ML20309A745
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McGuire Nuclear Station UFSAR Appendix 11A. Tables Appendix 11A. Tables
McGuire Nuclear Station UFSAR Table 11-1 (Page 1 of 2)
Table 11-1. Parameters Used in the Calculation of Reactor Coolant Fission Product Activities During Normal Operation
- 1. Ultimate core thermal power, MWt 3636
- 2. Clad defects, as a percent of rated core thermal power being generated by rods with clad defects 0.12
- 3. Reactor coolant liquid mass, lbm 4.62 x 105
- 4. Reactor coolant full power average temperature, °F 590
- 5. Purification flow rate (normal) gpm 75
- 6. Effective cation demineralizer flow, gpm 3.0
- 7. Volume control tank volumes
- a. Vapor, ft3 240 3
- b. Liquid, ft 160
- 8. Fission product escape rate coefficients: 1 a) Noble gas isotopes, sec-1 6.5 x 10-8 b) Br, Rb, 1 and Cs isotopes, sec-1 1.3 x 10-8 c) Te isotopes, sec-1 1.0 x 10-9 d) Mo isotopes, sec-1 2.0 x 10-9 e) Sr and Ba isotopes, sec-1 1.0 x 10-11 f) Y, La, Ce, Pr isotopes, sec-1 1.6 x 10-12
- 9. Volume Control Tank noble gas stripping factors 2 Isotope Stripping Fraction Kr-85 2.3 x 10-1 Kr-85m 2.7 x 10-1 Kr-87 6.0 x 10-1 Kr-88 4.3 x 10-1 Xe-131m 1.0 x 10-2 (14 APR 2005)
McGuire Nuclear Station UFSAR Table 11-1 (Page 2 of 2)
Xe-133 1.6 x 10-2 Xe-133m 3.7 x 10-2 Xe-135 1.8 x 10-1 Xe-135m 8.0 x 10-1 Xe-138 1.0
- 10. Boron Concentration and Reduction Rates
- a. Bo (initial cycle) 805 ppm B' (initial cycle) 2.1 ppm/day
- b. Bo (equilibrium cycle) 1080 ppm B' (equilibrium cycle) 3.9 ppm/day
- 11. Pressurizer Volumes
- a. Vapor 720 ft3
- b. Liquid 1080 ft3
- 12. Spray Line Flow 1.0 gpm
- 13. Pressurizer Stripping Fractions 1.0
- a. Noble gases
- b. All other elements Note:
- 1. Escape rate coefficients are based on Westinghouse Fuel defect tests performed at the Saxton reactor. Recent experience at two plants operating with fuel rod defects has verified the listed escape rate coefficients.
- 2. Volume control tank purge rate is 0.7 scfm.
Volume control tank stripping efficiency is 40 percent.
(14 APR 2005)
McGuire Nuclear Station UFSAR Table 11-2 (Page 1 of 1)
Table 11-2. Design Basis Tritium Production for One Unit Expected Release to Reactor Tritium Source Total Produced (curies/yr) Coolant (curies/yr)
Ternary Fission 10500 1050 Burnable Poison Rods (Initial Cycle) 1520 152 Soluble Boron (Initial Cycle) 222 222 (Equilibrium Cycle) 309 309 Lithium and Deuterium Reactions 110 110 Total Initial Cycle 12352 1540 Total Equilibrium Cycle 10919 1470 Basis:
Power Level 3565 MWt Load Factor 0.8 Release Fraction from Fuel 10%
Release Fraction from Burnable Poison Rods 10%
Burnable Poison Rod B-10 Mass 6160 gpm Reactor Coolant Boron Concentration (Initial Cycle) 860 ppm Reactor Coolant Boron Concentration (Equilibrium Cycle) 1200 ppm (14 OCT 2000)
McGuire Nuclear Station UFSAR Table 11-3 (Page 1 of 2)
Table 11-3. Reactor Coolant Fission and Corrosion Product Activities During Normal Operation Activity Activity Isotope (µCi/gm) Istope (µCi/gm)
H-3 1.0 Cs-134 2.8 x 10-2 Br-83 5.9 x 10-3 I-135 2.3 x 10-1 Br-84 3.3 x 10-3 Cs-136 1.5 x 10-2 Br-85 3.8 x 10-4 Cs-137 2.0 x 10-2 Rb-86 9.5 x 10-5 Ba-137m 2.0 x 10-2 Rb-88 2.5 x 10-1 Ba-140 2.4 x 10-4 Sr-89 3.7 x 10-4 La-140 1.7 x 10-4 Sr-90 1.1 x 10-5 Ce-141 7.4 x 10-5 Y-90 1.3 x 10-6 Ce-143 4.4 x 10-5 Sr-91 7.6 x 10-4 Pr-143 5.3 x 10-5 Y-91m 4.5 x 10-4 Ce-144 3.5 x 10-5 Y-91 6.8 x 10-5 Pr-144 4.2 x 10-5 Y-93 4.0 x 10-5 Cr-51 2.0 x 10-3 Zr-95 6.4 x 10-5 Mn-54 3.3 x 10-4 Nb-95 5.3 x 10-5 Fe-55 1.7 x 10-3 Mo-99 9.1 x 10-2 Fe-59 1.1 x 10-3 Tc-99m 5.7 x 10-2 Co-58 1.7 x 10-2 Ru-103 4.8 x 10-5 Co-60 2.1 x 10-3 Rh-103m 5.6 x 10-5 Kr-83m 2.2 x 10-2 Ru-106 1.1 x 10-5 Kr-85m 9.3 x 10-2 Rh-106 1.3 x 10-5 Kr-85 2.2 x 10-3 Te-125m 3.1 x 10-5 Kr-87 6.7 x 10-2 Te-127m 3.0 x 10-4 Kr-88 1.9 x 10-1 Te-127 9.9 x 10-4 Kr-89 6.3 x 10-3 Te-129 2.0 x 10-3 Xe-131m 5.6 x 10-3 I-130 2.4 x 10-3 Xe-133m 4.1 x 10-2 Te-131m 2.8 x 10-2 Xe-133 1.7 Te-131 1.4 x 10-3 Xe-135m 1.6 x 10-2 I-131 2.9 x 10-1 Xe-135 2.2 x 10-1 Te-132 2.9 x 10-2 Xe-137 1.1 x 10-2 (14 OCT 2000)
McGuire Nuclear Station UFSAR Table 11-3 (Page 2 of 2)
Activity Activity Isotope (µCi/gm) Istope (µCi/gm)
I-132 1.2 x 10-1 Xe-138 5.4 x 10-2 I-133 4.3 x 10-1 I-134 5.9 x 10-2 (14 OCT 2000)
McGuire Nuclear Station UFSAR Table 11-4 (Page 1 of 1)
Table 11-4. Maximum Anticipated Reactor Coolant Fission and Corrosion Product Activities During Operation Activity Activity Isotope (µCi/gm) Istope (µCi/gm)
H-3 3.5 Cs-136 0.15 Br-84 4.3 x 10-2 Cs-137 1.5 Rb-88 3.7 Cs-138 0.98 Rb-89 1.1 x 10-1 Ba-140 4.3 x 10-3 Sr-89 3.3 x 10-3 La-140 1.5 x 10-3 Sr-90 1.7 x 10-4 Ce-144 3.4 x 10-4 Sr-91 1.9 x 10-3 Pr-144 3.4 x 10-4 Sr-92 7.4 x 10-4 Kr-85 8.8
-4 Y-90 2.0 x 10 Kr-85m 2.1 Y-91 6.1 x 10-3 Kr-87 1.2 Y-92 7.2 x 10-4 Kr-88 3.7 Zr-95 7.0 x 10-4 Xe-131m 1.9 Nb-95 6.9 x 10-4 Xe-133 2.81 x 102 Mo-99 5.3 Xe-133m 3.1 I-131 2.5 Xe-135 6.3 I-132 0.9 Xe-135m 0.7 I-133 4.0 Xe-138 0.7 I-134 0.6 Cr-51 2.0 x 10-3 I-135 2.2 Mn-54 7.9 x 10-4 Te-132 0.26 Mn-56 3.0 x 10-2 Te-134 2.9 x 10-2 Co-58 2.6 x 10-2 Cs-134 0.3 Co-60 2.1 x 10-3 Note:
- 1. Based on operation with defects in cladding of rods generating 1 percent of the core rated power and with the Waste Gas System removed from service.
(05 APR 2011)
McGuire Nuclear Station UFSAR Table 11-5 (Page 1 of 1)
Table 11-5. Parameters Used in Calculating Main Steam Iodine Concentrations Fuel Defect Fraction 0.12%
Primary to Secondary Leak Rate 100 lbs/day Steam Generator Water Mass 88,000 lbs/generator Steam Generator Blowdown Rate 45,000 lbs/hr.
Steam Generator Internal Partition Factor for 0.01 Iodine Secondary System Demineralizer Iodine 10 Decontamination Factor (DF)
(14 OCT 2000)
McGuire Nuclear Station UFSAR Table 11-6 (Page 1 of 1)
Table 11-6. Main Steam Iodine Concentrations Resulting From Steam Generator Tube Leak Concentration Isotope (Microcuries/gram)
I-131 9.7 x 10-8 I-132 2.9 x 10-8 I-133 1.3 x 10-7 I-134 5.8 x 10-9 I-135 5.8 x 10-8 (14 OCT 2000)
McGuire Nuclear Station UFSAR Table 11-7 (Page 1 of 2)
Table 11-7. Design Basis Source Strengths for Radioactive Waste Systems Input Streams The following list is an explanation of source strengths for various effluent streams.
[HISTORICAL INFORMATION NOT REQUIRED TO BE REVISED]
X X: Maximum anticipated nuclide concentration (Table 11-3)
Y Y: Normal operational nuclide concentration (Table 11-4)
Flag Letter Source Strength A Reactor coolant containing fission and corrosion products B Reactor coolant downstream of mixed-bed demineralizer C Reactor coolant downstream of mixed-bed and cation-bed demineralizers D Reactor coolant, demineralized, gas-stripped (see Volume Control Tank Activities -
Table 11-8)
E Reactor coolant, fully degassed F Reactor coolant, fully degassed, diluted with other leakage (drain header, dilution factor = 1/50)
G Reactor coolant, diluted with other leakage (flush header, factor = 1/50)
H Reactor coolant, degassed, evaporated (DF = 1000)
I Reactor coolant, degassed demineralized, diluted 1/4.8 (Refueling water storage tank)
J Reactor coolant, degassed, demineralized, diluted 1/4.8 (Refueling mode)
K Reactor coolant, design basis LOCA sump L Reactor coolant, degassed, demineralized, diluted 1/8 (Fuel pool water)
M Fuel Pool water, demineralized (Fuel Pool demineralizers effluent)
N Evaporator concentrates, nonrecyclable (see Table 11-29 and Table 11-31, see Section 11.5.2 for inputs)
O Demineralizer resins (1 part combined resins plus 2 parts sluice water (spent resin conc. from Table 11-29 divided by factor of 3, see Section 11.5.2 for inputs)
P Demineralizer resin sluice water return (equal to Flag A)
Q Waste Gas Tank (normal) (See Table 11-18 and divide by tank volume of 600 Ft.3 for concentration)
R Secondary side activity caused by steam generator tube leak (See Table 11-9)
S Mixing and settling tank sludge (equal to Flag F)
T Liquid waste systems tanks vent header (vapor)
U Containment ventilation unit condensate drains V Spent resins (combined and decayed for 6 months assuming demineralizer resins replaced once per year - See Table 11-31 and Section 11.5.4)
(05 APR 2011)
McGuire Nuclear Station UFSAR Table 11-7 (Page 2 of 2)
W Maximum activity allowed by Environmental Technical Specifications divided by tank volume of 600 ft.3 for concentration (05 APR 2011)
McGuire Nuclear Station UFSAR Table 11-8 (Page 1 of 1)
Table 11-8. Maximum Volume Control Tank Activities. (Based on parameters given in Table 11-1)
Vapor Activity (Curies) 1 Stripping Fractions Assuming Operations Isotope with WGS Operating of WGS Plant Without WGS Kr-85 0.35 6.8 x 10-1 1.4 Kr-85m 0.50 6.6 6.6 Kr-87 0.69 2.2 2.3 1
Kr-88 0.57 1.0 x 10 1.1 x 101 Xe-131m 0.39 1.4 9.8 Xe-133 0.40 4.1 x 102 1.4 x 103 Xe-133m 0.41 8.3 1.5 x 101 Xe-135 0.48 2.6 x 101 2.6 x 101 Xe-138 1.00 4.5 x 10-1 4.7 x 10-1 Note:
- 1. Volume control tank purge rate is 0.7 scfm.
- 2. Stripping efficiency is 100 percent.
(14 OCT 2000)
McGuire Nuclear Station UFSAR Table 11-9 (Page 1 of 2)
Table 11-9. Steam Generator Blowdown Concentrations Activity Activity Isotope (µCi/gm) Isotope (µCi/gm)
H-3 1.0 x 10-3 I-134 5.9 x 10-7 Br-83 1.1 x 10-7 Cs-134 2.4 x 10-6 Br-84 2.3 x 10-8 I-135 5.8 x 10-6 Br-85 3.0 x 10-10 Cs-136 1.3 x 10-6 Rb-86 8.3 x 10-9 Cs-137 1.8 x 10-6 Rb-88 1.1 x 10-6 Ba-137m 1.4 x 10-6 Sr-89 3.4 x 10-8 Ba-140 1.7 x 10-8 Sr-90 6.8 x 10-10 La-140 1.2 x 10-8 Y-90 1.4 x 10-10 Ce-141 6.8 x 10-9 Sr-91 3.4 x 10-8 Ce-143 3.4 x 10-9 Y-91m 1.6 x 10-8 Pr-143 3.4 x 10-9 Y-91 5.1 x 10-9 Ce-144 3.4 x 10-9 Y-93 1.7 x 10-9 Pr-144 1.5 x 10-10 Zr-95 6.8 x 10-9 Cr-51 1.5 x 10-7 Nb-95 6.8 x 10-9 Mn-54 3.4 x 10-8 Mo-99 6.8 x 10-6 Fe-55 1.4 x 10-7 Tc-99m 5.0 x 10-6 Fe-59 1.0 x 10-7 Ru-103 3.4 x 10-9 Co-58 1.4 x 10-6 Rh-103m 3.1 x 10-9 Co-60 1.5 x 10-7 Ru-106 6.8 x 10-10 Kr-83m 5.6 x 10-9 Rh-106 6.0 x 10-10 Kr-85m 2.4 x 10-8 Te-125m 1.7 x 10-9 Kr-85 5.6 x 10-10 Te-127m 1.7 x 10-8 Kr-87 1.6 x 10-8 Te-127 5.1 x 10-8 Kr-88 4.9 x 10-8 Te-129m 1.0 x 10-7 Kr-89 1.6 x 10-9 Te-129 9.5 x 10-8 Xe-131m 1.5 x 10-9 I-130 6.9 x 10-8 Xe-133m 1.1 x 10-8 Te-131m 1.7 x 10-7 Xe-133 4.4 x 10-7 Te-131 3.1 x 10-8 Xe-135m 4.1 x 10-9 I-131 9.7 x 10-6 Xe-135 5.6 x 10-8 (14 APR 2005)
McGuire Nuclear Station UFSAR Table 11-9 (Page 2 of 2)
Activity Activity Isotope (µCi/gm) Isotope (µCi/gm)
Te-132 1.7 x 10-6 Xe-137 2.9 x 10-10 I-132 2.9 x 10-6 Xe-138 1.4 x 10-8 I-133 1.3 x 10-5 (14 APR 2005)
McGuire Nuclear Station UFSAR Table 11-10 (Page 1 of 16)
Table 11-10. Liquid Waste System Component Design Parameters 1 REACTOR COOLANT DRAIN TANK SUBSYSTEM PARAMETERS 1.1 REACTOR COOLANT DRAIN TANK HEAT EXCHANGER Number 1 (per unit)
Type Horizontal Shell & U-Tube Heat transfer rate at normal conditions, Btu/hr 2.23 x 106 Estimated UA, Btu/hr - °F 7.0 x 104 Shell Side Data:
Design pressure, psig 150 Design temperature, °F 250 Pressure loss at operating conditions, psid 15 Nozzle size, inches 3" Material of construction Carbon Steel Fluid circulated Component cooling water Tube Side Data:
Design pressure, psig 150 Design temperature, °F 250 Pressure loss at operating conditions, psid 10 Nozzle size, inches 3" Material of construction Stainless Steel Fluid circulated Borated reactor coolant Design Parameters: Shell Flow, lbm/hr 1.12 x 105 Inlet temperature, °F 95 Outlet temperature, °F 115 1.2 REACTOR COOLANT DRAIN TANK Number 1 (per unit)
Internal volume, gal 350 Design pressure, internal, psig 100 Design pressure, external, psig 15 Design temperature, °F 250 Operating pressure range, psig 2-5 Cover gas Hydrogen (13 OCT 2018)
McGuire Nuclear Station UFSAR Table 11-10 (Page 2 of 16)
Normal operating temperature, °F 170 or less Material of construction Stainless Steel 1.3 REACTOR COOLANT DRAIN TANK PUMPS Number 2 (per unit)
Type Canned centrifugal Design pressure, psig 150 Design temperature, °F 200 Material of construction Stainless Steel Design flow, gpm 100 Developed head @ design flow, ft 300 1.4 INCORE INSTRUMENTATION ROOM SUMP PUMPS Number 1 (per unit)
Type Vertical sump pump Design pressure, psig 150 Design temperature, °F 180 Material of construction Stainless Steel Design flow, gpm 50 Head at design flow, ft 75 1.5 CONTAINMENT FLOOR AND EQUIPMENT SUMP PUMPS Number 4 (per unit)
Type Vertical sump pump Design pressure, psig 150 Design temperature, °F 180 Material of construction Stainless Steel Design flow, gpm 50 gpm Head at design flow, ft 25 2 WASTE DRAIN TANK SUBSYSTEM PARAMETERS 2.1 WASTE DRAIN TANK Number 1 (for both units)
Internal volume, gal 5000 Design pressure; internal Atmospheric Design temperature, °F 200 Material of construction Stainless Steel (13 OCT 2018)
McGuire Nuclear Station UFSAR Table 11-10 (Page 3 of 16)
Type Vertical with diaphragm 2.2 WASTE DRAIN TANK PUMPS Number 2 (for both units)
Type Canned centrifugal & mechanical seal centrifugal Design pressure, psig 150 Design temperature, °F 200 Material of construction Stainless Steel Design flow, gpm Condition 1: 35 Condition 2: 100 Developed head, ft Condition 1: 250 Condition 2: 200 3 WASTE EVAPORATOR FEED TANK SUBSYSTEM PARAMETERS 3.1 WASTE EVAPORATOR FEED TANK Number 1 (for both units)
Internal volume, gal 5000 Design pressure, internal Atmospheric Design temperature, °F 200 Material of construction Stainless Steel Type Horizontal 3.2 WASTE EVAPORATOR FEED PUMPS Number 2 (for both units)
Type Mechanical seal centrifugal Design pressure, psig 150 Design temperature, °F 200 Material of construction Stainless Steel Design flow, gpm Condition 1: 35 Condition 2: 100 Developed head, ft Condition 1: 250 Condition 2: 200 3.3 WASTE EVAPORATOR FEED FILTERS Number 2 (for both units)
Type Disposable Design pressure, psig 150 (13 OCT 2018)
McGuire Nuclear Station UFSAR Table 11-10 (Page 4 of 16)
Design temperature, °F 200 Design flow, gpm 35 Pressure loss at design flow, psig Fouled - 20 Unfouled - 5 Deleted per 2018 Update Material of construction Stainless Steel 3.4 WASTE EVAPORATOR PACKAGE Number 1 (for both units)
Capacity 15 gpm Feed concentration 10-2000 ppm B (as dilute boric acid)
Bottoms concentration 7000-7,700 ppm B 3.5 WASTE EVAPORATOR CONDENSATE DEMINERALIZER Number 1 (for both units)
Type Flushable Resin type ROHM & HASS amberlite 1RM-150 or equivalent (H+ OH-- form)
Design pressure, internal, psig 150 Design temperature, °F 200 Resin volume, ft3 30 Design flow - through, gpm 35 Material of construction Stainless Steel 3.6 WASTE EVAPORATOR REAGENT TANK Number 1 (for both units)
Internal volume, gal 20 Design pressure, internal, psig 150 Design pressure, external Atmospheric Design temperature, °F 200 Material of construction Stainless Steel Type Vertical 3.7 WASTE EVAPORATOR CONDENSATE FILTER Number 1 (for both units)
Type Disposable Design pressure, psig 150 (13 OCT 2018)
McGuire Nuclear Station UFSAR Table 11-10 (Page 5 of 16)
Design temperature, °F 200 Design flow, gpm 35 Pressure loss at design flow, psid Fouled - 20 Deleted Per 2018 Update Material of construction Stainless Steel 3.8 RECYCLE MONITOR TANKS Number 2 (for both units)
Internal volume, gal 5000 Design pressure, internal Atmospheric Design temperature, °F 200 Material of construction Stainless Steel Type Vertical with diaphragm 3.9 RECYCLE MONITOR TANK PUMPS Number 2 (for both units)
Type A-canned rotor, B-Mechanical seal centrifugal Design pressure, psig 150 Design temperature, °F 200 Material of construction Stainless Steel Design flow, gpm Condition 1: 35 Condition 2: 100 Developed head, ft Condition 1: 250 Condition 2: 200 3.10 WASTE EVAPORATOR CONDENSATE RETURN UNIT Number for both units 1 Receiver volume, gal 100 Design pressure, psig 200 Design temperature, °F 350 No. of pumps 2 Design flow, gpm 25 Design head, ft 65 3.11 WASTE EVAPORATOR FEED TANK SUMP PUMP Number 1 (for both units)
Type Vertical sump pump (13 OCT 2018)
McGuire Nuclear Station UFSAR Table 11-10 (Page 6 of 16)
Design pressure, psig 150 Design temperature, °F 180 Material of construction Stainless Steel Design flow, gpm 50 Head at design flow, ft 31 3.12 RHR AND CS ROOM SUMP PUMPS Number 4 (for both units)
Type Vertical sump pump Design pressure, psig 150 Design temperature, °F 180 Material of construction Stainless Steel Design flow, gpm 100 Head at design flow, ft 65 3.13 EVAPORATOR CONCENTRATE LINES FLUSH TANK Number 1 (for both units)
Design pressure, psig 150 Design flow rate, gpm 15 Capacity, gal 50 Set temperature, °F 100-180 Min Inlet Temperature, °F 70 Time to heat total capacity, hrs 2.5 3.14 WASTE EVAPORATOR CONCENTRATES PUMP Number 1 (for both units)
Type Double mechanical seal centrifugal Design pressure, psig 150 Design temperature, °F 250 Material of construction Stainless Steel Design flow, gpm 35 Head at design flow, ft. 125 Seal cooling water requirements flow, gpm 0.5 min.
Temperature, °F 110 max.
Supply head, ft. 90 min.
3.15 MECHANICAL SEAL COOLING WATER PUMP (13 OCT 2018)
McGuire Nuclear Station UFSAR Table 11-10 (Page 7 of 16)
Number 1 (for both units)
Type Gear Design pressure, psig 100 Design temperature, °F 140 Material of construction Bronze Design flow, gpm 2 Head at design flow, ft. 140 3.16 MECHANICAL SEAL COOLING WATER HEAT EXCHANGER Number 1 (for both units)
Type Coil Heat transfer rate at normal conditions, Btu/hr 3.0 x 104 Shell Side Data:
Design pressure, psig 150 Design temperature, °F 140 Normal inlet temperature 95 Normal outlet temperature 101 Design flow rate, gpm 10 Pressure loss at normal operating conditions, 4 psid Material of construction Carbon Steel Tube Side Data:
Design pressure, psig 150 Design temperature, °F 140 Normal inlet temperature 140 Normal outlet temperature 110 Design flow rate, gpm 2 Pressure loss at normal operating conditions, 2 psid Material of construction Stainless Steel MECHANICAL SEAL COOLING WATER TANK Number 1 (for both units)
Internal volume, gal. 8.9 Design pressure, internal, psig Atmospheric Design pressure, external, psig Atmospheric (13 OCT 2018)
McGuire Nuclear Station UFSAR Table 11-10 (Page 8 of 16)
Material of construction Stainless Steel MECHANICAL SEAL COOLING WATER TANK Number 1 (for both units)
Internal volume, gal. 8.9 Design pressure, internal, psig Atmospheric Design pressure, external, psig Atmospheric Material of construction Stainless Steel MECHANICAL SEAL COOLING WATER FILTER Number 1 (for both units)
Type Disposable Design pressure, psig 100 Design temperature, °F 140 Design flow, gpm 2 Pressure drop, psid Negligible Deleted Per 2018 Update Material of construction Stainless Steel 4 LAUNDRY AND HOT SHOWER TANK SUBSYSTEM PARAMETERS 4.1 LAUNDRY AND HOT SHOWER TANK Number 1 (for both units)
Internal volume, gal. 10,000 Design pressure, internal Atmospheric Design temperature, °F 200 Material of construction Stainless Steel Type Horizontal 4.2 LAUNDRY AND HOT SHOWER TANK STRAINER Number 1 (for both units)
Type Basket Design pressure, psig 150 Design temperature, °F 200 Design flow, gpm 35 Pressure loss at design flow Negligible Strainer mesh number 40 (1/16 inch)
Material of construction Stainless Steel (13 OCT 2018)
McGuire Nuclear Station UFSAR Table 11-10 (Page 9 of 16) 4.3 LAUNDRY AND SHOWER TANK PUMP Number 1 (for both units)
Type Centrifugal Design pressure, psig 150 Design temperature, °F 200 Material of construction Stainless Steel Design flow, gpm Condition 1: 35 Condition 2: 100 Developed head, ft. Condition 1: 250 Condition 2: 200 4.4 LAUNDRY AND HOT SHOWER TANK PRIMARY FILTER Number 2 (for both units)
Type Disposable Design pressure, psig 150 Design temperature, °F 200 Design flow, gpm 35 Pressure loss at design flow, psid Fouled - 75 Unfouled - 5 Deleted Per 2018 Update Material of construction Stainless Steel 4.5 LAUNDRY AND SHOWER TANK SECONDARY FILTER Number 1 (for both units)
Type Disposable Design pressure, psig 150 Design temperature, °F 200 Design flow, gpm 35 Pressure loss at design flow, psid Fouled - 20 Unfouled - 5 Deleted Per 2018 Update Material of construction Stainless Steel 4.6 LAUNDRY AND HOT SHOWER TANK DEMINERALIZER (WM 1° IX)
Number 1 (for both units)
Type Flushable Design pressure, internal, psig 150 (13 OCT 2018)
McGuire Nuclear Station UFSAR Table 11-10 (Page 10 of 16)
Design temperature, °F 200 Resin ft3 20 Design flow-through, gpm 20 Material of construction Stainless Steel 4.7 WASTE MONITOR TANK DEMINERALIZER (WM 2° IX)
Number 1 (for both units)
Type Flushable Resin type Duolite S-37 Absorbent resin Design pressure, internal, psig 150 Design temperature, °F 200 Resin volume, ft3 30 Design flow-through, gpm 35 Material of construction Stainless Steel 4.8 WASTE MONITOR TANK FILTER Number 1 (for both units)
Type Disposable Design pressure, psig 150 Design temperature, °F 200 Design flow, gpm 35 Pressure loss at design flow, psid Fouled - 20 Unfouled - 5 Deleted Per 2018 Update Material of construction Stainless Steel 4.9 WASTE MONITOR TANKS Number 2 (for both units)
Internal volume, gal 6399 Design pressure, internal Atmospheric Design temperature, °F 200 Material of construction Stainless Steel Type Horizontal 4.10 WASTE MONITOR TANK PUMPS (13 OCT 2018)
McGuire Nuclear Station UFSAR Table 11-10 (Page 11 of 16)
Number 2 (for both units)
Type Mechanical seal Design pressure, psig 150 Design temperature, °F 200 Material of construction Stainless Steel Design flow, gpm Condition 1: 35 Condition 2: 100 Developed head, ft Condition 1: 250 Condition 2: 200 4.11 MIXING AND SETTLING TANK Number 1 (for both units)
Type Vertical cylindrical with steam panel coils and mixer Capacity, gal 800 Design pressure Atmospheric Design temperature, °F 180 Normal operating temperature, °F 65 Material of construction, tank Austenitic SS Material of construction panel coils Carbon Steel Heat Transfer Requirements:
Heat duty during heatup, Btu/hr 443,000 Steam temperature, °F 250 Initial fluid temperature, °F 32 Final fluid temperature, °F (design) 165 (65 normal)
Heatup time, hr 2 4.12 MIXING AND SETTLING TANK PUMP Number 1 (for both units)
Type Canned centrifugal with external flushing Design pressure, psig 150 Design temperature, °F 200 Material of construction Stainless Steel Design flow, gpm Condition 1: 35 Condition 2: 100 Developed head, ft Condition 1: 250 (13 OCT 2018)
McGuire Nuclear Station UFSAR Table 11-10 (Page 12 of 16)
Condition 2: 200 4.13 MIXING AND SETTLING TANK SLUDGE PUMP Number 1 (for both units)
Type Canned centrifugal with external flushing Design pressure, psig 150 Design temperature, °F 200 Material of construction Stainless Steel Design flow, gpm Condition 1: 35 Condition 2: 100 Developed head, ft Condition 1: 250 Condition 2: 200 4.14 MIXING AND SETTLING TANK REAGENT TANK Number 1 (for both units)
Internal volume, gal 20 Design pressure, internal, psig 150 Design pressure, external Atmospheric Design temperature, °F 200 Material of construction Stainless Steel 4.15 MIXING AND SETTLING TANK METERING PUMP Number 1 (for both units)
Type Positive displacement with metered capacity Design pressure, psig 150 Design temperature, °F 200 Material of construction Stainless Steel Design flow, gpm 1 to 5 4.16 MIXING AND SETTLING TANK CONDENSATE STRAINER Number 1 (for both units)
Type Basket Design pressure, psig 150 Design temperature, °F 200 Design flow, gpm 10 gpm Pressure loss at design flow Negligible (13 OCT 2018)
McGuire Nuclear Station UFSAR Table 11-10 (Page 13 of 16)
Strainer mesh number 40 Material of construction Stainless Steel 4.17 LAUNDRY AND HOT SHOWER TANK PRE-STRAINER Number 1 (for both units)
Type Basket Design pressure, psig 50 Design temperature, °F 200 Max Flow, gpm 30 Pressure loss at max flow Negligible Strainer mesh number 20 5 FLOOR DRAIN TANK SUBSYSTEM PARAMETERS 5.1 FLOOR DRAIN TANK Number 1 (for both units)
Internal volume, gal 10,000 Design pressure, internal Atmospheric Design temperature, °F 200 Material of construction Stainless Steel Type Horizontal 5.2 FLOOR DRAIN TANK STRAINER Number 1 (for both units)
Type Basket Design pressure, psig 150 Design temperature, °F 200 Design flow, gpm 35 Pressure loss at design flow Negligible Strainer mesh number 40 (1/16 inch)
Material of construction Stainless Steel 5.3 FLOOR DRAIN TANK PUMP Number 1 (for both units)
Type Centrifugal Design pressure, psig 150 Design temperature, °F 200 Material of construction Stainless Steel (13 OCT 2018)
McGuire Nuclear Station UFSAR Table 11-10 (Page 14 of 16)
Design flow, gpm Condition 1: 35 Condition 2: 100 Developed head, ft Condition 1: 250 Condition 2: 200 5.4 FLOOR DRAIN TANK FILTER Number 2 (for both units)
Type Disposable Design pressure, psig 150 Design temperature, °F 200 Design flow, gpm 35 Pressure loss at design flow Fouled - 75 Deleted Per 2018 Update Material of construction Stainless Steel 5.5 FLOOR DRAIN TANK SUMP PUMPS Number 8 (for both units)
Type Vertical sump pump Design pressure, psig 150 Design pressure, °F 180 Material of construction Stainless Steel Design flow, gpm 50 Head at design flow, ft 50 5.6 FLOOR DRAIN TANK PRE-STRAINER Number 3 (for both units)
Type Y Design pressure, psig 50 Design temperature, °F 200 Max flow, gpm 200 Pressure loss at max flow, psid .2 Strainer mesh number 20 5.7 VENTILATION UNIT CONDENSATE DRAIN TANK Number 1 (for each unit)
Internal volume, gal 4000 Design pressure, internal Atmospheric (13 OCT 2018)
McGuire Nuclear Station UFSAR Table 11-10 (Page 15 of 16)
Design temperature, °F 150 Material of construction Stainless Steel 5.8 VENTILATION UNIT CONDENSATE DRAIN TANK PUMPS Number 2 (for each unit)
Type Centrifugal Design pressure, psig 50 Design temperature, °F 150 Material of construction Stainless Steel Design flow, gpm Condition 1: 100 Condition 2: 50 Developed head, ft Condition 1: 31 Condition 2: 65 6 RADWASTE FACILITY SUBSYSTEM COMPONENTS 6.1 AUXILIARY FLOOR DRAIN TANK Number 1 (for both units)
Internal Volume, gal. 50,000 Design pressure, psig Atmospheric Design temperature, °F 200 Material of construction Seismic concrete with stainless steel liner 6.2 AUXILIARY WASTE EVAPORATOR FEED TANK Number 1 (for both units)
Internal volume, gal. 50,000 Design pressure, internal Atmospheric Design temperature, °F 200 Material of construction Seismic concrete with stainless steel liner 6.3 AUXILIARY FLOOR DRAIN TANK PUMP Number 1 (for both units)
Type Mechanical seal centrifugal Design pressure, psig 150 Design temperature, °F 200 Material of construction Stainless Steel Design flow, gpm 100 Head at design flow, ft. 200 (13 OCT 2018)
McGuire Nuclear Station UFSAR Table 11-10 (Page 16 of 16) 6.4 AUXILIARY WASTE EVAPORATOR FEED TANK PUMP Number 1 (for both units)
Type Mechanical seal centrifugal Design pressure, psig 150 Design temperature, °F 200 Material of construction Stainless Steel Design flow, gpm 100 Head at design flow, ft. 200 6.5 RADWASTE FACILITY SUMP PUMP Number 1 (for both units)
Type Vertical sump pump Design pressure, psig 150 Design temperature, °F 200 Material of construction Stainless Steel Design flow, gpm 50 Head at design flow, ft. 50 6.6 RADWASTE FACILITY PIPE TRENCH SUMP PUMPS Number 2 (for both units)
Type Vertical sump pump Design pressure, psig 150 Design temperature, °F 200 Material of construction Stainless Steel Design flow, gpm 35 Head at design flow, ft. 30 7.2 DECON EQUIPMENT SUMP PUMPS Number 2 (for both units)
Type Vertical sump pump Design pressure, psig 150 Design temperature, °F 200 Material of construction Stainless Steel Design flow, gpm 35 Head at design flow, ft. 30 (13 OCT 2018)
McGuire Nuclear Station UFSAR Table 11-11 (Page 1 of 1)
Table 11-11. Estimates of Annual Liquid Waste Quantities from Two Units Volume (gal/yr)
Processed and Discharged Reactor Coolant Leakage and Letdown 1,400,000 Laundry and Hot Shower 600,000 Miscellaneous Wastes (Decontaminations, Lab Rinses, etc.) 100,000 Turbine Building Drain1 8,400,000 Totals 9,516,000 Note:
- 1. Turbine Building drains are not normally processed.
(14 OCT 2000)
McGuire Nuclear Station UFSAR Table 11 11-15 (Page 1 of 1)
Table 11-12. Deleted Per 1992 Update Table 11-13. Deleted Per 1992 Update Table 11-14. Deleted Per 1992 Update Table 11-15. Deleted Per 1992 Update (14 OCT 2000)
McGuire Nuclear Station UFSAR Table 11-16 (Page 1 of 1)
Table 11-16. Estimates of Radioactivity Concentration in Hydro Station Discharges Downstream of McGuire The concentrations in the lakes indicated below can be expressed as a fraction of the channel concentration in Lake Norman as follows:
Hydro Station Average Stream Flow (CFS)
Cowans Ford 2670 Mountain Island 2700 Wylie 4400 Fishing Creek 4860 Great Falls 5150 Mountain Island = Lake Norman Wylie (2670)
= x Lake Norman (2700)
Fishing Creek (2670)
= x Lake Norman (4400)
Great Falls (2670)
= x Lake Norman (4860)
Below Great Falls (2670)
= x Lake Norman (5150)
Assumptions:
For a conservative estimate of the dilution of the concentration of radio-isotopes in the water discharged from Lake Norman, the following assumptions can be made:
- 1. Ignore decay (short transit time).
- 2. Assume that all additional dilution occurs just upstream of each hydro station.
(14 OCT 2000)
McGuire Nuclear Station UFSAR Table 11-17 (Page 1 of 1)
Table 11-17. Estimated Doses from Liquid Releases
[HISTORICAL INFORMATION NOT REQUIRED TO BE REVISED]
Maximum Whole Body Dose 0.86 mrem (Adult - all pathways)
Maximum Organ Dose - Liver 1.1 mrem (Adult - all pathways)
Assumptions:
- 1. Reactor coolant fission product concentrations associated with .12 percent fuel defects.
- 2. Activated corrosion product concentrations from Table 11-3.
(05 APR 2011)
McGuire Nuclear Station UFSAR Table 11-18 (Page 1 of 1)
Table 11-18. Waste Gas Tank Normal Inventories Activity Isotope (Curies)
KR 85M 2.6 x 101 KR 85 4.1 x 103 KR 87 3.1 x 100 Kr 88 2.8 x 101 XE 131M 4.9 x 102 XE 133M 4.8 x 102 XE 133 6.0 x 104 XE 135M 1.2 x 10-1 XE 135 2.1 x 102 Assumptions:
- 1. Volume control tank stripping fractions are based upon a stripping efficiency of 40% (See Table 11-1).
- 2. percent fuel defects.
- 3. Decay during buildup is the only loss term.
- 4. The above inventories correspond to an equilibrium accumulation from station operation plus the noble gas contents from two degassed reactor coolant system volumes.
- 5. A continuous letdown of 75 gpm.
(14 OCT 2000)
McGuire Nuclear Station UFSAR Table 11-19 (Page 1 of 2)
Table 11-19. Waste Gas System Component Data WASTE GAS COMPRESSORS Quantity (per plant) 2 Design temperature, °F 180 Design pressure, psig 150 Operating suction pressure, psig 0.5 Design flow (N2 at 140 °F and 110 psi 40 (discharge), scfm Material Stainless Steel or Bronze Operating temperature, °F 70-140 Operating pressure, psig 25-100 CATALYTIC HYDROGEN RECOMBINER Quantity (per plant) 2 Design temperature, °F Note 1 Design pressure, psig 150 Design flow, scfm 50 Catalyst bed design life, yrs 40 Material SS Operating Conditions, Inlet Temperature, °F 70-140 Pressure, psig 25-100 Operating Conditions, Outlet Temperature, °F 70-140 Pressure, psig 20 WASTE GAS DECAY TANKS (Normal Power Service Tanks)
Quantity 6 Type Vertical cylindrical Design temperature, °F 180 Design pressure, psig 150 Volume, ft3 600 Material CS SHUTDOWN/STARTUP TANKS (09 OCT 2015)
McGuire Nuclear Station UFSAR Table 11-19 (Page 2 of 2)
Quantity 2 Type Vertical cylindrical Design temperature, °F 180 Design pressure, psig 150 Volume, ft3 600 Material CS Note :
- 1. Varies by component, but exceeds component operating temperature by 100°F.
(09 OCT 2015)
McGuire Nuclear Station UFSAR Table 11-20 (Page 1 of 4)
Table 11-20. Waste Gas System Instrumentation - Design Parameters Channel Location of Primary Design Press. Design Alarm Control Location of Number Sensor (psig) Temp. (°F) Range Setpoint Setpoint Readout FLOW INSTRUMENTATION OWGFT Gas Decay Tank Water 150 180 0-6000 gal. Adjust in field Local 5190 Flush PRESSURE INSTRUMENTATION OWGPS Moisture Separator 150 180 0-100 psig Local 5040 OWGPS Moisture Separator 150 180 0-100 psig Local 5050 OWGPS Gas Decay Tank A 150 140 0-150 psig 140 psig WG panel 5100 OWGPS Gas Decay Tank B 150 140 0-150 psig 140 psig WG panel 5110 OWGPS Gas Decay Tank C 150 140 . 0-150 psig 140 psig WG panel 5120 OWGPS Gas Decay Tank D 150 150 0-150 psig 140 psig WG panel 5130 OWGPS Gas Decay Tank E 150 140 0-150 psig 140 psig WG panel 5140 OWGPS Gas Decay Tank F 150 140 0-150 psig 140 psig WG panel 5150 OWGPS Shutdown Tank A 150 140 0-150 psig 90 psig WG panel 5080 OWGPS Shutdown Tank B 150 140 0-150 psig 140 psig WG panel 5090 (13 APR 2008)
McGuire Nuclear Station UFSAR Table 11-20 (Page 2 of 4)
Channel Location of Primary Design Press. Design Alarm Control Location of Number Sensor (psig) Temp. (°F) Range Setpoint Setpoint Readout OGSPS Hydrogen Supply 150 120 . 0-160 psig WG panel 5020 Header OGNPG Nitrogen Supply 150 120 0-150 psig WG panel 5020 Header OWGPT Compressor Suction 100 180 2 psi vac. 0.5 psi vac. 0.5 psi WPS panel 5170 Header 2 psig OWGPG Gas Decay Tank 150 140 0-150 psig 2 psi Local 5900 Makeup Water OWGPG Volume Control Tank 150 200 0-20 psig Local 5000 and Discharge Pressure OWGPG 5010 OWGPG Gas Decay Tank Inlet 150 100 0-150 psig Local 5160 Nitrogen Pressure LEVEL INSTRUMENTATION OWGLT Compressor Moisture 150 180 0-30" H2O 12" H2O 15",-12", WPS panel 5040 Separator 8" H2O 8",
1" H2O OWGLT Compressor Moisture 150 180 0-30" H2O 12" H2O 15",-12" WPS panel 5050 Separator 8" H2O 8",
1" H2O INSTRUMENTATION SYMBOLS C - CONTROL ROOM INSTRUMENT R - REMOTE RACK OR PANEL INSTRUMENT LOCALLY MOUNTED INSTRUMENT V - UNIT DESIGNATION (13 APR 2008)
McGuire Nuclear Station UFSAR Table 11-20 (Page 3 of 4)
Channel Location of Primary Design Press. Design Alarm Control Location of Number Sensor (psig) Temp. (°F) Range Setpoint Setpoint Readout W - SYSTEM DESIGNATION X - INSTRUMENT DESIGNATION Y - INSTRUMENT LOOP NUMBER Z - IDENTIFIES MULTIPLE INSTRUMENTS OF THE SAME TYPE IN THE SAME LOOP.
SINGLE LETTER L.D.
P - RECEIVER EQUIP. TWO LETTER I.D.
RD - RTD ELEMENT CR - RECORDER LL - LIMIT SWITCH SV - SOLENOID VALVE VP - VALVE POSITION TRANSMITTER CS - CONTROL SWITCH EP - E/P CONVERTER PE - P/E CONVERTER PA - POWER ACTUATOR SS - SELECTOR STATION ML - MANUAL LOADER FIRST LETTER OF TWO LETTER I.D. SECOND LETTER OF TWO LETTER I.D.
T - TEMPERATURE T TRANSMITTER P - PRESSURE X TEST POINT F - FLOW A ALARM L - LEVEL I INDICATOR R - RADIATION S SWITCH (13 APR 2008)
McGuire Nuclear Station UFSAR Table 11-20 (Page 4 of 4)
Channel Location of Primary Design Press. Design Alarm Control Location of Number Sensor (psig) Temp. (°F) Range Setpoint Setpoint Readout C - CONDUCTIVITY E WITH T TO INDICATE THERMOCOUIPLE WELL S - SPEED E WITH F TO INDICATE FLOW ELEMENT V - VIBRATION E WITH C TO INDICATE CONDUCTIVITY ELEMENT M - MISCELLANEOUS G WITH P TO INDICATE PRESSURE GAGE H WITH T TO INDICATE THERMOMETER (13 APR 2008)
McGuire Nuclear Station UFSAR Table 11-21 (Page 1 of 1)
Table 11-21. Reduction in Reactor Coolant System Radioactive Fission Product Gaseous Activity.
Resulting from Normal Operation of the Waste Gas System At 3580 MWt Core Thermal Power with 1 Percent Fuel Defects Reactor Coolant Gaseous Fission Product Activities - uCi/cc (580°F)
Isotope WG Operating WG Not Operating Kr-85 0.15 8.8 Kr-85m 2.1 2.1 Kr-87 1.2 1.2 Kr-88 3.7 3.7 Xe-131m 0.3 1.9 Xe-133 83 280 Xe-133m 1.6 3.1 Xe-135 5.9 6.3 Xe-135m 0.7 0.7 Xe-138 0.7 0.7 Note:
- 1. Purification letdown rate = 75 gpm
- 2. Purge rate - 0.7 scfm (14 OCT 2000)
McGuire Nuclear Station UFSAR Table 11-22 (Page 1 of 1)
Table 11-22. Parameters Used to Estimate Annual Average Airborne Radioactivity Releases from Two Units Percent Fuel Defects 0.12%
Containment Building Primary Coolant Leakage Rate to Containment Atmosphere 0.001%/day Iodine (Percentage of Primary Coolant Inventory)
Nobles Gases (Percentage of Primary Coolant Inventory) 1.0%/day Frequency of Containment Purge 8 purges/year/plant Containment Auxiliary Carbon Filter Iodine DF (Lower compartment) 10 Auxiliary Building Primary Coolant Leakage Rate 320 lb/day/plant Iodine Partition Factor 0.0075 Primary to Secondary Leakage Rate 110 lb/day/unit Steam Generator Blowdown Rate 45000 lb/hr.
Secondary System Demineralizer Iodine DF 10 Secondary System Iodine Partition Factors Steam Generator Internal Partition 0.01 Air Ejectors 0.15 Steam Packing Exhauster 0.01 Turbine Building Main Steam Leakage Rate 3400 lb/hr/plant Iodine Partition Factor (Steam) 1.0 Liquid Leakage Rate to Turbine Bldg. Sump 20 gal/min plant Iodine Partition Factor (Liquid) 0.0075 (14 OCT 2000)
McGuire Nuclear Station UFSAR Table 11-23 (Page 1 of 1)
Table 11-23. Estimates of Annual Radioactivity Releases in Gaseous Waste from Two Units (Curies)
Auxiliary Waste Gas Decay Reactor Building Building Turbine Building Isotope Tanks Purge Ventilation Steam Leaks Air Ejector Total Kr-85m Note 1 5.5 2.0 Note 1 1.3 8.7 Kr-85 2.6 x 102 1.3 Note 1 Note 1 Note 1 2.6 x 102 Kr-87 Note 1 1.2 1.4 Note 1 Note 1 2.6 Kr-88 Note 1 7.5 4.1 Note 1 2.5 1.4 x 101 Xe-131m 3.4 3.0 Note 1 Note 1 Note 1 6.4 1
Xe-133m Note 1 1.4 x 10 Note 1 Note 1 Note 1 1.4 x 101 Xe-133 1.5 7.8 x 102 3.6 x 101 Note 1 2.2 x 101 8.4 x 102 Xe-135 Note 1 2.4 x 101 4.6 Note 1 2.9 3.2 x 101 Xe-138 Note 1 Note 1 1.2 Note 1 Note 1 1.2 I-131 Note 1 1.4 x 10-2 4.6 x 10-3 5.3 x 10-4 2.9 x 10-2 4.8 x 10-2 I-133 Note 1 8.4 x 10-3 6.8 x 10-3 7.3 x 10-4 4.2 x 10-2 5.8 x 10-2 Note:
- 1. indicates that release is <1.0 Ci/yr for noble gases and <0.001 Ci/yr for iodine.
(14 OCT 2000)
McGuire Nuclear Station UFSAR Table 11-24 (Page 1 of 1)
Table 11-24. Gaseous Discharges for 1971 From Westinghouse PWR Plants Total Released (Equiv. Avg. Annual Site Plant Xe-133) Curies Boundary Dose mr/yr Fraction 10CFR20 I 12.4 0.033 6.6 x 10-5 II 3990.0 7.1 1.4 x 10-2 III 7666.0 2.3 4.6 x 10-3 IV 31,855.0 4.5 9.0 x 10-3 V 838.0 0.067 1.4 x 10-3 (14 OCT 2000)
McGuire Nuclear Station UFSAR Table 11-25 (Page 1 of 1)
Table 11-25. Release Points Data Unit 1 Vent Unit 2 Vent Vent Shape Cylindrical Cylindrical Inside Diameter 7' - 0" 7' - 0" Maximum Effluent Velocity 3900 Fpm 3100 Fpm 1Maximum Effluent Velocity 3100 Fpm 2200 Fpm Maximum Heat Input to 5X106 BTU/h 4X106 BTU/h Atmosphere 1Maximum Heat Input to 4X106 BTU/h 3X106 BTU/h Atmosphere Note:
- 1. Occurs whenever the Containment Purge and Ventilation System is inactive.
(05 APR 2011)
McGuire Nuclear Station UFSAR Table 11-26 (Page 1 of 1)
Table 11-26. Estimated Doses From Gaseous Releases
[HISTORICAL INFORMATION NOT REQUIRED TO BE REVISED]
Maximum Whole Body Dose 0.45 mrem/yr (Exclusion Area Boundary)
Maximum Thyroid Dose 1.7 mrem/yr (Infant-Goat Milk Pathway)
Maximum Beta Air Dose 0.96 mrad/yr (Exclusion Area Boundary)
Maximum Gamma Air Dose 0.37 mrad/yr (Exclusion Area Boundary)
Maximum Skin Dose 0.75 mrem/yr (Exclusion Area Boundary)
(05 APR 2011)
McGuire Nuclear Station UFSAR Table 11-27 (Page 1 of 2)
Table 11-27. Liquid Process Radiation Monitoring Equipment Detect Detector Typical or Range Number Identification Location Function Sensitivity Type Counts/Minute Design Service 1-EMF-31 Conventional Turbine Monitor effluent to NaI 3x108 cpm per 101 - 107 Normal Waste/Water Bldg. Conventional Waste/Water Scint. µCi/ml Cs-137 Operation Gross Treatment Monitor EL 741 Treatment System. Stop Gamma 1-C-24-25 turbine room pumps and terminate discharge on high alarm when turbine room pump align to Conventional Waste/Water Treatment System.
1-EMF-34 Steam Generator EL 716 Detect Steam Generator tube NaI 3x108 cpm per 101 - 107 Normal (1) sample FF-55,56 leak and terminate sampling Scint. µCi/ml Cs-137 101 - 106 Operation Gross Gamma 1-EMF-44 Containment EL 716 Monitor effluent and NaI 3x108 cpm 101 - 107 Normal (1)
Ventilation Unit BB-50 terminate discharge on high Scint. perµCi/ml Cs-137 101 - 106 Operation Condensate alarm GM Gross Gamma Monitor 1-EMF-45A Nuclear Service EL 733 Detect Containment Spray NaI 3x108 cpm per 101 - 107 Post LOCA (1)
Water Monitor JJ-55 Heat exchanger tube failure Scint. µCi/ml Cs-137 101 - 106 Gross Gamma 1-EMF-45B 1-EMF-46A Component EL 750 Detect Heat exchanger leaks NaI 3x108 cpm per 101 - 107 Normal Cooling Water GG-56 Scint. µCi/ml Cs-137 Operation 1-EMF-46B Monitor Gross Gamma 0EMF-47 Boron Recycle EL 733 Monitor and divert NaI 3x108 cpm per 101 - 107 Normal Evaporator MM-56 evaporator condensate Scint. µCi/ml Cs-137 Operation Condensate Gross Gamma Monitor 1-EMF-48 Reactor Coolant EL 716 Detect Fuel Clad Failure NaI 8x103 cpm per 101 - 107 Normal Monitor EE, FF-54 Scint. µCi/ml F.P. Operation Gross Gamma 0EMF-49 Waste Liquid EL 716 Monitor effluent and NaI 3x108 cpm per 101 - 107 Normal (1)
Monitor KK, LL- terminate discharge on high Scint. µCi/ml Cs-137 101 - 106 Operation 56,57 alarm GM Gross Gamma (30 NOV 2012)
McGuire Nuclear Station UFSAR Table 11-27 (Page 2 of 2)
Detect Detector Typical or Range Number Identification Location Function Sensitivity Type Counts/Minute Design Service 2-EMF-31 Condensate Turbine Monitor effluent to NaI 3x108 cpm per 101 - 107 Normal Wastewater Bldg. conventional wastewater Scint. µCi/ml Cs-137 Operation Monitor EL 741 treatment system. Stop GM Gross Gamma U-28 turbine room pumps on high level alarm 2-EMF-34 Steam Generator EL 716 Detect Steam Generator tube NaI 3x108 cpm per 101 - 107 Normal (1)
Sample monitor EE, FF- leak and terminate sampling Scint. µCi/ml Cs-137 101 - 106 Operation 57,58 GM Gross Gamma 2-EMF-44 Containment EL 716 Monitor effluent and NaI 3x108 cpm per 101 - 107 Normal (1)
Ventilation Unit BB-62 terminate discharge on high Scint. µCi/ml Cs-137 101 - 106 Operation Condensate alarm GM Gross Gamma Monitor 2-EMF-45A Nuclear Service EL 733 Detect Containment Spray NaI 3x108 cpm per 101 - 107 Post LOCA Water Monitor JJ-57 heat exchanger tube failure Scint. µCi/ml Cs-137 Gross Gamma 2-EMF-45B GM 2-EMF-46A Component EL 750 Detect heat exchanger leaks NaI 3x108 cpm per 101 - 107 Normal Cooling Water GG-56 Scint. µCi/ml Cs-137 Operation 2-EMF-46B Monitor Gross Gamma 2-EMF-48 Reactor Coolant EL 716 Detect Fuel Clad Failure NaI 8x103 cpm per 101 - 107 Normal Monitor EE, FF- Scint. µCi/ml F.P. Operation 57,58 Gross Gamma Note:
- 1. High Range (Shielded) - GM (30 NOV 2012)
McGuire Nuclear Station UFSAR Table 11-28 (Page 1 of 5)
Table 11-28. Airborne Activity Process Radiation Monitoring Equipment Detector Detector Typical Design Number Identification Function Type Sensitivity Counts/Minute Location (1) Service 1-EMF-24 Main Steam Line Outboard Monitor Effluent G-M Per 10-1-104 mR/hr Normal Doghouse Release for noble Procedure Operation and gas tube rupture for gross gamma 1-EMF-25 Inboard Doghouse 1-EMF-26 Inboard Doghouse 1-EMF-27 Outboard Doghouse 1-EMF-33 Condensate Air Turb. Bldg Detect noble gas NaI Scint. Per 101 - 107 Normal Ejector indicative of SG tube Procedure Operation leak Gross Gamma 1-EMF-35 Unit Vent Air Part. EL 767 Monitor buildup on Plastic 4x1012 cpm 10 104 Normal JJ-50,51 filter from effluent Scint. per µCi/ml Operation sample Cs-137 Gross Beta 1-EMF-36 (HH) Unit Vent Activity U-1 Vent Monitor effluent Ionization per 10° - 108 R/hr LOCA Stack activity for noble gas procedure 1-EMF-36 Unit Vent Gas EL 767 Monitor effluent Plastic 2x107 cpm 101 - 107 Normal Op &
JJ-50,51 sample for noble gas Scint. GM (1)101 - 106 LOCA for noble per µCi/ml Xe-133 gas 1-EMF-37 Unit Vent Iodine EL 767 Monitor buildup on NaI Scint. 2x104 cpm 101 - 107 Normal Op &
JJ-50,51 filter from effluent per µCi/ml LOCA for sample I-131(2) Iodine 1-EMF-38 Containment Air EL 750 Monitor buildup on Plastic 4x1012 cpm 10 104 Normal Part. HH-53,54 filter from building Scint. per µCi/ml Operation sample Gross Beta Cs-137 (13 APR 2020)
McGuire Nuclear Station UFSAR Table 11-28 (Page 2 of 5)
Detector Detector Typical Design Number Identification Function Type Sensitivity Counts/Minute Location (1) Service 1-EMF-39 Containment Gas EL 750 Monitor building Plastic 2x107 cpm 101 - 107 Normal HH-53,54 sample for noble gas Scint. GM (1)101 - 106 Operation for per µCi/ml Xe-133 noble gas 1-EMF-40 Containment EL 750 Monitor buildup on NaI Scint. 2x104 cpm 101 - 107 Normal Iodine HH-53,54 filter from building per µCi/ml Operation for sample I-131(2) Iodine 0EMF-41 Auxiliary Building EL 750 Monitor Vent. for Plastic 2x107 cpm 101 - 107 Normal Ventilation KK-56 noble gas indicative Scint. per µCi/ml Operation for of leak Xe-133 noble gas 1-EMF-42 Spent Fuel EL 767 Monitor Vent. for Plastic 2x107 cpm 101 - 107 Normal Building QQ-52 noble gas Scint. per µCi/ml Operation for Ventilation Xe-133 noble gas 0EMF-43 Control Room EL 750, CC- Monitor Vent. for Plastic 2x107 cpm 101 - 107 Normal Ventilation 46 noble gas Scint. per µCi/ml Operation &
CC-66 Xe-133 Post LOCA for noble gas 0EMF-50 Waste Gas EL 716MM- Monitor effluent & Plastic 2x107 cpm 101 - 107 Normal Discharge 55,56 terminate discharge Scint. GM (1)101 - 106 Operation for per µCi/ml on high alarm Xe-133 Gross Beta 1-EMF-51A Reactor Bldg. L.C. 335°. Monitor Reactor Ionization Per 100 - 108R/hr Normal Activity 17R Building Activity Procedure Operation &
1-EMF-51B L.C. 200°, LOCA for gross 17R radioactivity 0EMF-52 Interim Radwaste 2" Floor Int. Monitor Vent. for Plastic 4x107 cpm 101 - 107 Normal Facility Ventilation Radwaste noble Gas Scint. per µCi/ml Operation for Exhaust Bldg. Xe-133 noble gas 0EMF-53 Contaminated EL 775 Monitor Vent. for Plastic 4x107 cpm 101 - 107 Normal Parts Warehouse VV-61,62 noble Gas Scint. per µCi/ml Operation for Ventilation Xe-133 noble gas Exhaust (13 APR 2020)
McGuire Nuclear Station UFSAR Table 11-28 (Page 3 of 5)
Detector Detector Typical Design Number Identification Function Type Sensitivity Counts/Minute Location (1) Service 0EMF-54 Technical Support EL-790 Monitor Vent. for Plastic 2x107 cpm 101 - 107 LOCA Center Ventilation 1J-34 noble Gas Scint. per µCi/ml Intake 2J-34 Xe-133 1-EMF-71 S/G A Leakage Turb Bldg Detect N-16 in NaI Scint. Per 101-107 Normal 1-EMF-72 S/G B Leakage Steam Line Procedure 100-105 GPD Operation 1-EMF-73 S/G C Leakage indicative of S/G above 40%
1-EMF-74 S/G D Leakage tube leak Reactor Power 2-EMF-10 Main Steam Line Outboard Monitor effluent G-M Per 10-1-104 mR/hr Normal Doghouse release for noble gas Procedure operation and tube rupture for gross gamma 2-EMF-11 Inboard Doghouse 2-EMF-12 Inboard Doghouse 2-EMF-13 Outboard Doghouse 2-EMF-33 Condenser Air Turb. Bldg. Detect noble gas NaI Scint. Per 101 - 107 Normal Ejector indicative of SG tube Procedure Operation leak Gross Gamma 2-EMF-35 Unit Vent Air Part. EL 767 Monitor buildup on Plastic 4x1012 cpm 10 104 Normal JJ-61,62 filter from effluent Scint. per µCi/ml Operation sample Cs-137 Gross Beta 2-EMF-36 (HH) Unit Vent Activity U-2 Vent Monitor Effluent Ionization Per 10° - 108 R/hr LOCA Stack Activity for noble gas Procedure (13 APR 2020)
McGuire Nuclear Station UFSAR Table 11-28 (Page 4 of 5)
Detector Detector Typical Design Number Identification Function Type Sensitivity Counts/Minute Location (1) Service 2-EMF-36 Unit Vent Gas EL 767 Monitor effluent Plastic 2x107 cpm 10¹ - 107 (3)10¹ Normal Op &
JJ-61,62 sample for noble gas Scint. GM per µCi/ml - 106 LOCA for noble Xe-133 gas 2-EMF-37 Unit Vent Iodine EL 767 Monitor buildup on NaI Scint. 2x104 cpm 101 - 107 Normal Op &
JJ-61,62 filter from effluent per µCi/ml LOCA for sample I-131(2) Iodine 2-EMF-38 Containment Air EL 750 Monitor buildup on Plastic 4x1012 cpm 10 104 Normal Part. HH-58,59 filter from building Scint. per µCi/ml Operation sample Cs-137 Gross Beta 2-EMF-39 Containment Gas EL 750 Monitor building Plastic 2x107 cpm 101 - 107 Normal HH-58,59 sample for noble gas Scint. GM (1)101 - 106 Operation for per µCi/ml Xe-133 noble gas 2-EMF-40 Containment EL 750 Monitor buildup on NaI Scint. 2x104 cpm 101 - 107 Normal Iodine HH-58,59 filter from building per µCi/ml Operation for sample I-131(2) Iodine 2-EMF-42 Spent Fuel EL 767 Monitor vent. for Plastic 2x107 cpm 101 - 107 Normal Building QQ-60 noble gas Scint. per µCi/ml Operation for Ventilation Xe-133 noble gas 2-EMF-51A Reactor Bldg. L.C. 335°, Monitor reactor Ionization Per 100 - 108R/hr Normal Activity 17'R building activity Procedure Operation &
LOCA for gross L.C. 200°, radioactivity 2-EMF-51B 17'R 2-EMF-59 U-2 Staging U-2 Staging Monitor Vent for Plastic 4x107 CPM 101 - 107 Normal Building Building Noble Gas Scint. per µCi/ml operation for Xe-133 noble gas (13 APR 2020)
McGuire Nuclear Station UFSAR Table 11-28 (Page 5 of 5)
Detector Detector Typical Design Number Identification Function Type Sensitivity Counts/Minute Location (1) Service 2-EMF-71 S/G A Leakage Turb Bldg Detec N-16 in Steam NaI Scint. Per 101-107 Normal 2-EMF-72 S/G B Leakage Line indicative of S/G Procedure 100-105 GPD Operation 2-EMF-73 S/G C Leakage tube leak above 40%
2-EMF-74 S/G D Leakage Reactor Power Note:
- 1. Based on activity deposited on collection medium.
- 2. 1EMF37 sample flow pathway has been bypassed and it no longer provides indication of unit vent iodine activity.
(13 APR 2020)
McGuire Nuclear Station UFSAR Table 11-29 (Page 1 of 2)
Table 11-29. Estimated Maximum Specific Activities Input to Nuclear Solid Waste Disposal System Spent Resins Arriving at Storage Tank (µCi/cc)
Br85 3.4 x 10-2 Rb88 1.7 x 100 Rb89 3.8 x 10-2 Sr89 7.1 x 100 Sr90 1.2 x 100 Sr91 2.9 x 10-2 Sr92 3.2 x 10-3 Y90 1.5 x 10-3 Y91M 1.9 x 10-2 Y91 1.3 x 100 Y92 3.9 x 10-4 ZR95 1.6 x 100 Nb95 8.8 x 10-1 Mo99 5.5 x 101 I131 7.6 x 102 I132 3.2 x 100 I133 1.2 x 102 I134 7.3 x 10-1 I135 2.2 x 101 Te132 3.2 x 101 Te134 3.2 x 10-2 Cs134 2.0 x 102 Cs136 6.8 x 100 Cs137 1.2 x 10-3 Cs138 7.6 x 10-2 Ba140 2.0 x 100 La140 8.8 x 10-2 Ce144 2.0 x 100 Pr144 1.4 x 10-4 Mn54 5.0 x 101 Mn56 1.2 x 100 (14 OCT 2000)
McGuire Nuclear Station UFSAR Table 11-29 (Page 2 of 2)
Spent Resins Arriving at Storage Tank (µCi/cc)
Co58 6.5 x 102 Co66 6.6 x 101 Fe59 1.7 x 101 Cr51 9.7 x 100 H3 ---
Total 2.5 x 103 (14 OCT 2000)
McGuire Nuclear Station UFSAR Table 11-30 (Page 1 of 3)
Table 11-30. Nuclear Solid Waste Disposal System Component Design Parameters (Two Units)
- 1. Spent Resin Storage Tanks
- a. Quantity 2
- b. Total Volume, GAL. 5000
- c. Resin Storage Volume, GAL. 3600
- d. Design Pressure, PSIG 100
- e. Design Temperature, °F 200
- f. Material Stainless Steel
- 2. Chemical Drain Tank
- a. Quantity 1
- b. Total Volume, GAL. 600
- c. Design Pressure, PSIG 0
- d. Design Temperature, °F 200
- e. Material Stainless Steel
- 3. Evaporator Concentrates Storage Tank
- a. Quantity 1
- b. Total Volume, GAL. 3000
- c. Design Pressure, PSIG 0
- d. Design Pressure, °F 200
- e. Material Stainless Steel
- 4. Resin Batching Tank
- a. Quantity 1
- b. Total Volume, GAL. 800
- c. Design Pressure, PSIG 0
- d. Design Pressure, °F 150
- e. Material Stainless Steel
- 5. (Deleted)
- 6. (Deleted)
- 7. (Deleted)
- 8. (Deleted)
- 9. Spent Resin Sluice Pump
- a. Quantity 1
- b. Design Flow, GPM 140 (14 OCT 2000)
McGuire Nuclear Station UFSAR Table 11-30 (Page 2 of 3)
- c. Total Head, FT 250
- d. Design Pressure, PSIG 150
- e. Design Temperature, °F 200
- f. Material Stainless Steel
- g. Type Canned Horizontal Centrifugal
- 10. Chemical Drain Tank Pump
- a. Quantity 1
- b. Design Flow, GPM 35
- c. Total Head, FT 250
- d. Design Pressure, PSIG 150
- e. Design Temperature, °F 200
- f. Material Stainless Steel
- g. Type Canned Horizontal Centrifugal
- 11. (Deleted)
- 12. Aux Radwaste Transfer Pump
- a. Quantity 1
- b. Design Flow, GPM 90
- c. Total Head, FT 220
- d. Material Stainless Steel
- e. Type Positive Displacement Duel Diaphragm
- 13. (Deleted)
- 14. Dewatering Pump
- a. Quantity 1
- b. Design Flow, GPM 10
- c. Total Head, PSIG 130
- d. Material Stainless Steel
- e. Type Single Stage Regenitive Turbine
- 15. Spent Resin Sluice Filter
- a. Quantity 1
- b. Type Disposable Cartridge
- c. Design Pressure, PSIG 150
- d. Design Temperature, °F 200
- e. Design Flow, GPM 150 (14 OCT 2000)
McGuire Nuclear Station UFSAR Table 11-30 (Page 3 of 3)
- f. Pressure Drop at Design Flow (Clean), 5 PSI
- 1) Retention for 25 Micron Particles, % 98
- g. Maximum Pressure Differential (Fouled), 20 PSI
- h. Material Stainless Steel
- 16. Resin Batching Tank Mixer
- a. Quantity 1
- b. Type Top Entering, Vertically Mounted, Turbine
- c. Motor, HP 5
- d. Material Stainless Steel
- 17. (Deleted)
- 18. (Deleted)
- 19. Contaminated Oil Transfer Pump
- a. Quantity 1
- b. Type Screw Type
- c. Design pressure, psig 150
- d. Design temperature, °F 120
- e. Material of construction Carbon Steel
- f. Design flow, gpm 14
- g. Pressure at design, flow 40
- 20. Evaporator Concentrates Batch Tank
- a. Quantity 1
- b. Total volume, gal 1450
- c. Design pressure, internal Atmospheric
- d. Design temperature, °F 200
- e. Material of construction Stainless Steel
- 21. Contaminated Oil Storage Tank
- a. Quantity 1
- b. Total volume, gal 6000
- c. Design pressure, internal Atmospheric
- d. Design temperature, °F 120
- e. Material of construction Carbon Steel (lined)
(14 OCT 2000)
McGuire Nuclear Station UFSAR Table 11-31 (Page 1 of 1)
Table 11-31. Estimated Maximum Volumes Discharged from Nuclear Solid Waste Disposal System (Two Units)
Volumes1 (ft3/year) Nature of Waste Spent Resins 2400 Chemical resins and fission and corrosion products - includes powdex Filters 300 Filter cartridges with fission and corrosion products, resin fines, particulates, etc.
Miscellaneous Solids 32,000 Rags, paper, glass, clothing, etc. with fission and corrosion products prior to compaction Note:
- 1. Does not include matrix or solidification materials.
(14 OCT 2000)
McGuire Nuclear Station UFSAR Table 11-32 (Page 1 of 1)
Table 11-32. Estimated Maximum Isotopic Activity Discharged from Nuclear Solid Waste Disposal System (Two Units)
Spent Resins (curies/year)
Sr89 2.4 x 100 Sr90 4.6 x 100 Sr91 ---
Sr92 ---
Y90 4.6 x 100 Y91M ---
Y91 5.9 x 10-1 Zr95 8.9 x 10-1 Nb95 1.7 x 100 Mo99 ---
I131 4.4 x 10-4 I132 ---
I133 ---
I135 ---
Te132 ---
Cs134 6.8 x 102 Cs136 1.6 x 10-3 Cs137 4.6 x 103 Ba140 3.9 x 10-4 La140 4.5 x 10-4 Ce144 5.0 x 100 Pr144 5.0 x 100 Mn54 1.3 x 102 Mn56 ---
Co58 4.2 x 102 Co60 2.4 x 102 Fe59 4.0 x 100 Cr51 4.0 x 10-1 H3 ---
TOTAL 5.4 x 103 (14 OCT 2000)
McGuire Nuclear Station UFSAR Table 11-33 (Page 1 of 1)
Table 11-33. Estimated Doses Concerning Critical Pathways to Man for Radionuclides Releases to the Environment mrem/yr Airborne Related Pathways
- 1. Submersion (all ages-skin) 0.75
- 2. Inhalation (infant-thyroid) 0.58
- 3. Milk (infant-thyroid) 1.7
- 4. Vegetation (child-thyroid) 0.77 Water Related Pathways
- 5. Lake and Shoreline Recreation 0.005 (teenager-whole body)
- 6. Water (infant-thyroid) 0.53
- 7. Fish (adult-liver) 0.99 (14 OCT 2000)
McGuire Nuclear Station UFSAR Table 11-34 (Page 1 of 1)
Table 11-34. Examples of Analytical Sensitivity Versus Permissible and Discharge Canal Concentrations Concentration Discharge Canal Permitted1 by NRC Concentration Regulations Sensitivity of Analysis Radionuclides µCi/ml µCi/ml µCi/ml
- 1. Releases into Water Tritium 1.9 x 10-6 1 x 10-3 2 x 10-9 Sr90 3.3 x 10-14 5 x 10-7 1 x 10-9 Cs137 4.4 x 10-10 1 x 10-6 1 x 10-9 Co60 1.5 x 10-12 3 x 10-6 1 x 10-8 I131 4.1 x 10-10 1 x 10-6 1 x 10-8
- 2. Releases into Air Radionuclide I131 3.7 x 10-14 2 x 10-10 1 x 10-14 Note:
- 1. 10CFR 20 Appendix B, Table 2 Limits (14 OCT 2000)