ML20189A099
Text
Oconee Nuclear Station UFSAR Appendix 11A. Tables Appendix 11A. Tables
Oconee Nuclear Station UFSAR Table 11-1 (Page 1 of 1)
(31 DEC 2000)
Table 11-1. Potential Radioactive Waste Quantities from Three Units Waste Source Quantity/Year(1)
(ft.3)
Assumptions & Comments Reactor Coolant System Startup Expansion 39,800 Four cold startups per unit Startup Dilution 49,000 One startup from cold condition at beginning of cycle, 77.5, 155 and 232.5 full power days, respectively, per unit Lifetime Shim Bleed 43,800 Dilution 1070 to 180 ppm boron in each unit System Drain 18,300 Drain of each unit to level of outlet nozzles during refueling Liquid Waste Primary System 161,019 3300 gal/day Rate of Input Spent Fuel Pool 26,349 540 gal/day Rate of Input Cask Decontamination 17,566 360 gal/day Rate of Input Component Coolant 17,566 360 gal/day Rate of Input Service Water 58,553 1200 gal/day Rate of Input Decontamination Room 87,828 1800 gal/day Rate of Input Resin Sluice 23,421 480 gal/day Rate of Input Miscellaneous System Leakage 351,312 5 gal/min Rate of Input OTSG Tube Leaks 40,140 1 Tube Leak/Unit/yr => 1 Vol Drain + 3 Flush Vols of Secondary Side LHST 161,019 3300 gal/day Rate of Input Gaseous Waste Waste Gas 131,400 Solid Waste Spent Bead Resins 2,000 Spent Powdex Resin 5,000 Note:
- 1. Quantities based on data gathered at ONS for years 1977 and 1978, and values found in Evaluation of compliance with 10CFR50 Appendix I, June 4, 1976. Actual amounts vary from year to year depending on unit operating history. The actual liquid waste generated is reported in the Oconee Annual Effluent Report. The actual gaseous waste activity that is released is reported in the Oconee Annual Effluent Release Report.
Oconee Nuclear Station UFSAR Table 11-2 (Page 1 of 1)
(31 DEC 2000)
Table 11-2. Estimated Maximum Rate of Accumulation Radioactive Wastes Per Operation Waste Source Maximum Rate of Accumulation Assumptions and Comments Reactor Coolant System(1)
Startup Expansion &
Dilution 9900 ft3/22 hrs Cold startup immediately prior to placing deborating demineralizers into service Lifetime Shim Bleed(2) 1200 ft3/10 days Last 10 days of processing bleed prior to placing deborating demineralizers into service System Drain 6100 ft3/refueling Liquid Waste Demineralizers Sluice 100 ft3/resin change One change of purification demineralizer resin Deborating Demineralizer Regeneration and Rinse 65 ft3/resin change One change of deborating demineralizer resin Gaseous Waste Off-Gas from Reactor Coolant System(2) 400 ft3/22 hrs Cold startup immediately prior to placing deborating demineralizers into service Letdown Storage Tank 900 ft3/purge Pressurizer 60 ft3/purge Solid Waste Demineralizer Resin 50 ft3/resin change One change of purification demineralizer resin Note:
- 1. Treated as waste for purpose of evaluation
- 2. Wastes processed through holdup tanks
- 3. This table includes estimated values and is not updated (Reference OSC-256). Total effluent quantities are reported in the Annual Radioactive Effluent Release Report in accordance with SLC 16.11.9, "Radiological Effluents Control".
Oconee Nuclear Station UFSAR Table 11-3 (Page 1 of 1)
(31 DEC 2000)
Table 11-3. Yearly Average Activity Concentrations in the Station Effluent for Three Units, Each Operating with One Percent Defective Fuel Liquid Waste Operation Yearly Average Concentration in Tailrace Discharge Fraction of MPC Lifetime Shim Bleed Including Startup Expansion and Dilution 0.077 Discharge of Miscellaneous Wastes 0.16 Gaseous Wastes Operation Yearly Average Concentration at Site Boundary, Fraction of MPC Lifetime Shim Bleed 0.058 Startup Expansion and Dilution 0.18 Venting of Letdown Storage Tank 0.015 Venting of Pressurizer 0.011 Reactor Building Purge 0.11 Steam Generator Tube Leakage of 1 gal/min in one unit 0.089 Note:
- 1. This table includes estimated values and is not updated (Reference OSC-256). Total effluent quantities are reported in the Annual Radioactive Effluent Release Report in accordance with SLC 16.11.9, "Radiological Effluents Control".
Oconee Nuclear Station UFSAR Table 11-4 (Page 1 of 1)
(31 DEC 2004)
Table 11-4. Escape Rate Coefficients for Fission Product Release Element Escape Rate Coefficient, sec-1 Xe 1.0 x 10-7 Kr 1.0 x 10-7 I
2.0 x 10-8 Br 2.0 x 10-8 Cs 2.0 x 10-8 Rb 2.0 x 10-8 Mo 4.0 x 10-9 Te 4.0 x 10-9 Sr 2.0 x 10-10 Ba 2.0 x 10-10 Zr 1.0 x 10-11 Ce, and other rare earths 1.0 x 10-11 Note:
- 1. This table is included for historical purposes only (Reference OSC-256).
Oconee Nuclear Station UFSAR Table 11-5 (Page 1 of 2)
(31 DEC 2000)
Table 11-5. Reactor Coolant Activity (Calculated)
µCi/ml at Operating Conditions Time, Full Power Days Isotope 100 150 200 260 310 Kr 85 m 1.5 1.5 1.5 1.5 1.5 Kr 85 8.7 9.7 9.1 6.3 1.3 Kr 87
.85
.85
.85
.85
.84 Kr 88 2.7 2.7 2.7 2.7 2.7 Rb 88 2.7 2.7 2.7 2.7 2.7 Sr 89
.041
.041
.041
.041
.038 Sr 90
.0027
.0028
.0030
.0032
.0031 Sr 91
.046
.046
.046
.046
.045 Sr 92
.017
.017
.017
.017
.017 Xe 131m 2.3 2.2 2.2 2.1 1.2 Xe 133m 2.8 2.8 2.8 2.8 2.3 Xe 133 248 246 242 234 166 Xe 135m
.94
.94
.94
.94
.93 Xe 135 6.6 6.6 6.6 6.6 6.3 Xe 138
.51
.51
.51
.51
.51 I 131 3.2 3.2 3.2 3.2 3.0 I 132 4.8 4.8 4.7 4.6 3.8 I 133 3.8 3.8 3.8 3.8 3.7 I 134
.50
.50
.50
.50
.50 I 135 1.9 1.9 1.9 1.9 1.9 Cs 136
.045
.045
.045
.045
.042 Cs 137
.29
.29
.29
.28
.26 Cs 138
.72
.72
.72
.72
.72 Mo 99 5.4 5.4 5.3 5.2 4.2 Ba 139
.082
.082
.082
.082
.082 Ba 140
.072
.072
.072
.072
.067 La 140
.025
.025
.025
.025
.022 Y 90
.24
.37
.51
.69
.84 Y 91
.18
.20
.20
.17
.076
Oconee Nuclear Station UFSAR Table 11-5 (Page 2 of 2)
(31 DEC 2000)
Ca 144
.0028
.0029
.0029
.0030
.0028 Bleed Rate in Reactor Coolant volume/sec 6.7x10-8 5.7x10-8 7.8x10-8 1.3x10-7 5.1x10-7 (Experimental)
Nuclide Concentration (µCi/cc)1 H 3 2.1 F 18 7.8 (-2)(3)
Na 24 2.0 (-2)
Ar 41 8.9 (-2)
Mn 54 4.1 (-3)
Mn 56 1.9 (-2)
Co 58 7.8 (-3)
Kr 85m 1.6 (-2)
Kr 87 1.4 (-2)
Kr 88 2.2 (-2)
Sr 89 3.6 (-5)
Sr 90 7.3 (-5)
I 131 1.2 (-2)
I 132 7.5 (-2)
I 133 3.7 (-2)
I 134 1.4 (-1)
I 135 7.5 (-2)
Xe 131m 2.1 (-2)
Xe 133 3.1 (-1)
Xe 133m 4.1 (-3)
Xe 135 9.4 (-2)
Cs 134 2.0 (-3)
Cs 137 2.1 (-3)
Ba 139 1.5 (-2)
Note:
- 1. Concentrations obtained from reactor coolant sample of Unit 1 October 9, 1975
- 2. This table is included for historical purposes only (Reference OSC-256)
- 3. Denotes power of 10
Oconee Nuclear Station UFSAR Table 11-6 (Page 1 of 7)
(31 DEC 2012)
Table 11-6. Waste Disposal System Component Data (Component Quantities for Three Units)
Low Activity Waste Tank Quantity 2
Volume each, cu. ft 398 Material Concrete with Stainless Steel Liner High Activity Waste Tank Quantity 2
Volume each, cu. ft.
262 Material Concrete with Stainless Steel Liner Misc. Waste Holdup Tank Quantity 2
Volume each, cu. ft 2,700 for Units 1 and 2 shared 1,550 for Unit 3 Material Carbon Steel with Stainless Clad Design Pressure Vessel Full Plus 10 ft. Hydro Head Spent Resin Storage Tank Quantity 2
Volume each, cu. ft.
450 for Units 1 and 2 shared 380 for Unit 3 Material Stainless Steel High Activity Spent Resin Storage Tank Quantity 1 for Unit 3 Volume, cu. ft.
380 Material Stainless Steel Reactor Building Normal Sump Quantity 3
Volume each, cu. ft.
48 (excluding embedded piping)
Material Concrete Reactor Building Emergency Sump Quantity 3
Volume each, cu. ft.
540 Material Concrete GWD Tank Quantity 4
Oconee Nuclear Station UFSAR Table 11-6 (Page 2 of 7)
(31 DEC 2012)
Volume each, cu. ft.
1,098 Material Carbon Steel Design Pressure, psig 100 Misc. Waste Evaporator Feed Tank(3)
Quantity 1
Volume, cu. Ft.
400 Material Stainless Steel Design Pressure Vessel Full Plus 10 ft. Hydro Head Waste Evaporator(3)
Quantity 1
Process Rates, lb/hr 5,060 Material Stainless Steel Design Pressure, psig 15 Low Activity Waste Tank Pump Quantity 4
Capacity each, gal/min 100 Diff. Head, ft.
200 High Activity Waste Tank Transfer Pump Quantity 4
Capacity each, gal/min 50 Diff. Head, ft.
200 Misc. Waste Transfer Pump Quantity 4
Capacity each, gal/min 50 Diff. Head, ft.
200 HISTORICAL INFORMATION NOT REQUIRED TO BE REVISED Spent Resin Sluicing Pump Quantity 2
Capacity each, gal/min 50 Diff. Head, ft.
50 Spent Resin Transfer Pump Quantity 2
Capacity each, gal/min 10 Diff. Head, ft.
100
Oconee Nuclear Station UFSAR Table 11-6 (Page 3 of 7)
(31 DEC 2012)
Reactor Building Normal Sump Pump Quantity 6
Capacity each, gal/min 25 Diff. Head, ft.
25 Waste Evaporator Feed Pump(3)
Quantity 1
Capacity, gal/min 7-1/2 Diff. Head, ft.
60 Waste Evaporator Recirculating Pump(3)
Quantity 1
Capacity, gal/min 160 Diff. Head, ft.
53 Waste Evaporator Distillate Pump(3)
Quantity 1
Capacity, gal/min 9-1/2 Diff. Head, ft(4) 62 GWD Filter Quantity 2
Rating, scfm 200 Type Prefilter, Absolute and Charcoal Material 11 Gauge Galvanized Steel GWD Exhauster Quantity 2
Rating, scfm 200 at 6 in. Water Gauge External Static Pressure Type Backward Curved - Centrifugal GWD Compressor Quantity 4
Capacity each, cfm 48 at 85 psig Type Centrifugal Displacement Interim Evaporator Feed Tanks(3)
Quantity 2
Volume, gal 17,000 Design Pressure Static head plus 5 psig
Oconee Nuclear Station UFSAR Table 11-6 (Page 4 of 7)
(31 DEC 2012)
Design Temperature, °F 200 Material 304 stainless steel Interim Evaporator Condensate Monitor Tanks(3)
Quantity 2
Volume, gal 9,000 Design Pressure Static head plus 5 psig Design Temperature, °F 200 Material 304 stainless steel Interim Evaporator Concentrates Storage Tank(3)
Quantity 1
Volume, gal 3,000 Design Pressure Static head plus 5 psig Design Temperature, °F 200 Material 304 stainless steel Interim Evaporator Condensate Return Tank(3)
Quantity 1
Receiver volume, gal 100 Design Pressure Atmospheric Design Temperature, °F 212 No. of Pumps 2
Design Flow, gal/min 25 Design Head, ft 65 Interim Evaporator Feed Filter(3)
Quantity 1
Type Cage Assembly (disposable synthetic cartridged)
Design Pressure, psig 200 Design Temperature, °F 250 Design Flow Rate, gal/min 35 Pressure Drop at Design Flow, psi Clean - 5 Fouled - 20 Retention of 25 Microns particles 98%
Material Stainless Steel Interim Evaporator Condensate Filter(3)
Oconee Nuclear Station UFSAR Table 11-6 (Page 5 of 7)
(31 DEC 2012)
Quantity 1
Type Cage Assembly (disposable synthetic cartridge)
Design Pressure, psig 300 Design Temperature, °F 250 Design Flow Rate, gal/min 150 Pressure Drop at Design Flow, psi Clean - 5 Fouled - 20 Retention of 25 Micron Particles 98%
Material Stainless Steel Interim Evaporator Condensate Demineralizer(3)
Quantity 1
Type Non-regenerable Design Temperature, °F 200 Design Pressure, psig 150 Vessel Volume, ft3 55 Resin Volume, ft3 50 Design Flow, gal/min 310 Material Stainless Steel Resin Type Mixed bed Interim Evaporator Feed Pump(3)
Quantity 1
Type Canned centrifugal Design Flow, gal/min 35 Design Head, ft 250 Design Pressure, psig 150 Design Temperature, °F 200 Operating Temperature, °F 120 Material Stainless Steel Interim Condensate Monitor Tank Pumps(3)
Quantity 2
Type Canned centrifugal Design Flow, gal/min 100 Design Head, ft 250 Design Pressure, psig 150
Oconee Nuclear Station UFSAR Table 11-6 (Page 6 of 7)
(31 DEC 2012)
Design Temperature, °F 200 Operating Temperature, °F 120 Material Stainless Steel Interim Evaporator Concentrates Transfer Pump(3)
Quantity 1
Type Canned centrifugal Design Flow, gal/min 35 Design Head, ft 250 Design Pressure, psig 150 Design Temperature, °F 200 Operating Temperature, °F 170 Material Stainless Steel Low Activity Equipment Drains Sump Pumps Quantity 2
Type Vertical Design Flow, gal/min 50 Design Head, ft 100 Material Stainless Steel High Activity Equipment Drains Sump Pumps Quantity 2
Type Vertical Design Flow, gal/min 50 Design Head, ft 100 Material Stainless Steel Interim Evaporator Distillate Pump(3)
Quantity 1
Type Canned Centrifugal Design Flow, gal/min 15.6 Design Head, ft 208 Design Pressure, psig 150 Design Temperature, °F 220 Operating Temperature, °F 80-110 Material Stainless Steel
Oconee Nuclear Station UFSAR Table 11-6 (Page 7 of 7)
(31 DEC 2012)
Interim Waste Evaporator Package (Westinghouse)
Quantity 1
Nominal Capacity, gal/min 15 Steam Supply Pressure, psig 50 Steam Flow, lb/hr 10,500 Cooling Water Flow, gal/min 780 Concentrates Batch Volume, gal 500 Max. Boron Concentration, ppm 21,000 Liquid DF(1) 106 Gaseous DF(2) 105 Interim GWD Tanks Quantity 3
Volume, ft3 1070 Design Pressure, psig 100 Design Temperature, °F Material 200 Carbon steel Notes:
- 1. DF for liquid =
distillate in activity es concentrat in activity
- 2. DF for gas =
distillate in activity feed in activity
- 3. Component is in a layup condition.
- 4. Waste Evaporator Distillate Pump data included for historical purposes only.
Oconee Nuclear Station UFSAR Table 11-7 (Page 1 of 4)
(31 DEC 2004)
Table 11-7. Process Radiation Monitors Channel Number and Function Type Detector MDC (Background Equivalent Concentration) and Sensitivity Range (Monitor Readout)
RIA-31 Monitors LPSW (Multipoint)
NaI 1-1/2"D x 1"L 4" Pb shield 2.5 mR/hr = 1.6 x 10-7 µCi/ml 1.28 x 108 cpm/µCi/ml (10-107 cpm)
RIA-32 3RIA-32 Aux. Bldg. Gas Monitor Plastic beta Scint.
2.125"D x.01"T 3" Pb shield 2.5 mR/hr = 3.6 x 10-7 µCi/ml 2.94 x 107 cpm/µCi/ml (10-107 cpm)
RIA-33 Waste Disposal (Normal)
NaI 11/2"D x 1"L 4" Pb Shield 2.5 mR/hr = 6.2 x 10-8 µCi/ml 1.28 x 108 cpm/µCi/ml (10-107 cpm) 1RIA-35 2RIA-35 3RIA-35 Total LPSW Discharge Header from Aux. Bldg.
NaI 1-1/2"D x 1"L 5" Pb Shield 2.5 mR/hr = 6.2 x 10-8 µCi/ml 1.28 x 108 cpm/µCi/ml (10-107 cpm)
RIA-37 3RIA-37 Waste Disposal Gas (Normal)
Plastic beta scint.
2"D x 0.007"T 4" Pb shield 2.5 mR/hr = 1.34 x 10-2 µCi/ml 2.38 x 107 cpm/µCi/ml (10-107 cpm)
RIA-38 3RIA-38 Waste Disposal Gas (High)
G.M.
4"Pb shield 2.5 mR/hr = 1.34 x 10-2 µCi/ml 7.47 x 102 cpm/µCi/ml (10-106 cpm)
RIA-39 3RIA-39 Control Room Gas Plastic beta scint.
2.125"D x.01"T 3" Pb shield 2.5 mR/hr = 3.6E-7 µCi/m 2.94 x 107 cpm/µCi/ml (10-107 cpm) 1RIA-40 2RIA-40 3RIA-40 Condenser Air Ejector off gas Plastic beta scint.
2.125"D x.01"T 3" Pb shield 2.5mR/hr = 3.6E-7 µCi/ml 2.94 x 107 cpm/µCi/ml (10-107 cpm)
Oconee Nuclear Station UFSAR Table 11-7 (Page 2 of 4)
(31 DEC 2004)
Channel Number and Function Type Detector MDC (Background Equivalent Concentration) and Sensitivity Range (Monitor Readout)
RIA-41 3RIA-41 Spent Fuel Bldg. Gas Plastic beta scint.
2.125"D x.01"T 3" Pb shield 2.5 mR/hr = 3.6E-7 µCi/ml 2.94 x 107 cpm/µCi/ml (10-107 cpm)
RIA-42 3RIA-42 Recirculating Cooling Water NaI 1-1/2"D x 1"L 4" Pb lead 2.5 mR/hr = 1.6 x107µCi/ml 1.28 x 108 cpm/µCi/ml (10-107 cpm) 1RIA-43 2RIA-43 3RIA-43 Unit Vent Particulates Plastic beta scint.
1-1/8" x 5/8" x.01"T 2.5" Pb shield 2.5 mR/hr = 7.0 x 10-12 µCi/ml (2 SCFM Flow) 3.31 x 1010 cpm/µCi/ml (10-107 cpm) 1RIA-44 2RIA-44 3RIA-44 Unit Vent Iodine NaI 2"D x 2"L 3" Pb shield 2.5 mR/hr = 3.1 x 10-11 µCi/ml (2 SCFM Flow) 2.72 x 109 cpm/µCi/ml (10-1E7 cpm) 1RIA-45 2RIA-45 3RIA-45 Unit Vent Gas (Normal)
Plastic beta scint.
2"D x.01"T 3" Pb shield 2.5 mR/hr = 5.5 x 10-7 µCi/ml 1.41 x 107 cpm/µCi/ml (10-1E7 cpm) 4RIA-45 Radwaste Facility Vent (Normal)
Plastic beta scint.
2"D x.01"T 5" Pb shield 5 mR/hr = 5.5 x 10-7 µCi/ml Ci/ml 1
2E to 7
2E
~
µ
Xe-133 (readout in µCi/ml) 1RIA-46 2RIA-46 3RIA-46 Unit Vent Gas (High)
Cadmium Telluride (CdTe) 2mm x 5mm x 2mm T 2" Pb shield 3.5 mR/hr = 1.1E-3 µCi/ml 3.15 x 103 cpm/µCi/ml (10-1E7 cpm)
Deleted row per 2002 Update
Oconee Nuclear Station UFSAR Table 11-7 (Page 3 of 4)
(31 DEC 2004)
Channel Number and Function Type Detector MDC (Background Equivalent Concentration) and Sensitivity Range (Monitor Readout) 1RIA-47 2RIA-47 3RIA-47 Reactor Building Particulate Plastic beta scint.
1 1/8" x 5/8" x.01"T 2.5" Pb shield 2.5 mR/hr=7.0 x 10-12 µCi/ml (3 SCFM Flow) 3.31 x 1010 cpm/µCi/ml (10-1E7 cpm) 1RIA-48 2RIA-48 3RIA-48 Reactor Building Iodine NaI 2"D x 2"L 3" Pb shield 2.5 mR/hr=3.1 x 10-11 µCi/ml (3 SCFM Flow) 2.72 x 109 cpm/µCi/ml (10-1E7 cpm) 1RIA-49 2RIA-49 3RIA-49 Reactor Building Gas Plastic Beta Scint.
2"D x.01"T 3" Pb shield 2.5 mR/hr=5.5 x 10-7 µCi/ml 1.41 x 107 cpm/µCi/ml (10-1E7 cpm) 1RIA-49A 2RIA-49A 3RIA-49A Reactor Building Gas (High)
Cadmium Telluride (CdTe) 2mm x 5mm x 2mm T 2" Pb shield 3.5 mR/hr=1.1E-3 µCi/ml 3.15 x 103 cpm/µCi/ml (10-1E7 cpm) 1RIA-50 2RIA-50 3RIA-50 Component Cooling Water NaI 1-1/2"D x 1"L 4" Pb shield 2.5 mR/hr = 1.6 x 10-7µCi/ml 1.28 x 108 cpm/µCi/ml (10-107 cpm)
RIA-53 Interim Radwaste Bldg.
Vent Gas Plastic Beta Scint.
2.125"D x 0.01"T 3" Pb shield 2.5 mR/hr = 3.6 x 10-7 µCi/ml 2.94 x 107 cpm/µCi/ml (10-107 cpm)
RIA-54 Turbine Bldg. Sump 3RIA-54 Turbine Bldg. Sump NaI Scint.
1-11/2"D x 1"L 4" Pb shield 2.5 mR/hr=1.6 x 10-7 µCi/ml 1.28 x 108 cpm/µCi/ml 10-107 cpm
Oconee Nuclear Station UFSAR Table 11-7 (Page 4 of 4)
(31 DEC 2004)
Channel Number and Function Type Detector MDC (Background Equivalent Concentration) and Sensitivity Range (Monitor Readout) 1RIA-16 1RIA-17 2RIA-16 2RIA-17 3RIA-16 3RIA-17 Steam Header Gross Activity G. M. Detector (Low Range)/
3.2"D x 6.6"L Ion Chamber (High Range) 2.5"D x 9.2"L 3" Pb shield 500 cpm/mR/hr 1.2 E-10 Amp/R/hr 0.01-103 mR/hr 102-107 mR/hr 1RIA-56 2RIA-56 3RIA-56 Unit Vent Gas(High High)
Ion Chamber unshielded 1 x 10-11 amp/R/hr 1-108 R/hr 1-108 R/hr 1RIA-57 2RIA-57 3RIA-57 1RIA-58 2RIA-58 3RIA-58 Reactor Building Gas(High High)
Coaxial Ion Chamber unshielded 1 x 10-11 amp/R/hr 1-108 R/hr(1) 1RIA-59 1RIA-60 2RIA-59 2RIA-60 3RIA-59 3RIA-60 Steam Header N-16 NAI(Tl) Scintillation unshielded Not applicable to N-16 Monitors Configurable 0-1000 gallons/day Note:
- 1. RIAs 57/58 are on-scale at approximately 1R/hr.