ML20309A769
Text
McGuire Nuclear Station UFSAR Appendix 12A. Tables Appendix 12A. Tables
McGuire Nuclear Station UFSAR Table 12-1 (Page 1 of 1)
Table 12-1. Design Radiation Zones Dose Rate Limit1 Zone (mem/hr) Occupancy Examples I .05 Continuous 1. Offsite areas II 0.5 Continuous 1. Control Room
- 2. Yard
- 3. Service Building
- 4. Turbine Building III 1.0 Extended 1. Cable Room
- 2. Battery Room
- 3. Electrical Penetrations IV 2.5 Periodic 1. Aux. Building Corridors
- 2. Spent Fuel Pool Surface V 15. Intermittent 1. Incore Instrument Room
- 2. Pipe Tunnel Cover VI >15. Infrequent 1. Demineralizer Rooms
- 2. Filter rooms Note:
- 1. For anticipated operational occurrences (14 OCT 2000)
McGuire Nuclear Station UFSAR Table 12-2 (Page 1 of 7)
Table 12-2. Minimum Shield Thicknesses Source Dimension (Note 11)
Location (Typical) Shield (ft)
Component Elevation/Columns R(in.) H(in.) Table/Flag (Note 10)
Reactor Coolant System Vessel 716 FF-49 86.5 488 (Note 1) 6.0 Pump 733 GG-47 72 72 12-6, SA,SB 3.0 Steam Generator 750 EE-47 56.3 180 12-6, SA,SB 3.0 (Note 2)
Pressurizer 767 DD-49 40 610 12-6, SC,SB 3.0 (Note 2)
Pressurizer Relief Tank 733 EE-49 60 222 12-6, SC 3.0 Safety Injection System Pump 716 HH-54 18 12 (Note 3) 2.0 Residual Heat Removal System Pump 695 GG-54 17.4 12 12-6, SK 3.0 Heat Exchanger 750 LL-52 18.4 354 12-6, SK 2.5 Containment Spray System Pump 695 GG-55 8 12 (Note 3) 2.5 Heat Exchanger 750 LL-52 28 485 (Note 3) 2.5 Chemical & Volume Control System Regenerative Heat Exchanger 733 DD-50 5.2 146 12-6, SA,SG 2.5 Excess Letdown Heat Exchanger 733 CC-50 4 160 12-6, SD 3.0 (Note 4)
Reciprocating Charging Pump 716 JJ-54 20.25 34 12-6, SG 2.0 Centrifugal Charging Pump 716 JJ-55 9 55 12-6, SG 2.0 (14 OCT 2000)
McGuire Nuclear Station UFSAR Table 12-2 (Page 2 of 7)
Source Dimension (Note 11)
Location (Typical) Shield (ft)
Component Elevation/Columns R(in.) H(in.) Table/Flag (Note 10)
Boric Acid Transfer Pump 733 NN-53 3.5 10 (Note 5) 3.0 Letdown Heat Exchanger 750 KK-53 11 215.5 12-6, SD 2.5 Seal Water Heat Exchanger 733 GG-54 7 165.5 12-6, SG 2.0 Volume Control Tank 733 KK-50 45 108.6 12-6, SF 3.0 Boric Acid Tank 733 PP-52 192 104 (Note 5) 3.0 Mixed Bed Demineralizer 733 LL-53 16.25 42 12-7 4.0 Cation Bed Demineralizer 733 MM-53 13.24 41.4 12-7 4.0 Reactor Coolant Filter 733 KK-52 3.375 19 12-8 2.5 Seal Water Return Filter 733 HH-52 3.375 19 12-8 2.0 Seal Water Injection Filter 7733 JJ-51 1.3 20 12-8 2.0 Boric Acid Filter 733 NN-51 3.375 19 12-8 3.0 Boronometer 733 GG-53 6.65 18.7 12-6, SF 1.0 Boron Recycle System Holdup Tank 716 PP-58 180 283 12-6, SE 3.0 Evaporator-Gas Stripper 695 NN-56 21 119 12-6, SL 3.0 Feed Pump 716 QQ-56 5.5 15 12-6, SE 3.0 Feed Demineralizer 733 QQ-56 16 100 12-7 4.0 Feed Filter 733 PP-56 3.375 19 12-8 2.0 Condensate Demineralizer 733 PP-56 13.15 65 12-7 2.0 (14 OCT 2000)
McGuire Nuclear Station UFSAR Table 12-2 (Page 3 of 7)
Source Dimension (Note 11)
Location (Typical) Shield (ft)
Component Elevation/Columns R(in.) H(in.) Table/Flag (Note 10)
Condensate Filter 733 NN-56 1.25 19 12-8 2.0 Concentrate Filter 733 NN-56 1.25 19 12-8 2.5 Boron Thermal Regeneration System Moderating Heat Exchanger 750 KK-54 10 215 (Note 6) 2.5 Letdown Chiller Heat Exchang. 750 LL-54 10 203.5 12-6, SF 2.5 Letdown Reheat Heat Exchang. 750 LL-54 4.3 86.9 12-6, SD,SF 2.5 Therm. Reg. Ion Exchanger 733 LL-54 21.25 28 12-7 4.0 Liquid Waste Recycle System Evaporator Feed Tank 716 LL-59 54 120 12-6, SH 2.5 Waste Drain Tank 716 LL-59 66 108 12-6, SD 2.5 Evaporator Feed Pump 716 MM-59 5.625 15 12-6, SH 2.0 Evaporator Feed Filter 733 MM-59 2 17 12-8 2.0 Waste Drain Tank Pump 716 MM-58 4 18 12-6, SD 2.0 Evaporator 695 LL-51 21 119 12-6, SL 3.0 Evaporator Condensate Dem. 733 KK-57 16.2 90 12-7 1.5 Evaporator Condensate Filter 733 KK-57 1.25 19 12-8 1.0 Reactor Coolant Drain Tank 733 HH-49 18 80 12-6, SD 3.0 RCDT Heat Exchanger 733 GG-49 7 175 12-6, SD 3.0 RCDT Pump 733 HH-49 5.5 15 12-6, SD 3.0 (14 OCT 2000)
McGuire Nuclear Station UFSAR Table 12-2 (Page 4 of 7)
Source Dimension (Note 11)
Location (Typical) Shield (ft)
Component Elevation/Columns R(in.) H(in.) Table/Flag (Note 10)
Aux Waste Evap Feed Tank 760 Yard 120 252 12-10 2.0 (Note 12)
Aux Waste Evap Feed Tank Pump 760 Yard 6 4 12-10 1.5 Liquid Waste Monitor & Disposal System Laundry & Hot Shower Tank 716 LL-51 69 180 12-6, SI 1.5 LHST Pump 716 KK-51 4 8 12-6, SI 1.5 LHST Pre-Filter, Post Filter 733 LL-55 1.25 19 12-8 2.0 LHST Carbon Filter 733 LL-55 1.25 19 12-8 2.0 Waste Monitor Tank Filter 733 KK-55 1.25 19 12-8 2.0 Waste Monitor Tank Demin. 733 KK-55 16.2 90 12-7 2.5 Floor Drain Tank 716 KK-52 60 240 12-6, SI 1.5 FDT Pump 716 KK-51 6 10 12-6, SI 1.5 FDT Filter 733 MM-55 1.25 19 12-8 2.0 Mixing and Settling 716 KK-55 60 24.5 12-6, SI 1.5 Sludge Pump 716 LL-55 4 15 12-6, SI 1.5 Mixing and Settling Tank Pump 716 KK-55 4 15 12-6, SI 1.5 Aux Floor Drain Tank 760 Yard 120 252 12-10 2.0 (Note 12)
Aux FDT Pump 760 Yard 6 4 12-10 1.5 (14 OCT 2000)
McGuire Nuclear Station UFSAR Table 12-2 (Page 5 of 7)
Source Dimension (Note 11)
Location (Typical) Shield (ft)
Component Elevation/Columns R(in.) H(in.) Table/Flag (Note 10)
Solid Waste Disposal System Chemical Drain Tank 695 LL-57 21 108 12-6, SH 3.0 Chemical Drain Tank Pump 695 LL-57 5.5 15 12-6, SH 3.0 Spent Resin Storage Tank 716 KK-53 107.3 132 12-6, SM 4.0 Spent Resin Sluice Pump 716 LL-53 5.5 14 12-6, SM 4.0 Spent Resin Sluice Filter 733 MM-52 4.325 20 12-6, SM 3.0 Resin Batching Tank 750 NN-55 30. 92.5 12-6, SN 3.0 Evaporator Concentrate Storage Tank 750 QQ-55 42. 120.0 12-6, SL 3.0 Drumming Room 750 PP-54 (Note 7) 3.0 Solid 171GD Liner Storage 760 VV-51a, (Note 12-6, SN 1.0 52a 13)
Waste Gas System Compressor 716 NN-52 6 25 12-6, SO 4.0 Tank 716 PP-53 60 91 12-6, SO 4.0 Hydrogen Recombiner 716 NN-53 6 25 12-6, SO 1.5 Spent Fuel Pool Cooling System Cooling Pump 750 PP-52 11 15 (Note 5) 2.0 Cooling Heat Exchanger 750 PP-53 17 228 (Note 5) 2.0 Cooling Strainer (Note 8) 750 PP-52 (Note 5) 2.0 Demineralizer 750 NN-53 19.45 60 12-7 2.0 (14 OCT 2000)
McGuire Nuclear Station UFSAR Table 12-2 (Page 6 of 7)
Source Dimension (Note 11)
Location (Typical) Shield (ft)
Component Elevation/Columns R(in.) H(in.) Table/Flag (Note 10)
Filter 733 MM-51 6 20 12-8 2.0 Skimmer Pump 750 PP-52 7 4 (Note 5) 2.0 Skimmer Strainer (Note 8) 750 PP-52 (Note 5) 2.0 Skimmer Filter 733 MM-51 3 18 (Note 5) 2.0 Sampling System Heat Exchangers (Note 9) 716 EE-53 3 90 12-6, SA 2.0 Steam Generator Blowdown Recycle System Tank 716 FF-53 36 120 (Note 5) 1.0 Pump 716 FF-53 4 5 (Note 5) 1.0 Heat Exchanger 733 FF-54 7 120 (Note 5) 2.0 Demineralizer 733 KK-55 13.8 60 12-7 3.0 Filter 733 HH-52 1.25 19 12-8 2.0 Note:
- 1. Source is reactor core at full power plus coolant activity.
- 2. Biological shielding (2 ft) provided above operating deck level for active height.
- 3. Accident source only.
- 4. Intermittent use only; no shield on annulus side.
- 5. Minimal radioactivity expected, shielding provided for conservatism.
- 6. Both shell and tube side are sources, no credit taken for activity removal across thermally regenerative ion exchanger.
(14 OCT 2000)
McGuire Nuclear Station UFSAR Table 12-2 (Page 7 of 7)
Source Dimension (Note 11)
Location (Typical) Shield (ft)
Component Elevation/Columns R(in.) H(in.) Table/Flag (Note 10)
- 7. Designed to handle wastes such as filter cartridges, evaporator bottoms, etc; handling area is 28.5 feet by 37 feet.
- 8. Strainer located on pump intake.
- 9. Heat exchangers for potentially radioactive samples are to be located behind a shield wall at the end of the Sample Room nearest the Reactor Building.
- 10. Ordinary concrete or equivalent.
- 11. Dimensions are for a right circular cylinder unless otherwise noted.
- 12. Dimensions of AUX WEFT and AUX FDT used in shielding calculations.
- 13. Largest Liner used in storage vault has a radius of 40 in. and a height of 106 in.
(14 OCT 2000)
McGuire Nuclear Station UFSAR Table 12-3 (Page 1 of 1)
Table 12-3. Primary Shield Description Region Material Thickness (in.)
Core baffle Stainless Steel 1.125 Coolant Water 6.52 Core Barrel Stainless Steel 2.25 Coolant/ Water/ 4.75/
1 Neutron pads Stainless Steel 2.75 Pressure Vessel Carbon Steel 8.625 Gap Air, Insulation 7.00 Biological shield Reinforced concrete Detector wells 72.0 Other 102.0 Note:
- 1. Neutron pads are affixed to the barrel and cover azimuthal regions which experience peak fast neutron exposures. There are four such panels covering the regions from 30° to 65°, 117° to 150°,
210° to 245°, and 297° to 330°.
(14 OCT 2000)
McGuire Nuclear Station UFSAR Table 12-4 (Page 1 of 1)
Table 12-4. Parameters Used for Design Basis Accident Analysis of Control Room Direct Dose Power Level 3565 MWt Equivalent fraction of core melting 1.0 Fission product fractional releases Noble gases 1.0 Halogens 0.5 Remaining inventory 0.01 Minimum full power operating time 650 days Clean-up rate following accident 0.0 Containment net free volume 1.22 x 106 ft3 Post-accident water depth 15.2 ft Shielding (see Section 12.1.2.5)
Occupancy time 30 days 0-1 day 100%
1-4 days 60%
4-30 days 40%
(14 OCT 2000)
McGuire Nuclear Station UFSAR Table 12-5 (Page 1 of 1)
Table 12-5. Design Basis Accident Containment Source Strength (gammas/cc-sec) vs (hours after release) 0 1 2 24 720 Gas 0.4 MeV 1.7E81 1.7E81 1.6E8 5.0E7 9.4E4 0.8 1.6E8 8.3E7 6.1E7 4.3E6 4.3E4 1.3 3.1E6 2.4E6 2.0E6 8.4E3 -
1.7 2.4E8 1.2E7 9.0E6 3.9E4 -
2.2 1.1E8 3.3E7 2.1E7 8.3E4 -
2.5 6.9E7 4.9E7 3.3E7 9.9E4 -
3.5 5.0E7 - - - -
Liquid 0.4MeV 3.9E8 3.4E8 3.4E8 3.1E8 1.8E8 0.8 3.0E9 2.5E9 1.9E9 3.6E8 4.5E7 1.3 6.1E8 4.1E8 3.2E8 1.9E7 4.5E5 1.7 2.0E8 9.9E7 7.5E7 1.8E7 4.0E6 2.2 5.5E8 4.7E8 4.2E8 4.2E7 1.8E5 2.5 5.3E7 2.8E7 2.1E7 2.3E8 2.4E5 3.5 4.1E7 9.0E6 2.6E6 3.1E4 8.3E3 Note:
- 1. 1.7E8 means 1.7 x 108 (14 OCT 2000)
McGuire Nuclear Station UFSAR Table 12-6 (Page 1 of 2)
Table 12-6. Design Basis Source Strengths for Fluids.
Gamma Groups Source Designation 1 2 3 4 5 6 SA Reactor coolant, high temperature, fission and corrosion products SS 1.08 E+6 3.23 E+5 2.00 E+5 7.55 E+4 7.20 E+4 5.16 E+4 E .114 .510 .888 1.40 1.94 2.50 SB Reactor coolant, nitrogen-16 term (per microcurie/cc)
SS ---- ---- ---- ---- ---- ---- 3.33 E+2 2.55 E+4 1.85 E+3 E 2.74 6.13 7.12 SC Reactor coolant, pressurizer SS 1.01 E+4 1.07 E+5 3.08 E+4 3.87 E+3 1.85 E+3 1.25 E+2 E .177 .524 .829 1.31 1.80 2.98 SD Reactor coolant, ambient temperature SS 1.53 E+6 4.58 E+5 2.83 E+5 1.07 E+5 1.02 E+5 7.31 E+4 E .114 .510 .888 1.40 1.94 2.50 SE Reactor coolant, downstream mixed-bed demineralizer SS 1.51 E+6 2.00 E+5 1.25 E+5 5.30 E+4 4.91 E+4 6.76 E+4 E .113 .514 .844 1.46 2.08 2.46 SF Reactor coolant, downstream mixed-bed and cation-bed demineralizer SS 1.51 E+6 1.93 E+5 1.19 E+5 5.05 E+4 4.85 E+4 6.73 E+4 E .113 5.10 .845 1.46 2.08 2.46 SG Reactor coolant, demineralizer, gas-stripped (volume control tank)
SS 1.11 E+6 1.42 E+5 1.01 E+5 4.23 E+4 2.63 E+4 3.73 E+4 E .111 .534 .844 1.44 2.11 2.46 SH Reactor coolant, fully degassed SS 4.04 E+4 3.70 E+5 2.44 E+5 8.75 E+4 6.49 E+4 9.50 E+3 E .180 .528 .894 1.36 1.86 2.88 SI Reactor coolant, degassed, diluted with other leakage (factor=1/50)
SS 8.08 E+2 7.40 E+3 4.88 E+3 1.75 E+3 1.30 E+3 1.90 E+1 E .180 .528 .894 1.36 1.86 2.88 SJ Reactor coolant, degassed, evaporated (DF=1000)
SS 4.04 E+1 3.70 E+2 2.44 E+2 8.75 E+1 6.49 E+1 9.50 E+0 E .180 .528 .894 1.36 1.86 2.88 (05 APR 2011)
McGuire Nuclear Station UFSAR Table 12-6 (Page 2 of 2)
Gamma Groups Source Designation 1 2 3 4 5 6 SK Reactor coolant, residual heat removal mode SS 1.30 E+6 2.59 E+5 1.11 E+5 3.64 E+4 2.25 E+4 1.79 E+4 E .105 .510 .873 1.36 1.92 2.42 SL Evaporator concentrates (non-recyclable)
SS 1.23 E+5 8.71 E+5 2.85 E+5 3.29 E+4 6.05 E+3 3.66 E+1 E .181 .517 .812 1.31 1.80 2.57 SM Demineralizer resins (combined, no sluice water)
SS 3.90 E+7 8.55 E+8 1.41 E+8 1.11 E+7 2.80 E+6 3.51 E+4 E .207 .571 .824 1.34 1.76 2.96 SN Demineralizer resins (combined, 6 mo. decay, no sluice water)
SS 2.14 E+4 1.65 E+8 2.40 E+7 1.43 E+6 1.01 E+3 4.52 E-1 E .122 .651 .817 1.35 2.19 2.54 SO Waste gas tank (maximum)
SS 5.43 E+7 5.90 E+5 1.91 E+4 1.10 E+4 1.42 E+4 3.02 E+4 E .084 .513 .850 1.55 2.18 2.42 Notes:
- 1. SS = Source Strength in gammas/cc-sec
- 2. E = Average energy in MeV
- 3. E + 6 means 106 (05 APR 2011)
McGuire Nuclear Station UFSAR Table 12-7 (Page 1 of 1)
Table 12-7. Design Basis Source Strengths for Demineralizers Demineralizer1 (in Place) 0.4 MeV 0.8 MeV 1.3 MeV 1.7 MeV 2.2 MeV 3.0 MeV Mixed Bed 3.8 x 108 5.0 x 108 3.1 x 107 1.0 x 107 2.0 x 106 1.1 x 105 Cation Bed 4.8 x 106 4.8 x 108 4.2 x 106 2.4 x 106 - -
Recycle Evaporator Feed 3.5 x 107 4.1 x 107 1.9 x 106 8.2 x 105 1.8 x 105 -
Boron Thermal Regeneration 6.3 x 106 2.6 x 106 5.2 x 105 1.9 x 105 5.5 x 104 -
6 5 3 3 Spent Fuel Pool 5.3 x 10 9.3 x 10 3.2 x 10 2.8 x 10 - -
Miscellaneous Low Activity: 1.1 x 105 2.8 x 104 4.2 x 103 1.5 x 103 4.5 x 102 -
(Recycle Evaporator Condensate)
(Waste Evaporator Condensate)
(Waste Monitor Tk)
(S.G. Blowdown Recycle)
Note:
- 1. See Table 12-2 for location and shielding.
(14 OCT 2000)
McGuire Nuclear Station UFSAR Table 12-8 (Page 1 of 1)
Table 12-8. Design Basis Source Strengths For Filters Estimated Source Strengths (Gamma/cc-sec)
Filter1 0.4 MeV 0.8 MeV 1.3 MeV Reactor Coolant 7.1 x 107 1.2 x 107 Seal Water Injection 6.0 x 107 9.2 x 106 Seal Water Return 1.4 x 107 2.3 x 106 Recycle Evaporator Feed 1.4 x 107 2.3 x 106 Recycle Evaporator Condensate 4.0 x 105 1.0 x 105 2.5 x 104 Recycle Evaporator Concentrate 1.5 x 106 -
Spent Fuel Pool (Pre and Post Filter, 1.4 x 107 2.3 x 106 Skimmer Filter)
Waste Evaporator Feed 4.25 x 107 6.85 x 106 Waste Evaporator Condensate 4.25 x 105 3.25 x 105 2.74 x 104 Waste Monitor Tank 4.25 x 105 3.25 x 105 2.74 x 104 Laundry and Hot Shower (Primary and 4.25 x 105 3.25 x 105 2.74 x 104 Secondary Tank Filter, Carbon Filter)
Boric Acid 1.5 x 106 -
Floor Drain Tank 4.25 x 107 6.85 x 106 Spent Resin Sluice 1.4 x 107 2.3 x 106 Note:
- 1. See Table 12-2 for location and shielding.
(14 OCT 2000)
McGuire Nuclear Station UFSAR Table 12-9 (Page 1 of 1)
Table 12-9. Reactor Coolant System Nitrogen-16 Activity N-16 Component µCi/gm Reactor Vessel, Core 95 Reactor Vessel, Upper Region 125 Reactor Outlet Pipe 113 Steam Generator 92 Coolant Pump 69 Reactor Inlet Pipe 65 (14 OCT 2000)
McGuire Nuclear Station UFSAR Table 12-10 (Page 1 of 1)
Table 12-10. Design Source Strengths for Outside Storage Tanks.
Gamma Groups 1 2 3 4 5 6 Refueling Water Storage Tank:
SS 1.96E+3 1.09E+2 1.2E+2 9.87E+0 --- ---
E .008 .483 .879 1.25 --- ---
Reactor Makeup Water Storage Tank:
SS 4.34E+1 3.74E+1 4.68E+1 6.67E+0 --- ---
E .159 .493 .889 1.26 --- ---
Radwaste Facility Tank #1:
SS 3.97E+4 3.52E+5 2.32E+5 8.28E+4 6.23E+4 9.02E+3 E .180 .525 .893 1.36 1.86 2.89 Radwaste Facility Tank #2:
SS 7.94E+2 7.04E+3 4.64E+3 1.66E+3 1.25E+3 1.80E+2 E .180 .525 .893 1.36 1.86 2.89 Notes:
- 1. SS = Source strength in gammas/cc-sec
- 2. E = Average energy in MeV
- 3. E+6 means 106 (05 APR 2011)
McGuire Nuclear Station UFSAR Table 12-11 (Page 1 of 3)
Table 12-11. Area Radiation Monitors Detector Number Detector Location 1 Type Range Fig. Ref.
1-EMF-1 Auxiliary Building Corridor - E1 695 - (FF, GG-56) G-M .1 to 104 mr/hr 1-2 1-EMF-2 Auxiliary Building Corridor - E1 716 - (MM, NN-56) G-M .1 to 104 mr/hr 1-3 1-EMF-3 Auxiliary Building Corridor - E1 716 - (LL, MM-59) G-M .1 to 104 mr/hr 1-3 1-EMF-4 Auxiliary Building Corridor - E1 716 - (GG-56) G-M .1 to 104 mr/hr 1-3 4
1-EMF-5 Sample Room Unit 1 - E1 716 (FF-54) G-M .1 to 10 mr/hr 1-3 1-EMF-6 Auxiliary Building Corridor - E1 733 (MM, NN-53) G-M .1 to 104 mr/hr 1-4 1-EMF-7 Auxiliary Building Corridor - E1 733 (NN-59) G-M .1 to 104 mr/hr 1-4 1-EMF-8 Auxiliary Building Corridor - E1 733 (HH-56) G-M .1 to 104 mr/hr 1-4 4
1-EMF-9 Reactor Building Incore Instrument Room Unit 1 G-M .1 to 10 mr/hr 1-4 1-EMF-10 Auxiliary Building Corridor - E1 750 (LL-56) G-M .1 to 104 mr/hr 1-5 1-EMF-11 Waste Drumming Area - E1 750 (PP-54) G-M .1 to 104 mr/hr 1-5 1-EMF-12 Control Room - E1 755 (CC-56) G-M .1 to 104 mr/hr 1-6 1-EMF-13 Laboratory - E1 767 (QQ-56) G-M .1 to 104 mr/hr 1-6 4
1-EMF-14 Auxiliary Building Corridor - E1 760 (RR-54) G-M .1 to 10 mr/hr 1-6 1-EMF-15 Hot Machine Shop Area - E1 760 (TT-59) G-M .1 to 104 mr/hr 1-7 1-EMF-16 Refueling Bridge Unit 1 Reactor Building G-M .1 to 104 mr/hr 1-7 1-EMF-17 Refueling Bridge Unit 1 Spent Fuel Building G-M .1 to 104 mr/hr 1-7 1-EMF-18 Reactor Coolant Filter 1A I-C .1 to 104 R/hr 1-EMF-19 Reactor Coolant Filter 1B I-C .1 to 104 R/hr 1-EMF-20 New Fuel Storage (North) G-M .1 to 104 mr/hr 1-EMF-21 New Fuel Storage (South) G-M .1 to 104 mr/hr 1-EMF-22 Tech Support CTR, ELE 767 (SS-32) G-M .1 to 104 mr/hr (14 OCT 2000)
McGuire Nuclear Station UFSAR Table 12-11 (Page 2 of 3)
Detector Number Detector Location 1 Type Range Fig. Ref.
1-EMF-23 RB Purge Filter, ELG-767 (JJ-53) G-M .1 to 104 mr/hr 1-EMF-24 Steam Line 1A, Outboard Doghouse, (GG-43) G-M .1 to 104 mr/hr 1-EMF-25 Steam Line 1B, Inboard Doghouse, (GG-53) G-M .1 to 104 mr/hr 1-EMF-26 Steam Line 1C, Inboard Doghouse, (GG-52) G-M .1 to 104 mr/hr 1-EMF-27 Steam Line 1D, Outboard Doghouse, (GG-44) G-M .1 to 104 mr/hr 1-EMF-28 Diesel Generator Room, (BB-45) G-M .1 to 104 mr/hr 1-EMF-36HH Unit Ventilation (Unit Vent) I-C 1 to 108 R/hr 1-EMF-51A Containment I-C 1 to 108 R/hr 1-EMF-51B Containment I-C 1 to 108 R/hr 2-EMF-1 Sample Room Unit 2 - E1 716 (EE, FF-58) G-M .1 to 104 mr/hr 1-3 4
2-EMF-2 Reactor Building Incore Instrumentation Room Unit 2 G-M .1 to 10 mr/hr 1-4 2-EMF-3 Refueling Bridge Unit 2 Reactor Building G-M .1 to 104 mr/hr 1-7 2-EMF-4 Refueling Bridge Unit 2 Spent Fuel Building G-M .1 to 104 mr/hr 1-7 2-EMF-5 Reactor Coolant Filter 2A ELE 733 (KK, JJ-60, 61) I-C .1 to 104 R/hr 1-7 2-EMF-6 Reactor Coolant Filter 2B ELE 733 (KK, JJ-60, 61) I-C .1 to 104 R/hr 2-EMF-7 New Fuel Storage (North) ELE 767 (TT-62) G-M .1 to 104 mr/hr 2-EMF-8 New Fuel Storage (South) ELE 767 (SS-62) G-M .1 to 104 mr/hr 2-EMF-9 RB Purge Filter, ELE 767, (JJ-59) G-M .1 to 104 mr/hr 2-EMF-10 Steam Line 2A, Outboard Doghouse, (FF-68) G-M .1 to 104 mr/hr 2-EMF-11 Steam Line 2B, Inboard Doghouse, (FF-59) G-M .1 to 104 mr/hr 2-EMF-12 Steam Line 2C, Inboard Doghouse, (FF-60) G-M .1 to 104 mr/hr 2-EMF-13 Steam Line 2D, Outboard Doghouse, (FF-69) G-M .1 to 104 mr/hr 2-EMF-14 Diesel Generator Room, (BB-69) G-M .1 to 104 mr/hr (14 OCT 2000)
McGuire Nuclear Station UFSAR Table 12-11 (Page 3 of 3)
Detector Number Detector Location 1 Type Range Fig. Ref.
2-EMF-36HH Unit Ventilation (Unit Vent) I-C 1 to 108 R/hr 2-EMF-51A Containment I-C 1 to 108 R/hr 2-EMF-51B Containment I-C 1 to 108 R/hr Note:
- 1. The approximate detector location is indicated. For example: 1-EMF-1 is located in the Auxiliary Building corridor at floor elevation 695 between column lines FF and GG at column line 56.
(14 OCT 2000)
McGuire Nuclear Station UFSAR Table 12-12 (Page 1 of 2)
Table 12-12. Annual Station Dose Estimates (person-rem/yr)
Dose (Rem)
Normal Operation & Anticipated Occurences Routine surveillance & plant operations 10 Valve maintenance 5 Miscellaneous maintenance 8 Primary sampling & analysis 1.5 Filter & strainer changeouts 1.5 Handling radioactive waste 2 Special maintenance (modifications, etc.) 3 In-service inspections 3 Total 34 Refueling Outage Stage area/equipment for Steam Generator work 6 Remove/replace Steam Generator primary manways & diaphragms 3 Install/remove Steam Generator nozzle dams 8 Steam Generator ECT testing 10 Steam Generator tubing plugging 8 Steam Generator tube plug removal 5 Reactor Coolant Pump seal maintenance 3 Reactor Coolant Pump motor maintenance 4 Reactor Head removal & replacement 8 Defuel/Refuel 1 Modifications 8 Miscellaneous preventitive maintenance 7 Miscellaneous clean-up & decontamination 4 Valve maintenance 25 Install/remove temporary shielding 10 In-service Inspections 10 Snubber Inspections 2 General Rx Bldg entry 1 Miscellaneous RP support 3 Miscellaneous Operations support 3 (14 OCT 2000)
McGuire Nuclear Station UFSAR Table 12-12 (Page 2 of 2)
Dose (Rem)
Penetration testing 1 Total 130 Total Station Dose 164 (14 OCT 2000)
McGuire Nuclear Station UFSAR Table 12-13 (Page 1 of 1)
Table 12-13. Estimated Occupancy Times During Normal Operations and Anticipated Occurrences (man-hrs/wk)
Administration & Technical Work Area Staff Operations Services Maintenance Guards ESS1 Janitorial QA
- 1. Aux. Bldg. 40 860 1100 960 - 900 800 800 Corridors
- 2. Sample Room & 40 10 800 40 - 40 - -
Hot Laboratory
- 3. Letdown & - 220 215 125 - 165 - -
Recycle Systems
- 4. Waste Gas - 220 215 100 - 165 - -
Processing
- 5. Liquid Waste - 220 215 125 - 165 - -
Processing
- 6. Solid Waste - 210 225 60 - 165 - -
Processing
- 7. Turbine Bldg. 40 860 350 1300 800 1800 500 200
- 8. Control Room 40 1280 400 1170 - 1000 100 200
- 9. Service & 840 280 1160 1360 2500 1600 600 2000 Administration Bldgs., Outside Total 1000 4160 4680 5240 3200 6000 2000 3200 Note:
- 1. ESS Maintenance (14 OCT 2000)
McGuire Nuclear Station UFSAR Table 12-14 (Page 1 of 2)
Table 12-14. Estimated Occupancy Times During A Refueling Outage (man-hrs)
Administration & Technical Staff Operations Services Maintenance Janitorial QA CRDM - - 50 690 - 50 Disconnect/Reconnect Head & Internals - - 250 1330 - 150 Movement Defuel/Refuel-Transfer - 2270 300 650 - -
Canal Defuel/Refuel-Spent - 850 900 200 - 800 Fuel Pool Head Flange Work on - - 30 300 - 10 Storage Stand CRDM Work on Storage - - 700 700 - -
Stand Reactor Coolant Pump - - 200 1300 - 100 Seal Work Reactor Coolant Pump - - 50 2300 - -
Motor Work Inservice Inspection - - 200 3800 - 1300 Eddy Current Inspection - - 1500 1450 - 200 Incore Instrumentation - - 150 1400 - 50 Reactor Building Valve - - 250 2000 - 20 Work Aux. Building Valve - - 150 1200 - 10 Work Preventive Maintenance - - 50 500 - 50
& Periodic Testing (11 NOV 2006)
McGuire Nuclear Station UFSAR Table 12-14 (Page 2 of 2)
Administration & Technical Staff Operations Services Maintenance Janitorial QA Misc. Cleanup & Decon - - 450 - 1400 -
Reactor Building 80 1160 3450 1380 50 450 General Entry Totals 80 4280 8680 19200 1500 3190 (11 NOV 2006)
McGuire Nuclear Station UFSAR Table 12-15 (Page 1 of 1)
Table 12-15. Estimated Occupational Dose by Job Function Function Dose1 Reactor Operations & Surveillance 5 Routine Maintenance 70 Inservice Inspection 3 Waste Processing 2 Defuel/Refuel 5 Misc. (less than 1 person rem/task) 10 Special Maintenance 5 100 Note:
- 1. Percent of total station dose
- 2. Basis. 1994 & 1995 actual values averaged and correlated to Tabe 12-14 values.
(14 OCT 2000)
McGuire Nuclear Station UFSAR Table 12-16 (Page 1 of 1)
Table 12-16. Estimates of Airborne Radioactive Contamination in the Containment Concentration Fraction of 10CFR 20.1201 Isotope (µC/ML) Limit AR41 8.6 x 10-08 1.2 x 10-3 KR83m 4.6 x 10-08 1.8 x 10-7 KR85m 3.0 x 10-07 6.0 x 10-4 KR85 7.7 x 10-05 3.1 x 10-2 KR87 1.2 x 10-07 9.6 x 10-4 KR88 8.9 x 10-07 1.8 x 10-2 KR89 1.3 x 10-09 5.2 x 10-4 XE131m 6.0 x 10-07 6.0 x 10-5 XE133m 8.9 x 10-07 3.6 x 10-4 XE133 8.3 x 10-05 3.3 x 10-2 XE135m 1.2 x 10-08 5.3 x 10-5 XE135 1.1 x 10-06 4.4 x 10-3 XE137 2.7 x 10-09 1.1 x 10-3 XE138 6.7 x 10-08 6.7 x 10-4 I130 2.7 x 10-12 3.6 x 10-7 I131 3.4 x 10-11 6.8 x 10-5 I132 1.4 x 10-09 1.9 x 10-5 I133 5.3 x 10-10 2.1 x 10-4 I134 5.5 x 10-11 1.1 x 10-7 I135 2.7 x 10-11 1.5 x 10-6 Total 1.6 x 10-04 9.2 x 10-2 Assumptions:
- 1. Reactor coolant activity from Table 11-3
- 2. Reactor coolant leak rate is 1%/day for noble gases; 0.001%/day for iodines.
- 3. Decay during build-up for 100 days.
- 4. Volume of lower compartment is 3.68 x 105 ft.3.
- 5. The Reactor Coolant System remains pressurized.
- 6. Recirculation cleanup time prior to entry into lower compartment is 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br />.
- 7. Purge time prior to entry into lower compartment is 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
- 8. Lower compartment purge rate is 7500 cfm.
- 9. The total containment volume of 1.038 x 106 ft.3 is available for dilution at the time of entry.
- 10. Occupancy time 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> per week.
- 11. Ar41 production by neutron capture near reactor vessel.
- 12. 10CFR 20.1201 derived air concentrations have been adjusted for occupancy.
(10 OCT 2009)
McGuire Nuclear Station UFSAR Table 12-17 (Page 1 of 1)
Table 12-17. Estimates of Airborne Radioactive Contamination in the Auxiliary Building Room Concentration Fraction of Isotope (µC/ML) 10CFR 20.1201 Limit KR83m 1.2 x 10-08 4.8 x 10-7 KR85m 5.1 x 10-08 1.0 x 10-3 KR85 1.2 x 10-09 4.8 x 10-6 KR87 3.6 x 10-08 2.9 x 10-3 KR88 1.0 x 10-07 2.0 x 10-2 KR89 2.8 x 10-09 1.1 x 10-2 XE131m 3.1 x 10-09 3.1 x 10-6 XE133m 2.2 x 10-08 8.8 x 10-5 XE133 9.3 x 10-07 3.7 x 10-3 XE135m 8.4 x 10-09 3.7 x 10-4 XE135 1.2 x 10-07 4.8 x 10-3 XE137 5.1 x 10-09 2.0 x 10-2 XE 138 2.8 x 10-08 2.8 x 10-3 I130 9.8 x 10-13 1.3 x 10-6 I131 1.2 x 10-10 2.4 x 10-3 I132 4.9 x 10-11 6.5 x 10-6 I133 1.8 x 10-10 7.2 x 10-4 I134 2.4 x 10-11 4.8 x 10-7 I135 9.4 x 10-11 5.4 x 10-5 Total 1.3 x 10-06 7.1 x 10-2 Assumptions:
- 1. Activity shown in Table 11-3 is reduced by demineralizer efficiencies shown in Table 11-12.
- 2. Leak rate is 160 lb/day/unit.
- 3. All of the noble gas and 0.75 percent of the iodine escapes from leakage.
- 4. The ventilation flow rate is 3270 cfm.
- 5. The volume of the room is 3168 ft.3.
- 6. Occupancy time is 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br /> per week.
- 7. Concentrations shown are equilibrium values.
- 8. 10CFR 20.1201 derived air concentrations have been adjusted for occupancy (10 OCT 2009)
McGuire Nuclear Station UFSAR Table 12-18 (Page 1 of 1)
Table 12-18. Estimates of Airborne Radioactive Contamination in the Turbine Building Concentration Fraction of Isotope (µC/ML) 10CFR 20.1201 Limit KR83m 8.4 x 10-15 8.4 x 10-13 KR85m 3.8 x 10-14 1.9 x 10-9 KR85 9.1 x 10-16 9.1 x 10-12 KR87 2.3 x 10-14 4.6 x 10-9 KR88 7.6 x 10-14 3.8 x 10-8 KR89 6.9 x 10-16 6.9 x 10-9 XE131m 2.4 x 10-15 6.0 x 10-12 XE133m 1.8 x 10-14 1.8 x 10-10 XE133 7.2 x 10-13 7.2 x 10-9 XE135m 8.2 x 10-15 9.1 x 10-10 XE135 9.0 x 10-14 9.0 x 10-9 XE137 1.4 x 10-15 1.4 x 10-8 XE138 1.5 x 10-14 3.8 x 10-9 I130 5.0 x 10-16 1.7 x 10-9 I131 1.3 x 10-13 6.5 x 10-6 I132 3.8 x 10-14 1.3 x 10-8 I133 1.8 x 10-13 1.8 x 10-6 I134 6.9 x 10-15 3.5 x 10-10 I135 7.9 x 10-14 1.1 x 10-7 Total 1.4 x 10-12 8.5 x 10-6 Assumptions:
- 1. Main steam iodine concentrations are shown in Table 11-6.
- 2. All of the iodine and noble gas from a 1700 lb/hr (per unit) steam leak is released.
- 3. 0.75 percent of the iodine present in a 5 gpm/unit liquid leak rate to the Turbine Building Sump is released.
- 4. Turbine Building volume is 8,880,000 ft.3.
- 5. Turbine Building ventilation flow rate is 690,000 cfm.
- 6. Concentrations shown are equilibrium values.
- 7. Occupancy is continuous.
(10 OCT 2009)
McGuire Nuclear Station UFSAR Table 12-19 (Page 1 of 2)
Table 12-19. RCA and RCA Control Points RCA Control Points RCA Figure & Boundaries (Column Elevation (Zones) Location Lines) Type 12-1 EL. 695+0 IV, V &VI 12-2 EL. 716+0 IV, V & VI 12-3 EL. 733+0 IV, V, & VI Aux bldg. door to U- CC-67 Incidental Access Point
& 739+0 2 D/G Rm.
Aux bldg. door to U- AA-67 Incidental Access Point 2 Turbine Bldg U-2 Aux Bldg AA-59 Incidental Access Point double sub hatch Aux bldg. door to U- CC-45 Incidental Access Point 1 D/G Rm.
Aux bldg. door to U- AA-45 Incidental Access Point 1 Turbine Bldg U-1 Aux Bldg AA-53 Incidental Access Point double sub hatch 12-4 EL. 750+0 IV, V, & VI U-1 Aux bldg, sub AA-54 Incidental Access Point hatch U-1 Aux Bldg. AA-52 Incidental Access Point double sub hatch U-2 Aux bldg. sub AA-58 Incidental Access Point hatch U-2 Aux Bldg. AA-60 Incidental Access Point double sub hatch 12-5 EL. 760+6 IV, V, and areas First Aid Rm SS-52 Incidental Access Point
& 767+0 of III to the left U-1 SFP door SS-52 Incidental Access Point of EE column 1000 line U-1 SFP door SS-48 Incidental Access Point 1000A U-1 SFP roll-up door RR-47 Incidental Access Point 1202 roll-up door YYA-62 Incidental Access Point Waste Shipping roll- YYA-68 Incidental Access Point up door (11 NOV 2006)
McGuire Nuclear Station UFSAR Table 12-19 (Page 2 of 2)
RCA Control Points RCA Figure & Boundaries (Column Elevation (Zones) Location Lines) Type Hot Tool Crib roll- UU-68 Incidental Access Point up door Hot Tool Crib door TT-68 Incidental Access Point 1039 U-2 SFP door SS-64 Incidental Access Point 1026A U-2 SFP roll-up door RR-65 Incidental Access Point Equip Staging Bldg. PPB-14 Incidental Access Point roll-up door Equip Staging Bldg. PPB-14 Incidental Access Point door 1063 Solid Pad roll-up YY-50 Incidental Access Point door Solid Pad door XX-50 Incidental Access Point south Solid Pad door VV-52 Incidental Access Point west U-1 Electrical Pen CC-53 Emergency entrance OPS Rm 925E (MG Set TCA Rm)
U-2 Electrical Pen CC-59 Emergency entrance OPS Rm 925F (MG Set TCA Rm) 12-6 EL. 774+0 III, IV, & VI RCA Entrance/Exit QQ-56 Primary RCA personnel
& 784+0 entrance/exit RP Office door XX-56 Incidental Access Point 1115 Corridor over Aux FF-56 Secondary RCA Bldg. roof, south personnel entrance/exit stairs (11 NOV 2006)
McGuire Nuclear Station UFSAR Table 12-20 (Page 1 of 1)
Table 12-20. Deleted Per 2011 Update (05 APR 2011)