ML17226A107

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5 to the Updated Safety Analysis Report, Chapter 12, Section 12.1-4 Tables - Basic Reactor Data (Initial Core Design and Power)
ML17226A107
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Site: River Bend  Entergy icon.png
Issue date: 07/28/2017
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Office of Nuclear Reactor Regulation, Office of Nuclear Material Safety and Safeguards
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RBG-47776, RBF1-17-0089
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RBS USAR Revision 17 1 of 3 TABLE 12.2-1 BASIC REACTOR DATA (initial core design and power)

A. Reactor Thermal Power 2,894 MW B. Average Power Density 52.4 watts/cm3 C. Physical Dimensions(1)

Radius (in)

1.

Core Equivalent Radius 84.56

2.

Inside Shroud Radius 91.0

3.

Outside Shroud Radius 93.0

4.

Inside Vessel Radius - Nominal 109.0

5.

Outside Vessel Radius - Nominal 114.41

6.

Outside Vessel Radius - Reinforced - Nominal 114.81

7.

Shroud Head Inside Radius 176.0

8.

Vessel Top Head Inside Radius 109.0

9.

Vessel Bottom Head Inside Radius 117.25 Elevation (in)

10. Outside of Vessel Bottom Head

-8.77

11. Inside of Vessel Bottom Head

-2.09

12. Vessel Bottom Head Tangent 115.16
13. Bottom of Core Support Plate 197.63
14. Top of Core Support Plate 199.63
15. Bottom of Active Fuel 208.56
16. Top of Reinforced Vessel Wall 207.09
17. Top of Active Fuel 358.56
18. Bottom of Top Guide 366.38
19. Top of Fuel Channel 372.94
20. Shroud Head Tangent 420.22
21. Inside of Shroud Head 445.57
22. Outside of Shroud Head 447.57
23. Normal Vessel Water Level 557.4

RBS USAR TABLE 12.2-1 (Cont) 2 of 3 August 1987 Elevation (in)

24. Top of Steam Dryer 713.13
25. Vessel Top Head Tangent 722.75
26. Inside of Vessel Top Head 831.75
27. Outside of Vessel Top Head 834.53 D.

Material Densities(2)grams/cm3 of Region Volume Region Coolant UO2 Zircaloy 304L Stainless A

0.740 0.0 0.0 0.178 B

0.338 0.0 0.0 4.349 C

0.318 2.334 0.978 0.056 C-1 0.597 0.0 0.166 1.697 C-2 0.234 0.0 1.099 0.255 D

0.240 0.0 1.004 1.209 E

0.390 0.0 0.0 0.0 F

0.669 0.0 0.0 0.200 G

0.036 0.0 0.0 0.0 H

0.740 0.0 0.0 0.0 I

0.740 0.0 0.0 0.26 E.

Typical Core Power Distributions Axial Power Distribution Radial Power Distribution (Typical End-of-Life)

Percent of Equivalent Relative Elevation(3)

Relative Radius Power (in)

Power 0

1.2

-75 0.343 20 1.2

-68 0.755 35 1.19

-60 1.055 50 1.17

-48 1.190 60 1.15

-36 1.200 70 1.12

-24 1.190 80 1.05

-12 1.170 85 0.995 0

1.155 90 0.778 12 1.140 92.5 0.590 24 1.105

RBS USAR TABLE 12.2-1 (Cont)

(1) Fig. 12.2-1 shows the relative locations of the dimensions.

(2)

Fig. 12.2-1 shows the region locations.

(3)

Elevations are measured from the midplane of the core.

3 of 3 August 1987 Axial Power Distribution Radial Power Distribution (Typical End-of-Life)

Percent of Equivalent Relative Elevation(3)

Relative Radius Power (in)

Power 95.0 0.430 36 1.055 97.0 0.375 48 0.945 98.0 0.395 60 0.715 99.0 0.432 68 0.462 100.0 0.518 75 0.212

RBS USAR TABLE 12.2-2 NOTE: 3.9 + 10 = 3.9 x 1010 Revision 17 1 of 1 CORE BOUNDARY NEUTRON FLUXES (initial core design and power)

Neutron Flux Energy Bounds (neutrons/cm2sec) 16.5 MeV 3.9+10 10.00 MeV 5.5+11 6.065 MeV 2.0+12 3.679 MeV 3.8+12 2.231 MeV 4.4+12 1.353 MeV 3.9+12 820.8 KeV 3.8+12 497.9 KeV 2.6+12 302.0 KeV 2.3+12 183.2 KeV 3.2+12 67.38 KeV 2.2+12 24.79 KeV 2.2+12 9.119 KeV 2.0+12 3.355 KeV 2.0+12 1.234 KeV 1.9+12 454.0 eV 2.0+12 167.0 eV 1.9+12 61.44 eV 1.8+12 22.60 eV 8.8+11 13.71 eV 8.8+11 8.315 eV 8.2+11 5.043 eV 8.4+11 3.059 eV 8.3+11 1.855 eV 8.2+11 1.125 eV 8.8+11 0.616 eV 3.2+13 0.000 eV

RBS USAR TABLE 12.2-3a NOTE: 7.8+8 = 7.8 x 108 Revision 17 1 of 1 GAMMA RAY SOURCE ENERGY SPECTRA Gamma Ray Sources in the Core During Operation (initial core design and power)

Energy Bounds Gamma Ray Source (MeV)

(MeV/sec-watt) 16.5 7.8+8 8.0 7.3+9 6.0 5.9+10 4.0 5.8+10 3.0 5.2+10 2.6 6.7+10 2.2 7.2+10 1.8 8.3+10 1.4 9.1+10 1.0 7.5+10 0.75 6.8+10 0.5 6.1+10 0.25 9.8+10 0.003

RBS USAR TABLE 12.2-3b

  • Operating history of 3.2 yr NOTE: 8.2+9 = 8.2 x 109 Revision 17 1 of 1 GAMMA RAY SOURCE ENERGY SPECTRA (initial core design and power)

Post Operation Gamma Sources in Core* (MeV/sec-watt)

Energy Bounds (MeV)

Time After Shutdown 0 sec 1 day 1 week 1 month 6.0 8.2+9

<1.0+6

<1.0+7

<1.0+6 4.0 1.8+10 7.0+6 4.6+6

<1.0+6 3.0 1.1+10 5.7+6 3.7+6

<1.0+6 2.6 1.7+10 2.9+8 1.7+8

<1.0+6 2.2 2.1+10 4.5+8 4.0+7 5.2+6 1.8 3.3+10 3.1+9 2.1+9 6.4+8 1.4 3.7+10 2.3+9 1.6+9 1.1+9 0.9 5.1+10 7.5+9 3.8+9 2.1+9 0.4 1.2+10 1.8+9 8.7+8 3.6+8 0.1

RBS USAR TABLE 12.2-3c NOTE: 2.8-1 = 2.8 x 10-1 Revision 17 1 of 1 GAMMA RAY SOURCE ENERGY SPECTRA (initial core design and power)

Gamma Ray Sources in Non Core Regions During Operation (MeV/cm3-sec-watt)

Energy Bounds (MeV)

Region H Shroud Inside Outside Inside Outside 16.5 2.8-1 3.6-2 2.5+2 4.1+1 8.0 2.5 3.0-1 8.2+3 1.3+2 6.0 4.8-3 6.2-3 2.4+2 3.9+1 4.0 2.3-2 4.1-3 1.1+2 1.4+1 3.0 1.0-3 1.4-4 4.3+1 1.3+1 2.6 2.3+2 4.4+1 2.4+1 4.5 2.2 5.4-3 1.0-3 2.7+1 5.4 1.8 6.3-5 8.1-5 7.1+1 1.3+1 1.4 2.6-3 5.0-4 3.3+1 6.5 1.0 7.5-3 1.4-3 3.4+1 4.9+1 0.75 4.6-4 5.8-5 2.9+1 4.7 0.50 1.2+2 1.8+1 0.25 8.7+2 1.4+1 0.003

RBS USAR TABLE 12.2-3d NOTE: 4.2-2 = 4.2 x 10-2 Revision 17 1 of 1 GAMMA RAY SOURCE ENERGY SPECTRA (MeV/cm3-sec-watt)

(initial core design and power)

Energy Bounds (MeV)

Region I (Jet Pumps)

Vessel Inside Outside Inside Outside 16.5 2.1 4.2-2 4.3-1 4.7-4 8.0 6.6 1.3-1 4.2 3.6-3 6.0 1.9 3.9-2 1.1 3.8-3 4.0 9.1-1 1.8-2 5.6-1 4.9-3 3.0 3.7-1 7.2-3 2.1-1 2.8-3 2.6 8.9 1.8-1 9.1-2 2.5-3 2.2 2.6-1 4.7-3 1.0-1 3.3-3 1.8 6.2-1 1.2-2 3.6-1 2.5-3 1.4 3.1-1 5.6-3 1.4-1 2.2-3 1.0 4.6-1 7.1-2 1.7-1 1.2-2 0.75 2.4-1 4.7-3 1.3-1 9.7-5 0.50 9.6-1 1.9-2 5.0-1 4.6-4 0.25 7.4-1 1.5-2 3.8-1 4.0-4 0.003

RBS USAR Revision 17 1 of 3 TABLE 12.2-4 GAMMA RAY AND NEUTRON FLUXES OUTSIDE THE VESSEL WALL (initial core design and power)

A. Neutron Fluxes Energy Bounds Neutrons/cm2 - sec 16.5 MeV 1.0+7 10.00 MeV 5.5+7 6.065 MeV 4.4+7 3.679 MeV 8.7+7 2.231 MeV 1.4+8 1.353 MeV 2.0+8 820.8 MeV 2.6+8 497.9 KeV 2.3+8 302.0 KeV 1.4+8 183.2 KeV 1.6+8 67.38 KeV 1.8+8 24.79 KeV 1.0+8 9.119 KeV 2.1+7 3.355 KeV 1.4+7 1.234 KeV 1.1+7 454.0 KeV 5.0+6 167.0 eV 7.4+6 61.44 eV 7.0+6 22.60 eV 3.5+6 13.71 eV 3.7+6 8.315 eV 3.4+6

RBS USAR 2 of 3 August 1987 TABLE 12.2-4 (Cont)

Energy Bounds Neutrons/cm2 - sec 5.043 eV 3.1+6 3.059 eV 2.9+6 1.855 eV 2.7+6 1.125 eV 1.6+6 0.616 eV 1.6+6 0

RBS USAR NOTE: 1.0+7=1.0 x 107 3 of 3 August 1987 TABLE 12.2-4 (Cont)

B. Gamma Ray Energy Fluxes Energy Bounds

____(MeV)

MeV/cm2-sec 16.5 1.8+9 8.0 6.2+9 6.0 5.7+9 4.0 3.0+9 3.0 1.2+9 2.6 1.8+9 2.2 1.2+9 1.8 1.1+9 1.4 9.7+8 1.0 5.9+8 0.75 7.5+8 0.50 5.8+8 0.25 1.4+7 0.003

RBS USAR NOTES: The data presented in this table are calculations of the primary and secondary radiation from the core and vessel. In power plant applications, the neutron fluxes above and below the core include contributions from radiation exiting the vessel at midplane and being scattered to these locations.

5.0+8 = 5.0 x 108 Data in this table is for initial core design and power.

Revision 17 1 of 1 TABLE 12.2-5 FAST NEUTRON FLUXES AND GAMMA RAY DOSE AROUND THE REACTOR VESSEL Fast Neutron Flux Gamma Ray Dose Location

(>1.0 MeV) (n/cm2-sec)

Rate (rads/hr)

Core - Midplane 5.0+8 3.2+4 Above top head 1.3+2 2.2+1 Below bottom head 6.8-10 2.0-1

1 of 2 August 1987 RBS USAR TABLE 12.2-6 REACTOR WATER CLEANUP SYSTEM DESIGN SOURCE TERMS (Ci/cc)

Isotope RWCU Heat Exchanger RWCU Backwash Tank RWCU Filter/Demin RWCU Process Pump Br-83 3.5-2 7.0-1 4.4+0 3.5-2 Br-84 3.4-2 1.6-1 9.7-1 3.4-2 Br-85 1.7-2 9.2-3 5.8-2 1.8-2 I-131 2.1-2 2.4-1 1.5+2 2.1-2 I-132 3.1-1 1.5-1 9.5+1 3.1-1 I-133 2.8-1 4.9-1 3.0+2 2.8-1 I-134 4.8-1 3.6+0 2.2+1 4.9-1 I-135 2.7-1 1.5+1 9.4+1 2.7-1 Rb-89 2.2-2 4.9-2 3.1-1 2.2-2 Sr-89 3.3-3 5.8+0 3.7+1 3.3-3 Sr-90 2.5-4 4.9-1 3.0+0 2.5-4 Sr-91 8.1-2 6.5+0 4.1+1 8.1-2 Sr-92 8.4-1 3.1+0 2.0+1 1.4-1 Y-90 5.3-8 3.6-1 2.2+0 3.8-8 Y-91m 5.3-4 2.6+0 1.6+1 3.7-4 Y-91 2.2-4 1.3+0 8.4+0 2.2-4 Y-92 3.1-2 4.1+0 2.5+1 3.1-2 Y-93 2.2-2 1.9+0 1.1+1 2.2-2 Mo-99 2.5-2 1.3+1 8.4+1 2.5-2 Tc-99m 1.1-1 1.7+1 1.1+2 1.1-1 La-141 8.3-4 6.1-1 3.8+0 5.9-4 La-142 2.5-2 3.2-1 2.0+0 2.5-2 Ce-141 1.7-4 4.4-1 2.8+0 1.7-4 Ce-143 1.6-4 4.4-2 2.8-1 1.0-4 Ce-144 3.8-5 7.2-2 4.6-1 3.8-5 Pr-143 2.2-4 3.3-1 2.0+0 2.2-4 Pr-144 1.8-6 7.2-2 4.5-1 1.3-6 Nd-147 1.7-5 2.2-2 1.4-1 1.7-5 Pm-147 1.0-11 1.3-4 8.0-4 7.2-12 Na-24 9.0-3 1.1+0 7.1+0 9.0-3 P-32 1.9-4 2.7-1 1.7+0 1.9-4 Cr-51 5.6-3 9.2+0 5.8+1 5.6-3 Mn-54 6.8-3 1.2-1 7.8-1 6.5-5 Mn-56 5.0-2 1.1+0 6.8+0 5.0-2 Fe-55 9.3-4 1.8+0 1.1+1 9.3-4 Fe-59 8.0-5 1.4-1 8.8-1 8.0-5 Co-58 5.0-3 9.1+0 5.7+1 5.0-3 Co-60 5.0-4 9.7-1 6.1+0 5.0-4 Ni-65 3.0-4 6.4-3 4.0-2 3.0-4 Cu-64 2.7-2 2.9+0 1.8-1 2.7-2 Zn-65 1.9-4 3.6-1 2.3+0 1.9-4 Zn-69m 1.8-3 2.1-1 1.3+0 1.8-3

2 of 2 August 1987 RBS USAR TABLE 12.2-6 (Cont)

Isotope RWCU Heat Exchanger RWCU Backwash Tank RWCU Filter/Demin RWCU Process Pump Zs-95 4.5-5 8.1-2 5.1-1 4.5-5 Tc-101 4.1-1 8.5-1 5.3+0 4.1-1 Tc-104 Neg.

9.5-1 6.0+0 Neg.

Ru-103 1.2-4 2.1-1 1.3+0 1.2-4 Ru-105 1.0-2 3.7-1 2.3+0 1.0-2 Ru-106 1.7-5 3.3-2 2.0-1 1.7-5 Rh-103m 1.7-6 2.1-1 1.3+0 1.2-6 Rh-105 2.9-6 1.6-4 1.0-4 2.3-5 Rh-106 1.4-5 3.3-2 2.0-1 1.2-5 Te-129m 3.7-4 6.2-1 3.9+0 3.7-4 Te-129 4.4-6 6.2-1 3.9+0 3.1-6 Te-131m 5.5-4 1.4-1 8.6-1 5.5-4 Te-131 3.6-6 2.8-2 1.7-1 2.6-6 Te-132 1.5-2 9.2+0 5.8+1 1.5-2 Cs-134 1.7-4 3.3-1 2.1+0 1.7-4 Cs-136 1.1-4 1.5-1 9.6-1 1.1-4 Cs-137 4.4-4 8.5-1 5.4+0 4.4-4 Cs-138 2.4-1 1.1+0 7.0+0 2.5-1 Ba-137m 1.1-4 7.8-1 4.9+0 8.3-5 Ba-134 2.0-1 2.3+0 1.5+1 2.0-1 Ba-140 9.5-3 1.3+1 8.1+1 9.5-3 Ba-141 2.3-1 6.1-1 3.8+0 2.3-1 Ba-142 2.1-1 3.4-1 2.1+0 2.2-1 La-140 3.3-6 1.1+1 7.0+1 2.3-6 Zs-97 3.6-5 5.0-3 3.2-2 3.6-5 Nb-95m 1.4-10 5.4-2 3.4-1 1.0-10 Nb-95 4.5-5 9.2-2 5.8-1 4.5-5 Nb-97m 2.0-5 4.8-3 3.0-2 1.6-5 Nb-97 1.4-7 9.8-3 6.2-2 7.9-8 Nb-98 Neg.

1.3-1 8.4-1 Neg.

Ag-110m 6.0-5 1.1-1 7.2-1 6.0-5 Ag-110 1.0-6 2.3-3 1.4-2 9.1-7 W-187 3.0-3 6.0-1 3.8+0 3.0-3 Np-239 Neg.

1.2+2 7.6+2 Neg.

N-16 9.6-2 Neg.

Neg.

7.5-1 NOTES: 3.5-2 = 3.5x10

-2 Neg. = Negligible

RBS USAR Revision 14 1 of 3 September 2001 TABLE 12.2-7 RCIC (TURBINE) AND RHR SYSTEM ACTIVITIES (µCi/CC)

Isotope RHR RCIC 14 Kr-83m 1.2-2 2.5-4 Kr-85m Negligible 4.5-4 Kr-85 Negligible 1.4-6 Kr-87 Negligible 1.5-3 Kr-88 Negligible 1.5-3 Kr-89 Negligible 9.0-3 Kr-90 Negligible 1.4-2 Xe-131m 1.8-4 1.1-6 Xe-133m 3.6-4 2.1-5 Xe-133 4.9-3 6.0-4 Xe-135m 5.0-2 2.0-3 Xe-135 5.0-2 1.7-3 Xe-137 Negligible 1.0-2 Xe-138 Negligible 6.3-3 Br-83 Negligible 2.4-5 Br-84 Negligible 2.4-5 Br-85 Negligible 1.4-5 I-131 1.9-2 1.6-5 I-132 9.1-2 2.2-4 I-133 2.2-1 2.2-4 I-134 1.8-2 4.4-4 I-135 1.6-1 2.0-4 Rb-88 Negligible 1.8-5 Rb-89 3.6-7 1.3-7 Sr-89 3.0-3 1.5-7 Sr-90 2.2-4 1.2-8 Sr-91 5.4-2 3.7-6 Sr-92 4.5-2 6.4-6 Y-90 9.5-6 6.2-13 Y-91m 2.3-2 8.9-9 Y-91 3.1-4 1.0-5 Y-92 5.2-2 1.4-6 Y-93 1.5-2 1.0-6 Zr-95 4.5-5 2.1-9 Zr-97 2.7-5 1.7-9 Nb-95m 2.5-8 6.6-16 Nb-95 4.0-5 2.1-9 Nb-97m 2.6-5 3.0-10 Nb-97 2.6-5 6.9-13 Mo-99 2.2-2 1.1-6 Tc-99m 6.9-2 4.6-6 14

RBS USAR Revision 14 2 of 3 September 2001 TABLE 12.2-7 (Cont)

Isotope RHR RCIC

  • 14 Tc-101 3.2-6 1.9-5 Ru-103 1.1-4 5.5-9 Ru-105 4.8-3 4.6-7 Ru-106 1.5-5 7.8-10 Rh-103m 1.0-4 2.0-11 Rh-105 2.1-6 3.5-11 Rh-106 1.5-5 2.7-10 Te-129m 3.3-4 1.7-8 Te-129 3.0-4 3.2-11 Te-131m 4.5-4 2.5-8 Te-131 9.1-5 4.7-11 Te-132 1.3-2 6.9-7 Cs-134 1.5-4 7.8-9 Cs-136 9.8-5 5.1-9 Cs-137 3.9-4 2.0-8 Cs-138 1.3-3 5.3-5 Ba-137m 3.6-4 1.5-9 Ba-139 2.4-2 9.2-6 Ba-140 8.4-3 4.4-7 Ba-141 2.4-5 1.1-5 Ba-142 3.6-8 1.0-5 La-140 5.6-4 3.8-11 La-141 9.0-3 9.6-9 La-142 3.7-3 1.0-6 Ce-141 1.9-4 7.8-9 Ce-143 1.3-4 7.4-9 Ce-144 3.4-5 1.8-9 Pr-143 2.0-4 7.8-14 Pr-144 3.4-5 2.1-11 Nd-147 1.5-5 7.8-10 Pm-147 1.8-9 1.2-16 N-13 3.5-9 3.2-4 N-16 Negligible 2.4+0 F-18 9.8-3 1.8-4 Na-24 6.7-3 4.1-7 P-32 1.7-4 8.7-9 Cr-51 5.0-3 2.6-7 Mn-54 5.8-5 3.0-9 Mn-56 1.5-2 2.3-6 Fe-55 8.3-4 4.3-8 Fe-59 7.1-5 3.7-9 Co-58 4.5-3 2.3-7 Co-60 4.5-4 2.3-8 Ni-65 9.0-5 1.4-8 14*

RBS USAR Revision 14 3 of 3 September 2001 TABLE 12.2-7 (Cont)

Isotope RHR RCIC

  • 14 Cu-64 2.0-2 1.2-6 Zn-65 1.7-4 8.7-9 Zn-69 1.3-3 7.3-8 Ag-110m 5.4-5 6.7-9 Ag-110 1.1-6 3.6-11 W-187 2.4-3 1.4-7 Np-239 2.2-1 1.2-5 14*

NOTE:

1.2-2 = 1.2x10

-2

RBS USAR TABLE 12.2-8 FUEL POOL COOLING AND CLEANUP SYSTEM ACTIVITIES Source Strength (MeV/cc-sec) at 3 Average Gamma Energies Source 0.4 MeV 0.8 MeV 1.3 MeV Spent Fuel Pool 1.3+4 6.7+5 3.2+5 Heat Exchanger Spent Fuel Pool 1.0+6 5.2+7 2.4+7 Cleanup Filters Spent Fuel Cleanup 9.1+3 4.8+5 2.2+5 Demineralizers NOTE:

1.3+4 = 1.3x10 4

1 of 1 August 1987

Revision 14 1 of 1 September 2001 RBS USAR TABLE 12.2-9 N-16 ACTIVITIES IN EQUIPMENT IN THE TURBINE BUILDING Component Activity (Ci/gm)

  • 14 Tube equalizer 2.5+2 High-pressure turbine 2.3+2 Moisture separator/reheater 2.1+2 Moisture separator drain tank 5.4+1 Reheater drain tank 2.6+1 Low-pressure turbine 2.0+2 Condenser 2.0+2 Hotwell 2.0+2 1st point heater (shell side) 2.1+2 2nd point heater 2.1+2 3rd point heater (shell side) 1.8+2 4th point heater 1.7+2 4th point drain cooler 1.4-1 5th point heater 2.0+2 Drain receiver tank 1.0+0 6th point heater 2.0+2 Air ejectors/air removal piping 8.8-1 14*

RBS USAR Revision 14 1 of 2 September 2001 TABLE 12.2-10 CONDENSATE - FEEDWATER SYSTEM SOURCE TERMS (µCi/cc)

Isotope Condensate Demineralizers Reactor Feedwater System

  • 14 Br-83 6.2-1 1.4-4 Br-84 1.3-1 1.4-4 Br-85 2.7-3 8.8-5 I-131 3.3+1 9.1-5 I-132 5.9+0 1.3-3 I-133 3.6+1 1.2-3 I-134 4.0+0 2.6-3 I-135 1.5+1 1.1-3 Rb-89 8.8-4 1.2-5 Sr-89 4.1-1 3.3-7 Sr-90 4.4-2 4.5-8 Sr-91 1.5-1 8.1-6 Sr-92 7.0-2 1.4-5 Sr-93 2.0-4 Neg Y-90 4.1-2 Neg Y-91m 6.0-2 Neg Y-91 1.0-1 2.2-8 Y-92 9.2-2 3.1-6 Y-93 4.3-2 2.2-6 Zr-95 6.0-3 4.5-9 Zr-97 1.2-4 3.6-9 Nb-95m 1.1-4 Neg Nb-95 7.4-3 4.5-9 Nb-97m 1.1-2 Neg Nb-97 1.2-4 Neg Nb-98 2.9-3 1.9-6 Mo-99 3.2-1 2.5-6 Tc-99m 4.0-1 1.1-5 Tc-101 1.5-2 4.3-5 Tc-104 1.8-2 3.8-5 Ru-103 1.4-2 1.2-8 Ru-105 8.4-3 1.0-6 Ru-106 2.9-3 1.7-9 Rh-103m 1.4-2 Neg Rh-105m 8.4-3 Neg Rh-105 2.3-5 Neg Rh-106 2.9-3 Neg Te-129m 3.9-2 3.7-8 Te-129 3.9-2 Neg Te-131m 3.1-3 5.5-8 Te-131 6.3-4 Neg Te-132 2.2-1 1.5-6 Cs-134 2.9-2 8.5-8 Cs-136 6.5-3 5.5-8 14*

RBS USAR Revision 14 2 of 2 September 2001 TABLE 12.2-10 (Cont)

Isotope Condensate Demineralizers Reactor Feedwater System Cs-137 7.8-2 2.2-7 Cs-138 2.3-2 1.3-4 Ba-137m 7.2-2 Neg Ba-139 5.1-2 2.0-5 Ba-140 5.3-1 9.5-7 Ba-141 1.2-2 2.4-5 Ba-142 5.7-3 2.3-5 La-140 5.3-1 Neg La-141 1.4-2 Neg La-142 7.1-3 2.5-6 Ce-141 2.7-2 1.7-8 Ce-143 1.0-3 1.6-8 Ce-144 6.3-3 3.8-9 Pr-143 1.4-2 2.2-8 Pr-144 6.3-3 Neg Nd-147 8.4-4 1.7-9 Pm-147 2.5-5 Neg Na-24 2.6-2 9.0-7 P-32 1.2-2 1.9-8 Cr-51 5.4-1 5.6-7 Mn-54 1.1-2 6.5-9 Mn-56 2.4-2 5.0-6 Fe-55 1.6-1 9.3-8

  • 14 Fe-59 9.5-3 8.0-9 Co-58 6.9-1 5.0-7 Co-60 8.8-2 5.0-8 Ni-65 1.4-4 3.0-8 Cu-64 6.6-2 2.7-6 Zn-65 3.1-2 1.9-8 Zn-69m 4.7-3 1.8-7 Ag-110m 9.9-3 6.0-9 Ag-110 2.0-4 Neg W-187 1.4-2 3.0-7 Np-239 1.8+0 2.6-5 N-13 Neg 4.2-3 F-18 Neg 4.0-4 14*

NOTE:

2.3-1 = 2.3x10

-1 Neg = Negligible

RBS USAR Revision 14 1 of 3 September 2001 TABLE 12.2-11a OFF GAS SYSTEM SOURCE ACTIVITIES (Ci)

Isotope Preheater Recombiner Off Gas Condenser Water Separator Holdup Pipe Kr-83m 2.7+3 8.1+3 2.3+5 3.2+4 5.3+6 Kr-85m 4.8+3 1.4+4 4.1+5 5.7+4 9.4+6 Kr-85 1.5+1 4.5+1 1.3+3 1.8+2 3.0+4 Kr-87 1.6+4 4.9+4 1.4+6 1.9+5 3.1+7 Kr-88 1.6+4 4.9+4 1.4+6 2.0+5 3.2+7 Kr-89 8.4+4 2.5+5 7.0+6 9.1+5 6.1+7 Kr-90 6.9+4 2.1+5 5.7+6 4.9+5 6.5+6 Xe-131m 1.2+1 3.6+1 1.0+3 1.4+2 2.4+4 Xe-133m 2.3+2 6.8+2 1.9+4 2.7+2 4.6+5 Xe-133 6.5+3 1.9+4 5.4+5 7.7+4 1.3+7 Xe-135m 2.0+4 6.1+4 1.7+6 2.4+5 3.3+7 Xe-135 1.8+4 5.4+4 1.5+6 2.1+5 3.6+7 Xe-137 9.9+4 3.0+5 8.3+6 1.1+6 8.4+7 Xe-138 6.6+4 2.0+5 5.6+6 7.7+5 1.0+8 Xe-139 8.6+4 2.6+5 7.2+6 6.8+5 1.1+7 Xe-140 1.8+4 5.4+4 1.4+6 6.9+4 3.9+5

  • 14 Br-83 6.9+2 2.1+3 5.8+4 8.2+3 1.3+6 Br-84 6.9+2 2.1+3 5.8+4 8.1+3 1.2+6 Br-85 3.5+2 1.0+3 2.9+4 3.8+3 2.4+5 I-131 4.5+2 1.4+3 3.8+4 5.4+3 9.0+5 I-132 6.2+3 1.9+4 5.2+5 7.4+4 1.2+7 I-133 5.8+3 1.7+4 4.9+5 7.0+4 1.2+7 I-134 1.3+4 3.8+4 1.1+6 1.5+5 2.4+8 I-135 5.7+3 1.7+4 5.2+5 6.8+4 1.1+7 14*

Rb-88 6.3+2 1.9+3 5.4+4 1.1+4 7.1+6 Rb-89 1.1+1 3.3+1 9.2+2 1.3+2 1.7+4 Sr-89 1.6+0 4.9+0 1.4+2 2.0+1 3.3+3 Sr-90 1.2-1 3.7-1 1.0+1 1.5+0 2.5+2 Sr-91 4.0+1 1.2+2 3.4+3 4.8+2 8.0+4 Sr-92 6.9+1 2.1+2 5.8+3 8.3+2 1.4+5 Y-90 2.2-5 6.7-5 1.9-3 3.9-4 2.9-1 Y-91m 2.2-1 6.6-1 1.9+1 3.8+0 2.7+3 Y-91 1.1-1 3.3-1 9.2+0 1.3+0 2.2+2 Y-92 1.6+1 4.7+1 1.3+3 1.9+2 3.3+4 Y-93 1.1+1 3.3+1 9.2+2 1.3+2 2.2+4 Zr-95 2.2-2 6.7-2 1.9+0 2.7-1 4.5+1 Zr-97 1.8-2 5.4-2 1.5+0 2.1-1 3.6+1 Nb-95m 5.9-8 1.8-7 5.1-6 1.0-6 7.7-4 Nb-95 2.2-2 6.7-2 1.9+0 2.7-1 4.5+1 Nb-97m 8.7-3 2.6-2 7.5-1 1.3-1 3.2+1 Nb-97 5.3-5 1.6-4 4.6-3 1.2-3 1.7+0 Mo-99 1.2+1 3.7+1 1.0+3 1.5+2 2.5+4 Tc-99m 5.5+1 1.6+2 4.6+3 6.6+2 1.1+5

2 of 3 August 1987 TABLE 12.2-11a (Cont)

Isotope Preheater Recombiner Off Gas Condenser Water Separator Holdup Pipe Tc-101 2.0+2 6.1+2 1.7+4 2.4+3 3.1+5 Ru-103 5.9-2 1.8-1 5.0+0 7.1-1 1.2+2 Ru-105 5.0+0 1.5+1 4.2+2 5.9+1 9.7+3 Ru-106 8.4-3 2.5-2 7.1-1 1.0-1 1.7+1 Rh-103m 7.1-4 2.1-3 6.1-2 1.2-2 8.9+0 Rh-105 1.1-3 3.1-3 9.1-2 1.5-2 5.6+0 Rh-106 6.3-3 1.9-2 5.4-1 8.8-2 1.7+1 Te-129m 1.8-1 5.5-1 1.6+1 2.2+0 3.7+2 Te-129 1.8-3 5.5-3 1.6-1 3.2-2 2.3+1 Te-131m 2.7-1 8.2-1 2.3+1 3.3+0 5.4+2 Te-131 1.5-3 4.5-3 1.3-1 2.6-2 1.8+1 Te-132 7.4+0 2.2+1 6.3+2 8.9+1 1.5+4 Cs-134 8.4-2 2.5-1 7.1+0 1.0+0 1.7+2 Cs-136 5.5-2 1.6-1 4.6+0 6.6-1 1.1+2 Cs-137 2.2-1 6.5-1 1.8+1 2.6+0 4.4+2 Cs-138 1.6+3 4.7+3 1.3+5 2.6+4 1.5+7 Ba-137m 4.8-2 1.4-1 4.1+0 7.8-1 3.1+2 Ba-139 9.8+1 2.9+2 8.3+3 1.2+3 1.9+5 Ba-140 4.7+0 1.4+1 4.0+2 5.7+1 9.4+3 Ba-141 1.1+2 3.4+2 9.6+3 1.4+3 1.9+5 Ba-142 1.1+2 3.2+2 9.0+3 1.3+3 1.5+5 La-140 1.4-3 4.1-3 1.2-1 2.3-2 1.8+1 La-141 3.5-1 1.0+0 3.0+1 5.9+0 4.0+3 La-142 1.2+1 3.7+1 1.0+3 1.5+2 2.4+4 Ce-141 8.4-2 2.5-1 7.1+0 1.0+0 1.7+2 Ce-143 7.9-2 2.4-1 6.7+0 9.5-1 1.6+2 Ce-144 1.9-2 5.6-2 1.6+0 2.3-1 3.8+1 Pr-143 1.1-1 3.3-1 9.2+0 1.3+0 2.2+2 Pr-144 7.4-4 2.2-3 6.4-2 1.3-2 8.4+0 Nd-147 8.4-3 2.5-2 7.1-1 1.0-1 1.7+1 PM-147 4.3-9 1.3-8 3.6-7 7.3-8 5.5-5 F-18 2.0+3 5.9+3 1.7+5 2.4+4 3.8+6 Na-24 4.5+0 1.3+1 3.8+2 5.4+1 8.9+3 P-32 9.4-2 2.8-1 7.9+0 1.1+0 1.9+2 Cr-51 2.8+0 8.3+0 2.3+2 3.3+1 5.6+3 Mn-54 3.2-2 9.6-2 2.7+0 3.9-1 6.4+1 Mn-56 2.5+1 7.4+1 2.1+3 3.0+2 4.8+4 Fe-55 4.6-1 1.4+0 3.9+1 5.5+0 9.2+2 Fe-59 4.0-2 1.2-1 3.3+0 4.8-1 7.9+1 Co-58 2.5+0 7.4+0 2.1+2 3.0+1 5.0+3 Co-60 2.5-1 7.4-1 2.1+1 3.0+0 5.0+2 Ni-65 1.5-1 4.4-1 1.3+1 1.8+0 2.9+2 Cu-64 1.3+1 4.0+1 1.1+3 1.6+2 2.7+4 Zn-65 9.4-2 2.8-1 7.9+0 1.1+0 1.9+2 Zn-69m 8.9-1 2.7+0 7.5+1 1.1+1 1.8+3 Ag-110m 3.0-2 8.9-2 2.5+0 3.6-1 6.0+1

RBS USAR Revision 14 3 of 3 August 1987 TABLE 12.2-11a (Cont)

Isotope Preheater Recombiner Off Gas Condenser Water Separator Holdup Pipe Ag-110 4.9-4 1.5-3 4.1-2 6.5-3 1.2+0 W-187 1.5+0 4.5+0 1.3+2 1.8+1 3.0+3 Nb-98 9.3+0 2.8+1 7.8+2 1.1+2 1.7+4 Tc-104 1.8+2 5.4+2 1.5+4 2.1+3 3.0+5 Np-239 1.3+2 3.9+2 1.1+4 1.5+3 2.6+5

  • 14 N-13 1.9+4 5.8+4 1.6+6 2.3+5 2.7+7 N-16 4.5+5 1.3+6 3.3+7 4.0+5 Negligible 14*

NOTE: 2.7+3 = 2.7x103

RBS USAR Revision 14 1 of 3 September 2001 TABLE 12.2-11b OFF GAS SYSTEM SOURCE ACTIVITIES (Ci)

Isotope Cooler Condenser Moisture Separator Prefilter Dryer Charcoal Bed (1st)

Charcoal Bed (Train)

Kr-83m 7.0+4 4.1+4 2.3+5 1.1+6 4.0+7 4.0+8 Kr-85m 1.3+5 7.4+4 4.2+5 2.0+6 1.5+8 1.8+8 Kr-85 4.1+2 2.4+2 1.4+3 6.5+3 1.0+6 4.2+6 Kr-87 4.0+5 2.4+5 1.3+6 6.4+6 1.5+8 1.5+8 Kr-88 4.3+5 2.5+5 1.4+6 6.8+6 3.5+8 3.7+8 Kr-89 2.3+5 1.4+5 7.4+5 3.2+6 2.1+6 2.1+6 Kr-90 7.1+0 4.2+0 1.9+1 5.2+1 7.7-1 7.7-1 Xe-131m 3.3+2 1.9+2 1.1+3 5.2+3 1.4+7 2.7+7 Xe-133m 6.3+2 3.7+2 2.1+3 1.0+4 1.0+8 1.1+8 Xe-133 1.8+5 1.0+5 5.9+5 2.8+6 5.2+9 7.0+9 Xe-135m 3.6+5 2.1+5 1.2+6 5.5+6 2.6+7 2.6+7 Xe-135 4.9+5 2.9+5 1.6+6 7.8+6 1.4+9 1.4+9 Xe-137 4.0+5 2.4+5 1.3+6 5.7+6 4.9+6 4.9+6 Xe-138 1.1+6 6.3+5 3.6+6 1.7+7 7.0+7 7.0+7 Xe-139 9.0+1 5.3+1 2.5+2 7.6+2 2.2+1 2.2+1 Xe-140 6.6-7 3.9-7 1.4-6 1.9-6 Negligible Negligible

  • 14 Br-83 1.8+4 1.0+4 5.9+4 2.8+5 Negligible Negligible Br-84 1.5+4 8.7+3 4.9+4 2.3+5 Negligible Negligible Br-85 8.3+2 4.9+2 2.7+3 1.1+4 Negligible Negligible I-131 1.2+4 7.2+3 4.1+4 2.0+5 Negligible Negligible I-132 1.6+5 9.4+4 5.3+5 2.6+6 Negligible Negligible I-133 1.6+5 9.2+4 5.3+5 2.5+6 Negligible Negligible I-134 3.0+5 1.8+5 1.0+6 4.8+6 Negligible Negligible I-135 1.5+5 8.9+4 5.1+5 2.4+6 Negligible Negligible 14*

Rb-88 1.6+5 9.7+4 5.3+5 2.6+6 3.62+8 3.85+8 Rb-89 1.9+2 1.1+2 6.1+2 2.9+3 Negligible Negligible Sr-89 4.5+1 2.6+1 1.5+2 7.1+2 Negligible Negligible Sr-90 3.4+0 2.0+0 1.1+1 5.4+1 Negligible Negligible Sr-91 1.1+3 6.3+2 3.6+3 1.7+4 Negligible Negligible Sr-92 1.8+3 1.1+3 6.0+3 2.9+4 Negligible Negligible Y-90 7.0-3 4.1-3 2.4-2 1.2-1 Negligible Negligible Y-91m 6.4+1 3.7+1 2.2+2 1.1+3 Negligible Negligible Y-91 3.0+0 1.8+0 1.0+1 4.9+1 Negligible Negligible Y-92 4.7+2 2.8+2 1.6+3 7.6+3 Negligible Negligible Y-93 2.9+2 1.7+2 9.8+2 4.7+3 Negligible Negligible Zr-95 6.1-1 3.6-1 2.0+0 9.7+0 Negligible Negligible Zr-97 4.8-1 2.8-1 1.6+0 7.7+0 Negligible Negligible Nb-95m 1.9-5 1.1-5 6.3-5 3.1-4 Negligible Negligible Nb-95 6.1-1 3.6-1 2.0+0 9.7+0 Negligible Negligible Nb-97m 4.6-1 2.7-1 1.6+0 7.4+0 Negligible Negligible Nb-97 4.4-2 2.6-2 1.5-1 7.5-1 Negligible Negligible Mo-99 3.4+2 2.0+2 1.1+3 5.4+3 Negligible Negligible Tc-99m 1.5+3 8.6+2 4.9+3 2.3+4 Negligible Negligible

RBS USAR Revision 14 2 of 3 September 2001 TABLE 12.2-11b (Cont)

Isotope Cooler Condenser Moisture Separator Prefilter Dryer Charcoal Bed (1st)

Charcoal Bed (Train)

Tc-101 3.3+3 1.9+3 1.1+4 5.1+4 Negligible Negligible Ru-103 1.6+0 9.5-1 5.4+0 2.6+1 Negligible Negligible Ru-105 1.3+2 7.7+1 4.4+2 2.1+3 Negligible Negligible Ru-106 2.3-1 1.4-1 7.7-1 3.7+0 Negligible Negligible Rh-103m 2.1-1 1.2-1 7.1-1 3.5+1 Negligible Negligible Rh-105 4.5-2 2.7-2 1.5-1 7.3+1 Negligible Negligible Rh-106 2.3-1 1.4-1 7.7-1 3.7+0 Negligible Negligible Te-129m 5.0+0 2.9+0 1.7+1 8.0+1 Negligible Negligible Te-129 5.5-1 3.2-1 1.9+0 9.2+0 Negligible Negligible Te-131m 7.4+0 4.3+0 2.5+1 1.2+2 Negligible Negligible Te-131 4.1-1 2.4-1 1.4+0 6.8+0 Negligible Negligible Te-132 2.0+2 1.2+2 6.8+2 3.2+3 Negligible Negligible Cs-134 2.3+0 1.4+0 7.7+0 3.7+1 Negligible Negligible Cs-136 1.5+0 8.7-1 5.0+0 2.4+1 Negligible Negligible Cs-137 6.0+0 3.5+0 2.0+1 9.5+1 Negligible Negligible Cs-138 3.2+5 1.9+5 1.1+6 5.2+6 1.3+8 1.3+8 Ba-137m 5.2+0 3.1+0 1.8+1 8.4+1 Negligible Negligible Ba-139 2.5+3 1.4+3 8.2+3 3.9+4 Negligible Negligible Ba-140 1.3+2 7.5+1 4.3+2 2.1+3 Negligible Negligible Ba-141 2.1+3 1.2+3 6.9+3 3.3+4 Negligible Negligible Ba-142 1.5+3 8.6+2 5.0+3 2.3+4 Negligible Negligible La-140 4.3-1 2.5-1 1.4+0 7.2+0 Negligible Negligible La-141 8.9+1 5.2+1 3.0+2 1.5+3 Negligible Negligible La-142 3.1+2 1.8+2 1.0+3 4.9+3 Negligible Negligible Ce-141 2.3+0 1.4+0 7.7+0 3.7+1 Negligible Negligible Ce-143 2.2+0 1.3+0 7.2+0 3.4+1 Negligible Negligible Ce-144 5.1-1 3.0-1 1.7+0 8.2+0 Negligible Negligible Pr-143 3.0+0 1.7+0 9.9+0 4.8+1 Negligible Negligible Pr-144 1.9-1 1.1-1 6.4-1 3.2+0 Negligible Negligible Nd-147 2.3-1 1.4-1 7.7-1 3.7+0 Negligible Negligible Pm-147 1.3-6 7.8-7 4.5-6 2.3-5 Negligible Negligible

  • 14 N-13 2.6+5 1.5+5 8.4+5 3.9+6 Negligible Negligible 14*

F-18 5.0+4 3.0+4 1.7+5 8.0+5 Negligible Negligible Na-24 1.2+2 7.1+1 4.0+2 1.9+3 Negligible Negligible P-32 2.6+0 1.5+0 8.6+0 4.1+1 Negligible Negligible Cr-51 7.6+1 4.4+1 2.5+2 1.2+3 Negligible Negligible Mn-54 8.8-1 5.1-1 2.9+0 1.4+1 Negligible Negligible Mn-56 6.4+2 3.8+2 2.1+3 1.0+4 Negligible Negligible Fe-55 1.3+1 7.4+0 4.2+1 2.0+2 Negligible Negligible Fe-59 1.1+0 6.3-1 3.6+0 1.7+1 Negligible Negligible Co-58 6.8+1 4.0+1 2.3+2 1.1+3 Negligible Negligible Co-60 6.8+0 4.0+0 2.3+1 1.1+2 Negligible Negligible Ni-65 3.9+0 2.3+0 1.3+1 6.1+1 Negligible Negligible Cu-64 3.6+2 2.1+2 1.2+3 5.8+3 Negligible Negligible Zn-65 2.6+0 1.5+0 8.6+0 4.1+1 Negligible Negligible

3 of 3 August 1987 TABLE 12.2-11B (Cont)

Isotope Cooler Condenser Moisture Separator Prefilter Dryer Charcoal Bed (1st)

Charcoal Bed (Train)

Zn-69m 2.4+1 1.4+1 8.0+1 3.9+2 Negligible Negligible Ag-110m 8.1-1 4.8-1 2.7+0 1.3+1 Negligible Negligible Ag-110 1.6-2 9.5-3 5.4-2 2.6-1 Negligible Negligible W-187 4.0+1 2.4+1 1.3+2 6.4+2 Negligible Negligible Nb-98 2.2+2 1.3+2 7.3+2 3.5+3 Negligible Negligible Tc-104 3.3+3 1.9+3 1.1+4 5.1+4 Negligible Negligible Np-239 3.5+3 2.1+3 1.2+4 5.6+4 Negligible Negligible NOTE: 7.0+4 = 7.0x104

RBS USAR TABLE 12.2-12 DESIGN SPECIFIC ACTIVITIES IN LIQUID RADWASTE SYSTEM TANKS (Ci/cc)

Floor Phase Waste Drain Regen Recovery Radwaste Separator Collection Collection Waste Sample Radwaste Deminer-Radwaste Flatbed

& Backwash Isotope Tank Tank Tank Tank Filter alizer Evaporator Filter Tanks (1)

Br-83 6.0-3 5.1-3 4.6-2 6.0-6 Neg 3.3-1 4.7-1 Neg 3.3-1 Br-84 1.3-3 1.1-3 6.2-3 1.3-6 Neg 1.6-2 2.3-2 Neg 7.2-2 Br-85 7.9-5 6.6-5 7.7-6 7.9-8 Neg 9.2-5 1.3-4 Neg 4.3-3 I-131 2.0-2 2.0-2 4.2+0 2.0-5 Neg 1.2+1 1.7+2 Neg 2.6+1 I-132 6.3-2 5.4-2 1.1+0 6.3-5 Neg 1.1+1 1.1+1 Neg 9.7+0 I-133 2.0-1 1.9-1 4.9+0 2.0-4 Neg 7.2+1 3.4+2 Neg 2.5+1 I-134 3.1-2 2.6-2 2.3-1 3.1-5 Neg 6.3-1 1.2+0 Neg 1.7+0 I-135 1.1-1 1.0-1 1.4+0 1.1-4 Neg l.7+1 3.0+1 Neg 7.0+0 Rb-89 4.2-4 3.5-4 1.4-4 2.1-5 Neg 2.5-3 3.2-4 Neg 2.3-2 Sr-89 3.3-3 3.3-3 7.0-1 3.3-6 Neg 2.2+0 3.0+0 Neg 1.0+l Sr-90 2.5-4 2.5-4 6.2-2 2.5-7 Neg 1.7-1 2.4-1 Neg 9.6-1 Sr-91 4.3-2 3.9-2 3.0-1 4.3-5 Neg 9.2+0 1.6+0 Neg 3.1+0 Sr-92 2.7-2 2.3-2 5.8-2 2.7-5 Neg 1.7+0 2.3-1 Neg 1.5+0 Y-90 2.5-5 2.5-5 5.2-2 2.5-8 Neg 4.6-2 1.0-1 Neg 8.7-1 Y-91m 1.7-2 1.5-2 1.3-1 l.7-5 Neg 4.0+0 6.4-1 Neg 1.2+0 Y-91 4.7-4 5.0-4 1.7-1 4.7-7 Neg 4.5-1 4.4-1 Neg 2.5+0 Y-92 3.3-2 2.9-2 1.4-1 3.3-5 Neg 4.4+0 6.0-1 Neg 1.9+0 Y-93 1.2-3 1.1-3 1.5-2 1.2-6 Neg 2.7-1 4.9-1 Neg 8.7-1 Mo-99 2.3-2 2.2-2 1.1+0 2.3-5 Neg 1.3+1 9.4+0 Neg 9.5+0 Tc-99m 5.5-2 5.0-2 1.2+0 5.5-5 Neg 1.7+1 8.7+0 Neg 1.1+1 Tc -101 7.4-3 6.1-3 2.4-3 7.4-6 Neg 4.1-2 4.0-3 Neg 3.9-1 Ru-103 1.2-4 1.2-4 2.4-2 1.2-7 Neg 7.9-2 1.1-1 Neg 3.5-1 Ru-105 3.1-3 2.6-3 1.0-2 3.1-6 Neg 3.2-1 4.2-2 Neg 1.7-1 Ru-106 1.7-5 1.7-5 4.1-3 1.7-8 Neg 1.1-2 1.6-2 Neg 6.4-2 Rh-103m 1.1-4 1.1-4 2.4-2 1.1-7 Neg 7.9-2 l.1-1 Neg 3.5-1 Rh-105 1.1-6 9.1-7 3.5-6 1.1-9 Neg 1.1-4 l.5-5 Neg 94-5 Rh-106 1.7-5 1.7-5 4.1-3 1.7-8 Neg l.l-2 1.6-2 Neg 6.4-2 Te-129m 3.7-4 3.7-4 7.3-2 3.7-7 Neg 2.4-1 l.l-i Neg 1.0+0 Tc-129 3.4-4 3.4-4 7.3-2 3.4-7 Neg Neg Neg Neg 1.0+0 Te-131m 4.4-4 4.2-4 9.l-3 4.4-7 Neg 1.9-1 4.2-2 Neg 7.6-2 Te-131 8.6-5 8.3-5 1.9-3 8.6-8 Neg 3.8-2 1.6-2 Neg 1.5-2 Te-132 1.4-2 1.4-2 7.4-1 1.4-5 Neg 7.8+0 3.3-1 Neg 6.8+0 Cs-134 1.7-4 1.7-4 4.2-2 8.5-6 Neg 1.1-1 3.3-1 Neg 6.5-1 Cs-136 1.1-4 1.1-4 1.6-2 5.4-6 Neg 7.0-2 8.3-2 Neg 2.0-1 Cs-137 4.4-4 4.4-4 1.1-1 2.2-5 Neg 2.9-1 1.7-2 Neg 1.7+0 Cs-138 9.7-3 8.1-3 6.2-3 4.8-4 Neg 1.2-1 6.4+0 Neg 5.2-1 Tc-104 8.2-3 6.9-3 1.8-3 6.9-6 Neg 5.7-2 7.4-3 Neg 4.4-1 Nb-98 1.2-3 9.7-4 4.3-4 1.2-6 Neg 2.2-2 2.8-6 Neg 6.2-1 Np-239 2.3-1 2.3-1 7.5-1 2.3-4 Neg 1.2+2 8.6+1 Neg 8.1+1 1 of 3 August 1987

RBS USAR TABLE 12.2-12 (Cont)

Floor Phase Waste Drain Regen Recovery Radwaste Separator Collection Collection Waste Sample Radwaste Deminer-Radwaste Flatbed

& Backwash Isotope Tank Tank Tank Tank Filter alizer Evaporator Filter Tanks (1)

Ba-137m 4.0-4 4.0-4 1.0-1 4.0-7 Neg 2.7-1 1.6-1 Neg 1.6+0 Ba-139 2.0-2 1.7-2 2.6-2 2.0-5 Neg 6.4-1 8.7-2 Neg 1.1+0 Ba-140 9.3-3 9.3-3 1.3-0 9.3-6 Neg 5.9+0 4.3-1 Neg l.7+1 Ba-141 5.3-3 4.4-3 2.2-3 5.3-6 Neg 3.7-2 1.6-2 Neg 2.8-1 Ba-142 3.0-3 2.5-3 7.l-4 3.0-6 Neg 1.2-2 3.9-1 Neg 1.6-1 La-140 1.4-3 1.7-3 7.6-0 1.4-6 Neg 2.4+0 8.1-2 Neg l.7+1 La-141 5.1-3 4.3-3 1.6-2 5.1-6 Neg 5.0-1 7.5+0 Neg 2.8-1 La-142 2.8-3 2.3-3 3.9-3 2.8-6 Neg 1.0-1 2.6-2 Neg 1.5-1 Ce-141 2.3-4 2.4-4 5.0-2 2.3-7 Neg 1.7-1 1.5-1 Neg 7.3-1 Ce-143 1.3-4 1.3-4 3.0-3 1.3-7 Neg 5.8-2 2.9-2 Neg 2.5-2 Ce-144 3.8-5 3.8-5 9.1-3 3.8-8 Neg 2.5-2 3.7-2 Neg 1.4-1 Pe-143 2.2-4 2.2-4 3.4-2 2.2-7 Neg 1.4-1 l.9-1 Neg 4.3-1 Pe-144 3.7-5 3.7-5 9.1-3 3.7-8 Neg 2.5-2 3.7-2 Neg 1.4-1 Nd-147 1.7-5 1.7-5 2.3-3 1.7-8 Neg 1.1-2 1.3-2 Neg 2.7-2 Pm-147 5.0-9 6.0-9 2.4-5 5.0-12 Neg 1.0-5 2.4-5 Neg 4.4-4 N-13 8.5-4 7.1-4 4.7-6 8.5-7 Neg 3.3-3 Neg Neg Neg F-18 6.5-3 5.4-3 3.9-4 6.5-6 Neg 2.8-1 Neg Neg Neg Na-24 5.9-3 5.5-3 7.1-3 5.9-6 7.0-1 1.8+0 4.3-1 7.1-3 5.4-1 P-32 1.9-4 1.9-4 3.2-3 1.9-7 2.7-2 1.2-1 1.5-1 3.2-3 3.6-1 Cr-51 5.5-3 5.5-3 1.4-1 5.5-6 7.8-1 3.6+0 4.8+0 1.4-1 1.5+1 Mn-54 6.5-5 6.5-5 2.5-3 6.5-8 9.3-3 4.3-2 6.0-2 2.5-3 2.4-1 Mn-56 9.3-3 7.8-3 4.5-3 9.3-6 5.5-1 5.6-1 7.3-2 4.5-3 5.0-1 Fe-55 9.3-4 9.3-4 3.7-2 9.3-7 1.3-1 6.2-1 9.0-1 3.7-2 3.5+0 Fe-59 8.0-5 7.9-5 2.3-3 8.0-8 1.1-2 3.6-2 7.4-2 2.3-3 2.4-1 Co-58 5.0-3 5.0-3 1.6-1 5.0-6 7.l-l 3.3+0 5.0+0 1.6-1 1.7+1 Co-60 5.0-4 5.0-4 2.0-2 5.0-7 7.1-2 3.3-1 4.7-1 2.0-2 1.9+0 Ni-65 5.5-5 4.6-5 2.7-5 5.5-8 3.2-3 3.3-3 4.2-4 2.7-5 3.0-3 Cu-64 1.7-2 1.5-2 1.8-2 1.7-5 2.0+0 4.5+0 9.6-l 1.8-2 1.4+0 Zn-65 1.9-4 1.9-4 7.2-3 l.9-7 2.7-2 1.3-1 1.8-1 7.2-3 7.0-1 Zn-69m 1.1-3 1.0-3 1.3-3 1.1-6 1.3-1 3.1-1 7.3-2 1.3-3 9.8-2 Zr-95 4.5-5 4.5-5 l.4-3 4.5-8 Neg 3.0-2 4.2-2 Neg 1.5-1 Zr-97 2.5-5 2.3-5 3.2-5 2.5-8 Neg 8.0-3 2.1-3 Neg 2.4-3 Nb-95m 3.4-6 4.0-6 3.6-4 3.4-9 Neg 6.4-3 1.5-2 Neg 1.3-1 Nb-95 4.5-5 4.5-5 1.8-3 4.5-8 Neg 3.0-2 4.3-2 Neg 2.0-1 Nb-97m 2.4-5 2.2-5 3.1-5 2.4-8 Neg 7.7-3 2.0-3 Neg 2.3-3 Nb-97 4.5-5 4.3-5 4.7-5 4.5-8 Neg 1.7-2 4.1-3 Neg 4.8-3 Ag-110m 6.0-5 6.0-5 2.3-3 6.0-8 Neg 4.0-2 6.0-2 Neg 2.2-1 2 of 3 August 1987

RBS USAR TABLE 12.2-12 (Cont)

Floor Phase Waste Drain Regen Recovery Radwaste Separator Collection Collection Waste Sample Radwaste Deminer-Radwaste Flatbed

& Backwash Isotope Tank Tank Tank Tank Filter alizer Evaporator Filter Tanks (1)

Ag-110 1.2-6 1.2-6 4.6-5 1.2-9 Neg 8.0-4 1.2-3 Neg 4.4-3 W-187 2.2-3 2.2-3 4.0-3 2.3-6 Neg 8.9-l 3.3-1 Neg 3.1-1 NOTE: 6.03-3 = 6.03 x 10

-3 Neg = Negligible (1)Phase separator tank source terms provide a conservative estimate of backwash rank source terms.

3 of 3 August 1987

1 of 1 August 1987 TABLE 12.2-13 MATERIAL COMPOSITION OF THE TIP SYSTEM COMPONENTS AS USED IN ACTIVATION CALCULATIONS Detector Region Material Weight (g )

AISI 304 Stainless Steel 4

Commercially Pure Titanium 3

Fosterite Ceramic 0.5 Nichrome 0.02 Uranium 235 0.001 Cable Region Weight (g/in)

AISI 3041 Stainless Steel 0.12 AISI C1070 Carbon Steel 2.10 Magnesium Oxide 0.12

1 of 1 August 1987 TABLE 12.2-14 TRAVERSING INCORE PROBE DETECTOR DECAY GAMMA ACTIVITIES IN MEV/SEC OF 0.001g OF U-235 Decay Time = 10 0 Sec Activation Time = 10 2 Sec Energy-mev Activity 0.1 - 0.4 3.4 + 9 0.4 - 0.9 1.5 + 10 0.9 - 1.35 1.2 + 10 1.35 - 1.8 1.1 + 10 1.8 - 2.2 8.0 + 9 2.2 - 2.6 6.4 + 9 2.6 - 3.0 5.6 + 9 3.0 - 3.5 5.1 + 9 3.5 - 4.0 4.3 + 9 4.0 - 4.5 2.5 + 9 4.5 - 5.0 1.5 + 9 5.0 - 5.5 7.9 + 8 NOTE:

3.4+9 = 3.4x10 9

TABLE 12.2-15 TRAVERSING INCORE PROBE DETECTOR DECAY GAMMA ACTIVITIES OF MATERIALS IN THE DETECTOR (EXCLUDING U-235) IN MICROCURIES IN THE IRRADIATED DETECTOR Decay Time = 10 0 sec Activation Time = 10 2 sec Activated Isotopes Activity FE-59 1.1 + 1 MN-56 1.7 + 5 CR-51 7.0 + 1 MN-54 2.1 + 0 CO-58M 3.5 + 3 CO-58 2.2 - 2 NI-57 1.1 - 1 CO-57 6.0 - 7 NI-65 4.0 + 2 CO-60M 7.6 + 3 CO-60 1.8 - 3 CO-61 9.6 + 0 SI-31 2.9 + 1 NOTE:

1.1+1 = 1.1x10 1

1 of 1 August 1987 TABLE 12.2-16 DECAY GAMMA ACTIVITIES OF MATERIALS IN THE CABLE IN MICROCURIES PER INCH OF IRRADIATED CABLE Decay Time = 10 0 sec Activation Time = 10 2 sec Activated Isotopes Activity FE-59 8.2 + 0 MN-56 7.4 + 4 CR-51 3.7 + 0 MN-54 1.6 + 0 CO-58M 1.0 + 2 CO-58 6.5 - 4 NI-57 3.3 - 3 CO-57 1.8 - 8 NI-65 1.2 + 1 CO-60M 2.2 + 2 CO-60 5.1 - 5 CO-61 2.8 - 1 SI-31 8.7 - 1 NOTE:

8.2+0 = 8.2x10 0

RBS USAR Revision 14 1 of 2 September 2001 TABLE 12.2-17 EXPECTED IN-PLANT AIRBORNE RADIOACTIVITY CONCENTRATIONS (Ci/cc)

Kr83m 6.5-11*

Neg Neg Kr85m 3.8-10 Neg Neg Kr85 5.3-10 Neg Neg Kr87 2.1-10 Neg Neg Kr88 7.0-10 Neg Neg Kr89 3.7-12 Neg Neg Xe131m 7.5-11 Neg Neg Xe133m 3.1-10 Neg Neg Xe133 2.0-8 Neg Neg Xe135m 2.3-11 Neg Neg Xe135 3.7-9 Neg Neg Xe137 6.0-12 Neg Neg Xe138 4.5-11 Neg Neg

  • 14 I131 3.2-11 1.5-10 5.6-11 I132 2.1-11 Neg Neg I133 7.4-11 2.1-9 7.9-10 I134 2.2-11 Neg Neg I135 3.6-11 Neg Neg Br83 2.4-12 Neg Neg Br84 8.2-13 Neg Neg Br85 4.0-14 Neg Neg Rb88 2.1-9 Neg Neg Cr51 Neg 5.5-12 2.0-13 Mn54 Neg 1.2-11 1.1-12 14*

Fe59 Neg 1.6-12 8.5-14 Co58 Neg 3.6-12 5.6-14 Co60 Neg 3.3-11 2.0-12 Zn65 Neg 4.9-11 8.5-14 Sr89 Neg 5.5-13 Neg Sr90 Neg 9.8-14 Neg Zr95 Neg 4.4-12 2.3-13 Nb95 Neg 8.7-12 1.1-15 Md99 Neg 1.6-12 8.5-16 Ru103 Neg 5.2-13 2.8-16 Ag110 Neg Neg Neg Ag110m Neg 3.0-14 Neg Sb124 Neg 4.9-13 2.0-14 Cs134 Neg 1.5-11 6.8-13 Cs136 Neg 3.0-12 Neg

RBS USAR Revision 14 2 of 2 September 2001 TABLE 12.2-17 (Cont)

Radwaste Containment Containment Building During Normal During Pump Isotope Operation Refueling Rooms Cs137 Neg 2.6-11 1.1-12

  • 14 Cs-138 1.25-10 Neg Neg 14*

Ba140 Neg 1.2-11 1.1-15 Ce141 Neg 3.6-12 2.0-15 H-3 Neg 2.0-7 Neg

  • 6.5

-11 = 6.5 x 10

-11

RBS USAR Revision 14 1 of 1 September 2001 TABLE 12.2-18 EXPECTED CONTAINMENT AIRBORNE RADIOACTIVITY CONCENTRATIONS FOLLOWING MSIV CLOSURE Concentration (Ci/cc) at Time Seconds Hours Isotope 200 1000 5000 3

6 18

7.56-9 1.79-8 2.21-8 7.90-9 1.39-10 I-132 4.81-8 9.93-8 1.99-7 2.03-7 2.94-8 1.41-11 I-133 4.51-8 9.72-8 2.26-7 2.75-7 9.00-8 1.11-9 I-134 9.77-8 1.89-7 3.02-7 2.50-7 8.17-9 1.12-14 I-135 4.41-8 9.37-8 2.10-7 2.42-7 6.41-8 3.39-10 Br-83 1.85-10 3.84-10 7.74-10 7.88-10 1.14-10 5.66-14 Br-84 1.75-10 3.18-10 4.25-10 3.18-10 2.49-12 Neg.

Br-85 5.74-11 3.47-11 2.29-11 1.58-11 Neg.

Neg.

14*

Kr-83M 9.3-7 1.8-6 3.5-6 3.4-6 4.2-7 9.7-11 Kr-85M 1.8-6 3.5-6 7.2-6 8.0-6 1.8-6 4.9-9 Kr-85 4.4-7 4.2-7 3.1-7 2.0-7 7.2-8 1.3-9 Kr-87 5.5-6 1.1-5 1.9-5 1.7-5 1.2-6 3.8-11 Kr-88 5.8-6 1.1-5 2.3-5 2.4-5 4.1-6 3.8-9 Rb-88 4.1-7 3.7-6 1.6-5 1.8-5 4.7-6 4.4-9 Kr-89 2.4-5 1.5-5 9.9-6 6.8-6 Neg.

Neg.

Xe-131M 4.5-8 4.6-8 4.6-8 4.0-8 1.4-8 2.6-10 Xe-133M 2.2-7 3.0-7 4.7-7 5.1-7 1.8-7 2.8-9 Xe-133 1.2-5 1.4-5 1.7-5 1.7-5 6.0-6 1.0-7 Xe-135M 6.5-6 9.7-6 9.0-6 6.2-6 8.1-10 6.7-13 Xe-135 7.8-6 1.4-5 3.0-5 3.4-5 1.0-5 7.3-8 Xe-137 2.9-5 2.1-5 1.4-5 9.6-6 Neg.

Neg.

Xe-138 2.1-5 3.3-5 3.2-5 2.2-5 4.7-9 Neg.

Cs-138 7.8-7 6.5-6 1.1-5 2.8-6 1.4-7 4.8-16

  • 1.3-9 = 1.3 x 10

-9

RBS USAR TABLE 12.3-1 AREA DIRECT RADIATION MONITOR LOCATIONS Equipment Range Monitor Number Area Monitor (mrem/hr)

Set Point Location 3

Revision 16 1 of 4 March 2003 1RMS

3

  • RE 20A Drywell - PAM A 10 0 - 10 8 R/hr See note 1 Drywell
  • RE 20B Drywell - PAM B 10 0 - 10 8 R/hr See note 1 Drywell

-RE 138 Personnel airlock to drywell 10 0 - 10 5

See note 3 Reactor Building El 130' - 7"

16

-RE 139 Removed From Service, Controlled 10 0 - 10 5

See note 3, 4 Reactor Building El 123' - 6" in Accordance with ADM-0045 16

-RE 140 Refueling floor near north 10 10 4

See note 3 Reactor Building El 186' - 3" entrance

-RE 141 Refueling floor near south 10 10 4

See note 3 Reactor Building El 186' - 3" entrance

-RE 143 RWCU precoat pump and tank area 10 10 4

See note 3 Reactor Building El 162' - 3"

-RE 144 General area 10 10 4

See note 3 Reactor Building El 141' - 0"

-RE 145 Fuel transfer tube area 10 10 4

See note 3 Reactor Building El 114' - 0"

-RE 146 Airlock 10 10 4

See note 3 Reactor Building El 114' - 0"

-RE 147 TIP area 10 10 4

See note 3 Reactor Building El 95' - 9"

RBS USAR TABLE 12.3-1 (Cont)

Equipment Range Monitor Number Area Monitor (mrem/hr)

Set Point Location 3 14

Revision 16 2 of 4 March 2003

14 3

-RE 149 Unit cooler general area 10 10 4

See note 3 Reactor Building El 162' - 3"

16

-RE 150 Removed From Service, Controlled 10 1 - 10 7 R/hr See note 3, 4 Reactor Building El 128' - 1 3/4" in Accordance with ADM-0045 16

-RE 151 Reactor sample station area 10 10 4

See note 3 Reactor Building El 162' - 3"

-RE 152 Hydraulic control units east bank 10 10 4

See note 3 Reactor Building El 114' - 0"

-RE 162 Off gas regeneration area 10 10 4

See note 3 Off Gas Building El 67' - 6"

-RE 164 Off gas sample rack area 10 10 4

See note 3 Off Gas Building El 123' - 6"

-RE 165 Off gas demineralizer 10 0 - 10 5

See note 3 Off Gas Building El 67' - 6" regeneration area

-RE 166 Off gas demineralizer/

10 10 4

See note 3 Off Gas Building El 95' - 0" strainer valve area

-RE 167 Off gas building valve area 10 0 - 10 5

See note 3 Off Gas Building El 137' - 6"

-RE 170 Main control room 10 10 3

See note 3 Control Building El 135' - 0"

-RE 171 High level counting room 10

-2 - 10 3

See note 3 Services Building

-RE 172 Hot machine shop 10

-2 - 10 3

See note 3 Auxiliary Control Building El 95' - 0"

12

-RE 180 Removed From Service.

10

-1 - 10 4

See note 3, 4 Radwaste Building El 136' - 0" Controlled in Accordance With ADM-0045 12

-RE 181 Radwaste sample room 10 10 4

See note 3 Radwaste Building El 106' - 0"

-RE 182 Radwaste recovery sample 10 10 4

See note 3 Radwaste Building El 65' - 0" pump area

RBS USAR TABLE 12.3-1 (Cont)

Equipment Range Monitor Number Area Monitor (mrem/hr)

Set Point Location 3

Revision 16 3 of 4 March 2003

16 3

-RE 185 Removed From Service, Controlled 10 0

- 10 5

See note 3, 4 Radwaste Building El 90' - 0" in Accordance with ADM-0045

-RE 186 Floor drain sump area 10 10 4

See note 3 Radwaste Building El 65' - 0"

-RE 187 High conductivity sump area 10 10 4

See note 3 Radwaste Building El 65' - 0"

-RE 188 Radwaste solidification area 10 0 - 10 5

See note 3 Radwaste Building El 106' - 0"

-RE 192 Fuel building 10

-1

- 10 4

See note 3 Fuel Building El 113' - 0" refueling platform

14

-RE 193 Fuel building operating floor 10

-1 - 10 4

See note 3 Fuel Building El 113' - 0" 14

-RE 194 Removed From Service, Controlled 10

+1 - 10 7

See note 3, 4 Fuel Building El 113' - 0" in Accordance with ADM-0045 16

-RE 195 Fuel building sample station 10

-1 - 10 4

See note 3 Fuel Building El 95' - 0"

-RE 196 Equipment drain sump area 10

-1

- 10 4

See note 3 Fuel Building El 70' - 0"

-RE 200 Turbine building 10

-1 - 10 4

See note 3 Turbine Building El 123' - 6" northeast hoist area

-RE 201 Air removal pumps area 10

-1

- 10 4

See note 3 Turbine Building El 95' - 0"

-RE 202 Reactor feed pump area 10

-1

- 10 4

See note 3 Turbine Building El 67' - 6"

-RE 203 Turbine building sample room 10

-1

- 10 4

See note 3 Turbine Building El 67' - 6"

-RE 204 Condensate demineralizer 10 - 10 4

See note 3 Turbine Building El 95' - 0" sample sink area

-RE 210 Post-accident sample panel area 10 10 3

See note 3 Auxiliary Building El 114' - 0"

RBS USAR TABLE 12.3-1 (Cont)

Equipment Range Monitor Number Area Monitor (mrem/hr)

Set Point Location 3

Revision 14 4 of 4 September 2001

3

-RE 211 Control rod drive maintenance 10 10 4

See note 3 Auxiliary Building El 95' - 9" area

-RE 212 HPCS area 10 10 4

See note 3 Auxiliary Building El 78' - 6"

-RE 213 RHR equipment room A 10 - 10 4

See note 3 Auxiliary Building El 70' - 0"

-RE 214 RHR equipment room B 10

-1 - 10 4

See note 3 Auxiliary Building El 78' - 6"

-RE 215 RHR equipment room C 10

-1 - 10 4

See note 3 Auxiliary Building El 95' - 9"

-RE 216 LPCS equipment room 10 - 10 4

See note 3 Auxiliary Building El 78' - 6"

-RE 217 HPCS penetration area 10

-1 - 10 4

See note 3 Auxiliary Building El 78' - 0"

-RE 218 LPCS penetration area 10

-1 - 10 4

See note 3 Auxiliary Building El 78' - 6"

-RE 219 RCIC equipment room 10

-1 - 10 4

See note 3 Auxiliary Building El 95' - 9" Notes: 1.

Set points for these monitors will be in accordance with Section 13.3, Emergency Planning.

14 8

2. Deleted 8 14
3. Set points for these monitors will be determined by Radiation Protection taking into account radiation zoning, personnel occupancy, plant operating mode, and other considerations.

12

4. Procedure ADM-0045, System Management and Utilization of the DRMS 12

RBS USAR TABLE 12.3-2 AIRBORNE PROCESS AND EFFLUENT RADIATION MONITORS Equipment Number QA Cat/

Seismic Category Monitor Location Monitor Type Detector Channels Limiting Channel Isotopes Range uCi/cc Set Points High Alert Functions Revision 22 1 of 3 IRMS

  • RE 5A I/I Fuel Bldg Ventilation Exhaust Fuel Bldg.

El 148 Offline gas auto-isokinetic sampling Gaseous Xe-133 10-7-105 Tech. Spec.

High/alert radiation levels alarm (5A,5B);

Diverts exhaust air through filter train on high radiation In fuel building.

  • RE 5B I/I Fuel Bldg Ventilation Exhaust Fuel Bldg.

El 148 Offline gas &

Particulate Auto-isokinetic sampling Particulate Gaseous I-131 Xe-133 10-11-10-5 10-7-10-1 (Particulate iodine sampling to 102 uCi/cc)

Tech. Spec.

Exhaust (5A,5B); Post-accident monitor (5A)

  • 8

-RE 6A II/Non Radwaste Bldg Ventilation Exhaust Radwaste Bldg. El 166 Offline Gas Auto-isokinetic sampling Gaseous Xe-133 Kr-85 10-7-105 10-7-105 Tech. Req.

High/alert radiation levels alarm

-RE 6B II/Non Radwaste Bldg.

Ventilation Exhaust Radwaste Bldg. El 166 Offline gas &

Particulate Auto-isokinetic sampling Particulate Gaseous I-131 Kr-85 Xe-133 10-11-10-5 10-7-10-1 10-710-1 (Particulate iodine sampling to 102 uCi/cc)

Tech. Req.

High/alert radiation levels alarm

  • RE 125 I/I Main Plant Exhaust Duct Aux. Bldg. El 170 Offline Gas Auto-isokinetic sampling Gaseous Gaseous Xe-133 Kr-85 10-7-105 10-7-105 Tech. Req.

High/alert radiation levels alarm (125, 126);

Post-accident monitor (125) 8*

RBS USAR TABLE 12.3-2 (Continued)

AIRBORNE PROCESS AND EFFLUENT RADIATION MONITORS Equipment Number QA Cat/

Seismic Category Monitor Location Monitor Type Detector Channels Limiting Channel Isotopes Range uCi/cc Set Points High Alert Functions

  • 8 Revision 22 2 of 3 IRMS

-RE 126 II/Non Main Plant Exhaust Duct Aux. Bldg.

El 170 Offline gas &

particulate auto-iso-kinetic sampling Particulate Gaseous I-131 Kr-85 Xe-133 10-11-10-5 10-7-10-1 10-710-1 (Particulate iodine sampling to 10-2 uCi/cc)

Tech. Req..

8* *10

Particulate sampling trees Particulate Gaseous I-131 Xe-133 Kr-85 10-11-10-5 10-7-10-1 10-7-10-1 High/alert radiation levels alarm; Reactor Coolant pressure boundary leak detection 10**13

  • RE 11A
  • RE 11B I/I Reactor Bldg Annulus Ventilation Aux. Bldg.

El 170 El 141 Offline Gas Isokinetic sampling Gaseous Xe-133 10-7-10-1 High/alert radiation levels alarm; Initiates standby gas treatment system on high radiation 13*

  • RE 112 I/I Drywell Atmosphere Containment El 141 Offline gas &

Particulate sampling trees Particulate Gaseous I-131 Xe-133 Kr-85 10-11-10-5 10-7-10-1 10-7-10-1 Tech Spec.

High/alert radiation levels alarm; Reactor coolant pressure boundary leak detection

  • RE 13A
  • RE 13B I/I Main Control Room Local Intake Control Bldg.

Offline Gas Isokinetic sampling Gaseous Xe-133 Kr-85 10-7-10-1 10-7-10-1 Tech. Spec.

High/alert level alarms Diverts exhaust air through filter train on high radiation of local outside air intake

  • 8
  • RE 14A
  • RE 14B I/I Main Control Room Remote Intake Offline Gas Isokinetic sampling Gaseous Xe-133 Kr-85 10-7-10-1 10-7-10-1 Tech. Req.

High/alert radiation levels alarm 8*

RBS USAR TABLE 12.3-2 (Continued)

AIRBORNE PROCESS AND EFFLUENT RADIATION MONITORS Equipment Number QA Cat/

Seismic Category Monitor Location Monitor Type Detector Channels Limiting Channel Isotopes Range uCi/cc Set Points High Alert Functions

  • 8 3 of 3 August 1987 1RMS

-RE 110 II/Non Aux. Bldg.

Ventilation Aux. Bldg. El 141 Offline gas &

Particulate Auto-isokinetic sampling Particulate Gaseous I-131 Xe-133 Kr-85 10-11-10-5 10-7-10-1 10-7-10-1 Tech Spec.

High/alert radiation levels alarm

-RE 118 II/Non Turbine Bldg.

Ventilation Turbine Bldg.

El 123 Offline Gas &

Particulate Auto-Iso-kinetic sampling Particulate Gaseous I-131 Xe-133 Kr-85 10-11-10-5 10-7-10-1 10-7-10-1 Tech. Spec.

High/alert radiation levels alarm

  • 8

-RE 124 II/Non Cond/Demin

& Offgas Bldg Ventilation Turbine Bldg.

El 123 Offline Gas &

Particulate Auto-iso-kinetic sampling Particulate Gaseous I-131 Xe-133 10-11-10-5 10-7-10-1 10-7-10-1 Tech. Spec.

High/alert radiation levels alarm

RRBBSS UUSSAARR 11 ooff 11 AAuugguusstt 11998877 TTAABBLLEE 1122..33--33 AAIIRRBBOORRNNEE PPAARRTTIICCUULLAATTEE RRAADDIIOOAACCTTIIVVIITTYY MMOONNIITTOORRIINNGG CCAAPPAABBIILLIITTIIEESS BBllddgg AArreeaa wwiitthh MMoonniittoorr EEqquuiilliibbrriiuumm** MMiinniimmuumm MMoonniittoorr MMiinniimmuumm PPaarrttiiccuullaattee CCoonncceennttrraattiioonnss aatt DDeetteeccttaabbllee CCoonncceennttrraattiioonn ((CCii//cccc))

MMaarrkk MMoonniittoorreedd VVeennttiillaattiioonn MMoonniittoorr CCoorrrreessppoonnddiinngg ttoo 11 MMPPCC

@@11 iinn//hhrr FFiilltteerr

@@00..55 iinn//hhrr FFiilltteerr NNuummbbeerr BBuuiillddiinngg FFllooww RRaattee IInn BBllddgg ((CCii//cccc))

IInn AArreeaa ((CCii//cccc))

SSppeeeedd SSppeeeedd 11RRMMSS--RREE111188 TTuurrbbiinnee BBllddgg MMVVPP aarreeaa ((440000 ccffmm))

55..4466xx1100--99 44..9966xx1100--1111 33..7788xx1100--1122 11..8899xx1100--1122

((4444,,000000 ccffmm))

11RRMMSS**RREE55BB FFuueell BBllddgg SSFFCC ddeemmiinn ccuubbiiccllee 22..9966xx1100--99 44..4444xx1100--1111 11..8811xx1100--1111 99..0055xx1100--1122

((1100,,000000 ccffmm))

((115500 ccffmm))

11RRMMSS--RREE111100 AAuuxx BBllddgg CCRRDD wwoorrkk aarreeaa 99..3311xx1100--99 11..8866xx1100--1100 66..5511xx1100--1122 33..2255xx1100--1122

((1100,,000000 ccffmm))

((220000 ccffmm))

11RRMMSS--RREE112244 OOffffggaass BBllddgg PPrreeffiilltteerr aarreeaa 55..4466xx1100--99 55..6688xx1100--1111 33..7722xx1100--1122 11..8899xx1100--1122

((99,,661100 ccffmm))

((110000 ccffmm))

11RRMMSS--RREE66BB RRaaddwwaassttee BBllddgg 11..5544xx1100--99 55..2211xx1100--1111 22..6611xx1100--1111

((8800,,440000 ccffmm))

    • EEqquuiilliibbrriiuumm iiss rreeaacchheedd wwiitthhiinn 11..77 hhrr aatt tthhee 11 iinn//hhrr ffiilltteerr ssppeeeedd aanndd wwiitthhiinn 33..44 hhrr aatt tthhee 00..55 iinn//hhrr ffiilltteerr//ssppeeeedd..
        • TThhee rraaddwwaassttee bbuuiillddiinngg eefffflluueenntt cchhaannnneell iiss ccaappaabbllee ooff ddeetteeccttiinngg 1100 MMPPCC--hhrr iinn aallll aarreeaass eexxcceepptt tthhee llaauunnddrryy rroooomm,, ttrruucckk ppiitt,, aanndd ssaammppllee rroooomm..

RBS USAR 1 of 1 August 1987 TABLE 12.3-4 DRMS PCAM PLUG-IN JUNCTION BOX LOCATIONS J-Box Mark No.

Building Elevation Description 1RMS-JB300 Containment 186'-3" East Side Refueling Floor 1RMS-JB301 Containment 186'-3" West Side Refueling Floor 1RMS-JB302 Containment 114'-0" East HCU Area 1RMS-JB303 Containment 114'-0" West HCU Area 1RMS-JB304 Auxiliary 95'-9" Outside RWCU Pump Room 1RMS-JB305 Auxiliary 95'-9" CRD Transfer and Work Area 1RMS-JB306 Auxiliary 114'-0" PASS Room 1RMS-JB307 Auxiliary 141'-0" Aux Bldg El 141'-0" 1RMS-JB308 Auxiliary 171'-0" Personnel Air Lock 1RMS-JB309 Fuel 113'-0" Fuel Handling and Containment Air Lock 1RMS-JB310 Fuel 148'-0" Ventilation Exhaust 1RMS-JB311 Offgas 123'-0" Off-gas Area 1RMS-JB312 Turbine 67'-6" Condensate Pump Area 1RMS-JB313 Turbine 95'-0" Air Removal Pump Area 1RMS-JB314 Auxiliary 95'-0" Hot Machine Shop Control 1RMS-JB315 Auxiliary 123'-6" Auxiliary Control Control Room 1RMS-JB316 Radwaste 106'-0" Passageway 1RMS-JB317 Radwaste 166'-0" Ventilation Exhaust 1RMS-JB318 Service 109'-3" HP/CHEM 1RMS-JB319 Service 123'-6" TSC 1RMS-JB320 Control 136'-0" Control Room 1RMS-JB321 Administra-97'-0" PAP tion 1RMS-JB323 Radwaste 136'-0" Laundry Room Area 1RMS-JB324 Radwaste 106'-0" Truck Pit Area

RBS USAR Revision 14 1 of 1 September 2001 TABLE 12.3-5 MAIN PLANT EXHAUST DUCT MONITOR - DOSES TO PHASE I PERSONNEL(1)

Approx.

Gamma Doses Travel/

at 7 Hr Occupancy Post-LOCA Area/Route Description Figure No.

Time(1)

(rem)(2)

  • 14 1.

OSC in services bldg to east-west tunnel 12.3-15 63 sec 0.04 entrance, el 123 ft-6 in Sh 1 2.

East-west tunnel entrance to control bldg 12.3-16 41 sec 0.222 stair tower at el 123 ft-6 in Sh 2 3.

Down the stairs to ground level; across 12.3-15 42 sec 0.232 yard to auxiliary bldg east stair tower Sh 3 entrance 4.

Up the stairs to el 170 ft-0 in of the 12.3-15 120 sec 0.026 auxiliary bldg Sh 4 5.

Stair tower landing to grab sample area 12.3-15 7 sec 0.672 Sh 4 6.

In grab sample area to remove shielded 12.3-15 10 min 2.583 grab sample and load onto cart Sh 4 7.

Across auxiliary bldg roof with cart and 12.3-15 53 sec 0.352 sample to west side of building behind Sh 4 west stair tower 8.

Down west stair tower; out of auxiliary 12.3-15 120 sec 0.026 bldg to waiting vehicle Sh 4 9.

Drive from auxiliary building west side to 12.3-15 120 sec 0.67 services bldg north entrance Sh 5

10. From services bldg north entrance 12.3-15 62 sec 0.041 to elevator, to el 123 ft-6 in, to OSC Sh 1, 6 Total 4.86 14*

(1) Walking speed along horizontal surfaces is assumed to be 3 ft/sec.

Driving time is based upon an assumed speed of 25 mph.

(2) The maximum possible beta dose for this scenario is 11 rem.

The maximum possible thyroid dose for this scenario, assuming the use of a pressure demand self-contained breathing apparatus with a dose reduction factor of 10,000, is 0.3 rem.

These are within the GDC-19 limts of 30-rem thyroid and 30-rem beta.

RBS USAR Revision 14 1 of 1 September 2001 TABLE 12.3-6 MAIN PLANT EXHAUST DUCT MONITOR - DOSES TO PHASE II PERSONNEL(1)

Approx.

Gamma Doses Travel/

at 7 Hr Occupancy Post-LOCA Area/Route Description Figure No.

Time(1)

(Rem)(2)

  • 14 1.

From OSC to elevator, down to el 95 ft 12.3-15 62 sec 0.041

-0 in; to services bldg north entrance Sh 1, 6 2.

Drive from services bldg north 12.3-15 120 sec 0.670 entrance to auxiliary bldg west side Sh 5 3.

From vehicle to auxiliary bldg door to 12.3-15 120 sec 0.026 west auxiliary stair tower to el 170 Sh 4 ft-0 in to waiting sample 4.

West side of auxiliary bldg roof 12.3-15 15 min 3.245 behind stair tower to rig and lower Sh 4 grab sample onto truck below 5.

Down west stair tower and out 12.3-15 120 sec 0.026 auxiliary bldg to waiting vehicle Sh 4 6.

Drive truck with sample from auxiliary 12.3-15 120 sec 0.670 bldg west side to services bldg north Sh 5 entrance 7.

From services bldg north entrance to 12.3-15 31 sec 0.021 elevator with cart and grab sample Sh 6 to el 109 ft-3 in 8.

From elevator to hot lab in chemistry 12.3-15 28 sec 0.018 lab with cart and sample, el 109 ft-Sh 7 3 in 9.

From laboratory back to elevator 12.3-15 28 sec 0.018 Sh 7 10.

Elevator to el 123 ft 6 in to OSC 12.3-15 31 sec 0.021 Sh 1 Total 4.75 14*

(1)

Walking speed along horizontal surfaces is assumed to be 3 ft/sec.

Driving time is based upon an assumed speed of 25 mph.

(2)

The maximum possible beta dose for this scenario is 10 rem.

The maximum possible thyroid dose for this scenario, assuming the use of a pressure demand self-contained breathing apparatus with a dose reduction factor of 10,000, 0.3 rem.

These are within the GDC-19 limtis of 30-rem thyroid and 30-rem beta.

RBS USAR Revision 14 1 of 1 September 2001 TABLE 12.3-7 POST-ACCIDENT SAMPLE SYSTEM - VITAL AREA AND ROUTE DOSES AT 1-HR POST-LOCA Approx.

Gamma Doses Travel/

at 1 Hr Occupancy Post-LOCA Area/Route Description Figure No.

Time(1)

(Rem)(2)

  • 14 1.

OSC in services bldg to east-west tunnel 12.3-16 63 sec 0.047 entrance, el 123 ft-6 in Sh 1 2.

East-west tunnel entrance to control bldg 12.3-16 60 sec 0.386 stair tower at el 123 ft-6 in Sh 2 3.

Stairway down to el 114 ft-0 in 12.3-16 18 sec 0.024 and along walkway to PASS room Sh 2 4.

In PASS room to draw a sample 12.3-16 20 min 1.082 Sh 2 5.

PASS room back to stairway with cart 12.3-16 18 sec 0.024 and grab sample Sh 2 6.

Hoist sample and cart to el 123 ft-6 in 12.3-16 30 min 2.521 east-west tunnel Sh 2 7.

To services bldg along east-west tunnel 12.3-16 60 sec 0.386 Sh 2 8.

From east-west tunnel through 12.3-16 76 sec 0.057 el 123 ft-6 in of services bldg to elevator Sh 1 9.

Elevator to el 109 ft-3 in of 12.3-16 20 sec 0.016 services bldg Sh 3

10. From elevator to hot laboratory in 12.3-16 28 sec 0.021 chemistry laboratory, el 109 ft-3 in Sh 3
11. From laboratory back to elevator 12.3-16 28 sec 0.021 Sh 3
12. Elevator to el 123 ft-6 in and 12.3-16 31 sec 0.024 over to OSC Sh 1 Total 4.61 (1)

Walking speed along horizontal sufaces is assumed to be 3 ft/sec.

Driving time is based upon an assumed speed of 25 mph.

(2)

The maximum possible beta dose for this scenario is 11 rem.

The maximum possible thyroid dose for scenario, assuming the use of a presssure demand self-contained breathing apparatus with a dose reduction factor of 10,000, is 0.3 rem.

These are within the GDC-19 limits of 30-rem thyroid and 30-rem beta.

14*

RBS USAR Revision 14 1 of 1 September 2001 TABLE 12.3-8 CHEMISTRY LABORATORY - POST-LOCA DOSES DURING SAMPLE ANALYSIS 1 Hr 2 Hr 8 Hr 24 Hr

  • 14 Gamma dose (rem)(1) 2.8 2.5 1.5 0.55 Beta dose (rem)(2) 1.0 1.2 1.3 0.76 Thyroid dose (rem)(2) 0.11 0.15 0.17 0.10 14*

(1)

Gamma doses are based upon the assumption that a

laboratory technician will spend 30 min in the shielded hot storage room and 30 min in the unshielded hot laboratory.

Doses due to sample handling will be administratively controlled to ALARA by use of shielding, remote handling tools, and procedures.

The GDC-19 gamma dose limit is 5 rem.

(2)

The beta and thyroid doses are based upon a laboratory technician spending 1 hr in the chemistry laboratory.

The TSC ventilation intake system provides filtration of radiohalogens to these areas.

The GDC-19 beta and thyroid dose limits are 30 rem each.

RBS USAR Revision 14 1 of 1 September 2001 TABLE 12.3-9 TECHNICAL SUPPORT CENTER POST-LOCA CONTINUOUS 30-DAY OCCUPANCY DOSES (1)

Calculated 30-day GDC-19 Limiting Dose (Rem)

Dose (Rem)

  • 14 Gamma dose 0.67 5

Beta dose 9.68 30 (2)

Thyroid dose 6.6 30 14*

(1)Based on Standard Review Plan 6.4 occupancy factors.

(2)75 rem with protective clothing.

RBS USAR

Reference:

NUREG-0713, Vol. 4 1 of 1 August 1987 TABLE 12.4-1 OPERATIONAL MAN-REM PER YEAR FOR SELECTED BWR PLANTS 1974 1975 1976 1977 1978 1979 1980 1981 1982

1. Dresden 1, 2, 3 1,662 3,423 1,680 1,693 1,529 1,800 2,105 2,802 2,923
2. Monticello 349 1,353 263 1,000 375 157 531 1,004 993
3. Nine Mile Point 824 681 428 1,383 314 1,497 591 1,592 1,264
4. Peach Bottom 2, 3 228 840 2,036 1,317 1,388 2,302 2,506 1,977
5. Quad Cities 1, 2 482 1,618 1,651 1,031 1,618 2,158 4,838 3,146 3,757
6. Vermont Yankee 216 153 411 258 339 1,170 1,338 731 205
7. Pilgrim 1 798 2,648 3,142 1,327 1,015 3,626 1,836 1,539
8. Millstone Point 1 1,430 2,022 1,194 392 1,239 1,793 2,158 1,496 929
9. Oyster Creek 984 1,140 1,078 1,614 1,279 467 1,733 917 865
10. Brunswick 1, 2 1,004 2,602 3,870 2,638 3,792
11. Browns Ferry 1, 2, 3 1,792 1,667 1,825 2,380 2,220
12. FitzPatrick 1,080 909 859 2,040 1,425 1,190 Average Man-Rem/Unit 594 878 784 974 686 872 1,419 1,183 1,140 Overall average of 948 man-rem/year-unit

RBS USAR Revision 24 1 of 1 TABLE 12.4-2 ESTIMATED DOSES AT LOCATIONS OUTSIDE THE PLANT STRUCTURES (MREM/YR) 8 Location N-16 Condensate Storage Tank Airborne Temporary Dry Active Waste Storage Facilities and Radioactive Material Storage Areas Turbine Rotor Modular Storage Enclosures Total Restricted Area Boundary Whole Body 1

Neg.

1

<1 Neg.

<3 Skin Neg.

3 Neg.

3 8

1 of 1 August 1987 TABLE 12.4-3 DISTRIBUTION OF ANNUAL MAN-REM BY WORK FUNCTIONS BASED ON OPERATING BWR DATA Percentage Work Function 1978 1979 1980 1981 1982 Average Reactor operations and surveillance 12.3 13.4 7.6 7.5 9.1 10.0 Routine maintenance 43.2 39.3 42.8 42.2 33.7 40.2 Waste processing 5.8 4.3 3.1 11.0 6.2 6.1 Refueling 2.0 4.4 5.2 2.5 2.7 3.4 Inservice inspection 2.6 7.3 3.3 3.7 4.3 4.2 Special maintenance 34.1 31.2 38.1 33.1 44.0 36.1

References:

NUREG-0594, Occupational Radiation Exposure at Commercial Nuclear Power Reactors, 1978, November 1979 NUREG-0713, Volume 1,

Occupational Radiation Exposure at Commercial Nuclear Power Reactors, 1979, March 1981 NUREG-0713, Volume 2,

Occupational Radiation Exposure at Commercial Nuclear Power Reactors, 1980, December 1981 NUREG-0713, Volume 3,

Occupational Radiation Exposure at Commercial Nuclear Power Reactors, 1981, November 1982 NUREG-0713, Volume 4,

Occupational Radiation Exposure at Commercial Nuclear Power Reactors, 1982, December 1983

RBS USAR 1 of 2 August 1987 TABLE 12.4-4 ESTIMATES OF OCCUPANCY TIMES IN-PLANT RADIATION AREAS AND OCCUPATIONAL RADIATION DOSE Average Radiation Dose Rate Occupancy Number of Annual Doses Function Zone (Mrem/hr)

(%)

Persons (Man-Rem/Yr)

Reactor operations I

0.2 70.0 32 9.3 and surveillance(1)

II 1.0 20.0 32 13.3 III 2.5 6.0 32 10.0 IV 10.0 3.0 32 20.0 V

50.0 0.9 32 30.0 VI 100.0 0.1 32 6.7 Total 89.3 Routine I

0.2 70.0 47 13.7 maintenance(1)

II 1.0 12.0 47 11.7 III 2.5 10.0 47 24.4 IV 10.0 5.0 47 48.9 V

50.0 2.0 47 97.8 VI 100.0 1.0 47 97.8 Total 294.3 Waste processing(1)

I 0.2 90.0 10 3.7 II 1.0 5.0 10 1.0 III 2.5 3.0 10 1.6 IV 10.0 1.4 10 2.9 V

50.0 0.5 10 5.2 VI 100.0 0.1 10 2.1 Total 16.5 Refueling(2)

I 0.2 30.0 44 0.4 II 1.0 20.0 44 1.4 III 2.5 24.0 44 4.2 IV 10.0 22.0 44 15.5 V

50.0 3.0 44 10.6 VI 100.0 1.0 44 7.0 Total 39.1

RBS USAR 2 of 2 August 1987 TABLE 12.4-4 (Cont)

Average Radiation Dose Rate Occupancy Number of Annual Doses Function Zone (Mrem/hr)

(%)

Persons (Man-Rem/Yr)

Inservice inspection(3)

I 0.2 5.0 28 0.1 II 1.0 10.0 28 0.5 III 2.5 20.0 28 2.7 IV 10.0 50.0 28 26.9 V

50.0 10.0 28 26.9 VI 100.0 5.0 28 26.9 Total 84.0 (1) Based on 2,080 hour9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br />s/yr-person (2)Based on 160 hour0.00185 days <br />0.0444 hours <br />2.645503e-4 weeks <br />6.088e-5 months <br />s/yr-person (3)Based on 192 hour0.00222 days <br />0.0533 hours <br />3.174603e-4 weeks <br />7.3056e-5 months <br />s/yr-person

1 of 1 August 1987 TABLE 12.4-5 ESTIMATED OCCUPATIONAL RADIATION DOSE BY WORK FUNCTIONS Annual Dose Percentage of Function (Man-rem/yr-unit)

Total Dose Reactor operations 89.3 10.8 and surveillance Routine maintenance 294.3 35.6 Waste processing 16.5 2.0 Refueling 44.7 5.4 Inservice inspection 84.0 10.1 Special maintenance 298.7 36.1 Total 827.5 100.0 Special maintenance man-rem is estimated from assuming that special maintenance is approximately 36 percent of total annual occupational radiation dose (Table 12.4-2).

RBS USAR 1 of 1 August 1987 TABLE 12.4-6 OCCUPATIONAL DOSE ESTIMATES DURING ROUTINE OPERATIONS AND SURVEILLANCE Average Exposure Dose Dose Rate Time Number of Workers (man-rem/year)

Activity (Mrem/hr)

(Hrs)

Utility Contractor Frequency Utility Contractor Total Main Control Room 0.1 8

3 1/shift 2.6 2.6 Auxiliary Control 0.1 8

6 1/day 1.8 1.8 Room Surveillance Turbine 20.0 0.1 1

1/shift 2.2 2.2 Feedwater heaters 10.0 0.5 1

1/shift 5.5 5.5 Feedwater pumps 10.0 0.2 1

1/shift 2.2 2.2 Misc. Turbine Bldg.

2.0 1.0 1

1/shift 2.2 2.2 ECCS cubicles 5.0 0.5 1

1/shift 2.7 2.7 RWCU pumps 50.0 0.05 1

1/shift 2.7 2.7 Misc. Auxiliary Bldg.

2.0 1.0 1

1/shift 2.2 2.2 FPC pumps 5.0 0.05 1

1/shift 0.3 0.3 Misc. Fuel Bldg.

1.0 1.0 1

1/shift 1.1 1.1 CRD HCUs 5.0 0.5 1

1/shift 2.7 2.7 SLC system 2.0 0.1 1

1/shift 0.2 0.2 RWC heat exchangers 20.0 0.05 1

1/shift 1.1 1.1 TIP area 10.0 0.1 1

1/shift 1.1 1.1 Misc. containment 5.0 1.0 1

1/shift 5.5 5.5 Condensate demineralizer 5.0 0.1 1

1/shift 0.5 0.5 Offgas process 10.0 0.1 1

1/shift 1.1 1.1 Samples, containment 5.0 1.0 1

1/shift 5.5 5.5 Sample stations, other buildings 1.0 2.0 1

1/shift 2.2 2.2 Radiation protection 100.0 1.0 1

1/week 5.2 5.2 surveys 10.0 2.0 1

1/day 7.3 7.3 2.0 4.0 1

1/day 2.9 2.9 Radiochemistry lab activities 0.1 6.0 10 1/day 2.2 2.2 Radiation protection lab activities 0.1 8.0 9

1/day 2.6 2.6 Total 65.6 65.6

TABLE 12.4-7 OCCUPATIONAL DOSE ESTIMATES DURING ROUTINE MAINTENANCE Average Exposure Dose Dose Rate Time Number of Workers (man-rem/yr)

Activity (mrem/hr)

(Hrs)

Utility Contractor Frequency Utility Contractor Total RWCU filter demineralizer percent 2.5 2.0 1

1/week 0.3 0.3 RWCU holding pumps, valves 20.0 0.5 2

1/week 1.0 1.0 RWCU pump valves 100.0 1.0 2

1/week 10.4 10.4 TIP system 10.0 2.0 2

1 1/month 0.7 0.7 CRD HCUs, control stations 5.0 1.0 1

1/day 1.8 1.8 Reactor recirculation pump valves 50.0 50.0 2

10 1/yr 5.0 25.0 30.0 Drywell and contain-ment utilization 5.0 7.0 2

1/yr 0.1 0.1 HVAC, other buildings 1.0 1.0 1

1/day 0.4 0.4 Radiation monitors, drywell, containment 5.0 50.0 2

1/yr 1.3 1.3 Radiation monitors, other buildings 2.0 150.0 2

1/yr 0.6 0.6 ECCS pumps, 25.0 0.5 2

1/week 1.3 1.3 valves, instruments 2.0 4.0 2

1/week 0.8 0.8 Reactor plant cooling water 2.0 1.0 2

1/week 0.2 0.2 Turbine plant cooling water 1.0 1.0 2

1/week 0.1 0.1 Feedwater pumps, condensate pumps 2.0 2.0 2

1/week 0.4 0.4 1 of 2 August 1987

TABLE 12.4-7 (Cont)

Average Exposure Dose Dose Rate Time Number of Workers (man-rem/yr)

Activity (mrem/hr)

(Hrs)

Utility Contractor Frequency Utility Contractor Total Feedwater heaters, MSRs 5.0 0.5 2

1/week 0.3 0.3 CRD pumps, filters 2.0 2.0 1

1/week 0.2 0.2 Fuel pool cooling components 5.0 0.5 2

1/week 0.3 0.3 Fuel pool cleanup components 10.0 1.0 2

1/week 1.0 1.0 Condensate demin-eralizers 2.0 1.5 2

1/day 2.2 2.2 Offgas components 5.0 1.0 2

1/day 3.7 3.7 I&C preventive maintenance 1.0 8.0 10 1/day 29.2 29.2 Electrical preventive maintenance 2.0 8.0 4

1/day 23.4 23.4 Mechanical preventive maintenance 5.0 8.0 7

1/day 102.2 102.2 Total 186.9 25.0 212.0 2 of 2 August 1987

RBS USAR 1 of 1 August 1987 TABLE 12.4-8 OCCUPATIONAL DOSE ESTIMATES DURING WASTE PROCESSING Average Exposure Dose Dose Rate Time Number of Workers (man-rem/yr)

Activity (mrem/hr)

(Hrs)

Utility Contractor Frequency Utility Contractor Total Operation of liquid radwaste system 0.2 8.0 2

1/day 1.2 1.2 Surveillance of 10.0 0.5 1

1/day 1.8 1.8 radwaste equipment 2.5 1.0 1

1/day 0.9 0.9 Operation of waste 50.0 1.0 1

1/week 2.6 2.6 solidification system 2.0 32.0 1

1/week 3.3 3.3 DAW compacting 2.0 32.0 1

1/week 3.3 3.3 Chemistry and radiation protection support 2.50 2.0 2

1/day 3.7 3.7 Total 10.7 5.9 16.8

RBS USAR 1 of 1 August 1987 TABLE 12.4-9 OCCUPATIONAL DOSE ESTIMATES DURING REFUELING Average Exposure Dose Dose Rate Time Number of Workers (man-rem/yr)

Activity (mrem/hr)

(Hrs)

Utility Contractor Frequency Utility Contractor Total Reactor vessel head and internals removal, installation 20.0 32 6

14 1/yr 3.8 9.0 12.8 Fuel handling and transfer 2.5 160 6

6 1/yr 2.4 2.4 4.8 Fuel sipping 5.0 200 1

2 1/yr 1.0 2.0 3.0 Radiation protection coverage 3.0 160 3

6 1/yr 1.4 2.9 4.3 Total 8.6 16.3 24.9

RBS USAR 1 of 1 August 1987 TABLE 12.4-10 OCCUPATIONAL DOSE ESTIMATES DURING INSERVICE INSPECTION Average Exposure Dose Dose Rate Time Number of Workers (man-rem/yr)

Activity (mrem/hr)

(Hrs)

Utility Contractor Frequency Utility Contractor Total Providing access in 100 20 2

1/yr 4.0

4.0 drywell

moving 20 20 4

1/yr 1.6 1.6 platforms, insulation equipment Reactor vessel and 100 50 6

1/yr 30.0 30.0 piping in drywell 20 150 6

1/yr 18.0 18.0 Piping in containment 20 20 6

1/yr 2.4 2.4 and other buildings 5

170 8

1/yr 6.8 6.8 Snubbers and 100 20 2

1/yr 4.0 4.0 pipe hangers 20 60 6

1/yr 7.2 7.2 5

120 12 1/yr 7.2 7.2 Total 81.2 81.2

RBS USAR 1 of 1 August 1987 TABLE 12.4-11 OCCUPATIONAL DOSE ESTIMATES DURING SPECIAL MAINTENANCE Average Exposure Dose Dose Rate Time Number of Workers (man-rem/yr)

Activity (mrem/hr)

(Hrs)

Utility Contractor Frequency Utility Contractor Total Servicing CRD under vessel 100 32 2

4 1/yr 6.4 12.8 19.2 rebuild room 10 56 3

3 1/yr 1.7 1.7 3.4 Servicing in-cores under vessel 100 20 1

2 1/yr 2.0 4.0 6.0 MSIV repair 75 50 2

4 1/yr 7.5 15.0 22.5 Turbine repair 5

250 10 15 1/3 yrs 4.2 6.3 10.5 Recirculation flow control valve repair 50 50 4

1/yr 10.0 10.0 RHR heat exchanger 50 50 2

2 1/yr 5.0 5.0 10.0 TOTAL 26.8 54.8 81.6

1 of 1 August 1987 TABLE 12.4-12

SUMMARY

OF OCCUPATIONAL DOSE ESTIMATES FROM DETAILED WORK FUNCTION TASKS Annual Dose Function (man-rem/yr)

Reactor operations 65.6 and surveillance Routine maintenance 212.0 Waste processing 16.8 Refueling 24.9 Inservice inspection 81.2 Special maintenance 81.6*

TOTAL 482.1

  • A more realistic special maintenance dose estimate is approximately 36 percent of the total man-rem which would predict:

Special maintenance 226 man-rem/yr Revised total 629 man-rem/yr

RBS USAR Revision 8 1 of 1 August 1996 TABLE 12.5-1

  • 7 TYPICAL COUNTING ROOM INSTRUMENTATION 7*

Instrument Efficiency (%)

Range Quantity Remarks

  • 7
  • 8 7*

GM counter scaler Approx. 10 for 0-105-2 For gross counting of Tc-99 counts radioactive material on smear survey, air particulate radioactivity, and evaporated liquid samples Scintillation low Approx. 30 for 0-105 2

For measuring radioactive background alpha, Th-230 counts material levels on survey samples and air particulate samples NAI counter Approx. 15 for 0-105 1

For measuring radioactive Ba-133 counts Concentrations in plant air samples 8*

RBS USAR Revision 8 1 of 2 August 1996 TABLE 12.5-2 PORTABLE RADIOLOGICAL SURVEY INSTRUMENTATION Accuracy Instrument

(%)

Range Quantity Remarks Alpha survey

+/-10 0-500,000 3

Similar to Eberline PRM-6 meter cpm w/probe Neutron survey

+/-10 0-5000 4

Neutron dose rate meter meter mRem/hr similar to Eberline Model PNR-4/NRD GM survey

+/-10 0-1000 8

Telescoping probe-similar meter R/hr to the Teletector GM survey

+/-10 0-50,000 10 Similar to Eberline Model meter cpm E140 GM survey

+/-10 0-50 12 Similar to Eberline E-140 meter mR/hr GM survey

+/-10 0-2000 12 Similar to Eberline meter mR/hr Model E-520

  • 8 Survey

+/-10 0-50,000 16 Count rate instrument meter (frisker) cpm similar to Eberline GM or gas flow Model RM-14 w/HP-260 or proportional HP-210 probe Micro "R"

+/-10 25-5000 4

Similar to Eberline Model meter R/hr PRM-7 8*

Ion chamber

+/-10 0-5000 14 Similar to Eberline Model survey meter mR/hr RO-3 or RO-2

RBS USAR Revision 21 2 of 2 TABLE 12.5-2 (Cont)

Accuracy Instrument

(%)

Range Quantity Remarks Ion chamber

10 0-50 8

Dose rate meter similar survey meter R/hr to Eberline RO-2A Beta air monitoring

10 10-100,000 4

Equivalent to Eberline system cpm Model AMS-3 Air sampler

10 1-6 scfm 15 Equivalent to Radeco Model (regulated)

H-809 V-1 Ion chamber

10 0-20,000 3

Similar to Eberline Model survey meter R/hr RO-7 Gamma area

10 1-10 2

Similar to Eberline Model monitor R/hr RM-21 Air sampler

10 10-40 cfm 10 High volume sampler similar to Radeco Model H-809VII or staplex Air sampler

10 1-3 cfm 16 Equivalent to Eberline Model RAS-1

8 Continuous air

10

.1-100 DAC 4

Similar to Merlin Gerin CAM monitor, solid state Area Survey monitor,

10 10 mR/h -

1 Similar to Dositec AR-20, solid state 1,000 R/h Merlin Gerin DMC-100 with AM-500 or telemetry system 8

RBS USAR Revision 20 1 of 2 TABLE 12.5-3 PERSONNEL MONITORING INSTRUMENTATION Instrument Sensitivity Range Quantity Remarks DLR 5 mR 10 mR-10 6mR

>500 TLDs with lithium chips or equivalent teflon cards for beta/Gamma/neutron dose measurement or OSLDs with aluminum oxide detectors or equivalent for beta/gamma/x-ray/neutron dose measurements

7 Direct reading dosimeter 1 mR 10 mR-10 7mR

>500 Electronic dosimeter (Merlin Gerin DMC-100s or equivalent)

Direct reading dosimeter 10 mR 10 mR 0-200 mR 0-500 mR 20 mR

>200

>200 or 0-1000 mR Direct reading ion chamber 7

Direct reading dosimeter 50 mR 0-5 R or 0-10 R

>50 Direct reading ion chamber

7

8 Whole body counter 1% of ALI for most gamma emit-ting isotopes 0-several %

of an ALI 1

Used to determine internal deposition of radioactive materials, Ge or NaI detector

2 Portal monitor Detect 1 Ci of Cs-137 0-1000 cpm 6

G-M, proportional or scintillation-type detectors 7 2

Dosimeter chargers 5

9 9

7 Personnel Contami-nation Monitor 5,000 dpm/100cm 2

Beta Activity 3

(PCM 1-B or equivalent) 7 8

RBS USAR Revision 8 2 of 2 August 1996 TABLE 12.5-3 (cont)

PERSONNEL MONITORING INSTRUMENTATION Instrument Sensitivity Range Quantity Remarks

  • 8 Portable survey meter, GM 1000 dpm/probe 0-50 Kcpm 10 10 Similar to Eberline RM-14 with HP-210 or NP-260 probe Portable survey meter, Gas flow proportional 5000 dpm/

100 cm2 0-5 Mcpm 10 Similar to Eberline RM-14SA with HP-100A probe 8*

RBS USAR Revision 8 1 of 1 August 1996 TABLE 12.5-4 ADDITIONAL RADIATION PROTECTION EQUIPMENT Equipment Quantity Range Remarks Portable continuous air monitor 4

0-100,000 cpm Used to monitor work area, similar to GA RD-60

  • 7 Air-purifying respirators

>100 Full face, negative pressure 7*

  • 8 Atmosphere supplying respirators

>10 Full face, continuous flow air hose 8*

Self-contained breathing apparatus

>30 Also used for fire fighting Atmosphere-supplying respirators

>10 Ventilated hood, continuous flow Radiation survey instrument calibrator 1

0.002-1,1000 R/hr Multiple source shielded self-contained calibrator capable of dose rates needed to calibrate all portable instrumentation Expendable items normally used in radiation protection work (1)

Examples: poly bags, sheeting and bottles; ropes and signs; decon and equipment, etc.

Protective clothing (1)

Examples: coveralls, lab coats, gloves, boots, hoods, others, as needed Air purification units 3

>500 scfm Portable-equippd with HEPA filters and charcoal, as required

  • 8 Air purification units 2

0-1,000 scfm 8*

Vacuum cleaners 1

Equipped with HEPA filters Glove boxes (1)

  • 7 Respirator fit testing equipment 1

Similar to TSI Porta Counter or the equivalent 8*

  • 2 2*

(1)

Adequate supplies are made available for routine operations and outage conditions.

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