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DSAR CHAPTER 14 - SAFETY ANALYSIS TABLE 14.11-2 Revision 36 Page 1 of 4
Table 14.11-2 Spent Fuel Cask Drop Radiological Analysis - Source Terms*
- Listed source term is for a single assembly.
30 Day 90 Day Nuclide Decay Decay (Curies) (Curies)
Co-58 0.0000E+00 0.0000E+00 Co-60 0.0000E+00 0.0000E+00 Kr-85 0.6563E+04 0.6493E+04 Kr-85m 0.0000E+00 0.0000E+00 Kr-87 0.0000E+00 0.0000E+00 Kr-88 0.0000E+00 0.0000E+00 Rb-86 0.3205E+03 0.3450E+02 Sr-89 0.5045E+06 0.2213E+06 Sr-90 0.5178E+05 0.5157E+05 Sr-91 0.1431E-16 0.0000E+00 Sr-92 0.0000E+00 0.0000E+00 Y-90 0.5184E+05 0.5159E+05 Y-91 0.6805E+06 0.3344E+06 Y-92 0.0000E+00 0.0000E+00 Y-93 0.3964E-15 0.0000E+00 Zr-95 0.8884E+06 0.4637E+06 Zr-97 0.1774E-06 0.0000E+00 Nb-95 0.1146E+07 0.7766E+06 Mo-99 0.6714E+03 0.1816E-03 Tc-99m 0.6469E+03 0.1749E-03 Ru-103 0.6102E+06 0.2118E+06 Ru-105 0.0000E+00 0.0000E+00 Ru-106 0.2925E+06 0.2611E+06 Rh-105 0.5545E+00 0.3056E-12 Sb-127 0.3350E+03 0.6807E-02 Sb-129 0.0000E+00 0.0000E+00 Te-127 0.8360E+04 0.5490E+04 Te-127m 0.8207E+04 0.5606E+04 Te-129 0.1138E+05 0.3301E+04 Te-129m 0.1748E+05 0.5071E+04 Te-131m 0.5959E-02 0.2118E-16 Te-132 0.1664E+04 0.4757E-02 DSAR CHAPTER 14 - SAFETY ANALYSIS TABLE 14.11-2 Revision 36 Page 2 of 4
Table 14.11-2 Spent Fuel Cask Drop Radiological Analysis - Source Terms*
30 Day 90 Day Nuclide Decay Decay (Curies) (Curies)
I-131 0.5355E+05 0.3038E+03 I-132 0.1715E+04 0.4902E-02 I-133 0.5526E-04 0.7976E-25 I-134 0.0000E+00 0.0000E+00 I-135 0.0000E+00 0.0000E+00 Xe-133 0.3313E+05 0.1194E+02 Xe-135 0.0000E+00 0.0000E+00 Cs-134 0.1016E+06 0.9612E+05 Cs-136 0.6310E+04 0.2638E+03 Cs-137 0.6483E+05 0.6459E+05 Ba-139 0.0000E+00 0.0000E+00 Ba-140 0.2450E+06 0.9480E+04 La-140 0.2819E+06 0.1091E+05 La-141 0.0000E+00 0.0000E+00 La-142 0.0000E+00 0.0000E+00 Ce-141 0.6297E+06 0.1752E+06 Ce-143 0.3033E+00 0.2220E-13 Ce-144 0.8358E+06 0.7222E+06 Pr-143 0.2630E+06 0.1226E+05 Nd-147 0.7146E+05 0.1663E+04 Np-239 0.2042E+04 0.1581E+02 Pu-238 0.2174E+04 0.2199E+04 Pu-239 0.2968E+03 0.2968E+03 Pu-240 0.2972E+03 0.2972E+03 Pu-241 0.8941E+05 0.8870E+05 Am-241 0.1070E+03 0.1260E+03 Cm-242 0.2428E+05 0.1882E+05 Cm-244 0.2743E+04 0.2726E+04 I-130 0.5151E-13 0.0000E+00 Kr-83m 0.0000E+00 0.0000E+00 Xe-138 0.0000E+00 0.0000E+00 Xe-131m 0.2962E+04 0.1204E+03 Xe-133m 0.5377E+01 0.3038E-07 Xe-135m 0.0000E+00 0.0000E+00 DSAR CHAPTER 14 - SAFETY ANALYSIS TABLE 14.11-2 Revision 36 Page 3 of 4
Table 14.11-2 Spent Fuel Cask Drop Radiological Analysis - Source Terms*
30 Day 90 Day Nuclide Decay Decay (Curies) (Curies)
Cs-138 0.0000E+00 0.0000E+00 Cs-134m 0.0000E+00 0.0000E+00 Rb-88 0.0000E+00 0.0000E+00 Rb-89 0.0000E+00 0.0000E+00 Sb-124 0.5599E+03 0.2806E+03 Sb-125 0.8790E+04 0.8446E+04 Sb-126 0.1278E+03 0.4525E+01 Te-131 0.1341E-02 0.4765E-17 Te-133 0.0000E+00 0.0000E+00 Te-134 0.0000E+00 0.0000E+00 Te-125m 0.1902E+04 0.1940E+04 Te-133m 0.0000E+00 0.0000E+00 Ba-141 0.0000E+00 0.0000E+00 Ba-137m 0.6132E+05 0.6110E+05 Pd-109 0.1499E-10 0.0000E+00 Rh-106 0.2925E+06 0.2611E+06 Rh-103m 0.5502E+06 0.1908E+06 Tc-101 0.0000E+00 0.0000E+00 Eu-154 0.6312E+04 0.6229E+04 Eu-155 0.4225E+04 0.4129E+04 Eu-156 0.2550E+05 0.1649E+04 La-143 0.0000E+00 0.0000E+00 Nb-97 0.1911E-06 0.0000E+00 Nb-95m 0.6589E+04 0.3441E+04 Pm-147 0.1206E+06 0.1162E+06 Pm-148 0.4604E+04 0.3221E+03 Pm-149 0.3193E+02 0.2179E-06 Pm-151 0.3097E-02 0.1665E-17 Pm-148m 0.1557E+05 0.5685E+04 Pr-144 0.8358E+06 0.7222E+06 Pr-144m 0.1003E+05 0.8666E+04 Sm-153 0.5430E+01 0.2827E-08 Y-94 0.0000E+00 0.0000E+00 Y-95 0.0000E+00 0.0000E+00 DSAR CHAPTER 14 - SAFETY ANALYSIS TABLE 14.11-2 Revision 36 Page 4 of 4
Table 14.11-2 Spent Fuel Cask Drop Radiological Analysis - Source Terms*
30 Day 90 Day Nuclide Decay Decay (Curies) (Curies)
Y-91m 0.9094E-17 0.0000E+00 Br-82 0.1919E-02 0.1012E-14 Br-83 0.0000E+00 0.0000E+00 Br-84 0.0000E+00 0.0000E+00 Am-242 0.1237E+02 0.1236E+02 Np-238 0.1195E+02 0.6211E-01 Pu-243 0.2743E-06 0.2743E-06
DSAR CHAPTER 14 - SAFETY ANALYSIS TABLE 14.11-3 Revision 36 Page 1 of 1
Spent Fuel Cask Drop Radiological Analysis - Inputs and Assumptions
Input/Assumption Value
Core Power Level Before Shutdown 2703 MWth Core Average Fuel Burnup 39,300 MWD/MTU Discharged Fuel Assembly Burnup 39,300 - 58,900 MWD/MTU Fuel Enrichment 3.0 - 5 w/o
Number of Fuel Assemblies Damaged 73
Delay Before Cask Drop 90 days
Source Terms See Table 14.11-2
Water Level Above Damaged Fuel Assembly 23.4 feet minimum Elemental - 285 Iodine Decontamination Factors Organic - 1 Overall - 200 Noble Gas Decontamination Factor 1
Chemical Form of Iodine In Pool Elemental - 99.85% Organic - 0.15%
Atmospheric Dispersion Factors Tables 14.19-4 Breathing Rates RG 1.183 Sections 4.1.3 and 4.2.6 Control Room Occupancy Factor RG 1.183 Section 4.2.6
DSAR CHAPTER 14 - SAFETY ANALYSIS TABLE 14.19-1 Revision 36 Page 1 of 1
FUEL HANDLING ACCIDENT (FHA) RADIOLOGICAL ANALYSIS - INPUTS AND ASSUMPTIONS
Input/Assumption Value Core Power Level Before Shutdown 2703 MWth Core Average Fuel Burnup 39,300 MWD/MTU Discharged Fuel Assembly Burnup 39,300 - 58,900 MWD/MTU Fuel Enrichment 3.0 - 5.0 w/o Maximum Radial Peaking Factor 2.04 Number of Fuel Assemblies Damaged 1 fuel assembly Delay Before Spent Fuel Movement 17 Days FHA Source Term for a Single Assembly Table 14.19-2 Water Level Above Damaged Fuel Assembly 22.5 feet minimum Elemental - 252 Iodine Decontamination Factors Organic - 1 Overall - 183.07 Noble Gas Decontamination Factor 1 Chemical Form of Iodine In Pool Elemental - 99.85% Organic - 0.15%
Atmospheric Dispersion Factors Table 14.9-4 Time of Control Room Ventilation System Isolation 20 minutes Breathing Rates RG 1.183 Sections 4.1.3 and 4.2.6 Control Room Occupancy Factor RG 1.183 Section 4.2.6
DSAR CHAPTER 14 - SAFETY ANALYSIS TABLE 14.19-2 Revision 36 Page 1 of 1
POST-PERMANENT SHUTDOWN AST FHA - SOURCE TERM
Nuclide Activity (Curies)
I-130 0.2546E+04 I-131* 0.1028E+07 I-132 0.7060E+06 I-133 0.3019E+06 I-135 0.8949E+04 Xe-131m 0.8276E+04 Xe-133 0.1298E+07 Xe-133m 0.3403E+05 Xe-135 0.8201E+05 Xe-135m 0.1434E+04 Kr-83m 0.3727E+00 Kr-85* 0.2104E+05 Kr-85m 0.1174E+03 Kr-88 0.4302E+01 Br-82 0.2060E+04 Br-83 0.8833E-01 Te-131m 0.3690E+05 Te-131 0.8307E+04 Te-132 0.6852E+06
DSAR CHAPTER 14 - SAFETY ANALYSIS TABLE 14.19-3 Revision 36 Page 1 of 1
POST-PERMANENT SHUTDOWN AST FHA - RELEASE FRACTIONS
Group Fraction I-131 0.08 Kr-85 0.10 Other Noble Gases 0.05 Other Halogens 0.05 Alkali Metals 0.12
DSAR CHAPTER 14 - SAFETY ANALYSIS TABLE 14.19-4 Revision 36 Page 1 of 1
POST-PERMANENT SHUTDOWN AST FHA - ATMOSPHERIC DISPERSION FACTORS 0-2 HOURS
Location Atmospheric Dispersion Factor Plant Stack to CR Normal Intake B 5.29x10-3 s/m3 EAB 5.39x10-4 s/m3 LPZ 6.66x10-5 s/m3
DSAR CHAPTER 14 - SAFETY ANALYSIS TABLE 14.19-5 Revision 36 Page 1 of 1
POST-PERMANENT SHUTDOWN AST FHA - ATMOSPHERIC DISPERSION FACTORS 0-2 HOURS
Location TEDE Dose Regulatory Limit (TEDE)
Control Room 4.71 rem 5.0 rem Exclusion Area 0.52 rem 6.3 rem Boundary