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DSAR CHAPTER 14 - SAFETY ANALYSIS TABLE 14.1-4 Revision 36 Page 1 of 1 DISPOSITION OF EVENTS
SUMMARY
FOR PALISADES POST-PERMANENT SHUTDOWN Bounding Updated SRP Event Event or FSAR Designation Name Disposition Reference Designation 15.7 RADIOACTIVE RELEASE FROM A SUBSYSTEM OR COMPONENT 15.7.1 Waste Gas System Failure Deleted(c) Ref. 1 14.21 15.7.2 Radioactive Liquid Waste System Leak or Failure (Release to Atmosphere) Deleted(c) Ref. 2 14.20 15.7.3 Postulated Radioactive Releases Due to Liquid-Containing Tank Failures Bounded Ref. 2 14.20 15.7.4 Radiological Consequences of Fuel Handling Accidents Analyzed Ref. 1 14.19 15.7.5 Spent Fuel Cask Drop Accidents Analyzed Ref. 2 14.11
- a. Deleted
- b. Deleted
- c. This section of the Standard Review Plan has been deleted.
DSAR CHAPTER 14 - SAFETY ANALYSIS TABLE 14.1-6 Revision 36 Page 1 of 2
SUMMARY
OF RADIOLOGICAL CONSEQUENCES OF THE CHAPTER 14 EVENTS FSAR SECTION SCENARIO DESCRIPTION OFFSITE DOSES AND LIMITS CONTROL ROOM HABITABILITY Exclusion Pre- Post- Low Control Offsite Area CRE Makeup Control Room Cask Drop Isolation Isolation Population Room Section 14.11: Dose Limits (5) Boundary Flow Dose Limits (6)
CASK DROP IN THE SPENT Scenario % Filter % Filter Zone Dose
[rem] (0-2 hrs) [cfm] [rem]
FUEL POOL Bypass Bypass [rem] [rem]
[rem]
90 Day Decay No Charcoal 100 100 TEDE 6.3 0.08 0.01 660 TEDE 5 1.67 Filters Exclusion Low Control Offsite Area CRE Makeup Control Room Population Room Dose Calculation Assumptions Dose Limits (5) Boundary Flow Dose Limits (6)
Zone Dose
[rem] (0-2 hrs) [cfm] [rem]
Section 14.19: [rem] [rem]
FUEL HANDLING ACCIDENT [rem]
One fuel bundle fails 17 days after shutdown, TEDE 6.3 0.52 0.28 660 TEDE 5 4.71 No Charcoal Filtration Low Site Control Offsite Dose Population Boundary Control Room Dose Limits (2) Room Dose Calculation Assumptions Limits (1) Zone (60 min) [rem] Dose Section 14.21.1: [rem] (60 min)
GAS DECAY TANK RUPTURE Thyroid 75 (4) (4) Thyroid 30 (4) 22 Hr Decay Tank Inventory Whole Body 6 (4) (4) Whole Body 5 (4)
DSAR CHAPTER 14 - SAFETY ANALYSIS TABLE 14.1-6 Revision 36 Page 2 of 2
SUMMARY
OF RADIOLOGICAL CONSEQUENCES OF THE CHAPTER 14 EVENTS Notes:
(1) The acceptance criteria for the offsite dose limits are given in 10CFR Part 100 Section 11 (Reference 42). It states that the public 'would not receive a total radiation dose to the whole body in excess of 25 rem or a total radiation dose in excess of 300 rem to the thyroid from iodine' following a stipulated fission product release. In addition, the terms 'well within and small fraction of' are utilized in the acceptance criteria in Chapter 15 of the Standard Review Plan (SRP 15) (Reference 43). The two terms correspond to 25% (75 rem thyroid, 6 rem whole body) and 10% (30 rem thyroid, 2.5 rem whole body) of the radiation levels given in 10 CFR Part 100 respectively.
(2) The acceptance criteria for the control room dose limits are given in 10CFR Part 50 Appendix A, General Design Criterion 19 (GDC 19) (Reference 44). It states that the doses will be less than '5 rem whole body or its equivalent to any part of the body, for the duration of the accident.' SRP 6.4 (Reference 45) interprets the limits of GCD 19 of being 5 rem whole body, 30 rem thyroid, and 30 rem skin dose.
(3) Deleted (4) The atmospheric dispersion coefficients and the source term for the revised FHA bound those of the design basis GDTR. It is therefore concluded that the dose consequences calculated for the FHA bound the dose consequences of a GDTR and the GDTR dose consequences remain within requirements of 10 CFR 100.
(5) The acceptance criteria for the offsite doses are given in RG 1.183 (Reference 54), which are based upon 10CFR Part 50 Section 67. RG 1.183 and 10CFR 50.67 do not provide specific acceptance criteria for the cask drop in the spent fuel pool. The acceptance criteria for the cask drop in the spent fuel pool are taken as those of the fuel handling accident.
(6) The acceptance criteria for the control room doses are given in 10CFR Part 50 Section 67.
DSAR CHAPTER 14 - SAFETY ANALYSIS TABLE 14.11-1 Revision 36 Page 1 of 1 POSTULATED CASK DROP ACCIDENTS Impact Cask Cask Drop Height Velocity @
Location Weight(Tons) Air(ft) Water(ft) Total(ft) Impact(in/sec) Penetration(in) Impact on Structure STRUCTUAL Cask Loading 97.5 4 35.6 39.6 498.2 Crush depth The Pressure transferred Area of foam=17.15 to the slab is less than P(Critical) for the slab MTC drop into 97.5 16 --- 16 385.2 Crush depth The Pressure transmitted washdown pit of foam=22.96 to the slab is less than P(Critical) for the slab MTC drop onto 93.5 5.83 --- 5.83 232.6 --- MTC remains intact VCC in Track Alley & LDS remains intact MTC seismic --- --- --- --- --- --- The loaded MTC/MSB overturn in pool will not tip over &
loading area damage fuel RADIOLOGICAL MTC Tip over 97.5 --- --- --- --- --- Failure of all 73 onto West 11x7 assemblies & doses fuel rack within applicable 10 CFR 50.67 limits Drop of the loaded 93.5 5.83 --- 5.83 232.6 --- The MTC/MSB will not MTC on to VCC fail. No radiological release.
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 Elemental - 99.85%
Chemical Form of Iodine In Pool 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 Table 14.19-2 Assembly Water Level Above Damaged Fuel 22.5 feet minimum Assembly Elemental - 252 Iodine Decontamination Factors Organic - 1 Overall - 183.07 Noble Gas Decontamination Factor 1 Elemental - 99.85%
Chemical Form of Iodine In Pool Organic - 0.15%
Atmospheric Dispersion Factors Table 14.9-4 Time of Control Room Ventilation 20 minutes System Isolation 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