack. The t op of the stack is at elevation 600 feet, and the base elevation is 401 feet. The next tallest structures are t he tops of the containments, w hich are at elevation 599 feet. This qual ifies the exhaust vent stacks as mixed-mode release poi nts, since they are 1 foot higher than any surrounding structures.
B/B-UFSAR 11.3-10 REVISION 9 - DECEMBER 2002 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 temperatu re range of this exhau st gas is from 40
°F to (in a few cases) 122
°F. 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 T able 11.3-9. These doses were calculated using the methodology of Regulatory Guide 1.109 (Reference 3). Site meteo rological data a nd the partially elevated release model were used to calculate the atmospheric dispersion of the effluents.
Various exposure pathways were examined. Consumpti on factors for the i ngestion pathways are given in Table 11.2-8.
Note that all of the se doses are well within the guidelines of Appendix I to 10 CFR
- 50. As discussed in Section 11.3.3.4 above, this assessme nt and Table 11.3-9 remain valid for uprate.
11.3.4 References
- 1. R. J. Lutz, "Design, Inspect ion, Operation, and Maintenance Aspects of the W NSSS to Maintain Oc cupational Radiation Exposures," WCAP-887 2, April 1977.
- 2. NUREG-0017, "Calcu lation of Releases of Radioactive Materials in Gaseous and Liqui d Effluents from Pre ssurized Water Reactors (PWR-GALE Code)," Office of Stan dards Development, U.S. Nuclear Regulatory Commissio n, April 1976.
- 3. Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for t he Purpose of Evaluating Compliance with 10 CFR Part 50, App endix I," U.S.
Nuclear Regulatory Com mission, October 1977.
B/B-UFSAR 11.3-11 TABLE 11.3-1 GASEOUS WASTE PROCESSING SYSTEM COMPONENT DATA
WASTE GAS COMPRESSORS
Number 2
Type Liquid seal rotary type
Design Flow rate, N 2 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, ft 3 600 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
B/B-UFSAR
11.3-12
REVISION 11 - DECEMBER 2006 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 30-300°F NA NA At Waste Gas (Dial Thermometer) Compressor
TI-1034 Seal water, compressor No. 2 150 300 30-300°F 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
B/B-UFSAR
11.3-13 REVI SION 10 - DECEMBER 2004 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
B/B-UFSAR
11
.3-14 REVISION 13 - DECEMBER 2010 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.
O/AIT-GW8003 (Byron)/
O/AT-GW8003 (Braidwood) Oxygen 300 212 0-19.99% 2% (Byron) none Local O/AR-GW8003 (Braidwood) Oxygen 300 212 0-5% 2% none Local O/AIT-GW004 Oxygen 300 212 0-5% 2% none Local O/AIT-GW8000 (Byron)/
O/AT-GW8000 (Braidwood) Hydrogen 25 130 0-100% - none Local O/AR-GW8000 (Braidwood) Hydrogen 25 130 0-100% - none Local
B/B-UFSAR
11.3-15
REVISION 3 - DECEMBER 1991 TABLE 11.3-3 PROCESS PARAMETERS AND REALISTIC, OPERATION BASIS ACTIVITIES IN GASEOUS WASTE SYSTEM(1) (CONCENTRATIONS IN
µC/cm 3)
POS NO.(2) LOCATION PRESSURE (psig) TEMP. (°F) FLOW RATE (cm 3/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 8 BRS Evaporator Unit 1 Vent (3) 1.5 155 3.82E+5 8.1E-04 1.9E-06 1.9E-02 3.2E-05 2.1E-05 9 BRS Evaporator Unit 2 Vent (3) 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
B/B-UFSAR
11.3-16 REVISI ON 1 - DECEMBER 1989 TABLE 11.3-3 (Cont'd)
POS NO.(2) LOCATION PRESSURE (psig) TEMP. (°F) FLOW RATE (cm 3/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
B/B-UFSAR 11.3-17 TABLE 11.3-3 (Cont'd)
POS NO.(2) LOCATION PRESSURE (psig) TEMP. (°F) FLOW RATE (cm 3/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 8 BRS Evaporator Unit 1 Vent (3) 1.5 155 3.82E+5 6.2E-06 1.1E-03 1.7E+00 7.3+02 1.1E-01 9 BRS Evaporator Unit 2 Vent (3) 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
B/B-UFSAR
11.3-18 REVISI ON 1 - DECEMBER 1989 TABLE 11.3-3 (Cont'd)
POS NO.(2) LOCATION PRESSURE (psig) TEMP. (°F) FLOW RATE (cm 3/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
B/B-UFSAR 11.3-19 TABLE 11.3-3 (Cont'd)
POS NO.(2) LOCATION PRESSURE (psig) TEMP. (°F) FLOW RATE (cm 3/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 8 BRS Evaporator Unit 1 Vent (3) 1.5 1.5 3.82E+5 1.2E+02 1.4E-05 4.1E-01 0.0E+00 0.0E+00 9 BRS Evaporator Unit 2 Vent (3) 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
B/B-UFSAR
11.3-20
REVISION 1 - DECEMBER 1989 TABLE 11.3-3 (Cont'd)
POS NO.(2) LOCATION PRESSURE (psig) TEMP. (°F) FLOW RATE (cm 3/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 Tanks - - 0 5.9E+01 8.1E-06 2.4E-01 2.0E-06 3.4E-07 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
B/B-UFSAR 11.3-21 TABLE 11.3-3 (Cont'd)
POS NO.(2) LOCATION PRESSURE (psig) TEMP. (°F) FLOW RATE (cm 3/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 8 BRS Evaporator Unit 1 Vent (3) 1.5 155 3.82E+5 0.0E+00 0.0E+00 0.0E+00 0.0E+00 9 BRS Evaporator Unit 2 Vent (3) 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 GWPS (5) 1.5 VAR 2.48E+7 2.8E-08 4.1E-07 7.6E-09 1.5E-07 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
B/B-UFSAR
11.3-22 REVISI ON 1 - DECEMBER 1989 TABLE 11.3-3 (Cont'd)
POS NO.(2) LOCATION PRESSURE (psig) TEMP. (°F) FLOW RATE (cm 3/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 Tanks - - 0 2.8E-08 4.1E-07 7.6E-09 1.5E-07 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 Inlet 110 AMB 1.64E+8 3.9E-10 5.4E-08 4.1-11 6.1E-09 24 From Gas Decay Tanks To BRS HTs (6) 3 AMB 1.64E+8 3.9E-10 5.4E-08 4.1-11 6.1E-09
___________________
AMB - Ambient VAR - Variable
B/B-UFSAR 11.3-23 TABLE 11.3-3 (Cont'd)
NOTES:
- 1. This is a synthe sis of information from operating reactors.
- 2. These position numbe rs correspond to positions marked on Figure 11.3-2.
- 3. Boron Recycle System (BRS).
- 4. Metastable (M).
- 5. Gaseous Waste Pr ocessing System (GWPS).
- 6. Holdup Tank (HT)
B/B-UFSAR
11.3-24 REVISION 3
- DECEMBER 1991 TABLE 11.3-4 ASSUMPTIONS USED IN CALC ULATING EXPECTED SYSTEM ACTIVITIES A. EXPECTED SYSTEM ACTIVITY
- 1. The major inputs to the gas sy stem during normal operation are vents on the Boron Recyc le 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 gase ous activities are b ased on Regulatory Guide 1.112 as modified to reflect Byr on/Braidwood plant parameters.
- 3. Twenty-five percent of dissolved radioga ses in the reactor coolant entering the RCDTs a nd 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 assum ed to be filled to 80% capacity before processing by the BRS evaporat or. The RCDTs are assumed to be filled to 280 ga llons before draining.
- 6. Values for liquid flow rates to the ta nks were based on estimates of ann ual 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 parti tion coefficient in the RCDTs and BRS HUTs was: liquid in cc/Ci vapor in cc/Ci 10 X 5.7 3µµ (Based on Regulatory Guide 1.112).
- 9. The hydrogen con centration in the primary coolant was assumed 35 cc/kg.
B/B-UFSAR
11.3-2 5 REVISION 3 -
DECEMBER 1991 TABLE 11.3-4 (Cont'd)
B. ANNUAL RELEASES The following additional assumptions were us ed in calculating expected annual releases:
- 1. One refueling per ye ar per unit was assu med, 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 s ystem. This gaseous activity is rele ased 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 cool ant is eventually released to the environment.
- 3. From the calcula tion of system activities, t he activity in a single gas decay tank was determined a fter 60 days decay. It was assumed that one tank was released every 60 days for purposes of this analysis only.
B/B-UFSAR 11.3-26 TABLE 11.3-5 TYPICAL GASEOUS RELEASES FROM OPERATING REACTORS
NOBLE GASES (10 3 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
B/B-UFSAR
11.3-27 R
EVISION 1 - DECEMBER 1989 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 (µCi/g) (µCi/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 B/B-UFSAR
11.3-28 R
EVISION 1 - DECEMBER 1989 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 (µCi/g) (µCi/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
B/B-UFSAR 11.3-29 TABLE 11.3-6 (Cont'd)
AIRBORNE PARTICULATE RELEASE RATE - CURIES PER YEAR 1
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 re leases, 25 Ci/yr of argo n-41 are released from the containment and 8 Ci/yr of carbon-14 are released from the w aste gas processing sy stem. This table was developed taking into ac count both releases from normal oper ations and also operational occurrences.
KEY: 4.5-03 = 4.5 x 10
-3 B/B-UFSAR
11.3-3 0 REVISION 6 -
DECEMBER 1996 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 est imate included r elease data for the volume reduction system. This system is no longer used.
BYRON-UFSAR 11.3-31 REVISION 5 - DECEMBER 1994 TABLE 11.3-7 COMPARISON OF MAXIMU M OFFSITE AIRBORNE CONCENTRATIONS WITH 10 CFR 20 LIMITS MAXIMUM SITE ANNUAL RELEASE BOUNDARY
- FROM ONE UNIT CONCENTRATION CONCENTRATION ISOTOPE (Ci/yr)
(µCi/ml) (µCi/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/m 3 ** Limits used are those that were in effect at the time of the analysis.
KEY: 3.5 - 11 = 3.5 x 10-11 BYRON-UFSAR 11.3-32 REVISION 1 - DECEMBER 1989 TABLE 11.3-8 ATMOSPHERIC DILUTION FACTORS USED IN DETERMINING OFFSITE DOSES
/Q 2 D/Q* LOCATION (sec/m
- 3) (l/m 2) 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 Regu latory Guide 1.111, Revision 1, July 1977.
KEY: l.ll - 06 = 1.11 x 10
-6
BYRON-UFSAR 11.3-33 TABLE 11.3-9 BYRON-EXPECTED INDIVID UAL DOSES FROM G ASEOUS EFFLUENTS DOSE RATE (mrem/yr)
LOCATION PATHWAY TOTAL BODY SKIN THYROID BONE LIVER LUNG GI-LLI Nearest Residence Plume 0.023 0.073 (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 0.00 5 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 0.00 6 0.006 0.006 Teen 0.004 0.023 0.00 2 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 0.05 7 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 0.01 9 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 0.02 7 0.025 0.025 Teen 0.037 0.164 0.02 4 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 BRAIDWOOD-UFSAR 11.3-34 REVISION 5 - DECEMBER 1994 TABLE 11.3-7 COMPARISON OF MAXIMU M OFFSITE AIRBORNE CONCENTRATIONS WITH 10 CFR 20 LIMITS
- 0.30 mi NW /Q = 8.10 x 10
-7 sec/m 3 ** Limits used are those that were in effect at the time of the analysis.
KEY: 2.6 - 11 = 2.6 x 10-11 MAXIMUM SITE ANNUAL RELEASE BOUNDARY 3 10 CFR 20
- FROM ONE UNIT CONCENTRATION CONCENTRATION ISOTOPE (Ci/yr)
(µCi/ml) (µCi/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 7.8-032.0-165.0-10 BRAIDWOOD-UFSAR 11.3-35 TABLE 11.3-8
ATMOSPHERIC DILUTION FACTORS USED IN DETERMINING OFFSITE DOSES
/Q 4 D/Q* LOCATION (sec/m
- 3) (l/m 2) 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 Regu latory Guide 1.111, Revision 1, July 1977.
KEY: 8.10 - 07 = 8.10 x 10-7 BRAIDWOOD-UFSAR
11.3-36
REVISION 3 -
DECEMBER 1991 TABLE 11.3-9
BRAIDWOOD-EXPECTED I NDIVIDUAL DOSES FROM GASEOUS EFFLUENTS
DOSE RATE (mrem/yr)
LOCATION PATHWAY TOTAL 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 0.00 5 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 0.03 5 0.034 0.034 Teen 0.025 0.072 0.01 2 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 0.29 8 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 0.00 6 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
BRAIDWOOD-UFSAR 11.3-37 TABLE 11.3-9 (Cont'd)
DOSE RATE (mrem/yr)
LOCATION PATHWAY TOTAL BODY SKIN THYROID BONE LIVER LUNG GI-LLI Nearest Milk Cow Milk (1.7 mi WSW) Adult 0.020 0.051 0.008 0.02 0 0.019 0.019 Teen 0.028 0.081 0.01 6 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 0.01 8 0.017 0.017 Teen 0.024 0.049 0.00 8 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
B/B-UFSAR 11.3-38 REVISION 2 - DECEMBER 1990 TABLE 11.3-10 EXHAUST STACK AI RFLOW TABULATION CASE 1 CASE 2 REFUELING EXCEPTNORMAL 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 Exhaust0 1,400 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 Containment Purge System Mini-Purge Exhaust (3000 CFM)0 0
Main-Purge Exhaust 43,900 0 189,510 147,042
B/B-UFSAR 11.4-1 REVISION 12 - DECEMBER 2008 11.4 SOLID WASTE MA NAGEMENT SYSTEM 11.4.1 Design Bases The solid radwaste system ha s been desig ned to receive, concentrate, solidify if require d, package, hand le, and provide temporary storage facilities f or radioactive w et solid wastes generated by Units 1 and 2 prior to offsite shipment and disposal.
The system has provisions for transferring w et solid radwaste to vendor-supplied radwaste system for processing a nd disposal. The solid waste management s ystem also receives, decontaminates and/or compacts (Byron only), a nd provides temporar y storage facilities for radioactive dry wastes produced during sta tion operation and maintenance prior to o ffsite shipment and di sposal. This system does not normally handle large w aste materials s uch as activated core components.
11.4.1.1 Power Genera tion Design Bases The solid radwaste system is d esigned to minimize the volume of solidified waste requiring shi pment offsite. The system is designed specifically for a 40-year service life, maximum reliability, minimum maintenance, and minimum exposure to operating and maintenance pers onnel. The system has the flexibility to handle a wide range of radioact ive waste products.
Equipment and storage capacities, as noted in Table 11.4-1, are selected to meet the station's s olid waste pro cessing needs in all the operational modes of the station, includ ing anticipated operational occurrences, without imp airing 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 am ount of time was selec ted to allow for some decay of drumme d 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 a nd DOT regulations inclu ding 49 CFR 170-178 and 10 CFR 71.
DOT-approved drums a re used for packaging solidified wet solid wastes and for p ackaging dry solid was tes and spent filter cartridges. Steel lin ers and high integrity containers (HICs) are used for solidified wet solid wastes and dewater ed resin. HICs are used for spent filter ca rtridges, dry so lid wastes, or solidified, wet solid wastes.
System safety is empha sized through redundan cy in design of primary components, compartmenta lization of equipment layout, remote automatic and/or manual operation, shie lding, containment of B/B-UFSAR 11.4-2 REVISION 9 - DECEMBER 2002 possible spills and disp laced air, remote de contamination, if required, accurate process m onitoring, and i nterlocking of process controls.
Complete solidification of wastes requiring solidification that is handled by the vendor-supplied radwaste system is ensured by complying with the vendo r's process control program.
The solid radwaste system is d esigned to fail safe upon loss of system power, water, or air supply. System controls are designed to avoid a malfunction or sp ill due to operator error. The system is designed to keep t he containers clean, reducing decontamination and clea ning requirements.
The solid radwaste sto rage area, the non used volume reduction (VR) system and the non used VR product soli dification system are enclosed in a Safety C ategory II structure.
The Byron non used solid radwaste processing equipment is in a Safety Category I structure. The below grade walls are pa rt of the total structural shear wall system and as such are designed to withstand the effects of an ea rthquake. All piping and components of the system are designed and constructed in accordance with requirem ents for classification of Quality Group D.
Waste may be sent to an offs ite vendor in ac ceptable DOT containers for processing prior to disposal.
The vendor may volume reduce, sort, decontaminate, and process to p roduce a form acceptable f or burial.
To reduce leakage, piping is w elded and pump lea koffs are taken to the drain sys tem. Most valves, exc ept for a few specialty valves, are of the plug type designed to minimize leakage.
The design-basis solid r adwaste system output volume is shown in Table 11.4-2.
11.4.1.3 Type of Waste The types of wastes handled by t he solid radwaste system consist of the following:
- a. Expended deep bed demine ralizer bead r esins typically consisting primarily of a copolymer of styrene and divinylbenzene.
- b. Disposable cartridge filter elements typically consisting of epoxy-impregna ted cellulose fiber or resin-impregnated glass fibe r bonded in stainless steel hardware.
B/B-UFSAR 11.4-3 REVISION 9 - DECEMBER 2002 c. Low-level dry active was tes 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 lev el dry wastes (e.g., core components) are not solidified, but decont aminated and shipped in special containers.
11.4.1.4 Expected Volumes and Isotopic Compositions Table 11.4-2 indicates the design-basis solid radwas te system output (maximum and expe cted annual volumes).
The radionuclide content of the v arious 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 Br aidwood Nuclear Stations have uprated the core power level to 3586.6 MWt. The original licensed power level was 3411 MWt. The original expected solid radwaste release data present ed in the UFSAR is based on a power lev el of 3565 MWt.
As uprated does not appreciably change the estimated coolant activity, and maintenance and operational practices remain unaffected by uprate, the calcul ated specific ac tivity of the solid waste is expec ted to remain essent ially unchanged. The volume of solid waste is also not expected to increase since power uprate does no t 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 was te estimates presented in this section.
Actual data from dischar ged wastes are avail able in the effluent release reports, which a re prepared in accorda nce with the ODCM.
Dry active waste and all other waste streams are sampled in accordance with 10 CFR 61 to support a ccurate characte rization of the waste. Station and/or corpo rate procedures are then used to characterize and quantify th e 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 Tre atment Systems Branch (ETSB), Branch Technical Posi tion BTP 11-3.
BYRON-UFSAR 11.4-4 REVISION 13 - DECEMBER 2010 11.4.1.6 Comparison of Processing Capacity and Design Basis Waste Volumes The vendor-supplied ra dwaste system is c apable of filling, dewatering, drying, and preparing a liner of spent resin for shipment. Each line r would contain vary ing amounts of resin based upon the r adiation dose being emit ted by the material on the resins. Based u pon the preparation rate , there is adequate capacity to process the expected waste volume.
Table 11.4-2 gives t he following annual expe cted values of waste to be processed and the resultant nu mber of containers:
Exhausted deep bed resins 1,600 ft 3 10 liners or 2,393 drums *Sludges and liquids 18,690 ft 3 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 process ed is based on the volumes of waste as in dicated above and on t he following drumming efficiencies:
Exhausted deep bed resins 110 to 200 ft 3/liner *Sludges and liquids 27.5 gal/drum (average)
The actual data are av ailable in the eff luent release reports, which are prepared in accordance with the ODCM.
The processing capacity of the solid was te system is adequate to handle the maximum e xpected volumes of waste. The solid waste system has exc ess capacity.
- Sludges and liquids are normal ly processed by the liquid radwaste system.
BRAIDWOOD-UFSAR 11.4-5 REVISION 13 - DECEMBER 2010 11.4.1.6 Comparison of Processing Capacity and Design Basis Waste Volumes The vendor-supplied ra dwaste system is c apable of filling, dewatering, drying, and preparing a liner of spent resin for shipment. Each line r would contain vary ing amounts of resin based upon the r adiation dose being emit ted by the material on the resins. Based u pon the preparation rate , there is adequate capacity to process the expected waste volume.
Station operating ex perience indicates that it requires approximately 1/2 shift, i.e., 4 hou rs, to remove a filter from its vessel, place it in a cement-lined drum, and transport the drum to the radwaste building for temp orary storage and/or further processing.
Filters, after decay, are placed in a vendor-sup plied container for disposal. Each co ntainer holds up to 15 0 filter elements.
Operating experience i ndicates it takes appr oximately one shift to place 10 to 15 filters in a container. Based upon the aforementioned rate, there is adequate c apacity to p rocess the expected number of filters.
Table 11.4-2 gives t he following annual expe cted values of waste to be handled and the result ant number of containers:
Exhausted deep bed resins 1,600 ft 3 10 liners *Sludges and liquids 18,690 ft 3 156 liners or 5140 drums Cartridge filter elements --- 2 liners Total: 168 liners or 12 liners and 5140 drums The number of containe rs to be processed is ba sed on the volumes of waste as indicated above and on the following drumming efficiencies:
- Sludges and liquids are norma lly processed by the liquid radwaste system.
BRAIDWOOD-UFSAR 11.4-6 REVISION 7 - DECEMBER 1998 Exhausted deep bed resins 110 to 200 ft 3/liner Sludges and liquids 120 ft 3/liner Cartridge filter elements 150 filter elements/liner
The actual data are av ailable in the eff luent release reports, which are prepared in accordance with the ODCM.
The processing capacity of the solid was te system is adequate to handle the maximum e xpected volumes of waste. The solid waste system has exc ess capacity.
B/B-UFSAR 11.4-7 REVISION 9 - DECEMBER 2002 11.4.1.7 Solid Radwaste System Monitoring The solid radwaste system mo nitoring 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 st atistical nature of the measurements. For a furth er discussion on t he confidence levels and the i ndicated ranges of the monitoring equipment refer to Subsection 12.3.4.
11.4.2 System Description Operation of the sol id waste management system is indicated by Figure 11.4-1. Layouts of the packaging, st orage, and shipping areas are shown on D rawings M-9 and M-12.
The solid radwaste system is c omprised of a numb er of components or subsystems. They a re 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
B/B-UFSAR 11.4-8 through 11.4-10 REVISION 6 - DECEMBER 1996
Pages 11.4-8 through 11.4-10 have been deleted inten tionally.
B/B-UFSAR 11.4-11 REVISION 7 - DECEMBER 1998 11.4.2.4 Drum-Handling Equipment This equipment i ncludes four remotely op erated cranes with three of the cranes ha ving television cameras for visual surveillance two drum transfer carts and one cartridge filt er transfer vehicle (Braidwood only).
At Byron, the two fi xed bridge cranes in the drumming area are used to remotely trans port 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 ei ther intermediate or low level storage, r etrieve and transport them to trucks for offsite disposal, and load prepared drums onto and remove processed drums from the drum tr ansfer carts. T wo electrical circuits are provided for the trolle y, bridge, and h oist, one for the high-speed and one for the low-speed mot ors. This ensures that electrical failure will not prevent rem ote removal of the crane from a radiation z one or completing the operation in process at time of failure.
An adaptor is supplied which can be attached to the grab for righ ting drums which h ave come to rest horizontally. A crane t arget grid system comb ined with television cameras is provided for accurate remote control positioning. For safety, the container mu st be raised to the full-up position before high speed operat ion is possible, and t he container cannot be released from the grab wh ile the containe r is suspended.
At Byron, the remotely operated crane without a television camera is used to lower the drum onto a drum transf er cart. At Braidwood, the r emotely operated cra ne without a tel evision camera is used to remove a drum contain ing a filter from the cartridge filter transfer vehicle and lower the drum o nto 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 D AW 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 par allel. Each cart is designed to carry one drum at a time; howeve r, each cart has room to carry two drums if necessary. The carts a re a-c powered w ith 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 in to the floor. Ope ration of the carts is semiautomatic.
B/B-UFSAR 11.4-12 REVISION 12 - DECEMBER 2008 The cartridge filter t ransfer vehicle holds one 55-gallon drum.
This vehicle transpo rts drums containing spe nt 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 fil ter dose rate indicates that shielding is requ ired, a drum that contains a precast concrete lin er 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 tran sfer cart for transport to the radwaste building.
11.4.2.5 Smear Test a nd Label Station This portion of the so lid waste management s ystem consists of a setdown position for a s ingle drum within an open-topped shielded cubicle provided with si de access opening and working tools to accomplish remote labe ling, smear testing, a nd radiation monitoring of all external surfaces of sealed drums prior to offsite disposal.
If a drum is found to be contami nated, it is dec ontaminated prior to storage. This syst em is normally not used.
11.4.2.6 Dry Waste Comp actor (Byron only)
The dry waste compac tor compresses paper, fa brics, plastics, and light metal into 55-gallon drums. An air filtration assembly is provided to maintain c ontrol of contaminated particles during compactor operation. Capture of rad ioactive dust is accomplished by means of a roughing f ilter and two HEPA fil ters operating in parallel.
The radioactivity of most of the dry waste is low enough to permit handling by contact. The comp actor is designed to meet OSHA standards for safe operation and built to standards for a 40-year expected life of the station. T his component is nor mally not used.
11.4.2.7 Storage Areas Shielded areas are pro vided for storage of i ntermediate and low activity containers and compacted dry waste dr ums per requirements noted in Table 11.4-1.
Visual surveillance for the intermediate and low-level storage area is provid ed by the traveling bridge crane television cameras or ot her remote cameras. S torage is provided for uncompressible dry solid waste. The storage areas are drained to the radwaste building sump with the exceptio n of the low-level storage area at Braidwoo
- d. This bermed area may be used for low activity concentrated liquid waste storage tan ks. The drains are sealed to prevent acci dental spillage from e ntering the floor drain system, since the spilled liquid may have high boron concentration.
Radioactive waste may also be stored at an int erim storage location away from the processing area while awaiting process ing or shipment to a burial site.
B/B-UFSAR 11.4-13 REVISION 12 - DECEMBER 2008 11.4.2.8 Control Room This room houses the equipment w hich is capable of remote visual monitoring and c ontrol of the solid radw aste system. A record board is mounted on the radwaste con trol room wall to record the location of all containers within the storage ar ea. Container setdown positions are re presented by hooks onto which tags are placed. The volume redu ction system control p anel and the volume reduction product solidification system control pane l are also in this area.
At Byron, a liquid/sol id interface control p anel is provided for transferring waste to the solid radwaste system from the liquid radwaste subsystem for processing.
In the solid radwast e system, compressed air is used as the handling system instrume nt air. It is at a pressure of 70-100 psig and is used to operate various valves. Service air is used in the solid radwast e system to operate air-driven pumps, vacuums, and other air-driven eq uipment. 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 inte rface descriptions, li ne numbers, sizes, design pressures, temper atures, flow rates, expe cted batch sizes, and expected gross rad ioisotope concentration are given in Table 11.4-3.
11.4.2.13 Deleted
B/B-UFSAR 11.4-14 REVISION 6 - DECEMBER 1996 11.4.3 Volume Reducti on System Description The text for Subsection 11.4.3 has been dele ted intentionally.
Byron and Braidwood Stat ions do not intend to use this equipment.
11.4.4 Polymer/VR Pro duct Drumming Station The text for Subsection 11.4.4 has been dele ted intentionally.
Byron and Braidwood Stat ions do not intend to use this equipment.
B/B-UFSAR Pages 11.4-15 through 11.4-51 REVISION 6 - DECEMBER 1996
Pages 11.4-15 through 11.4-51 have been deleted intentionally.
BYRON-UFSAR
11.4-52 REVISION 7 - DECEMBER 1998 TABLE 11.4-1 SOLID WASTE MANAGEME NT SYSTEM EQUIPMENT AND STORAGE DESI GN CAPACITIES
PROCESSING EQUIPMENT QUANTITYDESIGN 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 ft 3 CS Drum processing unit 2 1 Drum 304L SS Packaging container (drum) - 55 gallons CS Packaging container (liner)- Up to 200 ft 3 CS or Polyethylene
Dry waste compactor 1 1 Drum CS
Traveling bridge crane 1 1 9.3 tons CS Fixed bridge crane 1 2 1.0 ton CS Drum transfer car 2 2 2 drums CS Startup heater 1 395 scfm 304SS/
347SS
Air heater 1 320 scfm 304SS/
316L-SS Gas heater 1 786 scfm 304SS/
Fluid bed dryer air blower 1 317 scfm CS
Dry waste processor air blower 1 300 scfm CS
BYRON-UFSAR
11.4-53 TABLE 11.4-1 (Cont'd)
PROCESSING EQUIPMENT QUANTITYDESIGN 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
BYRON-UFSAR
11.4-54 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 ft 3 316L-SS Storage hopper 1 80 ft 3 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 filter1 75 scfm 304SS Volume reduction solidi- 1 180 scfm 304L fication system product blower filter
BYRON-UFSAR
11.4-55 REVISION 7 - DECEMBER 1998 TABLE 11.4-1 (Cont'd)
STORAGE AREA NUMBER OF STORAGE AREAS DESIGN CAPACITY 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 ft 3
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
BYRON-UFSAR
11.4-56
REVISION 7 - DECEMBER 1998 TABLE 11.4-2 EXPECTED AND DESIGN BASIS ANNUAL VOLUMES OF (UNITS 1 AND 2)
SOLID WASTE MANAGEME NT SYSTEM OUTPUT*
Solid waste processed by the solid r adwaste management system and quant ities of processed was te requiring onsite storage or offsi te disposal EXPECTED NUMBER OF DESIGN NUMBER OF TYPE OF WASTE VOLUMES CONTAINERS VOLUME CONTAINERS Deep Bed Resin 1,600 ft 3 2,393 drums 1,600 ft 3 2,393 drums or 10 liners or 10 liners Disposable Filter Elements 75 ft 3 190 drums 75 ft 3 190 drums or 2 liners or 2 liners Sludges and Liquids*** 16,850 ft 3 4,580 drums 18,690 ft 3 5,140 drums Dry Active Waste 36,220 ft 3 580** drums 36,220 ft 3 1,160** drums 73 boxes 73 boxes Total 54,745 ft 3 7,743 drums, 56,585 ft 3 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 approxi mate. The actual data a re available in the effluent release reports, which a re prepared in accorda nce with the ODCM. ** Not solidified. *** Sludges and liqu ids are normally processed in the liquid radwaste system.
BYRON-UFSAR
11.4-57
REVISION 6 - DECEMBER 1996 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 Concentratesf 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.
f Evaporator concentrates are normally processed in the liquid radwaste system.
BYRON-UFSAR
11.4-58 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. H 2O 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
- o. Dry active water - - ambient ambient 20 ft 3/min 7.5 ft 3 Low
BYRON-UFSAR
11.4-59 RE VISION 6 - DECEMBER 1996 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. H 2O ambient 10 scfm continuous 0.0 station vent
- l. Blower discharge OVR180A 2-1/2 in. 0.5 psig 120 60 scfm intermittent Low
B/B-UFSAR
11.4-60 through 11.4-63 REVISION 6 - DECEMBER 1996
Pages 11.4-60 through 11.4-63 have been deleted intentionally.
BRAIDWOOD-UFSAR
11.4-64 REVISION 12 - DECEMBER 2008 TABLE 11.4-1 SOLID WASTE MANAGEME NT SYSTEM EQUIPMENT AND STORAGE DESI GN CAPACITIES
PROCESSING EQUIPMENT QUANTITY DESIGN CAPACITY MATERIALS Packaging container - up to 200 ft 3 CS or (liner) polyethylene Packaging container (drum) - 55 gal CS Traveling bridge crane 1 1 9.3 tons CS Fixed bridge crane 1 2 1.0 ton CS Drum transfer car 2 2 2 drums CS Cartridge filter transfer vehicle 3 1 1 drum CS
NOTE: Processing equipment for the volume reduction and radwaste solidification systems has been intentio nally deleted from this table. Braidwo od station does not intend to use this equipment.
BRAIDWOOD-UFSAR
11.4-65 REVISION 9 - DECEMBER 2002 TABLE 11.4-1 (Cont'd)
Page 11.4-65 has bee n deleted intentionally.
BRAIDWOOD-UFSAR
11.4-66 REVISION 9 - DECEMBER 2002 TABLE 11.4-1 (Cont'd)
Page 11.4-66 has bee n deleted intentionally.
BRAIDWOOD-UFSAR
11.4-67 REVISION 7 - DECEMBER 1998 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 ft 3 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
BRAIDWOOD-UFSAR
11.4-68
REVISION 7 - DECEMBER 1998 TABLE 11.4-2 EXPECTED AND DESIGN BASIS ANNUAL VOLUMES OF (UNITS 1 AND 2)
SOLID WASTE MANAGEME NT SYSTEM OUTPUT*
Solid waste processed by the solid r adwaste management system and quant ities of processed waste requiring onsite storage or of fsite disposal
EXPECTED NUMBER OF DESIGN NUMBER OF TYPE OF WASTE VOLUMES CONTAINERS VOLUME CONTAINERS Deep Bed Resin 1,600 ft 3 10 liners 1,600 ft 3 10 liners Disposable Filter Elements 75 ft 3 2 liners 75 ft 3 2 liners Sludges and Liquids*** 16,850 ft 3 141 liners 18,690 ft 3 156 liners Dry Active Waste 36,220 ft 3 580 drums** 36,220 ft 3 1,160 drums** 73 boxes 73 boxes Total 54,745 ft 3 153 liners 56,585 ft 3 168 liners 580 drums 1,160 drums 73 boxes 73 boxes
___________________
- The values given are approxi mate. The actual data are available in the effluent release reports, which are p repared in accordance with the ODCM. ** Not solidified.
- Sludges and liquids are no rmally processed in the liquid radwaste system.
BRAIDWOOD-UFSAR
11.4-69
REVISION 6 - DECEMBER 1996 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 Systemf
- 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. f Braidwood does not operate the volume reduction system.
BRAIDWOOD-UFSAR
11.4-70
REVISION 6 - DECEMBER 1996 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. H 2O 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
- m. Dry active waste - - ambient ambient 20 ft 3/min 7.5 ft 3 Low
- 6. Volume Reduction Systemf 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
BRAIDWOOD-UFSAR
11.4-71 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. H 2O ambient 10 scfm continuous 0.0
- n. Blower discharge OVR180A 2-1/2 in. 0.5 psig 120 60 scfm intermittent Low
BRAIDWOOD-UFSAR
11.4-72 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
B/B-UFSAR REVISION 9 - DECEMBER 2002
Figures 11.2-1 through 11.2-41 have been del eted intentionally.
B/B-UFSAR REVISION 9 - DECEMBER 2002
Figure 11.3-1 has been deleted inten tionally.
BYRON/BRAIDWOOD STATIONS UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 11.3-2 GASEOUS WASTE PROCESSING SYSTEM FLOW DIAGRAM CARTRIDGE DRY ACTIVE FILTERS WASTES SLUDGES AND LIQUIDS LOW ACTMTY SPENT RESIN REVISION 6 DECEMBER 1996 HIGH ACTMTY SPENi RESIN HIGH ACTIVITY SPENT RESIN STORAGE TANK PACKAGE STORAGE AREA COMPACTOR PACKAGE SPENT RESIN.STORAGE TANK MOBILE t AUX.BLOC.MOBILE LINER STORAGE RADWASTE RADWASTE AREA , SYSTEM FLOOR DRAINS SYSTEM I UNER UNER STORAGE AREA TRUCK TRUCK TRUCK DISPOSAL SITE BRAIDWOOD STATION UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 11.4-1 RADWASTE DISPOSAL SYSTEM FLOW DIAGRAM CARTRIDGE DRY ACTIVE FILTERS WASTES SLUDGES AND LIQUIDS LOW ACTIVITY SPENT RESIN REVISION 6 DECEMBER 1996 HIGH ACTIVITY SPENT RESIN PACKAGE STORAGE AREA LINER TRUCK COMPACTOR PACKAGE STORAGE AREA TRUCK MOBILE RADWASTE SYSTEM LINER t AUX.BLOC.FLOOR ORAINS SPENT RESIN STORAGE TANK MOBILE RADWASTE SYSTEM LINER STORAGE AREA TRUCK DISPOSAL SITE BYRON STATION UPDATED FINAL SAFElY ANALYSIS REPORT FIGURE 11,4-1 RADWASTE DISPOSAL SYSTEM FLOW DIAGRAM B/B-UFSAR REVISION 9 - DECEMBER 2002
Figures 11.4-2 through 11.4-4 have been deleted intentionally.