ML21125A307
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FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND TABLE 11-1 RADIATION PROTECTION Revision 21 Page 1 of 3 PRIMARY COOLANT FISSION AND CORROSION PRODUCT ACTIVITIES Design Activity (1% Failed Fuel) Normal Activity Normal (Microcuries/ (Microcuries/Cubic Design Inventory Inventory Isotope Cubic Centimeter) Centimeter)(a) (Curies) (Curies)
H-3 2.80 0.21 860 65 Br-84 4.66 x 10
-2
- 13.4 -
Kr-85(m) 1.50 0.030 432 8.6 Kr-85 2.34 3.52 x 10 674 0.10
-4 Kr-87 0.81 0.037 233 10.6 Kr-88 2.48 0.060 714 17.3 Rb-88 2.44 0.122 702 35.1 Rb-89 6.10 x 10 3.05 x 10-4 0.18 9.0 x 10-4
-2 Sr-89 5.33 x 10 ) 2.28 x 10-5(b) 1.53 ) 7.0 x 10-3(b)
-3 Sr-90 1.50 x 10 ) 4.3 x 10-2)
-4 Y-90 5.77 x 10
-4
- 0.17 -
Sr-91 3.70 x 10 8.01 x 10-5 1.06 0.023
-3 Y-91(m) 0.24 1.76 x 10 68.4 0.50
-3 Mo-99 2.26 3.70 x 10
-5 649 0.010 Te-129 2.72 x 10
-2
- 7.84 -
I-129 5.66 x 10 - 1.63 x 10-5 -
-8 I-131 4.40 0.114 1,266 32.8 Te-132 0.36 3.22 x 10
-5 102 9.1 x 10-3 (a) Based on typical data from January 14, 1981; primary coolant at 17% of Technical Specifications limit for dose equivalent I-131.
(b) Total value consisting of summation of Sr-89 and Sr-90.
FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND TABLE 11-1 RADIATION PROTECTION Revision 21 Page 2 of 3 PRIMARY COOLANT FISSION AND CORROSION PRODUCT ACTIVITIES Design Activity (1% Failed Fuel) Normal Activity Normal (Microcuries/ (Microcuries/Cubic Design Inventory Inventory Isotope Cubic Centimeter) Centimeter)(a) (Curies) (Curies)
I-132 1.13 0.095 324 27.2 I-133 6.38 0.141 1,830 40.4 Xe-133 255 0.472 6.47 x 10 135.7 4
Cs-134 1.42 1.35 x 10 725 6.9 x 10-3
-5 Te-134 2.63 x 10 - 7.55 -
-2 I-134 0.64 0.134 184 38.5 I-135 2.78 0.142 801 40.9 Xe-135 6.75 0.090 1,943 25.9 Cs-136 0.15 1.90 x 10 43.4 5.5 x 10-3
-5 Cs-137 10.6 2.32 x 10
-5 3,064 6.7 x 10-3 Xe-138 0.36 (b) 103 (b)
Cs-138 0.69 0.059 198 16.9 Ba-140 6.78 x 10
-3 5.09 x 10-4 1.95 0.15 La-140 6.52 x 10
-3 6.97 x 10-4 1.88 0.20 Co-60 1.1 x 10 2.78 x 10-5 0.37 9.4 x 10-3
-3 Fe-59 7.7 x 10 1.41 x 10-5 2.6 x 10-3 4.8 x 10-3
-6 Co-58 7.9 x 10
-3 4.28 x 10-4 2.67 0.14 Mn-56 2.3 x 10 1.55 x 10 7.77 0.052
-2 -4 (a) Based on typical data from January 14, 1981; primary coolant at 17% of Technical Specifications limit for dose equivalent I-131.
(b) Data for nuclides with less than 15 minute half-lives is not documented.
FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND TABLE 11-1 RADIATION PROTECTION Revision 21 Page 3 of 3 PRIMARY COOLANT FISSION AND CORROSION PRODUCT ACTIVITIES Design Activity (1% Failed Fuel) Normal Activity Normal (Microcuries/ (Microcuries/Cubic Design Inventory Inventory Isotope Cubic Centimeter) Centimeter)(a) (Curies) (Curies)
Mn-54 2.0 x 10-5 2.70 x 10-5 6.8 x 10-3 9.2 x 10-3 Cr-51 2.4 x 10
-3 5.35 x 10-4 0.81 0.18 Zr-95 1.9 x 10 1.08 x 10-5 6.4 x 10-3 3.6 x 10-3
-5 Total 275.7 1.708 79,663 497 (a) Based on typical data from January 14, 1981; primary coolant at 17% of Technical Specifications limit for dose equivalent I-131.
FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND TABLE 11-2 RADIATION PROTECTION Revision 21 Page 1 of 2 RADIOACTIVE WASTE QUANTITIES OF SIGNIFICANT ACTIVITY Quantity/Year-Liquid Waste Sources Gallons Assumptions Chemical and Volume 69,500 Start-up after refueling Control System 900 Cold shutdown Day 1 37,200 Start-up from cold condition Day 1 13,200 Hot shutdown(a) Day 50 1,200 Start-up from hot condition Day 50 17,400 Hot shutdown(a) Day 140 1,700 Start-up from hot condition Day 140 32,300 Hot shutdown (a) Day 230 2,000 Start-up from hot condition Day 230 2,200 Cold shutdown Day 240 104,300 Start-up from cold condition Day 240 68,900 Hot shutdown(a) Day 270 2,300 Start-up from hot condition Day 270 17,500 cold shutdown to refuel 216,000 Boron reduction for cycle shim bleed Total 586,600 Primary System Drain 1,500 Primary coolant pump seal leakage at Tank 1 gpd per pump for four pumps 1,000 Safety injection check valve leakage 64,900 Drain primary system for maintenance at Day 240 13,800 Drain primary system for refueling 21,300 Drain refueling shield Total 102,500 (a) Hot shutdown quantities are based on maintaining the shutdown margin during xenon buildup by boron dilution and on Plant start-up eight hours after shutdown during the xenon buildup peak.
FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND TABLE 11-2 RADIATION PROTECTION Revision 21 Page 2 of 2 RADIOACTIVE WASTE QUANTITIES OF SIGNIFICANT ACTIVITY Quantity/Year-Liquid Waste Sources Gallons Assumptions Equipment Drain Tank 11,400 Coolant charging pump seal leakage at 31 gpd maximum leakage 7,000 Spent fuel pool overflow 3,900 Spent resin tank overflow from resin flushing - 260 ft3/year of resin replacement at 2 ft3/ft3 resin 1,900 Demineralizers drain from resin charging - 260 ft3/year of resin replacement at 1 ft3/ft3 resin Total 24,200 Radiochemistry Lab 11,000 12 samples per day at 2.5 gallons Drain Tank per sample Total Liquid Waste of Significant Activity 724,300 Quantity/Year-Gaseous Waste Sources ft3 Assumptions Degas of Primary System 2,418 Degas to 5 cm /kg prior to 3 cold 3
shutdowns including gas in volume control tank Off-Gas Liquid Waste 867 See start-up and shutdown schedule From Shutdowns and above Start-Ups Off-Gas for Chemical 1,011 Boron dilution generates 216,000 Shim Reduction gallons liquid waste with 35 cm /kg 3
gas content Off-Gas Liquid Drained 243 for Refueling Maintenance and Miscellaneous _______
Total Gaseous Waste of Significant Activity 4,539
FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND TABLE 11-3 RADIATION PROTECTION Revision 23 Page 1 of 10 EQUIPMENT RATINGS AND CONSTRUCTION CODES - ORIGINAL EQUIPMENT
- 1. CLEAN WASTE RECEIVER TANKS (T-64A, B, C, D)
Number 4 Material Type 304 Stainless Steel Capacity (Each) 50,000 gal (7,000 ft3)
Design Pressure 5 psig (Vapor Space)
Design Temperature 103F Code API 620
- 2. PRIMARY SYSTEM DRAIN TANK (T-74)
Number 1 Material Type 304 Stainless Steel Capacity 900 gal Design Pressure 50 psig Design Temperature 250°F Code ASME B&PV Code,Section III, Class C
- 3. EQUIPMENT DRAIN TANK (T-80)
Number 1 Material Type 304 Stainless Steel Capacity 550 gal Design Pressure 50 psig Design Temperature 150°F Code ASME B&PV Code,Section VIII
- 4. SPENT RESIN STORAGE TANK (T-69)
Number 1 Material Type 304 Stainless Steel Capacity 3,000 gal (400 ft3)
Design Pressure 125 psig Design Temperature 200°F Code ASME B&PV Code,Section III, Class C
- 5. CONTROLLED CHEM LAB DRAIN TANK (T-76)
Number 1 Divided Into 2 Compartments Material Type 304 Stainless Steel Capacity 900 gal (Total)
Design Pressure 50 psig Design Temperature 150°F Code ASME B&PV Code,Section VII
FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND TABLE 11-3 RADIATION PROTECTION Revision 23 Page 2 of 10 EQUIPMENT RATINGS AND CONSTRUCTION CODES - ORIGINAL EQUIPMENT
- 6. TREATED WASTE MONITOR TANKS (T-66A, B)
Number 2 Material Carbon Steel Internal Coating Baked Phenolic, 6-8 Mils Capacity 5,500 gal Design Pressure 10 psig Design Temperature 150°F Code ASME B&PV Code,Section VIII
- 7. DIRTY WASTE DRAIN TANK (T-60)
Number 1 Divided Into 2 Compartments Material Carbon Steel Capacity 3,800 gal Design Pressure 10 psig Design Temperature 150°F Code ASME B&PV Code,Section VIII Requirements
- 8. FILTERED WATER MONITORING TANKS (T-63)
Number 1 With 2 Compartments Material Carbon Steel Internal Coating Baked Phenolic, 6-8 Mils Capacity 5,500 gal Design Pressure 10 psig Design Temperature 150°F Code ASME B&PV Code,Section VIII
- 9. WASTE GAS SURGE TANK (T-67)
Number 1 Material Carbon Steel Capacity 550 gal (80 ft3)
Design Pressure 20 psig Design Temperature 150°F Code ASME B&PV Code,Section III, Class C
FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND TABLE 11-3 RADIATION PROTECTION Revision 23 Page 3 of 10 EQUIPMENT RATINGS AND CONSTRUCTION CODES - ORIGINAL EQUIPMENT
- 10. WASTE GAS DECAY TANKS (T-68A, B, C)
Number 3 Material Carbon Steel Capacity 800 gal (100 ft3)
Design Pressure 120 psig Design Temperature 550°F Code ASME B&PV Code,Section III, Class C
- 11. LAUNDRY DRAIN TANK (T-70)
Number 1 Divided Into 2 Compartments Material Carbon Steel Capacity 1,000 gal (Total)
Design Pressure 15 psig Design Temperature 150°F Code ASME P&PV Code,Section VIII
- 12. VACUUM DEGASIFIER
- a. Tank (T-57)
Number 1 Performance Handle Solution With 0-50 Std cm3 H2 (kg of Liquid Waste. Reduced H2 Concentration to 1/40 of Influent Concentration)
Design Flow 0-160 gpm Design Pressure 75 psig & 30" Hg Design Temperature 200°F Material Stainless steel Code ASME B&PV Code,Section III, Class C
- b. Vacuum Pumps (C-51A, B)
Number 2 Capacity 28 scfm @ 28" Hg Type Rotary, Water-Sealed, Water-Lubricated with Closed Cooling Loop Motor 3 hp Material Stainless steel
FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND TABLE 11-3 RADIATION PROTECTION Revision 23 Page 4 of 10 EQUIPMENT RATINGS AND CONSTRUCTION CODES - ORIGINAL EQUIPMENT
- 13. RADWASTE DEMINERALIZER
- a. Demineralizer Tanks (T-55A, B, C)
Number 3 Material of Tank Stainless Steel Flow Rate (Each) 48 gpm (Rated), 100 gpm (Max)
Unit Flow Rate (at Ratings) 5.0 gpm/ft2 Resin Volume (Each) 32 ft3 Resin Type Equivalent Capacity Mixture of Nuclear Grade Cation and Anion Design Pressure 125 psig Design Temperature 160°F Code ASME B&PV Code,Section III, Class C and ASME B&PV Code,Section VIII, Para UW-2 (a)
- b. Clean Resin Transfer Tank (T-61)
Number 1 Material PVC Lined Carbon Steel Capacity 32 ft3 Design Pressure 125 psig Design Temperature 125°F Code ASME B&PV Code,Section VIII
- 14. CLEAN WASTE FILTERS (F-57A, B, C)
Type Cartridge Type With Replaceable Elements Number 3 Material, Container Stainless Steel Material, Filter Media Polypropolene Filter Media Rating 150 Micron Flow Rate 100 gpm Design Pressure 125 psig Design Temperature 160°F Code ASME B&PV Code,Section III, Class C and ASME B&PV Code,Section VIII, Para UW-2 (a)
FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND TABLE 11-3 RADIATION PROTECTION Revision 23 Page 5 of 10 EQUIPMENT RATINGS AND CONSTRUCTION CODES - ORIGINAL EQUIPMENT
- 15. EQUIPMENT DRAIN FILTER (F-56)
Number Cartridge Type with Replaceable Elements Material, Container Stainless Steel Material, Filter Media Polypropolene Filter Media Rating 25 Microns Design Pressure 125 psig Design Temperature 212°F Code ASME B&PV Code,Section III, Class C and ASME B&PV Code,Section VIII, Para UW-2 (a)
- 16. DIRTY WASTE FILTER (F-53)
Type Cartridge Type With Replaceable Elements Number 1 Material, Container Stainless Steel Material, Filter Media Polypropolene Filter Media Rating 200 Microns Flow Rate 75 gpm Design Pressure 100 psig Design Temperature 160°F Code ASME B&PV Code,Section III, Class C and ASME B&PV Code,Section VIII, Para UW-2 (a)
- 17. LAUNDRY DRAIN FILTER (F-55)
Type Cartridge Type With Replaceable Elements Number 1 Material, Container Stainless Steel Material, Filter Media Polypropolene Filter Media Rating 25 Microns Flow Rate 20 gpm Design Pressure 100 psig Design Temperature 160°F Code ASME B&PV Code,Section III, Class C and ASME B&PV Code,Section VIII, Para UW-2 (a)
FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND TABLE 11-3 RADIATION PROTECTION Revision 23 Page 6 of 10 EQUIPMENT RATINGS AND CONSTRUCTION CODES - ORIGINAL EQUIPMENT
- 18. PRIMARY SYSTEM DRAIN TANKS PUMPS (T-71A, B)
Type Horizontal Centrifugal With Mechanical Seals Number 2 Capacity (Each) 75 gpm Head 80 ft TDH Material Type 316 Stainless Steel Motor 5 hp, 3 Phase, 60 Hertz, 460 Volt Codes Motor NEMA; Pump, Standards of Hydraulic Institute
- 19. DEGASIFIER PUMPS (P-68A, B)
Type Horizontal Centrifugal With Mechanical Seals Number 2 Capacity (Each) 160 gpm Head 190 ft TDH Material Type 316 Stainless Steel Motor 20 hp, 3 Phase, 60 Hertz, 460 Volt Codes Motor NEMA; Pump, Standards of Hydraulic Institute
- 20. EQUIPMENT DRAIN TANK PUMPS (P-75A, B)
Type Horizontal Centrifugal With Mechanical Seals Number 2 Capacity (Each) 100 gpm Head 266 ft TDH Material Type 316 Stainless Steel Motor 25 hp, 3 Phase, 60 Hertz, 460 Volt Codes Motor NEMA; Pump, Standards of Hydraulic Institute
- 21. CONTROLLED CHEM LAB DRAIN PUMPS (P-61A, B)
Type Horizontal Centrifugal With Mechanical Seals Number 2 Capacity (Each) 10 gpm Head 158 ft TDH Material Type 316 Stainless Steel Motor 7.5 hp, 3 Phase, 60 Hertz, 460 Volt Codes Motor NEMA; Pump, Standards of Hydraulic Institute
FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND TABLE 11-3 RADIATION PROTECTION Revision 23 Page 7 of 10 EQUIPMENT RATINGS AND CONSTRUCTION CODES - ORIGINAL EQUIPMENT
- 22. RECEIVER TANK (CWRT) PUMPS (P-69A, B)
Type Horizontal Centrifugal With Mechanical Seals Number 2 Capacity (Each) 100 gpm Head 200 ft TDH Material Type 316 Stainless Steel Motor 15 hp, 3 Phase, 60 Hertz, 460 Volt
- 23. RECEIVER TANK (CWRT) CIRCULATING PUMP (P-70)
Type Horizontal Centrifugal With Mechanical Seals Number 1 Capacity (Each) 250 gpm Head 121 ft TDH Material Type 316 Stainless Steel Motor 15 hp, 3 Phase, 60 Hertz, 460 Volt Codes Motor NEMA; Pump, Standards of Hydraulic Institute
- 24. TREATED WASTE MONITOR PUMPS (P-58A, B)
Type Horizontal Centrifugal With Mechanical Seals Number 2 Capacity (Each) 150 gpm Head 140 ft TDH Material Type 316 Stainless Steel Motor 15 hp, 3 Phase, 60 Hertz, 460 Volt Codes Motor NEMA; Pump, Standards of Hydraulic Institute
- 25. SAFETY INJECTION ROOM SUMP PUMPS (P-72A, B AND P-73A, B)
Type Vertical Centrifugal Number 4 (2 Sets With 2 Pumps per Set)
Capacity (Each) 25 gpm Head 35 ft TDH Material Stainless Steel Motor 1 hp, 3 Phase, 60 Hertz, 460 Volt Codes Motor NEMA,
FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND TABLE 11-3 RADIATION PROTECTION Revision 23 Page 8 of 10 EQUIPMENT RATINGS AND CONSTRUCTION CODES - ORIGINAL EQUIPMENT
- 26. DIRTY WASTE DRAIN TANK PUMPS (P-60A, B)
Type Horizontal Centrifugal With Mechanical Seals Number 2 Capacity (Each) 75 gpm Head 160 ft TDH Material Type 316 Stainless Steel Motor 10 hp, 3 Phase, 60 Hertz, 460 Volt Codes Motor NEMA; Pump, Standards of Hydraulic Institute FILTERED WASTE MONITOR PUMP (P-63)
Type Horizontal Centrifugal With Mechanical Seals Number 1 Capacity (Each) 75 gpm Head 150 ft TDH Material Type 316 Stainless Steel Motor 10 hp, 3 Phase, 60 Hertz, 460 Volt Codes Motor NEMA; Pump, Standards of Hydraulic Institute
- 28. WASTE GAS COMPRESSORS (C-50A, B)
- a. Compressor Number 2 Type Single Head, Single Stage Diaphragm Type Capacity (Each) 2.35 scfm at 14.7 psia Suction, 0.44 scfm at 7.5 psia Suction Discharge Pressure 100 psig at Maximum Delivery Material Stainless Steel Motor 2 hp, 3 Phase, 60 Hertz, 460 Volt, TEFC
- b. Aftercoolers Number 2 Type Shell and Tube With Moisture Separator and Drain Trap Material Tube Side (Gas) Stainless Steel, Shell Side (Water) Carbon Steel
FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND TABLE 11-3 RADIATION PROTECTION Revision 23 Page 9 of 10 EQUIPMENT RATINGS AND CONSTRUCTION CODES - ORIGINAL EQUIPMENT
- 29. WASTE GAS COMPRESSOR (C-54)
- a. Compressor Number 1 Type Diaphragm Type Capacity (Each) 5 scfm Avg Between Suction Pressures of 7.5 and 15.0 psia Discharge Pressure 100 psig Material Motor 7.5
- b. Aftercoolers Number 1
- 30. PIPING, FITTING AND VALVES
- a. Liquid Systems Material Stainless Steel Design Pressure Floor Drains - Atmosphere, Process -
50 psig Joints, 2" and Larger Butt Weld 1-1/2" and Smaller 2,000 lb SW Valves, 2" and Larger Stainless Steel, Butt Weld Ends, 150 lb 1-1/2" and Smaller Stainless Steel, 2,000 lb SW Ends, 150 lb Butterfly Valves Stainless Steel, Flangeless, 150 lb Plug Vales Stainless steel, FF Flanged, 150 lb Code ASA B31.1, Code for Pressure Piping, Including Applicable Nuclear Code Cases, ASA B16.5 Radiography All Butt Weld in Nuclear Service Systems Rated for Higher Than 50 psig and 212°F Are Radiographed 100. All Butt Welds in Nuclear Systems Rated for Less Than 50 psig and 212°F Are Radiographed 10%
FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND TABLE 11-3 RADIATION PROTECTION Revision 23 Page 10 of 10 EQUIPMENT RATINGS AND CONSTRUCTION CODES - ORIGINAL EQUIPMENT
- b. Gaseous Systems Material Carbon Steel Design Pressure 100 psig Joints, 2" and Larger Butt Weld 1-1/2" and Smaller 3,000 lb SW Valves, 2" and Larger Carbon Steel, 150 lb BW 1-1/2" and Smaller Carbon Steel, 600 lb, 3,000 lb SW Butterfly Carbon Steel, 150 lb, FF Flanged Plug Ductile Iron, 150 lb, FF Flanged Code ASA B31.1, Code for Pressure Piping, Including Applicable Nuclear Code Cases, ASA B16.5 Radiography All Welds Are 100% Radiographed
FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND TABLE 11-4 RADIATION PROTECTION Revision 21 Page 1 of 7 EQUIPMENT RATINGS AND CONSTRUCTION CODES -
ADDITIONAL EQUIPMENT INSTALLED 1971-1973
- 1. CLEAN WASTE HOLDUP TANK (T-85)
Number 1 Material of Tank SA240 Type 304 SS Capacity 5,000 gal Design Pressure Atm Design Temperature 212°F Code API-620, 1970 Exam ASME B&PV Code,Section III, 1971
- 2. CLEAN WASTE TRANSFER PUMP (P-94)
Type Gould 3196 Number 1 Capacity 80 gpm Head 85 ft Material Stainless Steel Motor 5 hp Code ASME B&PV Code,Section III, Class 3, 1971
- 3. CLEAN AND DIRTY WASTE EVAPORATORS (M-59A, B)
- a. Evaporator Vessel Number 2 Material 316 SS Capacity 1,600 gal Design Pressure 15 psig Design Temperature 200°F Code ASME B&PV Code,Section III, Class 3, 1971
- b. Recirculation Pump Type Gould 3196 - 3 x 4-13 Number 4 Capacity 200 gpm Head 30 ft Material 316 SS Motor 5 hp, 3 Phase, 60 Hertz, 460 Volt Code ASME B&PV Code,Section III, Class 3, 1971
FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND TABLE 11-4 RADIATION PROTECTION Revision 21 Page 2 of 7 EQUIPMENT RATINGS AND CONSTRUCTION CODES -
ADDITIONAL EQUIPMENT INSTALLED 1971-1973
- c. Distillate Pump Type Gould 3196 - 1 x 1-1/2-6 Number 4 Capacity 25 gpm Head 130 ft Material 316 SS Motor 5 hp Code ASME B&PV Code,Section III, Class 3, 1971
- d. Concentrate Pump Type Gould 3196 - 1 x 1-1/2-6 Number 4 Capacity 25 gpm Head 100 ft Material 316 SS Motor 3 hp Code ASME B&PV Code,Section III, Class 3, 1971
- e. Vacuum Pump Type Nash Number 4 Capacity 48 cfm @ 20" vacuum Head 2 psig Material 316 SS Motor 3 hp Code N/A
- 4. CLEAN WASTE DISTILLATE TANK (T-86)
Number 1 Material SA240 Type 304 SS Capacity 5,000 gal Design Pressure Atm Design Temperature 212°F Code API-650, 1970 Exam ASME B&PV Code,Section III, 1971
FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND TABLE 11-4 RADIATION PROTECTION Revision 21 Page 3 of 7 EQUIPMENT RATINGS AND CONSTRUCTION CODES -
ADDITIONAL EQUIPMENT INSTALLED 1971-1973
- 5. CLEAN WASTE DISTILLATE PUMP (P-97A, B)
Type Gould 3196 Number 2 Capacity 80 gpm Head 85 ft Material 316 SS Motor 5 hp - Pacemaker Code ASME B&PV Code,Section III, Class 3, 1971
- 6. CLEAN (MISCELLANEOUS) WASTE CONCENTRATE TANKS (T-94, T-95)
Number 2 Material SA240 Type 304 SS Capacity 1,500 gal Design Pressure Atm Design Temperature 212°F Code API-650, 1970 Exam ASME B&PV Code,Section III, 1971
- 7. MISCELLANEOUS WASTE FILTER (F-59)
Type Cartridge Type With Replaceable Elements Number 1 Material, Container 304 SS Material, Filter Media Epoxy Impregnated Cellulose Filter Media Rating 150 Micron*
Flow Rate 30 gpm Design Pressure 50 psig Design Temperature 212°F Code ASME B&PV Code,Section III, Class 3, 1971
- May be in service with element removed.
- 8. CLEAN (MISCELLANEOUS) WASTE CONCENTRATE PUMPS (P-95A, B)
Type Gould 3196, 1 x 2-8 Number 2 Capacity 30 gpm Head 75 ft Material 316 SS Motor 3 hp - Pacemaker Code ASME B&PV Code,Section III, Class 3, 1971
FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND TABLE 11-4 RADIATION PROTECTION Revision 21 Page 4 of 7 EQUIPMENT RATINGS AND CONSTRUCTION CODES -
ADDITIONAL EQUIPMENT INSTALLED 1971-1973
- 9. POLISHING (MISCELLANEOUS WASTE) DEMINERALIZERS (T-88, T-89A, B)
Number 3 Material of Tank 304 SS Flow Rate 50 gpm (Rated), 100 gpm (Max)
Unit Flow Rate (At Max) 10 gpm/ft2 Resin Volume 32 ft3 Resin Type Equivalent Capacity Mixture of Nuclear Grade Cation and Anion
- 10. MISCELLANEOUS WASTE HOLDUP TANKS (T-92A, B, C)
Number 3 Material SA240 Type 304 SS Capacity 20,000 gal Design Pressure Atm Design Temperature 212°F Code API-620, 1970 Exam ASME B&PV Code,Section III, 1971
- 11. MISCELLANEOUS WASTE TRANSFER PUMPS (P-92A, B)
Type Gould 3196, 2 x 3-13 Number 2 Capacity 80 gpm Head 120 ft Material 316 SS Motor 10 hp - Pacemaker Code ASME B&PV Code,Section III, Class 3, 1971
- 12. MISCELLANEOUS WASTE DISTILLATE TANK (T-87)
Number 1 Material SA240 Type 304 SS Capacity 8,000 gal Design Pressure Atm Design Temperature 212°F Code API-650, 1970 Exam ASME B&PV Code,Section III, 1971
FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND TABLE 11-4 RADIATION PROTECTION Revision 21 Page 5 of 7 EQUIPMENT RATINGS AND CONSTRUCTION CODES -
ADDITIONAL EQUIPMENT INSTALLED 1971-1973
- 13. MISCELLANEOUS WASTE DISTILLATE PUMPS (P-89A, B)
Type Gould 3196, 1-1/2 x 3-6 Number 2 Material 316 SS Capacity 80 gpm Head 110 ft Motor 7-1/2 hp - Pacemaker Code ASME B&PV Code,Section III, Class 3, 1971
- 14. RADWASTE SPENT RESIN STORAGE TANK (T-100)
Number 1 Material 304 SS Capacity 200 ft3 Design Pressure 125 psig Design Temperature 200°F Code ASME B&PV Code,Section III, Class 3, 1971
- 15. WASTE GAS DECAY TANKS (T-101A, B, C)
Number 3 Material Carbon Steel Capacity 225 ft3 Design Pressure 120 psig Design Temperature 550°F Code ASME B&PV Code,Section III, Class 3, 1971
FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND TABLE 11-4 RADIATION PROTECTION Revision 21 Page 6 of 7 EQUIPMENT RATINGS AND CONSTRUCTION CODES -
ADDITIONAL EQUIPMENT INSTALLED 1971-1973
- 16. PIPING, FITTINGS AND VALVES
- a. Liquid Radwaste System (Process)
Material Stainless Steel Design Pressure 125 psig and 150 psig Fittings 2-1/2" and Larger 150 lb Thickness To Match Pipe Butt Weld Ends 2-1/2" and Smaller 3,000 lb Socket Weld Valves 2-1/2" and Larger 150 lb Butt Weld Ends 2" and Smaller 150 lb Socket Weld Ends Joints 2-1/2" and Larger Butt Weld Ends 2" and Smaller Socket Weld Ends Code ASME B&PV Code,Section III, Nuclear Power Plant Components, Nuclear Class 3, 1971, per AEC Safety Guide 26, March 27, 1972
- b. Atmospheric Radwaste Drainage Piping Material Stainless Steel Design Pressure Atmospheric Fittings 8" and Smaller Butt Weld Ends Joints 8" and Smaller Butt Weld Code ANSI B31.1.0 - 1967 Power Piping
- c. Gaseous Radwaste System (Process)
Material Carbon Steel Design Pressure 150 psig Fittings 2-1/2" and Larger 150 lb Thickness To Match Pipe Butt Weld Ends 2" and Smaller 3,000 lb Socket Weld Ends Valves 2-1/2" and Larger 150 lb Butt Weld Ends 2" and Smaller 600 lb Socket Weld Ends Joints 2-1/2" and Larger Butt Weld Ends 2" and Smaller Socket Weld Code ASME B&PV Code,Section III, Nuclear Power Plant Components, Nuclear Class 3, 1971, per AEC Safety Guide 26, March 23, 1972
FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND TABLE 11-4 RADIATION PROTECTION Revision 21 Page 7 of 7 EQUIPMENT RATINGS AND CONSTRUCTION CODES -
ADDITIONAL EQUIPMENT INSTALLED 1971-1973
- 17. PRIMARY SYSTEM MAKEUP STORAGE TANK (T-90)
Number 1 Material Carbon Steel Capacity 200,000 gal Design Pressure Atmospheric Code API-650, 1970
- 18. UTILITY WATER STORAGE TANK (T-91)
Number 1 Material Carbon Steel Capacity 75,000 gal Design Pressure Atmospheric Code API-650, 1970
FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND TABLE 11-5 RADIATION PROTECTION Revision 21 Page 1 of 1 PRIMARY SYSTEM DRAIN TANK Letdown and Regenerative HX Drain Shutdown Cooling Header Relief SI Tanks Leakage PCS Loop Drains Quench Tank Drains Flange Leak Detector Drain Controlled Bleed-Off Relief PCS Pump Seal Leakage
FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND TABLE 11-6 RADIATION PROTECTION Revision 30 Page 1 of 1 EQUIPMENT DRAIN TANK Spent Resin Storage Tanks Primary Coolant Sample Drain Clean Resin Transfer Tank Radwaste Demineralizer Drains Fuel Pool Overflow Fuel Pool HX Drains Fuel Pool Demineralizer Drains Fuel Pool Filter Drains Blowdown Drain Tank HPI Header Relief SIRW Tank Overflow Drain SIRW Tank HX Drain SI Tank Sample Flush Waste Gas Surge Tank Drain Chemical Addition Tank Drain Charging Pump Relief and Drains VCT Drain Purification Filters Drain
FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND TABLE 11-7 RADIATION PROTECTION Revision 21 Page 1 of 1 DIRTY WASTE DRAIN TANK Radwaste Addition Area Sample Sink Drains Clean Resin Transfer Tank Drains Pump Leak-Offs Auxiliary Building Floor Drains Decontamination Pit Drains Cask Washdown Area Drains Controlled Chemical Laboratory Drain Tank Drains Component Cooling Surge Tank Drain Boric Acid Batching Tank Drain Boric Acid Filter Drains Treated Waste Monitor Tanks VCT Relief Vacuum Degasifier Relief Turbine Building Sump Pump Discharge Containment Sump Drains Shutdown Cooling HX Drains Spent Resin Storage Tank (T-100)
Primary System Makeup and Utility Water Tanks Overflow Laundry Drain Tank Drains Auxiliary Building Sump Pumps
FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND TABLE 11-8 RADIATION PROTECTION Revision 26 Page 1 of 2 LIQUID RADWASTE Clean Liquid Waste Activities (Ci/cm3)* Dirty Liquid Waste Activities (Ci/cm3)*
After After After Processiong After After As Received Processing Processing Through Processing Processing in Receiver After 30 Through Two Through Polishing As Received Through Through Isotope Half-Life Tanks Days' Decay Demineralizers Evaporator Demineralizer in Drain Tank Evaporator Demineralizers Fission Products Br-84 32m 1.25 x 10-2 (a) (a) (a) (a) 4.66 x 10-4 4.66 x 10-8 (a)
-1 Rb-88 18m 6.61 x 10 (a) (a) (a) (a) 2.44 x 10-2 2.44 x 10-6 2.44 x 10-8
-2 Rb-89 15m 1.66 x 10 (a) (a) (a) (a) 6.10 x 10-4 6.10 x 10-8 (a)
-3 SR-89 54d 1.44 x 10 9.80 x 10-4 9.80 x 10-6 (a) (a) 5.33 x 10-5 (a) (a)
-5 Sr-90 28y 4.00 x 10 4.00 x 10-5 4.00 x 10-7 (a) (a) 1.50 x 10-6 (a) (a)
-4 Y-90 64h 1.55 x 10 6.51 x 10-8 (a) (a) (a) 5.77 x 10-6 (a) (a)
-3 Sr-91 9.7h 1.00 x 10 (a) (a) (a) (a) 3.70 x 10-5 (a) (a)
-2 Y-91 58d 6.50 x 10 4.53 x 10-2 4.53 x 10-4 4.53 x 10-8 (a) 2.40 x 10-3 2.40 x 10-7 (a)
-1 Mo-99 67h 6.12 x 10 3.67 x 10-4 3.67 x 10-6 (a) (a) 2.26 x 10-2 2.26 x 10-6 2.26 x 10-8
-3 Te-129 33d 7.36 x 10 3.93 x 10-3 3.93 x 10-5 (a) (a) 2.72 x 10-4 2.72 x 10-8 (a) 7 I-129 1.7 x 10 y 1.52 x 10-8 1.52 x 10-8 (a) (a) (a) (a) (a) (a)
-2 I-131 8.0d 1.18 8.87 x 10 8.87 x 10-4 8.87 x 10-7 8.87 x 10-8 4.40 x 10-2 4.40 x 10-5 4.40 x 10-7
-2 Te-132 77h 9.75 x 10 1.46 x 10-4 1.46 x 10-6 (a) (a) 3.60 x 10-3 3.60 x 10-7 (a)
-1 I-132 2.3h 3.05 x 10 (a) (a) (a) (a) 1.13 x 10-2 1.13 x 10-5 1.13 x 10-7
-2 I-133 21h 1.73 (a) (a) (a) (a) 6.38 x 10 6.38 x 10-5 6.38 x 10-7
-1 Cs-134 2.3y 3.84 x 10 3.78 x 10-1 3.70 x 10-3 3.78 x 10-7 3.78 x 10-8 1.42 x 10-2 1.42 x 10-6 1.42 x 10-8
-3 Te-134 44m 7.12 x 10 (a) (a) (a) (a) 2.63 x 10-4 2.63 x 10-8 (a)
-1 I-134 52m 1.73 x 10 (a) (a) (a) (a) 6.40 x 10-3 6.40 x 10-5 6.40 x 10-7
-1 I-135 6.7h 7.53 x 10 (a) (a) (a) (a) 2.78 x 10-2 2.78 x 10-6 2.78 x 10-8
-2 Cs-136 13d 4.06 x 10 8.20 x 10-3 8.20 x 10-5 (a) (a) 1.50 x 10-3 1.50 x 10-7 (a)
-2 Cs-137 30y 2.87 2.87 2.87 x 10 2.87 x 10-6 2.87 x 10-7 1.06 x 10-1 1.06 x 10-5 1.06 x 10-7
-1 Cs-138 32m 1.87 x 10 (a) (a) (a) (a) 6.90 x 10-3 6.90 x 10-7 (a)
-3 Ba-140 12.8d 1.84 x 10 3.65 x 10-4 3.65 x 10-6 (a) (a) 6.78 x 10-5 (a) (a)
-3 La-140 40.2h 1.27 x 10 (a) (a) (a) (a) 6.52 x 10-5 (a) (a)
Corrosion Products Cr-51 27d 6.50 x 10-4 3.02 x 10-4 3.02 x 10-6 (a) (a) 2.4 x 10-5 (a) (a)
-6 Mn-54 300d 5.22 x 10 4.87 x 10-6 4.87 x 10-8 (a) (a) 2.0 x 10-7 (a) (a)
-3 Mn-56 2.58h 6.00 x 10 (a) (a) (a) (a) 2.3 x 10-4 2.3 x 10-8 (a)
-3 Co-58 71d 2.07 x 10 1.55 x 10-3 1.55 x 10-5 (a) (a) 7.9 x 10-5 (a) (a)
-6 Fe-59 45d 2.02 x 10 1.27 x 10-6 1.27 x 10-8 (a) (a) 7.7 x 10-8 (a) (a)
-4 Co-60 5.2y 2.98 x 10 2.95 x 10-4 2.95 x 10-6 (a) (a) 1.1 x 10-5 (a) (a)
-6 Zr-95 65d 4.96 x 10 3.61 x 10-6 3.61 x 10-8 (a) (a) 1.9 x 10-7 (a) (a)
-8 (a) Less Than 10
FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND TABLE 11-8 RADIATION PROTECTION Revision 26 Page 2 of 2 LIQUID RADWASTE Assumptions:
Factor of 10 reductionin each demineralizer for all isotopes except tritium.
3 10 reduction for iodine in evaporator.
4 10 reduction for all other isotopes except tritium.
19% of clean waste is direct from primary system.
81% of clean waste is from Chemical and Volume JControl System and passes through one ion exchanger prior to entering clean waste receiver tanks.
No holdup period assumed in Miscellaneous Waste Holdup Tank.
1% defective fuel.
Dirty waste activity is 1% of primary coolant activity.
- The above information pertaining to isotopic activities are based on decontamination factors (DF) which were provided as part of the initial safety analysis or added as changes to the systems were made. Operating experience has demonstrated that the reactor coolant activity levels are much lower than the activity levels assumed in the radwaste system design. The ODCM provides information pertaining to the monitoring of waste streams and ensures the resultant offsite doses are in compliance with current regulatory requirements. The above information is considered historical.
FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND TABLE 11-9 RADIATION PROTECTION Revision 21 Page 1 of 1 MAXIMUM CALCULATED TRITIUM RELEASE DUE TO EVAPORATION FROM REFUELING CAVITY AND SPENT FUEL POOL Conc in Release From Conc in Release From Spent Fuel Spent Fuel Total Yr of Contain Bldg Contain Bldg Bldg Bldg Release Oper (Ci/cm3) (Ci/Yr) (Ci/cm3) (Ci/Yr) (Ci/Yr) 5 1.1 x 10-13 18 8.5 x 10-14 13 31 10 2.1 x 10-13 35 2.2 x 10-13 33 68 15 3.0 x 10-13 50 3.6 x 10-13 53 103 20 3.8 x 10-13 63 4.9 x 10-13 72 135 25 4.5 x 10-13 75 6.1 x 10-13 90 165 30 5.1 x 10-13 85 7.1 x 10-13 105 190 35 5.6 x 10-13 93 8.0 x 10-13 118 211 40 6.0 x 10-13 100 8.6 x 10-13 127 227
FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND TABLE 11-10 RADIATION PROTECTION Revision 21 Page 1 of 1 LADTAP INPUT DATA AND RESULTS MAXIMUM INDIVIDUAL DOSE CALCULATIONS Usage Rates (kg/yr or h/yr)
Exposure Pathway Dilution Factor Transit Time (h) Adult Teen Child Infant Fish Ingestion 15 12 21.0 16.0 6.9 0.0 Water Ingestion 1,000 24 730.0 510.0 510.0 510.0 Shoreline Use 1 0 12.0 67.0 14.0 0.0 Swimming 1 0 12.0 67.0 14.0 0.0 Boating 15 0 52.0 52.0 29.0 0.0 Dose Results (mrem/yr)(a)
Adults Teenager Exposure Pathway T Body Liver Skin T Body Liver Skin Fish Ingestion 5.25(-1)(b) 6.96(-1) - 2.97(-1) 6.91(-1) -
Water Ingestion 5.66(-4) 6.13(-4) - 3.10(-4) 4.06(-4) -
Shoreline Use 7.96(-3) 7.96(-3) 9.3(-3) 4.45(-2) 4.45(-2) 5.19(-2)
Swimming 8.24(-5) 8.24(-5) - 4.6 (-4) 4.6 (-4) -
Boating 1.19(-5) 1.19(-5) - 1.19(-5) 1.19(-5) -
Totals 5.34(-1) 7.04(-1) 9.3(-3) 3.43(-1) 7.36(-1) 5.19(-2)
(a) Doses to other individuals and organs are smaller than those presented.
(b) 5.25(-1) = 5.25 x 10-1
FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND TABLE 11-11 RADIATION PROTECTION Revision 21 Page 1 of 1 ACTIVITY IN COOLANT AND GASEOUS WASTE Activity Activity in Surge Tank Fraction of 10 CFR 20 Ci/cm3 Ci/cm3 H2 10 CFR 20 Limit at Boundary Isotope Half-Life Coolant As Received 60-Day Hold Ci/cm3 No Hold 60-Day Hold Kr-85(m) 4.4h 1.50 42.9 (a) 1 x 10-7 .0065 (a)
Kr-85 10.4y 2.34 66.9 65.6 3 x 10-7 .0034 .0034 Kr-87 78m 0.81 23.1 (a) 2 x 10-8 .017 (a)
Kr-88 2.8h 2.48 70.9 (a) (b) (b) (b)
Xe-133 5.27d 225 6,430 2.48 3 x 10-7 0.32 .00012 Xe-135 9.2h 6.75 193 (a) 1 x 10 .029 (a)
-7 Xe-138 17m 0.36 10.3 (a) (b) (b) (b)
(a)Less than 10
-8 (b)Unlisted in 10 CFR 20
FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND TABLE 11-12 RADIATION PROTECTION Revision 21 Page 1 of 1 SPECIAL LOCATION GASPAR INPUT DATA Distance Normal Depleted Deposition Number (Miles) Direction Description X/Q(s/m3) X/Q(s/m3) D/Q(1/m2) 1 0.63 S Residence 5.56(-6) 4.66(-6) 3.08(-8) 2 0.88 ENE Garden 2.06(-6) 1.67(-6) 2.31(-8) 3 1.00 ESE Meat Animal 2.13(-6) 1.69(-6) 1.49(-8) 4 2.50 NE Goat Milk 2.60(-7) 1.85(-7) 8.14(-10) 5 2.75 ENE Milk Cow 1.81(-7) 1.26(-7) 1.59(-9)
Value for Parameter Appropriate Locations Fraction fresh leafy vegetables grown locally 1.0 Fraction of year cows, cattle, goats on pasture 0.5 Fraction of vegetable intake grown in garden 0.76 Fraction of feed from pasture while on pasture 1.0 Air water content, g/m3 8.0
FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND TABLE 11-13 RADIATION PROTECTION Revision 21 Page 1 of 1 DOSE RESULTS FOR SPECIAL LOCATIONS MAXIMUM INDIVIDUAL DOSES BY AGE GROUP AND ORGAN mrem/yr(a)
Adults Teenagers Children Infants Location(a) Description T Body Skin Thyroid T Body Skin Thyroid T Body Skin Thyroid T Body Skin Thyroid 1 Plume 1.13(-1) 3.38(-1) 1.13(-1) 1.13(-1) 3.38(-1) 1.13(-1) 1.13(-1) 3.38(-1) 1.13(-1) 1.13(-1) 3.38(-1) 1.13(-1)
Ground 1.43(-1) 1.68(-2) 1.43(-2) 1.43(-2) 1.68(-2) 1.43(-2) 1.43(-2) 1.60(-2) 1.43(-2) 1.43(-2) 1.68(-2) 1.43(-2)
Inhalation 9.25(-2) 9.20(-2) 3.40(-1) 5.13(-2) 5.09(-2) 2.58(-1) 5.22(-2) 5.16(-2) 3.25(-1) 5.57(-2) 5.49(-2) 5.23(-1) 2 Garden 2.05(-1) 1.99(-1) 1.71(0) 2.43(-1) 2.37(-1) 1.43(0) 5.02(-1) 4.95(-1) 2.30(0) - - -
3 Meat 5.09(-2) 5.06(-2) 1.10(-1) 3.52(-2) 3.50(-2) 7.62(-2) 6.16(-2) 6.14(-2) 1.24(-2) - - -
4 Goat Milk 1.45(-2) 1.36(-2) 2.58(-1) 1.84(-2) 1.72(-2) 3.84(-1) 3.66(-2) 3.46(-2) 7.60(-1) 6.84(-2) 6.49(-2) 1.81(0) 5 Cow Milk 6.79(-3) 6.33(-3) 1.84(-1) 9.47(-3) 8.77(-3) 2.76(-1) 2.03(-2) 1.90(-2) 5.48(-1) 3.89(-2) 3.74(-2) 1.31(0)
(a) See Table 11-12 for location data
FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND TABLE 11-15 RADIATION PROTECTION Revision 31 Page 1 of 4 PROCESS RADIATION SERVICE AND EQUIPMENT Process Radiation Detection Equipment/ Alarm and Control Monitoring Systems Sampling Equipment Readout Equipment Sensitivity Service Water, RE0833 Scintillation detector/detector Digital indicator 5 x 10-6 Ci/cm3 of Alarm on high radiation, well in service water line to 10-107 CPM. Cs-137 equivalent. circuit failure.
discharge structure.
Steam Generator Scintillation detector/external Digital rate meter 5 x 10-6 Ci/cm3 of Alarm on high radiation Blowdown, RE0707 to blowdown tank, drain to 10-107 CPM. Cs-137 equivalent. signal; isolates blowdown P98A/B suction. tank.
Radwaste Liquid Scintillation detector on Digital rate meter 5 x 10-6 Ci/cm3 of Alarm on high radiation, Discharge, RE1049 radwaste liquid line to 10-107 CPM. Cs-137 equivalent. cirtuit failure. Isolates discharge structure. radwaste release.
Component Cooling Scintillation detector/piping, Digital indicator 5 x 10-5 Ci/cm3 of Alarm on high radiation, Water, RE0915 valves, and detector housing.10-107 CPM. Cs-137 equivalent. circuit failure; isolates CC pump dP for flow. component cooling water surge tank vent.
Circ Water Discharge, Scintillation detector/piping, Digital indicator 4 x 10-6 Ci/cm3 of Alarm on high radiation, RE1323 valves, sample pump and 10-107 CPM. Cs-137 equivalent. circuit failure.
detector housing; circulating from mixing basin prior to discharge.
Off-Gas Monitoring, Scintillation detector/piping, Digital rate meter analyzer 1 x 10-5 Ci/cm3 of Alarm on high radiation and RE0631 valves and detector housing;10-107 CPM. Xe-133 equivalent. circuit failure.
main condenser steam jet air ejector noncondensibles to stack.
FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND TABLE 11-15 RADIATION PROTECTION Revision 31 Page 2 of 4 PROCESS RADIATION SERVICE AND EQUIPMENT Process Radiation Detection Equipment/ Alarm and Control Monitoring Systems Sampling Equipment Readout Equipment Sensitivity Radwaste Area Geiger-Mueller tube/piping, Linear rate meter 4 x 10-5 Ci/cm3 of Alarm on high radiation and Ventilation, RE1809 valves, sample pump and 0-106 CPM. Xe-133 equivalent. circuit failure; isolates detector housing; air radwaste vent system.
monitoring prior to discharge to stack.
Engineered Safeguards Geiger-Mueller tube; piping, Digital rate meter 1 x 10-4 Ci/cm3 of Alarm on high radiation and Pump Rooms Vent, valves, sample pump and 10-107 CPM. Xe-133 equivalent. circuit failure; isolates RE1810, 1811 detector housing; to stack, pump room vent supply and 2 systems, East and West exhausts.
rooms.
Waste Gas Radiation, Geiger-Mueller tube/piping, Digital rate meter 1 x 10-4 Ci/cm3 of Alarm on high radiation and RE1113 valves and detector housing;10-107 CPM. Xe-133 equivalent. circuit failure; isolation from the waste gas surge tank waste gas surge tank and and waste gas decay tanks to decay tanks.
stack.
Containment Building Geiger-Mueller tube/piping Linear rate meter 1 x 10-4 Ci/cm3 of Alarm on high radiation and Gas Monitoring solenoid valves and detector 10-107 CPM. Xe-133 equivalent. circuit failure.
System, RE1817 housing; from 5 sample locations on (4) cooler fan discharges.
Failed Fuel, RE0202 Scintillation detector/detector Linear rate meter, N/A Alarm on high radiation, housing in letdown line. 0-106 CPM, local. circuit failure.
FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND TABLE 11-15 RADIATION PROTECTION Revision 31 Page 3 of 4 PROCESS RADIATION SERVICE AND EQUIPMENT Process Radiation Detection Equipment/ Alarm and Control Monitoring Systems Sampling Equipment Readout Equipment Sensitivity Steam Generator Scintillation detector/in well on Digital rate meter, 2 x 10-5 Ci/cm3 of Alarm on high radiation, Blowdown Vent, blowdown vent line.10-107 CPM. Cs-137 equivalent. circuit failure.
RE2320 Turbine Building Sump, Scintillation detector/piping, Digital rate meter, 5 x 10-6 Ci/cm3 of Alarm on high radiation, RE5211 valves, and detector housing,10-107 CPM. Cs-137 equivalent. circuit failure.
sump pump discharge to drain.
Radwaste Addition Beta scintillation/dP across Digital rate meter, 5 x 10-6 Ci/cm3 of Alarm on high radiation Vent, RE5711 roughing filter used for flow.10-107 CPM. Xe-133 equivalent. circuit failure; high radiation isolates radwaste addition vent.
Fuel Building Addition Beta scintillation/dP across Digital rate meter, 5 x 10-6 Ci/cm3 of Alarm on high radiation Vent, RE5712 roughing filter used for flow.10-107 CPM. Xe-133 equivalent. circuit failure; high radiation isolates fuel building vent.
RGEMS 2327 Scintillation detectors for beta, Log count rate meter, 1 x 10-6 Ci/cm3 of Alarm, set recorder speed, gamma, ionization recorded; stack flow, Xe-133 equivalent. isolate samples on alert chamber/piping, valves, recorded; sample flow level. Alarm transfer flow filters, sample collection recorded;10-106 CPM beta to upper range on high bottle; discharge to stack (log),10-107 CPM (log), radiation.
inlet. gamma 1-107 mr/h (ion chamber) or 4 x 106 Ci/s digital.
FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND TABLE 11-15 RADIATION PROTECTION Revision 31 Page 4 of 4 PROCESS RADIATION SERVICE AND EQUIPMENT Process Radiation Detection Equipment/ Alarm and Control Monitoring Systems Sampling Equipment Readout Equipment Sensitivity RGEMS RE2325, Scintillation detectors for beta, Digital rate meter 3.9 x 10-7 Ci/cm3 of Alarm, set recorder speed, RE2326 gamma, ionization RIA-2325: 10-106 CPM Xe-133 equivalent. isolate samples on alert chamber/piping, valves, RIA-2326: 10-107 CPM level. Alarm transfer flow filters, sample collection to upper range on high bottle; discharge to stack radiation.
inlet.
Main Steam, RE2323, Geiger-Mueller tube/in lead Digital rate meter 5 x 10-2 Ci/cm3 of Alarm on high radiation.
2324 collimator adjacent to main 10-107 CPM. dose equivalent I-131 steam lines.
FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND TABLE 11-16 RADIATION PROTECTION Revision 21 Page 1 of 2 AREA RADIATION DETECTORS Instrument(a), (b) Range Containment 590' Elev NW Side (b) 10-2-104 Rem/hr Containment 590' Elev SW Side (b) 10-2-104 Rem/hr Containment 590' Elev NE Side (b) 10-2-104 Rem/hr Containment 590' Elev SE Side (b) 10-2-104 Rem/hr East Engineering Safeguards Room 0.1-107 mrem/hr Radwaste Service Corridor 0.1-107 mRem/hr Radwaste Control Area (C-40 Panel) 0.1-107 mrem/hr 2.4 kV Switchgear Room (1C) 0.1-107 mRem/hr Control Lab Corridor 0.1-107 mrem/hr Access Control Station 0.1-107 mrem/hr Outside Cont Personnel Air Lock 607' Elev 0.1-107 mrem/hr Containment Purge Unit Room-North 0.1-107 mrem/hr Radwaste Demineralizer Room Roof 0.1-107 mrem/hr Control Room/Turbine Bldg Corridor 0.1-107 mrem/hr Control Room Entrance 0.1-107 mrem/hr Turbine Floor East Side 0.1-107 mrem/hr Health Physics Offices 0.1-107 mrem/hr Spent Fuel Pool-South 0.1-107 mrem/hr Air Room 590' Elev 0.1-107 mrem/hr Inside of Cont Personnel Air Lock 1.0-107 mrem/hr Containment 649' Elev Rx Cavity 1.0-107 mRem/hr Containment 649' Elev Rx Cavity 1.0-107 mRem/hr Containment Hi range-left channel 1-107 Rem/hr Containment Hi range-right channel 1-107 Rem/hr Decontamination Room 0.1-107 mrem/hr Evaporator "A" 0.1-107 mrem/hr Evaporator "B" 0.1-107 mrem/hr Evaporator Control Panel C-105 0.1-107 mrem/hr Waste Gas Decay Tank T-101, A, B & C 0.1-107 mrem/hr (a) Sensitivity for all instruments except containment detectors has energy dependence of 20% of the actual radiation intensity over a photon energy spectrum of 100 keV to 2.5 MeV (b) Sensitivity for containment detector instruments has an energy dependence of 15% of actual radiation intensity over a photon energy spectrum of 100 keV to 2.5 MeV.
(c) Sensitivity for the radwaste monitor is 30% of the actual intensity over a photon energy spectrum from 80 keV to 1.33 MeV.
FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND TABLE 11-16 RADIATION PROTECTION Revision 21 Page 2 of 2 AREA RADIATION DETECTORS Environmental Lab Entrance 0.1-107 mrem/hr Radwaste Packaging Area-East 0.1-107 mrem/hr Radwaste Packaging Area-West 0.1-107 mrem/hr Radwaste Demineralizer 649' Elev 0.1-107 mrem/hr Steam Dumps Area 0.1-107 mrem/hr Radwaste Monitors (c) Local Readout East Processing Building 1.0-105 mRem/hr East Storage Building 1.0-105 mRem/hr South Storage Building 1.0-105 mRem/hr (Not Used for Radwaste Storage at this time)
(a) Sensitivity for all instruments except containment detectors has energy dependence of 20% of the actual radiation intensity over a photon energy spectrum of 100 keV to 2.5 MeV (b) Sensitivity for containment detector instruments has an energy dependence of 15% of actual radiation intensity over a photon energy spectrum of 100 keV to 2.5 MeV.
(c) Sensitivity for the radwaste monitor is 30% of the actual intensity over a photon energy spectrum from 80 keV to 1.33 MeV.
FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND TABLE 11-17 RADIATION PROTECTION Revision 28 Page 1 of 2 Primary Coolant Fission and Corrosion Product Activities for AST Dose Analyses Nuclide Activity* Nuclide Activity*
(Ci/g) (Ci/g)
Co-58 7.0E-03 Np-239 -
Co-60 8.0E-04 Pu-238 -
Cr-51 4.7E-03 Pu-239 -
Fe-55 1.8E-03 Pu-240 -
Fe-59 4.5E-04 Pu-241 -
Mn-54 2.4E-03 Am-241 -
Kr-85 5.3E-01 Cm-242 -
Kr-85m 1.2E+00 Cm-244 -
Kr-87 7.5E-01 I-130 1.1E-01 Kr-88 2.2E+00 Kr-83m 3.2E-01 Rb-86 1.5E-02 Xe-138 4.7E-01 Sr-89 5.4E-03 Xe-131m 4.5E-01 Sr-90 4.9E-04 Xe-133m 1.7E+00 Sr-91 1.5E-03 Xe-135m 4.8E-01 Sr-92 5.9E-04 Cs-138 7.0E-01 Y-90 6.4E-04 Cs-134m 4.6E-02 Y-91 1.8E-02 Rb-88 2.3E+00 Y-92 7.2E-04 Rb-89 5.8E-02 Y-93 4.4E-04 Sb-124 1.1E-03 Zr-95 1.2E-03 Sb-125 9.2E-03 Zr-97 4.9E-04 Sb-126 6.2E-04 Nb-95 1.2E-03 Te-131 1.5E-02 Mo-99 4.2E+00 Te-133 6.1E-03 Tc-99m 3.2E+00 Te-134 2.1E-02 Ru-103 1.2E-03 Te-125m 2.0E-03 Ru-105 1.4E-04 Te-133m 1.2E-02 Ru-106 5.3E-04 Ba-141 9.1E-05 Rh-105 5.5E-04 Ba-137m 2.5E+01 Sb-127 4.3E-02 Pd-109 -
Sb-129 2.4E-02 Rh-106 5.3E-04 Te-127 4.6E-02 Rh-103m 1.2E-03 Te-127m 7.2E-03 Tc-101 1.5E-02 Te-129 3.8E-02 Eu-154 -
Te-129m 2.2E-02 Eu-155 -
Te-131m 3.7E-02 Eu-156 -
Te-132 4.8E-01 La-143 1.1E-05 I-131 5.2E+00 Nb-97 8.1E-05 I-132 1.2E+00 Nb-95m 8.5E-06
FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND TABLE 11-17 RADIATION PROTECTION Revision 28 Page 2 of 2 Primary Coolant Fission and Corrosion Product Activities for AST Dose Analyses Nuclide Activity* Nuclide Activity*
(Ci/g) (Ci/g)
I-133 5.4E+00 Pm-147 1.2E-04 I-134 4.7E-01 Pm-148 1.7E-04 I-135 2.3E+00 Pm-149 3.0E-04 Xe-133 7.0E+01 Pm-151 8.3E-05 Xe-135 7.4E+00 Pm-148m 2.6E-05 Cs-134 4.9E+01 Pr-144 9.3E-04 Cs-136 4.3E+00 Pr-144m 1.6E-05 Cs-137 2.6E+01 Sm-153 -
Ba-139 4.3E-04 Y-94 1.4E-05 Ba-140 7.1E-03 Y-95 8.6E-06 La-140 3.4E-03 Y-91m 8.9E-04 La-141 2.4E-04 Br-82 2.5E-02 La-142 6.8E-05 Br-83 6.6E-02 Ce-141 1.1E-03 Br-84 2.7E-02 Ce-143 6.3E-04 Am-242 -
Ce-144 9.3E-04 Np-238 -
Pr-143 1.0E-03 Pu-243 -
Nd-147 4.3E-04 Activities based on 1% failed fuel. Listed activities are adjusted to Technical Specification limits for performance of AST dose calculations.