NL-15-1898, Enclosure 3: Hatch EAL Calculations - License Amendment Request for Changes to EAL Schemes to Adopt NEI 99-01 Rev. 6 and to Modify Radiation Monitors at Farley Nuclear Plant. Part 3 of 3

Enclosure 3: Hatch EAL Calculations - License Amendment Request for Changes to EAL Schemes to Adopt NEI 99-01 Rev. 6 and to Modify Radiation Monitors at Farley Nuclear Plant. Part 3 of 3

ML16071A146
Person / Time
Site:	Hatch, Vogtle, Farley
Issue date:	03/03/2016
From:	Southern Nuclear Operating Co
To:	Office of Nuclear Reactor Regulation
Shared Package
ML16071A108	List: ML16071A110 ML16071A126 ML16071A132 ML16071A136 ML16071A137 ML16071A140 ML16071A144 ML16071A146 ML16071A147 ML16071A149 ML16071A150 ML16071A152 ML16071A153 ML16071A158 ML16071A160 ML16071A166 ML16071A170 ML16071A174 ML16071A176 ML16071A180 ML16071A181 ML16071A184 ML16071A185 ML16071A187 ML16071A188 ML16071A193 ML16071A195 ML16071A198 NL-15-1898, Enclosure 2: EAL Deviations and Differences Maxtrix (Farley, Hatch, and Vogtle) Part 1 of 4 NL-15-1898, Enclosure 2: EAL Deviations and Differences Maxtrix (Farley, Hatch, and Vogtle) Part 2 of 4 NL-15-1898, Enclosure 2: EAL Deviations and Differences Maxtrix (Farley, Hatch, and Vogtle) Part 3 of 4 NL-15-1898, Enclosure 2: EAL Deviations and Differences Maxtrix (Farley, Hatch, and Vogtle) Part 4 of 4 NL-15-1898, Enclosure 3: Hatch EAL Calculations - License Amendment Request for Changes to EAL Schemes to Adopt NEI 99-01 Rev. 6 and to Modify Radiation Monitors at Farley Nuclear Plant. Part 1 of 3 NL-15-1898, Enclosure 3: Hatch EAL Calculations - License Amendment Request for Changes to EAL Schemes to Adopt NEI 99-01 Rev. 6 and to Modify Radiation Monitors at Farley Nuclear Plant. Part 2 of 3 NL-15-1898, Enclosure 3: Hatch EAL Calculations - License Amendment Request for Changes to EAL Schemes to Adopt NEI 99-01 Rev. 6 and to Modify Radiation Monitors at Farley Nuclear Plant. Part 3 of 3 NL-15-1898, Enclosure 4: EAL Verification and Validation Documents - License Amendment Request for Changes to EAL Schemes to Adopt NEI 99-01 Rev. 6 and to Modify Radiation Monitors at Farley Nuclear Plant. Part 1 of 6 NL-15-1898, Enclosure 4: EAL Verification and Validation Documents - License Amendment Request for Changes to EAL Schemes to Adopt NEI 99-01 Rev. 6 and to Modify Radiation Monitors at Farley Nuclear Plant. Part 2 of 6 NL-15-1898, Enclosure 4: EAL Verification and Validation Documents - License Amendment Request for Changes to EAL Schemes to Adopt NEI 99-01 Rev. 6 and to Modify Radiation Monitors at Farley Nuclear Plant. Part 3 of 6 NL-15-1898, Enclosure 4: EAL Verification and Validation Documents - License Amendment Request for Changes to EAL Schemes to Adopt NEI 99-01 Rev. 6 and to Modify Radiation Monitors at Farley Nuclear Plant. Part 4 of 6 NL-15-1898, Enclosure 4: EAL Verification and Validation Documents - License Amendment Request for Changes to EAL Schemes to Adopt NEI 99-01 Rev. 6 and to Modify Radiation Monitors at Farley Nuclear Plant. Part 5 of 6 NL-15-1898, Enclosure 4: EAL Verification and Validation Documents - License Amendment Request for Changes to EAL Schemes to Adopt NEI 99-01 Rev. 6 and to Modify Radiation Monitors at Farley Nuclear Plant. Part 6 of 6 NL-15-1898, Enclosure 5: Marked-Up EAL Schemes - License Amendment Request for Changes to EAL Schemes to Adopt NEI 99-01 Rev. 6 and to Modify Radiation Monitors at Farley Nuclear Plant. Part 1 of 8 NL-15-1898, Enclosure 5: Marked-Up EAL Schemes - License Amendment Request for Changes to EAL Schemes to Adopt NEI 99-01 Rev. 6 and to Modify Radiation Monitors at Farley Nuclear Plant. Part 2 of 8 NL-15-1898, Enclosure 5: Marked-Up EAL Schemes - License Amendment Request for Changes to EAL Schemes to Adopt NEI 99-01 Rev. 6 and to Modify Radiation Monitors at Farley Nuclear Plant. Part 3 of 8 NL-15-1898, Enclosure 5: Marked-Up EAL Schemes - License Amendment Request for Changes to EAL Schemes to Adopt NEI 99-01 Rev. 6 and to Modify Radiation Monitors at Farley Nuclear Plant. Part 4 of 8 NL-15-1898, Enclosure 5: Marked-Up EAL Schemes - License Amendment Request for Changes to EAL Schemes to Adopt NEI 99-01 Rev. 6 and to Modify Radiation Monitors at Farley Nuclear Plant. Part 5 of 8 NL-15-1898, Enclosure 5: Marked-Up EAL Schemes - License Amendment Request for Changes to EAL Schemes to Adopt NEI 99-01 Rev. 6 and to Modify Radiation Monitors at Farley Nuclear Plant. Part 6 of 8 NL-15-1898, Enclosure 5: Marked-Up EAL Schemes - License Amendment Request for Changes to EAL Schemes to Adopt NEI 99-01 Rev. 6 and to Modify Radiation Monitors at Farley Nuclear Plant. Part 7 of 8 NL-15-1898, Enclosure 5: Marked-Up EAL Schemes - License Amendment Request for Changes to EAL Schemes to Adopt NEI 99-01 Rev. 6 and to Modify Radiation Monitors at Farley Nuclear Plant. Part 8 of 8 NL-15-1898, Enclosure 5: Vogtle Marked-Up EAL Schemes - License Amendment Request for Changes to EAL Schemes to Adopt NEI 99-01 Rev. 6 and to Modify Radiation Monitors at Farley Nuclear Plant. Part 1 of 4 ... further results
References
NL-15-1898
Download: ML16071A146 (157)

Text

SM-SNC524602-001 ATCMN 2SET0-ATTACHMENT C2 SHEET C2-5 CRTD-Vol.

58 ASME INTERNATIONAL STEAM TABLES FOR INDUSTRIAL USE Second Edition Based on the IAPWS Industrial Formulation 1997 for the Thermodynamic Properties of Water and Steam (IAPWS-1F97)

Prepared by WILLIAM T. PARRY General Electric Company JAMES C. BELLOWS Siemens Energy, Inc.JOHN S, GALLAGHER Retired ALLAN H. HARVEY National Institute of Standards and Technology on behalf of ASME Research and Technology Committee on Water and Steam in Thermal Systems, Subcommittee on Properties of Steam THE AMERICAN SOCIETY OF MECHANICAL ENGINEERS Three Park Avenue em New York, N.Y. 10016 SM-SNC524602-001 ATTACHMENT 02 SHEET C2-6 Table U-2. Properties of Saturated Water and Steam (Pressure) p -I Volume, ir/lb., J Enthalpy, B tu/lbm, Entropy, BtuI(lb,..*R)

{p_p ~ t ("F) v L Av v h IL Ah h v si As s v Ip s!..0.1 0.12 0.14 11.16 0.2 0.25 0.3 0.35 04 0.45 0,5 0.6 0.7 0.8 0.9 1.0 1.2 1.4 1.6 1.8 2.0 2.2 2.4 2.6 2.3 3.0 3.5 4.0 4.5 5.0 5.5 6.0 6..5 7.0 7.5 3.0 8.5 9.0 9.5 10.0 10.5 11.0 11.5 12.0 12.5 13.0 13.5 14.0 14.066 15 16 17 18 19 20 21 22 23 24 25 35.1105 39.632 43.620 47.134 53,132 59.293 64.452 68.906 72.834 76.355 79.549 85.180 90.046 94.342 98.195 1 01.694 107.869 113.212 117.934 122. 174 126.027 129.563 132.835 135 .881I 138.734 141.418 147.515 152.913 157 .767 162.184 166.243 170.002 173.505 176.790 179.883 182.807 185.582 188.224 190.746 193.160!195.475 197 .700 199.842 201.908 203.904 205.834 207.704 209.517 211J.954 212.988 216.273 2 19.392 222.363 225.201I 227.9 18 230.526 233.034 235.450 237.781 240.034 0(116(020 2945.0 0.016 020 2476.9 (0.016020 2139.9 0.016 022 1885.3 0.016 027 1525.9 (1.016 034 1235.2 0.016 042 1039.4 0.016 050 898.40 0.016057 791.84 0.016 065 708.43 0.016073 641.31 0.016 087 539.89 0.016 100 466.80 0.016 113 411.56 0.016 125 368.30 0.016 137 333.49 0.0 16 158 280.87 0.0 16 178 242.93 0.016 196 214.25 0.016214 191.79 0.016 230 173.70 0.016 245 158.82 0.016 260 146.35 0.016 273 135.75 0.016 287 126.63 0.016 299 118.69 0.016 329 102.70 0.016 356 90.612 0.016 382 81.137 0.016 406 73.507 0.016 428 67.226 0.016 449 61.963 0.0 16 469 57.487 0.0 16 488 53.632 0.016 507 50.277 0.016 524 47.328 0.016 541 44.717 0.0 16 558 42.387 0.0 16 573 40.295 0.016 589 38.406 0.016604 36.692 0.016618 35.128 0.016 632 33.697 0.016 646 32.381 0.016659 31.167 0.016 672 30.04.4 0.0 16 685 29.002 0.016 697 28.031 0.016 714 26.787 0.016 721 26.278 0.016 745 24.738 0.016 767 23.374 0.016788 22.156 0.016 809 21.063 0.016 829 20.075 0.016849 19.179 0.016 868 18.361 0.016886 17.613 0.016 904 16.924 0.016 922 16.289 2945.0 2476.9 2139.9 1885.3 1525.9 1235.2 1039.4 898.41 791.86 708.44 64 1.32 539.90 466.81I 411.57 368.32 333.51 280.89 242.95 214.27 191.80 173.72 158.84 146.37 135.77 126.65 118.70 102.72 90.628 81.154 73.523 67.242 61.979 57.503 53.649 50.293 47.345 44.733 42.404 40.3 12 38.423 36.708 35.145 33.7 14 32.398 31.184 30.06 1 29.018 28.048 26.804 26.295 24.755 23.390 22.173 21.079 20.092 19.196 18.378 17.629 16.941I 16.306 3.009 7.662 11.668 15. 193 21.204 27.37 I 32.532 36.985 40.911 44.428 47.618 53.242 58. 110 62.389 66.236 69.728 75.892 8 1.225 85.939 90. 172 94.019 97.551 100.82 103.86 106.71 109.39 115.49 120.89 125.74 130.16 134.23 137.99 141 .50 144.79 147.90 150.83 153.61 156.27 158.80 161.22 163.55 165.79 167.94 170.02 172.03 173.97 175.85 177.68 180.13 181.18 184.49 1 87.63 190.63 193.50 196.25 198.88 201.42 203.86 206.23 208.51 1073.5 1076.5 1070.9 1078.5 1068.6 1080.3 1066.6 1081.8 1063.2 1084.4 1059.8 1087.1I 1056.8 1089.4 1054.3 1091.3 1052.1 1093.0 1050.1I 1094,5 1048.3 1095.9 1045.1 1098.3 1042.3 1100.4 1039.9 1102.3 1037.7 1103.9 1035.7 1105.4 1032.2 1108.1 1029.1 110.3 1026.4 112.3 1024.0 114.1 1021.7 115.8 1019.7 117.2 1017.8 118.6 1016.0 119.9 1014.4 1121.1 1012.8 1122.2 1009.2 1124.7 1006.1 1126.9 1003.2 1128.9 1000.6 1130.7 998.14 1132.4 995.90 1133.9 993.79 1135.3 991.81 1136.6 989.94 1137.8 988.17 1139.0 986.48 1140.1 934.87 1141.1 983.32 1142.1 981.84 1143.1 980.42 1144.0 979.04 1144.8 977.71 1145.7 976.43 1146.4 975.19 1147.2 973.93 1148.0 972.81 1148.7 971.67 1149.4 970.14 1150.3 969.48 1150.7 967.40 1151.9 965.42 1153.1 963.52 1154.2 961.70 1155.2 959.95 1156.2 958.26 1157.1I 956.63 1158.0 955.05 1158.9 953.52 1 159.7 952.04 1160.5 0.0061 0.0155 0.0235 0.0304 0.0422 0.0542 0.0641 0.0725 0.0799 0.0865 0.0925 0.1028 0.1117 0.1195 0.1264 0.1326 0.1435 0. 1529 0. 1611I 0. 1684 0. 1750 0. 1810 0.1865 0. 1916 0. 1964 0.2009 0.2110 0.2 198 0.2277 0.2349 0.2414 0.2474 0.2529 0.2581 0.2630 0.2675 0.2719 0.2760 0.2799 0.2836 0.2871I 0.2905 0.2938 0.2969 0.3000 0.3029 0.3057 0.3084 0.3121 0.3 137 0.3 136 0.3232 0.3276 0.33 18 0.3358 0.3396 0.3433 0.3468 0.3502 0.3534 2.1701 2.1447 2.,1233 2.1046 2.0734 2.0421 2.0 164 1.9947 1.9758 1.959 I 1.9441I 1.9 182 1.8962 1.8770 1.8601 1.8450 1.8187 1.7964 1.7770 1.7599 1.7445 1.7305 1.7178 1.7060 1,6951I 1.6849 1.6621 1.6423 1.6247 1.6090 1.5947 1.5816 1.5695 1.5583 1.5479 1.5381 1.5288 1.52.01!.5118 1.5040 1.4965 1.4393!.4825 1.4759 1.4696 1.4635 1.4577 1.4520 1.4445 i.44 13 1.43 12 1.4217 1.4127 i1.4042 1.3961 1.3884 1.38 10 1.3739 1.3671I 1.3606 2.1762 2.1602 2.1467 2.1351 2.1156 2.0962 2.0805 2.0672 2.0557 2.0456 2.0366 2.02 10 2.0079 1.9965 1.9865 1.9776 1.9623 1.9493 1.938 I 1.9283 1.9 195 1.9115 1.9043 1.8977 1.89 15 1.8858 1.8731 1.8621 1.8525 1.8438 1.8361 1.8290 1.8224 1.8164 i1.8 108 1.8056 1.8007 1.7961 1.7917 1.7875 1.7836 1.7799 1.7763 1.7728 1.7696 1.7664 1.7634 1.7605 1.7566 1.7549 1.7497 1.744.9 1.7403 1.7360 1.7319 1.7280 1.7243 1.7207 1.7 173 1.7 141 0.1 0.12 0.14 0.16 0.2 0.25 0.3 0.35 0.4 0.45 0.5 0.6 0.7 0.8 0.9 1.0 1.2 1.4 1.6 1.8 2.0 2.2 24 2.6 2.8 3.0 3.5 4.0 4.5 5.0 5.5 6.0 6.5 7.0 7.5 8.0 9.0 9.5 10.0 10.5 11.0 11.5 12.0 12.5 13.0 13.5 14.0 14.696 15 16 17 13 19 20 21 22 23 24 25 174 SM-SNC524602-001 ATTACHMENT C2 SHEET C2-7 Table U-3 (continued).

Properties of Superheated Steam and Compressed Water (0) 14 psia (ht, 1.= 209.52 0 F) 15psia (t,., = 21.9 °F) 1 psia (4,., = 216,27 (F)Sal. Liq. 0.016697 177.68 0.3084 0.016721 181.18 0.3137 0.016745 184.49 0.3186 Sal. Liq.Sai. Yap. 28.048 1149.4 1.7605 26.295 I150.7 1.7549 24.755 1151.9 1.7497 Sal. Yap.32 0.016021 0.024 0.0000 0.016 021 0.027 0.0000 0.016021I 0.030 0.0000 32 40 0.016019 8.073 0.0162 0.016 019 8.076 0.0162 0.016019 8.079 0.0162 40 SO 0.016023 18.106 0.0361 0.016023 18,109 0.0361 0.016023 18.112 0.0361 SO 60 0.016034 28,118 0.0555 0.016034 28.120 0.0555 0.016034 28.123 0.0555 60 70 0.016051 38.116 0.0746 0.016051 38.119 0.0746 0.016 051 38.122 0.0746 70 80 0.016 073 48.106 0.0933 0.016073 48.109 0.0933 0.016 073 48.111 0.0933 80 90 0.016 100 58.090 0.1116 0.016 100 58.093 0,1116 0.016 100 58.096 0.1I116 90 100 0.016 131 68.071 0.1296 0.016 130 68.074 0.1296 0.016 130 68.077 0.1296 100 110 0.016 165 78.052 0.1473 0.016 165 78.054 0.1473 .0.016 165 78.057 0.1473 110 120 0.016204 88.033 0.1647 0.016 204 88.036 0.1646 0.016 204 88.038 0.1646 120 130 0.016246 98.017 0.1817 0.016246 98.019 0.1817 0.016246 98.022 0.1817 130 140 0.016292 108.00 0.1985 0.016292 108.01 0.1985 0.016292 108.01 0.1985 140 150 0.016 341 118.00 0.2151 0.016 341 118.00 0.2150 0.016 341 118.00 0.2150 150 160 0.016393 128.00 0.2313 0.016393 128.00 0.2313 0,016393 128.00 0.2313 160 170 0.016449 138.01 0.2473 0.016449 138.01 0.2473 0.016448 138.01 0.2473 170 180 0.016 507 148.03 0.2631 0.016 507 148.03 0.2631 0.016 507 148.03 0.2631 180 190 0,016569 158.06 0.2787 0.016568 158.06 0.2787 0.016568 158.06 0.2787 190 200 0.016633 168.10 0.2940 0.016633 168.11 0.2940 0.016633 168.11 0.2940 200 210 28.070 1149.6 1.7608 0.016701 178.17 0.3092 0.016701 178.17 0.3092 210 220 28.521 1154.5 1.7681 26.591 1154.1 1.7601 24.903 1153.7 1.7525 220 230 28.969 1159.4 1.7752 27.012 1159.0 1.7672 25.299 1158.7 1.7597 230 240 29.415 1164.2 1.7822 27.430 1163.9 1.7742 25.692 1163.6 1.7667 240 250 29.860 1169.0 1.7890 27.846 1168.7 1.7811 26,084 1168.4 1.7736 250 260 30.303 1173.8 1.7958 28.26 I 1173.6 1.7878 26.474 1173.3 1.7804 260 270 30.744 1178.6 1.8023 28.674 1178.4 1.7945 26.862 1178. I 1.7871 270 280 31. 185 1183.4 1.8088 29.086 1183.1I 1.801I0 27.249 I1182.9 1.7936 280 290 31.624 1188.1I 1.8152 29.497 1 187.9 1.8074 27.635 1 187.7 1.8000 290 300 32.062 1192.9 1.8215 29.906 1192.7 1.8137 28.020 1192.4 1.8063 300 310 32.499 1197.6 1.8277 30.315 1197.4 1.8199 28.405 1197.2 1.8125 310 320 32.935 1202.3 1.8338 30.723 1202.1 1,8260 28.788 1202.0 1.8187 320 330 33.371 1207.1I 1,8398 3I. 131 1206.9 1.8320 29. 170 1206.7 1.8247 330 340 33.806 1211.8 1.8457 31.537 1211.6 1.8380 29.552 1211.4 1.8307 340 350 34.240 1216.5 1.8516 31.943 1216.3 1.8438 29.933 1216.2 1.8366 350 360 34.674 1221.2 1.8574 32.349 1221.1I 1.8496 30.314 1220.9 1.8424 360 370 35.107 1225.9 1.8631 32.754 1225.8 1.8554 30.694 1225.6 1.8481 370 350 35.540 1230.6 1.8688 33.158 1230.5 1.8610 31.074 1230.4 1.8538 380 390 35.972 1235.4 1.8743 33.562 1235.2 1.8666 31.453 1235.1 "1.8594 390 400 36.404 1240.1I 1.8799 33.966 1239.9 1.8721 31.832 1239.8 1.8649 400 410 36.836 1244.8 1.8853 34.369 1244.7 1.8776 32.210 1244.5 1.8704 410 420 37.267 1249.5 1,8907 34,772 1249.4 1.8830 32.588 1249.3 1.8758 420 430 37.698 1254.2 1.8961 35.174 12.54.1I 1.8884 32.966 1254.0 1.8811 430 440 38.129 1259.0 1.9013 35.577 1 258.9 1.8936 33.344 1258.7 1.8864 440 450 38.559 1263.7 1.9066 35.979 1263.6 1.8989 33.721 1263.5 1.8917 450 460 38.990 1268.4 1.9117 36.381 1268.3 1.904 1 34.098 1268.2 1.8969 460 470 39.420 1273.2 1.9169 36.782 1273.1 1.9092 34.475 1273.0 1.9020 470 480 39.849 1277.9 1.9220 37,184 1277.8 1.9143 34.851 1277.7 1.9071 480 490 40.279 1282.7 1.9270 37.585 1282.6 !.9193 35.228 1282.5 1.9121 490 500 40.708 1287.4 1.9320 37.986 1287.3 1.9243 35.604 1287.2 1.9171 500 510 41. 137 1292.2 1.9369 38.387 1292.1I 1.9292 35.980 1292.0 1.9220 510 520 41.567 1297.0 1.9418 38.787 1296.9 1.9341 36.356 1296.8 1.9269 520 530 41i.995 1301.7 1.9466 39.188 1301.6 1.9390 36.732 1301!.6 1.9318 530 540 42.424 1306.5 1.9514 39.588 1306.4 1.9438 37.107 1306.4 1.9366 540 550 42.853 1311.3 1.9562 39.989 1311.2 1.9485 37.483 1311I.1 1.9414 550 560 43.281 1316 1 1.9609 40.389 1316.0 1.9533 37.858 1315.9 1.9461 S60 570 43.710 1320.9 1.9656 40.789 1320.8 1.9580 38.233 1320.7 1.9508 570 580 44.138 1325.7 1.9703 4I. 189 1325.6 1.9626 38.608 1325.6 1.9554 580 590 44.566 1330.5 1.9749 41.589 1330.4 1.9672 38.983 1330.4 1.9601 590 600 44.994 1335.3 1.9794 41.988 1335.3 1.9718 39.358 1335.2 1.9646 600 UNITS: i' in ft 3/1b., ; h in Btu/1bm ; s in Btul(ibm'"R) 198 SM-SNC524602-001 ATTACHMENT C2 SHEET C2-8 Table U-3 (continued).

Properties of Superheated Steam and Compressed Water 1800 palQ, = 623.07"F) 2eoo a,, =635.85 F) 2Nm ala,, 1 9.= -____ ____F_____________

__________

s_____ h s t('F)Sat. L.q.Sat. Vip.32 40 50 60 70 80 90 110 120 130 140 IS0 160~170 180 150 200 210 220 230 240 230 260 270 280 290 300 310 320 330 340 350 360 370 38O 390 400 410 420 430 440 450 460 470 480 490 O00 510 520 530 S40O 560 570 580 590 0.024 73 0.2184 0.015 923 0.015 923 0,015931 0.015 944 0.015 962 0`015 936 0.016 013 0.016 044 0,016 079 0.016 118 0`016 360 0.0I6 205 0.016 253 0.016 304 0.016 356 0.016415 0.016 475 0.016 537 0.036 603 0.016 6713 0.016 742 0.016 836 0.016 893 0.036 973 0.037 056 0.017 142 0.017 23!0037 324 0.037 420 0.017 539 0.017 623 0.037 730 0.037 841 0.017 956 0.0350 76 0.031320 0.01i8 329 0.013 464 0.0183604 0.011 749 0.018 902 0.039061 0`039 227 0.019 402 0.0I9 585 0.019 7781 0.039 983 0.020 395 0.020 422 0.020 663 0.020 921 0.023 196 0.021 492 0.0218133 0.022 362 0.022 545 0.022 970 0.023 448 648.27 1150.7 5.367 13.333 23.232 33,3"4 43.053 52.960 62.868 72.776 82.687 92.6013 302.52 332.44 322.37 132.33I 342.26 352.22 362.39 372.17 382.36 392.37/20'2.20 232.25 222.31I 232.40 242.50 252.64 262.60 272.98 283.20 293.45 303.73 334.05 324.43!334.83 345.26 355.76 366.33 376.92 38"7.60 398.34 409.35 420.04 4313.02 442.09 453.27 464.56 475.96 487.51 499.20 511.06 523.10 535.35 547.84 560.59 573.66 587.10 600.97 635.39 0.8415S 1.3063 0.o010 0.0161 0.03581 0.0O550 0.0739 0.0925 0.1106 0.1285 0.1461 0.13633 0. 1803 0.1970 0.21334 0.2296 0.2455i 0.2632 0.2766 0.2939 0.3069 0.3238 0 3364 0.3509 0.3652 0.3793 0.3932 0.40"70 0.4206 0.4341I 0.4475 0.4607 0.4738 0.4863 0.4997 0.5125 0.5251 0.53770.5626 0.5750 0.5873 0.5995 0.6337 0.6233 0.6359 0.6480 0.6603 0.6721 0.6842 0.6963 0.7085 0.7207 0.733 3 0.7455 07533 0.7706 0.7338 0.7971 0,.8107 0,025 63 0.1882 0.0315932 0.035933 0.035 923 0.015 934 0.035 953 0.035 976 0.0316003 0.016 035 0.0!6070 0.036 108 0.036 350 0.036 395 0.036 243 0.016 294 0.016 348 0.036 405 0.036464 0.0136 527 0.036 592 0.0136660 O0.06 733 0.036805 0.016 833 0.036 961 0.037044 0.037 329 0.037 2131 0.037 310 0.037406 0.037 505 0.017607 0.037 713 0.037 824 0.037 938 0.0183057 0.031 3810 0.013309 O0103442 0.018 531 0.0313726 0.033 876 0.019 034 0,019 399 0.039371 0.0I9 552 0.0139 743 0.039943 0.020 154 0.020 378 0.020 615 0.020 867 0.0213137 0.023 427 0.021 739 0,022 078 0.022 450 0.022 359 0.023 317 671.80 11336.5 5.960 13.894 23.802 33.703 43.603 53,501 63.400 73.303 83.205 93,112 303.02 1 12.94 322.86 132.80 342.74 352.69 162.65 372.62 382.63 392.62 202.64 232.67 222.73 232,81 242.93 253.03 263.38 273.36 283.56 293.80 304.07 314.38 324733 335.32 345.56 356.04 366.58 377.37 387.83 3981.55 409.34 420.23 433.16 442.23 453.35 464.60 475.98 487.48 499.32 5130.93 522.31 535.09 547.49 560.35 73,13'586.41 600.13 634.33 0.8622 1.2864 0.0001 0.013613 0,035"7 0.0550 0.0739 0.0924 0.13105 0.3284 0. 1459 0. 1632 0.13803 0.1968 0.2332 0.2294 0.2453 0.2610 0.2764 0.2917 0.3O67 0.3215S 0.3363 0.35O6 0.3649 03790 0.3929 0.4067 0.4203 0.4338 0.4473 0.4604 0.4735 0.4864 0.4993 0.5120 0.5247 0.5373 0.5497 0.5623 0.5744 0.5867 0.5989 0.633i3 0.6232 0.6352 0.6473 0.6593 0.67 14 0.6834 0.6955 0.7076 0.71398 0.7320 0.7444 0.7568 0.7695 0.73123 0,7954 0.8089 0.026 68 0.I1627 0.015 901 0.035 903 0.015 930 0.0 15 924 0.015 943 0.035 966 0.035 994 0.0 36 025 0.036 060 0.016099 0.036 341 0.016 336 0.0136 234 0.0136 284 0.036 338 0.016 395 0.016 454 0.0136 5813 0.016 649 0.016 720 0.016 793 0.0136 870 0.016 949 0.037 031 0,017 3316 0.0137 205 0.037 296 0.037 39t 0.037 490 0.0317 592 0,037 697 0.03730 0.017 921I 0.018 039 0.013 363 0.0 13 289 0.0181421 0.018 559 0.018 702 0.0181 853 0.039 007 0.019 373 0.019 343I 0.039 520 0.0319 708 0.019 906 0.020 314 0.020 334 0.020 567 0.020335 0.021 080 0.021 363 0.021 668 0.02f 3581 0.022 754 0.023 193 695.09 1120.4 6.553 14.475 24.370 34.262 44.1351 54.o413 63.932 73.825 83.721 93.62 3 303.53 133344 323.35 333.28 343.23 353.36 363.33 173.08 383.06 393.06 203.07 233.30 223.35 233.22 243.31 253.43 263.57 273.74 283.93 294.36 304.42 3134.72 325.06 335A3 345.35 356.32 366.85 377.42 388.06 398.76 409.53 420.33 431.31 442.33 453.44 464.66 476.00 43'7.46 499.06 530.81 522.73 534.85 547.138 559.75 572.59 535.76 599.31 633.33 0.8825 3,2659 0.0001 0,01363 0.0357 0.0549 0.0738 0.0923 0.1104 0. 1283 0.1458 0.31630 0.31800 0.31966 0.2330 0.2292 0.2451 0.2607 0.2762 02934 0.3064 0.3233 0.3359 0.`3503 0.3646 0.3787 0.3926 0.4064 0.4200 0A433S 0.4468 0.4600 0.4731 0.4860 0.4989 0.511 6 0.5242 0.5363 0.5492 0.,56136 0.5739 033862 0.5983 0.6305 0.622.5 0.6346 0.6466 0.6586 0.67/06 0`6326 0.6946 0.7/067 0,7388 0.7330 0.7433 0.7556 0.768I2 0.7809 0.7939 0.8071 Sat, L~iq.Sat. Vap.32 40 50 60 70 80 90 100 110 120 130 140 150 160 170 180 390 200 210 220 230 240 250 260 270 230 290 300 310 320 340 350 370 380 390 400 410 420 430 450 460 470 48I0 490 520 530 S4O 560'7..590 400 UNITS: v ia ; h in Btu/3b, ; in 8tu/(Ib.-°R) 238 SM-SNC524602-001 ATTACHMENT 02 SHEET C2-9 Table U-3 (continued).

Properties of Superheated Steam and Compressed Water... 2400sIma ( = 662.16'F) 2600 pIta (t:n 673 98 *F) 2800 pita 685.03 0 F)t (W) 'f '" A : J ' h v " h ____(°F Sai. Liq.Sai Vdp.32 40 50 60 70 80 90 100 110 120 13O 140 150 160 370 180 190 200 210 22.0 230 240 250 240O 270 280 290 300 310 320 330 340 350 360 380 400 430 420 440 450 460 470 480 500 530 540 550 560 600 0.027 89 0.1407 0.015 890 0.0)589 0.015 900 0.015 914 0,015 933 0.015 957 0.015 985 0.016016 0016 051 0.0 16 090 0016 131 0.016 176 0016 224 0.016 275 0.016 328 0.016 385 0,016 444 0.016 506 0,016 571 0.016 638 0.016 7/09 0.016 782 0.016858 0.1116 937 0,017 103 007191 0,017 283 0.017 377 0.017 475 0O0I7 576 0017 681 0017 790 0.017 903 0.018021 0.018 142 0.018 269 0.018 400 0,018 536 0.018 679 0.018 827 0,018 981 0.019 343 0.0193 12 0.019 488 0.019 674 0.0!9 869 0.020 074 0.020 291 0.020 521 0.020 764 0.021 024 0-021 30)0.021 599 014)23 921 0.022 653 0.023 076 718,67 1101.9 7.141 15.054 24.938 34.8 19 44.700 54.581 64.464 74.349 84.238 94.131 104.03 11393 123.14 133,76 143.69 153.63 163.57 173.54 183,51I 193.50 203.51 213.53 223.57 233.63 243.72 253,82 263.96 274.11 284.30 294.52 304.77 315.06 325.38 335.75 346.15 356h61 367.12 377.68 388.30 398.91 409,73 420.55 431.46 442,45 453.54 464 72 476.02 487.45 499.00 510.71 522.58 534.63 546.88 559.37 572.11 585.16 598.56 612.38 0.9O27 1.2443 0,1001I 0.0161 0.0357 0,0549 0.0737 0.0922 0.1103 0.1281 0 1457 0. 1629 0.1798 0.1965 0.2128 0.2290 0.2449 0.2605 0.2760 0,39)2 0.3062 0.32)0 0 3356 0.3500 0.3643 03784 0.392.3 0.4060 0.4196 0.4331 0.4464 0.4596 0.4727 0,4856 0.4985 0.5112 0.5238 0.5363 0.5488 0.5611 0.5734 0.5856 0.5978 0.6099 0.62 19 0.6339 0.6459 0.6579 0.6699 0.68 18 0,6938 0,7058 0.7179 0.7300 0.7422 0.7545 0.7669 0.'7795 0.7924 0,8055 0.029 38 0.1211 0-015 880 0.015 882 0.015 890 0.015 905 0.015 924 0.015 947 0,015 975 0,016007/0,1116042 0.016 080 0.016 122 0.016 167/0.016 214 0.016 265 0.016 319 0 0)6 375 0.016 434 0,016 496 0.016 560 0.016 628 0,016 698 0.016 771 0.016 846 0.016 925 0.0)7 006 0.017091 0.0)7 178 0.0)7 269 0.017 363 0.017 460 0.017 56)I 0.0 17 666 0.017 774 0.0)7 886 0.018 003 0.018 123 0.018 249 0.018 379 0.018 515 0.018 656 0,018 802 0.0)8 955 0.0)9 !15 0,019 282 0.019 457 0.019641 0,019 833 0.020036 0.020 249 0.020 475 0.0207)5 0.020 970 0.021 24)0.02) 533 0.02) 847 0.022 186 0.022 557 0.022 965 743,27 1060.'2 7.730 15.632 25.505 35,376 45.247 55.120 64.995 74.873 84.754 94 .640 10453 11[4.43 124.33 134.24 144.16 154.10 164.04'73.99 183.96 193.94 203.94 2 13.96 223.99 234.05 244.12 254.22 264,34 274.49 284.67 294,.88 305.12 315.39 325.71t 336.06 346.46 356.90 367.39 377.93 388.53 399.20 ,409.93 420.7'3 431.61 442.58 453.64 464,79 476.06 487.44 498.96 510.62 522.43 534.42 546.61 559.01 571.66 584.60 597.87 611.52 0.9236 1.2208 0.0001 0.0 161 0.0356 0.0548 0.07/36 0.0921 0.1102 0.1210 0.1455 0. 1627 0.1796 0. 1963 0.2127 0.2288 0.2447 0.2603 0.27/57 0.2909 0.3059 0.3207 0.3353 0.3498 (1.3640 0.378)0.3920 0,405"7 0.4193 0.43211 0.446!0.4593 0.4723 0.4852 0.4980 0.5106 0.5234 0.5359 0.5483 0.5606 0.5729 0.5851 0.5972 0.6093 0.6213 0.6333 0.6453 0.6572 0.6691 0.681 I 0.6930 0.7049 0.7169 0.7290 0.7411 0.7534 0.7657/0.7782 0.7909 0.5039 0,031 34 0.,1029 0.015 869 0.015 872 0.0)5 880 0.0)5 895 0.015 914 0.015 938 0.015 966 0-015 997 0.016 032 0.016071 0.0)6 113 0.016 157 0.016 205 0.016 255 0.0)6 309 0.0)6 365 0.0! 6 424 0,016 485 0.016 550 0.016 6)7 0.016 687 0.016 759 0.016 835 0.016 913 0.0)6 994 0.017078 0.017 165 0.0)7 255 0.0)7 349 0.0)7 446 0.0 17 546 0-017 650 0.0)7 758 0.017 869 0,017 985 0.018 105 0.018 229 0.01I8 359 0,018 493 0.0)8 633 0.018 17"8 04)18 930 0.019068 0.019 254 0.0)9 426 0.0 19 608 0.019 798 0.0!9 998 0.020 208 0.020 431 0.020 666 0.020 917 0.021 183 0.02) 468 0.021 7/75 0.022 l0S 0.022 465 0.022 859 770.20 1053A 8.317 16.2 10 26.07)35.932 45.794 55.658 65 .525 7 5.396 85.270 95,149 105.03 114.92 124.82 134,73 144.64 154.56 164.50 174.45 184.41 194.39 204.33 214.39 224.4)I 234.46 244.53 254.62 26473 274 .87 285.04 295.24 305.47 315.73 326.04 336.38 346.76 35"/.19 367.66 378.19 388.7/8 399.42 4 10,.13 420.92 431.77 442,7/)453.7/4 464.87 476.10 487.45 498.92 5)0.54 522.30 534.23 546.35 558.68 571.24 584.08 597.22 610,72 0.9462 1.1936 0.0)60 0.0356 0.0547 0.0735 0.0920 0. 1t01 o.1279 0. 1454 0.1626 0.1795 0.1961 0.2 125 0.2286 0.2445 0.2601 0,2755 0.2907/0.305'7 0. 3205 0.335)0.3 495 0-3637 0 .3778 0.3917 0.4054 0.4 190 0.4324 0.4457 0.4589 0.47i19 0.4848 0.4976 0.5 103 0.5229 0.5354 0.5478 0.5601 0.5724 0,5846 0.5967 0.6087 0.62O7 0.6327 0.6446 0.6565 0.6684 0.6803 0,6922 O.704)0.7 160 0.7280 0.7401 0.7522 0.7645 0.7769 0.7595 0.8023 Sal. Lzq Sal. Yap 32 40 50 60 70 80 90 100 110 120 1.30 140 ISO 160 170 180 190 200 2)0 220 230 240 250 260 270 280 290 300 310 320 330 340 350 360 370 310 390 400 410 420 430 440 460 470 4,9 500 520 540 550 560 6OO UNITS: p, in h in £ in BluJ(lbm'R) 240 Southern Nuclear Design Calculation IPlant: Farley Unit: 1&2 ICalculaton Number: SM-SNC524602-o01 Sheet: D-1 I Attachment D -Water Level Elevations Corresponding to Fuel Uncovery Several EALs are based on the water level elevations that correspond to uncovery of irradiated fuel in the reactor vessel, the spent fuel pool, and the spent fuel transfer canal during refueling operations.

RPV Level at 6" Below Bottom ID of RCS LOOD Hot Leg Centerline Elevation-'Ax I D =-1/2 x29" Elevation

@ bottom of loop 6-inch level reduction= 122'-9" = 121'-21"= -0'-14.5"[Design Input #9][Design Input #9]= 121 '-6.5" (= 121 '-21" -0'-14.5")Elevation

@ 6" below bottom of loop = 121'-0.5" =-121'Cold Leg Centerline Elevation-1/2 x ID =1/2x 27.5" Elevation

@ bottom of loop 6-inch level reduction-122'-9" = 121'-21"--0'-1 3.75"= 121'-7.25"[Design Input #9][Design Input #9]Elevation

@ 6" below bottom of loop = 1 20'-1 .25" = -121'Top of Active Fuel (TOAF) in Reactor Vessel The elevation of the top of the irradiated fuel in the reactor vessel is determined by referencing reactor vessel dimensions from drawings U168878 & U206587 to the centerline of the cold and hot leg nozzle centerline elevation as shown to the right.The upper core plate elevation is the CL/HL centerline elevation (122'-9";

Design Input #9) plus the distance to the reactor vessel mating surface (82.437";

Design Input #9) then minus the distance from the mating surface to the upper core plate (124.687";

Design Input #9): ELucP = 122.75 ft + [(82.437 in -124.687 in) x (1 ft/12 in)]ELucP = 122.75 ft -3.53 ft ELucp = -119 ft Mating Surface A A 32.437" I (uieaa7a &I U2OUUJ CL&HL* EL 122'S" 124.667" (U1671 &U206667)Upper Core Plate The elevation of TOAF (ELTOAF) is approximately 1 foot below this elevation (Assumption

1. 10): ELTOAF =-118' = 119' -1' Southern Nuclear Design Calculation IPlant: Farley U nit: I 2 ICalculationNumber:

SM-SN0524602-00O1 Sheet: D-2 I Attachment D -Water Level Elevations Corresponding to Fuel Uncovery Spent Fuel Pool The bottom elevation of the Spent Fuel Pool is 1 14'-5" (Design Input #6). The top of the spent fuel rack is 14'-5.375" (Design Input #7) above this as shown to the right.The elevation corresponding to a water level at the top Ak.lZ L of the spent fuel racks is ELsFP = 1 14'-5" + 14'-5.375" ELsFP = 128'-10.375" ELsFP = -129 ft The fuel transfer tube centerline elevation is 11 5'-101/=" (Design Inputs #6 & 8). A fuel assembly is 8.426" on a side (Design Input #11). Thus, the elevation corresponding to just covering the fuel assembly is ELXFR = 1 15'-101/2" + (8.426"/2)

= 1 15'-101/2" + 4.213" ELxFR = 1 15'-14.71 3" ELXFR = '-116 ft Southern Nuclear Design Calculation SPlant: Farley Unit: 1 &2 Calculation Number: SM-SNC524602-001I Sheet: E-l Attachment E -TEDE & Thyroid CDE Dose Calculations Description of Pages El -Plant Vent Stack TEDE & Thyroid ODE Calculations 6 E2A -SJAE Release Path TEDE & Thyroid CDE Calculations 6 (No Core Damage)E2B -SJAE Release Path TEDE & Thyroid ODE Calculations 6 (Core Damage)E3A -SIG ARV & SRV Release Path TEDE & Thyroid ODE Calculations 6 (No Core Damage)E3B -SIG ARV & SRV Release Path TEDE & Thyroid ODE Calculations 6 (Core Damage)E4A -TDAFWP Exhaust Release Path TEDE & Thyroid ODE Calculations 6 (No Core Damage)E4B -TDAFWP Exhaust Release Path TEDE & Thyroid ODE Calculations 6 (Core Damage)Total Number of Pages Including Cover Sheet 4 43 SM-SNC524602-001 ATCMN lSETE-ATTACHMENT E1 SHEET E1-1 Plant Vent Stack Release Path TEDE & Thyroid CDE Calculations Postulated Release Activity XRLS -- Release Concentration (pCi/cc)XRLS = [Partition Factor x Xrcs (p#Ci/g)]

x [pris (g/cc)]Partition Factors[Assumption

1. 5]Noble Gases: 1.0 Iodine, liquid leakage to Auxiliary Building:

0.01 Iodine, primary coolant leakage to Containment building:

0.01 Iodine, primary coolant leakage to steam generator:

0.01 Iodine, SJAEs: 1 .0E-04 RCS coolant activity (piCi/cc)RCS Equilibrium Activity (p.Ci/g) +[Release Fraction x Core Inventory (Ci) x (1 Ci)]/MRcs (g)Xrcs =Xrcs =RCS Equilibrium Activity:

Design Input #14 Core Inventory:

Design Input #14 Release Fractions

[Assumption

1. 6]1.0 for Noble Gases (RG 1.183 Table 2, LOCA)0.4 for Iodine (RG 1.183 Table 2, LOCA)0 for no core damage MRCS = RCS coolant mass (Ibm)MRcs = 417,219 Ibm x (453.59 g/1 Ibm) [Design Input #11]MRCS = 1 .89E+08 g pris = Density of release fluid (g/cc)pris = 1 .00E+00 g/cc [Arbitrary Value]

SM-SNC0524602-001 ATCMN lSETE-ATTACHMENT E1 SHEET E1-2 Isotope Core Core Xeq Xrcs (jtC ilg) Partition XRLS Inventory Release (.iCilg) Factor (JllCi/cc)(Ci) Fraction Kr-83m 9,70E+06 1.00 4.50E-01 5.IE+04 1.00 5.1E+04 Kr-85 7.20E+05 1.00 7.70E+00 3.8E+i03 1.00 3.8 E+03 SKr-85m 2.10E+07 1.00 1.80E+00 1.1IE+05 1.00 1.1IE+05 Kr-87 4.00E+07 1.00 1.20E+00 2.1E+05 1.00 2.1E+05 Kr-88 5.70E+07 1.00 3.50E+00 3.0E+05 1.00 3.0E+05 Kr-89 6.90E+07 1.00 1.10E-01 3.6E+05 1.00 3.6E+05;Xe-131 m 8.40 E+05 1.00 2.90E+00 4.4E+03 1.00 4.4 E+03 Xe-133 1.50E+08 1.00 2.40E+02 7.9E+05 1 oo 7.9E+05 Xe-133m 4.80E+06 1.00 4.60E+00 2.5E+04 1.00 2.5E+04 Xe-135 3.50E+07 1.00 7.90E+00 1.8E+05 1.00 1.8E+05 Xe-135m 3.00E+07 1.00 4.50E-01 1.6E+05 1.00 1.6E+05 Xe-137 1.40E+08 1.00 2.00E-01 7.4E+05 1.00 7.4E+05 Xe-138 1.30E+08 1.00 7.20E-01 6.9E+05 1.00 6.9E+05 1-131 7.50E+07 0,40 1,40E+00 1.6E+05 0,01 1.6E+03 I-132 1.10E+08 0.40 2.30E+00 2.3E+05 0.01 2.3E+03 I-133 1.60E+08 0.40 2.70E+00 3.4E+05 0.01 3.4E+03 1-134 1.70E+08 0.40 6.30E-01 3.6E+05 0.01 3.6E+03 I-135 1.50E+08 0.40 1.90E+00 3.2E+05 0.01 3.2E+03 SM-SNC524602-001 TAHETElSETE-ATTACHMENT E1 SHEET E1-3 Postulated Release TEDE Calculations TEDE =Total Effective Dose Equivalent (mREM)TEDE =EDE + CEDE EDE =Effective Dose Equivalent (mREM) from external exposure EDE =DCFFGR-12 X XEAB X texp DCFFGR-12

= FGR-12 dose conversion factor [(mREM/hr)/(pCi/cc)]

CEDE --Committed Effective Dose Equivalent (mREM) from inhalation CEDE --DCFFGR-11 x XEAB X BR X texp DCFFGR-11

= FGR-11I dose conversion factor (mREM/iCi)

XEAB =Radionuclide concentration at Exclusion Area Boundary (pCi/cc)XEAB =[QRLS (m^3/sec)]

X [X/Q (sec/m^3)]

x [XRLS (pCi/cc)]Qris =Release flow rate (m^3/sec)Qris = 150,000 CFM x [1 mini60 sec] x [0.0283 mA3/ft^3]

[Design Input #21]Qris "-70.8 mA3/sec X/Q =Atmospheric dilution factor (sec/m^3)X/Q = 4.87E-05 sec/m3 [Assumption

1. 3]texp Exposure time texp =I1.0 hour0 days <br />0 hours <br />0 weeks <br />0 months <br /> [Assumption

1. 1]BR =Breathing Rate (m^3/sec)BR = 3.47E-04 m^3/sec [Assumption

1. 2]BR 1 1.25E+06 cc/hr = m^3/sec x [(1 .0E6 cc)/(1 mA3)] x [3600 sec/i hr]

SM-SNC524602-001 ATCMN lSETE-ATTACHMENT E1 SHEET E1-4 Isotope Release XEAB FGR-12 EDE FGR-11 CEDE Activity DCF (mREM) DCF (mREM)(1.+/-Cilcc) (mREM/hr)/ (mREM/(j4Ci/cc) Kr-83m 5.1IE+04 1.8E+02 2.00E+O1 3.5E+03 0.OOE+O0 O.OE+OO Kr-85 3.8E+03 l.3E+Ol l.59E+03 2.1 E+04 O.OOE+OO O.OE+OO Kr-85m 1.1 E+05 3.8E+02 9.96E+04 3.8E+07 O.OOE+00 O.OE+OO Kr-87 2.1 E+05 7.3E+02 5.49E+05 4.OE+08 O.O0E+OO O.OE+OO Kr-88 3.0E+05 I1.0E+03 I1.36E+06 I1.4E+09 O.OOE+OO O.QE+OO Kr-89 3.6E+05 I1.3E+03 O.OOE+OO O.OE+OO O.OOE+OO O.OE+OQ Xe-131m 4.4E+03 1.5E+01 5.18E+03 7.9E+04 O.OOE+OO O.OE+OO Xe-I133 7.9E+05 2.7E+03 2.08E+04 5.7E+07 O.OOE+OO O.OE+OO Xe-133m 2.5E+04 8.7E+01 1.82E+04 1.6E+06 O.OOE+OO O.OE+OO Xe-135 1.8E+05 6.4E+02 I.59E+05 1.0E+08 O.OOE+OO O.OE+OO Xe-135m 1.6E+05 5.5E+02 2.72E+05 1.5E+08 O.OOE+OO O.OE+OO Xe-i137 7.4E+05 2.6E+03 O.OOE+00 O.OE+OO O.O0E+OO O.OE+OO Xe-138 6.9E+05 2.4E+03 7.69E+05 1.8E+09 O.OOE+OO O.OE+OO 1-131 1.6E+03 5.5E+00 2.42E+05 1.3E+06 3.29E+01 2.2E+08 1-132 2.3E+03 8.0E+00 1.49E+06 1.2E+07 3.81E-01 3.8E+06 1-133 3.4E+03 1.2E+01 3.92E+05 4.6E+06 5.85E+00 8.5E+07 1-134 3.6E+03 1.2E+01 1.73E+06 2.1E+07 1.31E-01 2.OE+06 ,1-135 3.2E+03 1.1E+01 1.06E+06 1.2E+07 1.23E+00 1.7E+07 Total = 4.0E+09 mREM Total = 3.3E+08 mREM TEDE = EDE + CEDE EDE.=CEDE =TEDE = 4.4E+09 4.0E+09 mREM 3.3E+08 mREM mREM SM-SNC524602-001 SM-SNC52602-001ATTACHMENT El1HETE-SHEET E1-5 100 & 1000 mREM TEDE Thresholds Xioo = 100 mREM TEDE Noble Gas concetration (jFCi/cc)Xioo = [(100 mREM)/(TEDE mREM)] x XRLS TEDE = 4.4E+09 mREM Xioo =2.3E-08 x XRLS Xiooo = 1000 mREM TEDE Noble Gas concetration (FtCi/cc)Xiooo =l0 x Xoo Isotope XRLS X100 Xio00 (ltC i/cc) (jiC i/cc) (lpCi/cc)SKr-83m 5.IE+04 1.2E-03 1.2E-02 Kr-85 3.8E+03 8.7E-05 8.7E-04 Kr-85m 1.1 E+05 2.5E-03 2.5E-02 Kr-87 2.1E+05 4.8E-03 4.8E-02 Kr-88 3.0E+05 6.9E-03 6.9E-02 Kr-89 3.6E+05 8.4E-03 8.4E-02 Xe-I131rm 4.4E+03 1 .0E-04 I1.OE-03 Xe-133 7.9E+05 1.8E-02 1.8 E-0I Xe-I133m 2.5E+04 5.8E-04 5.8E-03 Xe-I135 1 .8E+05 4.2E-03 4.2E-02 Xe-I135m i .6E+05 3.6E-03 3.6E-02 Xe-137 7.4E+05 1.7E-02 l.7E-01 Xe-138 6.9E+05 1.6E-02 1.6E-01 Totals 8.3E-02 1 4C i/cc Ci/cc SM-SNC524602-001 ATCMN lSETE-ATTACHMENT E1 SHEET E1-6 Thyroid CDE Calculations CDETHY = Thyroid Committed Dose Equivalent (mREM) from inhalation CDETHY -DCFFGR-11 X XEAB X BR x texp DCFFGR-11

= FGR-11I dose conversion factor (mREM/pFCi/cc) texp = 1.00 hour0 days <br />0 hours <br />0 weeks <br />0 months <br /> BR = 1 .25E+06 cc/hr X500T = 500 mREM Thyroid CDE Noble Gas concentration (liCi/cc)X500T = [(500 mREM CDE)/(CDETHY mREM)] x XRLS X500T=- 500/ 1.1E+10 x XRLS=- 4.8E-08 X XRLS X5000T = 5000 mREM Thyroid CDE Noble Gas concentration (pzCi/cc)X5000T = 10 x X500m Postulated Release Thyroid CDEThresholds Isotope XEAB FGR-11I CDETHY XRLS X500T X5000T DCF (mREM) (pCi/cc)(mREM/pCi)Kr-83m 1.8E+02 0.00E+00 0.0E+00 5.1E+04 2.4E-03 2.4E-02 Kr-85 I1.3E+01 0.00E+00 0.0E+O0 3.8E+03 I1.8E-04 1 .8E-03 Kr-85m 3.8 E+02 0.00E+00 0.0E+00 1.1 E+'05 5.3 E-03 5.3E-02 Kr-87 7.3E+02 0.00E+00 0.0E+00 2.1E+05 1.0E-02 1.0E-01 Kr-88 1 .0E+03 0.00E+00 0.0E+00 3.0E+05 1 .4 E-02 I.4E-01 Kr-89 I1.3E+03 0.00E+00 0.0E+00 3.6E+05 1 .7E-02 1 .7E-01 Xe-131 m 1.5E+01 0.00E+00 0.0E+00 4.4E+03 2.1E-04 2.1E-03 Xe-i133 2.7E+03 0.00E+00 0.0E+00 7.9E+05 3.8E-02 3.8E-01 Xe-133m 8.7E+01 0.00E+00 0.0OE+00 2.5E+04 1.2 E-03 1.2 E-02 Xe-135 6.4E+02 0.00E+00 0.0E+00 1.8E+05 8.8E-03 8.8E-02 Xe-135m 5.5 E+02 0.00E+00 0.0E+00 1.6E+05 7.5 E-03 7.5E-02 Xe-137 2.6E+03 0.00E+00 0.0E+00 7.4E+05 3.5E-02 3.5E-01 Xe-I138 2.4E+03 0.00E+00 0.0E+00 6.9E+05 3.3E-02 3.3E-01 1-131 5.5E+00 1.08E+03 7.4E+09 I-132 8.0E+00 6.44E+00 6.4E+07 I-133 1.2E+01 1.80E+02 2.6E+09 I-134 1 .2E+01 I1.07E+00 I1.6E+07 I-135 1.1IE+01 3.13E+01 4.3E+08 Total CDETHY " 1.1 E+10 mREM Totals 1.7E-01 lpCi/cc 1 .7E+00 pCilcc SM-SNC524602-001 SM-SNC52602-001ATTACHMENT E2ASHEEA-SHEET E2A-1 SJAE Release Path TEDE & Thyroid CDE Calculations (No Core Damage)Postulated Release Activity XRLS "-Release Concentration (pCi/cc)XRLS =[Partition Factor x Xr~cs (p.Cij/g)]

x [pris (g/cc)]Partition Factors[Assumption

1. 51 Noble Gases: 1.0 Iodine, liquid leakage to Auxiliary Building:

0.01 Iodine, primary coolant leakage to Containment building:

0.01 Iodine, primary coolant leakage to steam generator:

0.01 Iodine, SJAEs: 1.0E-04 Xrcs " RCS coolant activity Xrcs --RCS Equilibrium Activity +[Release Fraction x Core Inventory (Ci) x (1 .0E+06pFCi/1 Ci)]/MRcs (g)RCS Equilibrium Activity:

Design Input #14 Core Inventory:

Design Input #14 Release Fractions

[Assumption

1. 6]1.0 for Noble Gases (RG 1.183 Table 2, LOCA)0.4 for Iodine (RG 1.183 Table 2, LOCA)0 for no core damage MRCS = RCS coolant mass (Ibm)MRCS = 417,219 Ibm x (453.59 g/1 Ibm) [Design Input #11]MRcs = 1.89E+08 g pris -"Density of release fluid (g/cc)pris 1 1.00E+00 g/cc [Arbitrary Value]

SM-SNC524602-001 ATCMN 2 HE 2-ATTACHMENT E2A SHEET E2A-2 Isotope Core Core Xeq Xrcs ilg) Partition XRLS Inventory Release Factor (jiCi/cc)(Ci) Fraction Kr-83m 9.70E+06 0.00 4.50E-01 4.5E-01 1.00 4.5E-01 Kr-85 7.20E+05 0.00 7.70E+00 7.7E+00 1.00 7.7E+00 Kr-85m 2.10E+07 0.00 1.80E+00 1.8E+00 1.00 1.8E+00 Kr-87 4.00E+07 0.00 1 .20E+00 1 .2E+00 1.00 1 .2E+00 Kr-88 5.70E+07 0.00 3.50E+00 3.5E+00 1.00 3.5E+00 Kr-89 6.90E+07 0.00 1.10E-01 1.1E-01 1.00 1.1E-01 Xe-131m 8.40E+05 0.00 2.90E+00 2.9E+00 1.00 2.9E+00 Xe-133 1.50E+08 0.00 2.40E+02 2.4E+02 1.00 2.4E+02 Xe-I133m 4.80E+06 0.00 4.60E+00 4.6E+00 1.00 4.6E+00 Xe-135 3.50E+07 0.00 7.90E+00 7.9E+00 1.00 7.9E+00 Xe-I 35m 3.00E+07 0.00 4.50E-01 4.5E-01 1.00 4.5E-01 Xe=137 1.40E+08 0.00 2.00E-01 2.0E-01 1.00 2.0E-01 Xe-138 1.30E+08 0.00 7.20E-01 7.2E-01 1.00 7.2 E-01 1-131 7.50E+07 0.00 1.40E+00 1.4E+00 1.00E-06 1.4E-06 I-132 1.10E+08 0.00 2.30E+00 2.3E+00 1.00E-06 2.3E-06 I-133 1.60E+08 0.00 2.70E+00 2.7E+00 1.00E-06 2.7E-06 I-134 1.70E+08 0.00 6.30E-01 6.3E-01 1.00E-06 6.3E-07 1-135 1.50E+08 0.00 1.90E+00 1.9E+00 1.00E-06 1.9E-06 SM-SNC524602-001 SM-SNC52602-001ATTACHMENT E2ASHEE2-SH EET E2A-3 Postulated Release TEDE Calculations TEDE = Total Effective Dose Equivalent (mREM)TEDE = EDE + CEDE EDE = Effective Dose Equivalent (mREM) from external exposure EDE = DCFFGR-12 X XEAB X texp DCFFGR-12

= FGR-12 dose conversion factor [(mREM/hr)I(jpCilcc)]

CEDE = Committed Effective Dose Equivalent (mREM) from inhalation CEDE = DCFFGR-11 X XEAB X BR x texp.DCFFGR-11

= FGR-1 1 dose conversion factor (mREM/pCi)

XEAB = Radionuclide concentration at Exclusion Area Boundary (j#Ci/cc)XEAB = [QRLS (m^3/sec)]

x [XIQ (sec/m^3)]

x [XRLS (pCi/cc)]Qris = Release flow rate (m^3/sec)Qris = 1,060 CFM x [1 mini60 sec] x [0.0283 mA3/ftA3]

[Design Input #20]Oris = 0.50 mA3/sec X/Q = Atmospheric dilution factor (sec/mA3)X/Q = 4.87E-05 sec/m3 [Assumption

1. 3]texp = Exposure time texp = 1 .0 hour0 days <br />0 hours <br />0 weeks <br />0 months <br /> [Assumption

1. 1]BR = Breathing Rate (mA3/sec)BR = 3.47 E-04 mA3/sec [Assumption

1. 2]BR = 1 .25E+06 cc/hr = mA3/sec x [(1 .0E6 cc)/(1 mA3)] x [3600 sec/I hr]

SM-SNC524602-001 SM-SNC52602-OO1ATTACHMENT E2ASHEEA4 SHEET E2A-4 Isotope Release XEAB FGR-12 EDE FGR-11 CEDE Activity (1 iCi/cc) DCF (mREM) DCF (mREM)i/cc) i(m REMIh r)/ (m RE M/(p.Ci/cc) Kr-83m 4.5E-01 1.1IE-05 2.O0E+O1 2.2E-04 O.OOE+OO O.OE+O0 Kr-85 7.7E+00 1.9E-04 1.59E+03 3.0E-01 O.OOE+OO O.OE+OO Kr-85m I1.8E+O0 4.4E-05 9.96E+04 4.4E+00 O.OOE+O0 O.OE+OO Kr-87 I1.2E+O0 2.9E-05 5.49E+05 I1.6E+O1 O.OOE+OO O.OE+OO Kr-88 3.5E+00 8.5E-05 1.36E+06 1.2E+02 O.OOE+OO 0.0E+00 Kr-89 1.1 E-O1 2.7E-06 O.OOE+OO O.OE+OO O.OOE+O0 O.OE+0O Xe-131m 2.9E+00 7.lE-05 5.18E+03 3.7E-01 O.OOE+OO O.OE+OO Xe-133 2.4E+02 5.8E-03 2.08E+04 1.2E+02 O.OOE+OO O.OE+OO Xe-133m 4.6E+00 1.1E-04 1.82E+04 2.0E+OO O.OOE+OO O.OE+OO Xe-135 7.9E+O0 1.9E-04 1.59E+05 3.1 E+01 O.OOE+OO O.OE+OO Xe-135m 4.5E-01 1.1E-05 2.72E+05 3.OE+00 O.OOE+OO O.OE+OO Xe-I137 2.0E-01 4.9E-06 O.OOE+OO O.OE+OO O.OOE+OO O.OE+OO Xe-138 7.2E-01 1.8E-05 7.69E+05 1.3E+01 O.OOE+OO O.OE+OO 1-131 1.4E-06 3.4E-11 2.42E+05 8.3E-06 3.29E+01 1.4E-03 1-132 2.3E-06 5.6E-11 1.49E+06 8.4E-05 3.81E-01 2.7E-05 1-133 2.7E-06 6.6E-11 3.92E+05 2.6E-05 5.85E+00 4.8E-04 1-134 6.3E-07 1.5E-11 1.73E+'06 2.7E-05 1.31E-01 2.5E-06 1-135 1.9E-06 4.6E-11 1.06E+06 4.9E-05 1.23E+00 7.1E-05 Total = 3.1 E+02 mREM Total = 2.0E-03 mREM TEDE = EDE + CEDE EDE =CEDE =TEDE = 3.1E+02 3.1E+02 mREM 2.0E-03 mREM mREM SM-SNC524602-001 ATCMN 2 HE 2-ATTACHMENT E2A SHEET E2A-5 100 & 1000 mREM TEDE Thresholds Xioo = 100 mREM TEDE Noble Gas concetration Xioo = [(100 mREM)/(TEDE mREM)] x XRLS Xiooo =Xlooo =TEDE =3.3E-01 1000 mREM 10 xXioo 3.1E+02 mREM X XRLS TEDE Noble Gas concetration (pCi/cc)Isotope XRLS Xi00 Xi000(lpCi/cc)Kr-83rn 4.5E-01 1 .5E-01 I1.5E+00 Kr-85 7.7E+00 2.5E+00 2.5E+01 Kr-85m I1.8E+00 5.9E-01 5.9E+00 Kr-87 1.2E+-00 3.9E-0I 3.9E+00 Kr-88 3.5E+i00 I.1E+i00 1.1E+01 Kr-89 1.1IE-01 3.6 E-02 3.6E-01 Xe-131 m 2.9E+00 9.4 E-0I 9.4E+00 Xe-I133 2.4E+02 7.8E+01 7.8E+02 Xe-133m 4.6E+00 1.5E+00 1.5E+01 Xe-135 7.9E+00 2.6E+00 2.6E+01 Xe-135m 4.5E-01 1.5E-01 1.5E+00 Xe-137 2.0E-01 6.5E-02 6.5E-01 Xe-I138 7.2E-01 2.3E-01 2.3E+00 Totals 8.8E+01 8.8E+02 pCiIcc pC i/cc a SM-SNC524602-001 SM-SNC52602-001ATTACHMENT E2ASHEEA6 SHEET E2A-6 Thyroid CDE Calculations CDETHY = Thyroid Committed Dose Equivalent (mREM) from inhalation CDETnY = DCFFGR-11 X XEAB X BR x texp DCFFGR-11

= FGR-11I dose conversion factor (mREM/tCi/cc) texp = 1.00 hour0 days <br />0 hours <br />0 weeks <br />0 months <br /> BR = 1 .25E+06 cc/hr xS00T = 500 mREM Thyroid CDE Noble Gas concentration

(#iCi/cc)X5O0T = [(500 mREM CDE)/(CDETHY mREM)] x XRLS X500T = 500/ 6.3E-02 X XRLS = 7.9E+03 x XRLS X5000T = 5000 mREM Thyroid CDE Noble Gas concentration

(#iCi/cc)X5000T = 10 X X500T Postulated Release Thyroid CDE Thresholds Isotope XEAB FGR-11I CDETHY XRLS X500T X5000T (piCilcc)

DCF (mREM) (mREM/piCi)Kr-83m 1.1IE-05 0.00E+00 0.0E+00 4.5E-01t 3.6E+03 3.6E+04 Kr-85 1.9E-04 0.00E+00 0.0E+00 7.7E+00 6.1E+04 6.1E+05 Kr-85m 4.4E-05 0.00E+00 0.0E+00 1 .8E+00 1 .4E+04 1 .4E+05 Kr-87 2.9E-05 0.00E+00 0.0E+00 1.2E+00 9.5E+03 9.5E+04 Kr-88 8.5E-05 0.00E+00 0.0E+00 3.5E+00 2.8E+04 2.8E+05 Kr-89 2,7E-06 0.00E+00 0.0E+00 1.1E-01 8.7E+02 8.7E+03 Xe-131 m 7.1E-05 0.00E+00 0.0OE+00 2.9E+00 2.3 E+04 2.3 E+05 Xe-133 5.8E-03 0.00E+00 0.0E+00 2.4E+02 1.9E+06 1.9E+07 Xe-133m 1.1E-04 0.00E+00 0.0E+00 4.6E+00 3.6E+04 3.6E+05 Xe-135 1.9E-04 0.00E+00 0.0E+00 7.9E+00 6.3E+04 6.3E+05 Xe-135m 1.1 E-05 0.00E+00 0.0E+00 4.5E-01 3.6E+03 3.6E+04 Xe-137 4.9E-06 0.00E+00 0.0E+00 2.0E-0I 1.6E+03 1.6E+04 Xe-138 1.8E-05 0.00E+00 0.0E+00 7.2E-01 5.7E+03 5.7E+04 1-131 3.4E-11 '1.08E+03 4.6E-02 1-132 5.6E-11 6.44E+00 4.5E-04 I-133 6.6E-11 1.80E+02 1.5E-02 I-134 1 .5E-1 1 1 .07E+00 2.0E-05 1-135 4.6E-11 3.13E+01 1.8E-03 Total CDETHY =-6.3E-02 mREM Totals 2.2E+06 2.2E+07 lpCi/cc SM-SNC524602-001 ATCMN 2 HE 2-ATTACHMENT E2B SHEET E2B-1 SJAE Release Path TEDE & Thyroid CDE Calculations (Core Damage)Postulated Release Activity XRLS = Release Concentration (iC i/cc)XRLS = [Partition Factor x Xrcs x [prls (glcc)]Partition Factors[Assumption

1. 5]Noble Gases: 1.0 Iodine, liquid leakage to Auxiliary Building:

0.01 Iodine, primary coolant leakage to Containment building:

0.01 Iodine, primary coolant leakage to steam generator:

0.01 Iodine, SJAEs: 1.0E-04 Xrcs = RCS coolant activity (p, Ci/cc)Xrcs = RCS Equilibrium Activity (pCi/g) +[Release Fraction x Core Inventory (Ci) x (1 .0E+061iCi/1 Ci)]/MRcs (g)RCS Equilibrium Activity:

Design Input #14 Core Inventory:

Design Input #14 Release Fractions

[Assumption

1. 6]1.0 for Noble Gases (RG 1.183 Table 2, LOCA)0.4 for Iodine (RG 1.183 Table 2, LOCA)0 for no core damage MRCS = RCS coolant mass (Ibm)MRcs = 417,219 Ibm x (453.59 g/1 Ibm) [Design Input #11]MRCS = 1 .89E+08 g prls = Density of release fluid (g/cc)prls = 1 .00E+00 g/cc [Arbitrary Value]

SM-SNC524602-001 ATCMN 2 HE 2-ATTACHMENT E2B SHEET E2B-2 Isotope Core Core Xeq Xrcs (.LC ig) Partition XRLS Inventory Release Factor (jtCi/cc)(Ci) Fraction SKr-83m 9.70E+06 1.00 4,50E-01 5.1E+04 1.00 5,1E+04 Kr-85 7,20E+05 1.00 7.70E+00 3.8E+03 1.00 3.8 E+'03 Kr-85m 2.10E+07 1.00 1.80E+00 1.I E+05' 1.00 1,1IE+05 Kr-87 4.00E+07 1.00 1.20E+00 2.1E+05 1.00 2.IE+05 Kr-88 5,70E+07 1.00 3.50E+00 3.OE+05 1.00 3.0E+05 Kr-89 6.90E+07 1.00 1.10E-01 3.6E+05 1.00 3.6E+05 Xe-131 m 8.40 E+05 1.00 2.90 E÷00 4.4E+03 1.00 4.4E+03 Xe-133 1.50E+08 1.00 2.40E+02 7.9E+05 1.00 7.9E+05 Xe-133m 4.80E+06 1.00 4.60E+00 2.5E+04 1.00 2.5E+04 Xe-135 3.50E+07 1.00 7.90E+00 1.8E+05 1.00 1.8E+05 Xe-135m 3.00E+07 1.00 4.50E-01 1.6E+05 1.00 1.6E+05 Xe-137 1.40E+08 1.00 2.00E-01 7.4E+05 -1.00 7.4E+05 Xe-138 1.30E+08 1.00 7.20E-01 6.9E+05 1.00 6.9E+05 1-131 7.50E+07 0.40 1 40E+00 I 6E+05 I .OE-06 I 6E-01 I-132 1.10E+08 0.40 2.30E+00 2.3E+05 1.00E-06 2.3 E-01 1-133 1.60E+08 0.40 2.70E+00 3.4E+i05 1.00E-06 3.4E-01 1-134 1 .70E+08 0.40 6.30E-01 3.6E+05 1 .00E-06 3.6E-01 1-135 1.50E+08 0.40 l.90E+00 3.2E+05 1.00E-06 3.2E-01 SM-SNC524602-001 SM-SNC52602-001ATTACHMENT E2BSHEE23 SHEET E2B-3 Postulated Release TEDE Calculations TEDE = Total Effective Dose Equivalent (mREM)TEDE = EDE + CEDE EDE = Effective Dose Equivalent (mREM) from external exposure EDE = DCFFGR-12 x XEAB x texp DCFFGR-12

-FGR-12 dose conversion factor [(mREM/hr)/(j, Cilcc)]CEDE = Committed Effective Dose Equivalent (mREM) from inhalation CEDE = DCFFGR-11 x XEAB X BR x texp DCFFGR-11

= FGR-1 1 dose conversion factor (mREM/pCi)

XEAB = Radionuclide concentration at Exclusion Area Boundary (pCi/cc)XEAB = [QRLS (m^3/sec)]

x [X/Q (sec/m^3)]

x [XRLS (pCi/cc)]Qris = Release flow rate (mA3/sec)Qris = .1,060 CFM x [1 min/60 sec] x [0.0283 mA3/ft^3]

[Design Input #201 Qris = 0.50 mA3/sec X/Q = Atmospheric dilution factor (sec/m*3)X/Q = 4.87E-05 sec/m3 [Assumption

1. 3]texp =Exposure time texp = 1.0 hour0 days <br />0 hours <br />0 weeks <br />0 months <br /> [Assumption

1. 1]BR = Breathing Rate (mA3/sec)BR = 3.47E-04 mA3/sec [Assumption

1. 2]BR = 1 .25E+06 cc/hr = m^3/sec x [(1 .0E6 cc)/(1 m*3)] x [3600 sec/Ilhr]

SM-SNC524602-001 SM-SNC52602-OO1ATTACHMENT E2BSHEE24 SHEET E2B-4 Isotope Release XEAB FGR-12 EDE FGR-11 CEDE Activity (1DCF (mREM) DCF (mREM)(mREM/hr)l (mREMI Kr-83m 5,1E+04 1.2E+00 2.00E+01 2.5E+01 O.OOE+OO O.QE+OO Kr-85 3.8E+03 9,3E-02 1,.59E+03 1 .5E+02 O.OOE+OO O.OE+OO Kr-85m 1,1E+05. 2.7E+00 9.96E+04 2,7E+05 O,00E+OO O,0E+OO Kr-87 2,1E+05 5,1E+00 5,49E+05 2.8E+06 O.OOE+OO O.OE+OO Kr-88 3,0E+05 7.3E+00 1,.36E+06 I1,0E+07 0.OOE+OO O.OE+00 Kr-89 3,6E+05 8,9E+00 O,00E+OO O.OE+O0 0.OOE+OO O,0E+00 Xe-131m 4,4E+03 1.1E-01 5.18E+03 5,6E+02 0,00E+00 O.OE+OO Xe-133 7.9E+05 1,9E+01 2,08E+04 4.0E+05 O,00E+OO 0.0E+00 Xe-133m 2,5E+04 6.2E-01 1.82E+04 1,1E+04 O,00E+OO O,0E+OO Xe-135 1.8E+05 4,5E+00 1,59E+05 7.1E+05 O,00E+OO O.OE+O0 Xe-135m 1,6E+05 3.9E+00 2.72E+05 1,0E+06 0,00E+00 O,0E+00 Xe-137 7,4E+05 1,8E+01 0,00E+00 O,0E+OO O,00E+00 O,0E+00 Xe-138 6,9E+05 1.7E+01 7,69E+05 1,3E+07 0,00E+00 0,0E+00 1-131 1.6E-01 3.9E-06 2.42E+05 9.4E-01 3.29E+0-1 1.6E+02 1-132 2.3E-01 5.7E-06 1.49E+06 8.5E+00 3.81E-01 2.7E+00 1-133 3.4E-01 8.2E-06 3.92E+05 3.2E,+00 5.85E+00 6.0E+01 1-134 3.6E-01 8.8E-06 1.73E+06 1.5E+01 1.31E-01 1.4E+00 1-135 3.2E-01 7.7E-06 1.06E+06 8.2E+00 1.23E+00 1.2E+01 Total = 2.8E+07 mREM Total = 2.3E+02 mREM TEDE = EDE + CEDE EDE = 2.8E+07 mREM CEDE = 2.3E+02 mREM TEDE = 2.8E+07 mREM SM-SNC524602-001 SM-SNC52602-001ATTACHMENT E2BSHEE2-SHEET E2B-5 100 & 1000 mREM TEDE Thresholds Xioo =100 mREM TEDE Noble Gas concetration (jiCi/cc)Xioo =[(100 mREM)/(TEDE mREM)] x XRLS TEDE = 2.8E+07 mREM Xl000 =Xl000 -3.6E-06 1000 mREM 10 xXioo x XRLS TEDE Noble Gas concetration (gCi/cc)Isotope XRLS Xi00 Xi000i/cc) i/cc) Kr-83m 5.1 E+04 1.8 E-01 1.8E+00 Kr-85 3.8E+03 1 .4E-02 1 .4E-01 Kr-85m 1.1E+05 3.9 E-01 3..9E+00 Kr-87 2.1 E+05 7.5E-01 7.5E+00 Kr-88 3.0E+05 1.1IE+00 1.1 E+01 Kr-89 3.6E+05 1 .3E+00 1 .3E+01 Xe-131 m 4.4E+03 1.6E-02 1.6E-01 Xe-i133 7.9E+05 2.8E+'00 2.8E+01 Xe-133m 2.5E+'04 9,0E-02 9.0E-01 Xe-135 1.8 E+05 6.6E-01 6.6 E+00 Xe-135m 1.6E+05 5.6E-01 5.6 E+00 Xe-I137 7.4E+05 2.6E+00 2.6E+01 Xe-i138 6.9E+05 2.4E+00 2.4E+01 Totals 1.3E+01 1.3E+02 pCilcc pCi/cc SM-SNC524602-001 SM-SN052602-001ATTACHMENT E2BSHEE26 SHEET E2B-6 Postulated Release Thyroid CDE Calculations CDETHY = Thyroid Committed Dose Equivalent (mREM) from inhalation CDETHY = DCFFGR-11 X XEAB X BR X texp DCFFGR-I1

= FGR-11I dose conversion factor (mREM/tCi/cc) texp -1.00 hour0 days <br />0 hours <br />0 weeks <br />0 months <br /> BR = 1 .25E+06 cc/hr X5OOT = 500 mREM Thyroid ODE Noble Gas concentration X500T = [(500 mREM CDE)/(CDETHY mREM)] x XRLS X5OOT = 500/ 7.4E+03 x XRLS = 6.7E-02 x XRLS X5000T = 5000 mREM Thyroid ODE Noble Gas concentration (pCi/cc)X5000T = 10 x X500T Postulated Release Thyroid CDE Thresholds Isotope XEAB FGR-11I CDETHY XRLS X500T X5000T (jxCilcc)

DCF (mREM) (jtCi/cc) (jiCi/cc) (mREMI pCi)Kr-83m 1.2E+00 0.00E+00 0.0E+00 5.1E+04 3.5E+03 3.5 E+04 Kr-85 9.3E-02 0.00E+00 0.0E+00 *3.8E+03 2.6E+02 2.6E+03 Kr-85m 2.7E+00 0.00E+00 0.0OE+00 1.1IE+05 7.5E+03 7.5E+04 Kr-87 5.1E+00 0.00E+'00 0.0E+00 2.1E+05 1.4E+04 1.4E+05 Kr-88 7.3E+00 0.00E+00 0.0E+00 3.0E+05 2.0E+04 2.0E+05 Kr-89 8.9E+I00 0.00E+00 0.0E+00 3.6E+05 2.5E+04 2.5E+05 Xe-131 m 1.1E-01 0.O0E+00 0.0OE+00 4.4E+03 3.0OE+02 3.0E+i03 Xe-133 1.9E+01 0.OOE+00 0.0E+00 7.9E+05 5.3E+04 5.3E+05 Xe-133m 6.2E-01 0.00E+00 0.0E+00 2.5E+04 1.7E+03 1.7E+04 Xe-135 4.5E+00 0.00E+00 0.0E+00 1.8E+05 1.2E+04 1.2E+05 Xe-135m 3.9E+00 0.00E+00 0.0E+00 1.6E+05 1.IE+04 1.1E+05 Xe-137 1.8E+01 0.00OE+00 0.0E+00 7.4E+05 5.0OE+04 5.0E+05 Xe-138 1.7E+01 0.00E+00 0.0E+00 6.9E+05 4.6E+04 4.6E+05 I-131 3.9E-06 1.08E+03 5.2 E+03 I-132 5.7E-06 6.44E+00 4.6E+01 I-133 8.2E-06 1.80E+02 1.9E+03 I-134 8.8E-06 1.07E+00 1.2E+01 1-135 7.7E-06 3.13E+01 3.0E+02 Total CDETHY " 7.4E+03 mREM Totals 2.4E+05 ipCilcc 2.4E+06 SM-SNC524602-001IATCMN 3 HE 3-ATTACHMENT E3A SHEET E3A-1 SIG SRVs & ARVs Release Path TEDE & Thyroid CDECalculations (No Core Damage)Postulated Release Activity XRLS = Release Concentration (FiCi/cc)XRLS = [Partition Factor x Xrcs (jiCi/g)]

x [prls (g/cc)]Partition Factors[Assumption

1. 5]Noble Gases: 1.0 Iodine, liquid leakage to Auxiliary Building:

0.01 Iodine, primary coolant leakage to Containment building:

0.01 Iodine, primary coolant leakage to steam generator:

0.01 Iodine, SJAEs: 1 .0E-04 Xrcs = RCS coolant activity (p.Ci/cc)Xrcs = RCS Equilibrium Activity +[Release Fraction x Core Inventory (Ci) x (1 .0E+06 pCi/I Ci)]IMRcs (g)RCS Equilibrium Activity:

Design Input #14 Core Inventory:

Design Input #14 Release Fractions

[Assumption

1. 6]1.0 for Noble Gases (RG 1.183 Table 2, LOCA)0.4 for Iodine (RG 1.183 Table 2, LOCA)0 for no core damage MRCS = RCS coolant mass (Ibm)MRcs = 417,219 Ibm x (453.59 g/1 Ibm) [Design Input #111 MRcs- =1I.89E+08 g prls = Density of release fluid (g/cc)pris = 1 .00E+00 g/cc [Arbitrary Value]

SM-SNC524602-001 ATCMN 3 HE 3-ATTACHMENT E3A SHEET E3A-2 Isotope Core Core Xeq Xrcs ilg) Partition XRLS Inventory Release (jxCilg) Factor (Ci) Fraction Kr-83m 9.70E+06 0.00 4,50E-01 4,5E-01 1.00 4.5E-01 Kr-85 7.20E+05 0.00 7,70E+00 7.7E+00 1.00 7.7E+00 Kr-85m 2.10E+07 0.00 1.80E+00 1.8E+00 1.00 1.8E+00 Kr-87 4.00E+07 0.00 1 .20E+00 1 .2E+00 1.00 1 .2E+00 Kr-88 5.70E+07 0.00 3.50E+00 3.5E+00 1.00 3.5E+00 Kr-89 6.90E+07 0.00 1.10E-01 1.1E-01 1.00 1.1E-01 Xe-131 m 8,40 E+05 0.00 2.90E+00 2,9 E+00 1.00 2,9 E+00 Xe-133 1.50E+08 0.00 2.40E+02 2.4E+02 1.00 2.4E+02 Xe-133m 4.80E+06 0.00 4,60E+00 4.6E+00 1.00 4.6E+00 Xe-135 3.50E+07 0.00 7,90E+00 7.9E+00 1.00 7,9E+00 Xe-135m 3.00E+07 0.00 4.50E-01 4.5E-01 1.00 4,5E-01 Xe-137 1.40E+08 0.00 2,00E-01 2.0E-01 1.00 2.0E-01 Xe-138 1.30E+08 0.00 7,20E-01 7.2 E-01 1.00 7.2E-01 I-131 7.50E+07 0.00 1.40E+00 1.4E+00 0.01 1.4E-02 I-132 1.I0E+08 0.00 2.30E+00 2.3E+00 0.01 2.3E-02 1-133 1.60E+08 0.00 2.70E+00 2.7E+00 0.01 2.7E-02 I-134 1.70E+08 0.00 6.30E-01 6.3E-01 0.01 6.3E-03 1-135 1.50E+08 0.00 1.90E+00 1.9E+00 0.01 1.9E-02 SM-SNC524602-001 SM-SNC52602-001ATTACHMENT E3ASHEE33 SHEET E3A-3 Postulated Release TEDE Calculations TEDE = Total Effective Dose Equivalent (mREM)TEDE = EDE + CEDE EDE = Effective Dose Equivalent (mREM) from external exposure EDE = DCFFGR-12 x XEAB X texp DCFFGR-12

= FGR-12 dose conversion factor [(mREM/hr)/(pfCi/cc)]

CEDE = Committed Effective Dose Equivalent (mREM) from inhalation CEDE = DCFFGR-11 X XEAB X BR x texp DCFFGR-11

-FGR-11I dose conversion factor (mREM/jiCi)

XEAB "- Radionuclide concentration at Exclusion Area Boundary (!tCi/cc)XEAB = [QRLS (m^3/sec)]

X [X/Q (sec/m^3)]

x [XRLS (jtCi/cc)]

Oris = Release flow rate (m^3/sec)QRLS = 613,000 Ibm/hr x SVstm (cu ft/Ibm) x [1 hr/60 mini [Assumption

1. 4]SVstm = Specific Volume of Saturated Steam @ Patrm SVstm = 26.804 cu ft/Ibm [Assumption

1. 8]QRLS "- 2.74E+05 CFM x [1 min/60 sec] x [0.0283 m^3/ft^3]QRLs = 129.2 mA3/sec X/Q = Atmospheric dilution factor (sec/m^3)X/Q = 4.87E-05 sec/m3 [Assumption

1. 3]texp = Exposure time texp -1.0 hour0 days <br />0 hours <br />0 weeks <br />0 months <br /> [Assumption

1. 1]BR = Breathing Rate (mA3/sec)BR = 3.47E-04 mA3/sec [Assumption

1. 2]BR = 1 .25E+06 cc/hr = m^3/sec x [(1 .0E6 cc)/(1 mA3)] x [3600 sec/i hr]

SM-SNC524602-001 SM-SNC52602-OOIATTACHMENT E3ASHEE3-SHEET E3A-4 Isotope Release XEAB FGR-1 2 EDE FGR-11I CEDE Activity (jltCilcc)

DCF (mREM) DCF (mREM)(JlCilcc) (mREM/hr)l (mREMI pCi)Kr-83m 4.5E-01 2.8E-03 2.00E+01 5.7E-02 O.OOE+OO O.OE+OO Kr-85 7.7E+00 4.8E-02 1 .59E+03 7.7E+01 0.OOE+OO O.OE+OO Kr-85m 1.8E+00 1.IE-02 9.96E+04 1.1E+'03 0.OOE+00 0.OE+00O Kr-87 1.2E+00 7.6E-03 5.49E+05 4.1E+03 O.OOE+OO O.OE+OO Kr-88 3.5E+00 2.2E-02 I1.36E+06 3.0E+04 O.OOE+00 O.OE+OO Kr-89 1.1E-01 6.9E-04 0.OOE+OO 0.0E+00O O.OOE+OO 0.0E+00 Xe-131m 2.9E+00 1.8E-02 5.18E+03 9.5E+01 O.00E+OO O.OE+OO Xe-133 2.4E+02 I.5E+00 2.08E+04 3.1E+04 O.OOE+OO 0.0E+00O Xe-133m 4.6E+00 2.9E-02 1.82E+04 5.3E+02 O.O0E+OO 0.OE+00 Xe-135 7.9E+00 5.0E-02 1.59E+05 7.9E+03 O.OOE+00 O.OE+O0 Xe-I135m 4.5E-01 2.8E-03 2.72E+05 7.7E+I02 0.OOE+OO O.OE+OO Xe-137 2.0E-01 I.3E-03 O.OOE+OO O.OE+O0 O.OOE+OO O.OE+OO Xe-I138 7.2E-01 4.5E-03 7.69E+05 3.5E+03 O.00E+OO O.QE+OO;I-131 1.4E-02 8.8E-05 2.42E+05 2.1E+01 3.29E+01 3.6E+03!1-132 2.3E-02 1.4E-04 1.49E+06 2.2E+02 3.81E-01 6.9E+01 1-133 2.7E-02 1.7E-04 3.92E+05 6.7E+01 5.85E+00 1.2E+03 1-134 6.3E-03 4.0E-05 1.73E+06 6.9E+01 I.31E-01 6.5E+00 1-135 I.9E-02 1.2E-04 1.06E+06 1.3E+02 1.23E+00 1.8E+02 Total = 8.0E+04 mREM Total = 5.1 E+03 mREM.5 TEDE = EDE + CEDE EDE =CEDE =TEDE = 8.5E+04 8.0E+04 mREM 5.1E+03 mREM mREM SM-SNC524602-001 ATCMN 3 HE 3-ATTACHMENT E3A SHEET E3A-5 100 & 1000 mREM TEDE Thresholds Xioo = 100 mREM TEDE Noble Gas concetration (pCi/cc)Xioo = [(100 mREM)/(TEDE mREM)] x XRLS TEDE = 8.5E+04 mREM Xioo = 1 .2E-03 X XRLS X1000 Xiooo-1000 mREM= 10 xXioo TEDE Noble Gas concetration (p.Ci/cc)Isotope XRLS Xioo Xi000 Kr-83m 4.5E-01 5.3E-04 5.3E-03 Kr-85 7.7E+00 9.1E-03 9.1E-02 Kr-85m 1.8E+00 2.1E-03 2.1IE-02 Kr-87 1 .2E+00 I1.4E-03 1 .4E-02 Kr-88 3.5E+00 4.1E-03 4.1E-02 Kr-89 1.1 E-01 1.3E-04 1.3E-03 Xe-131 m 2.9E+00 3.4 E-03 3.4 E-02 Xe-I133 2.4E+'02 2.8E-01 2.8E+00 Xe-I133m 4.6E+00 5.4E-03 5.4E-02 Xe-1 35 7.9E+00 9.3E-03 9.3E-02 Xe-i135m 4.5E-0I 5.3E-04 5.3E-03 Xe-I137 2.0E-0l 2.4E-04 2.4E-03 Xe-i138 7.2E-0I 8.5E-04 8.5E-03 Totals 3.2E-01 3.2E+00 pCi/cc pC ilc c SM-SNC524602-001 ATCMN 3 HE 3-ATTACHMENT E3A SH EET E3A-6 Thyroid CDE Calculations CDETHY = Thyroid Committed Dose Equivalent (mREM) from inhalation CDETHY = DCFFGR-11 X XEAB X BR x texp DCFFGR-11

= FGR-11I dose conversion factor (mREM/jiCi/cc)

X500T =XS00T =X500T =X5000T =texp " 1.00 hour0 days <br />0 hours <br />0 weeks <br />0 months <br /> BR 1 1.25E+06 cc/hr 500 mREM Thyroid CDE Noble Gas concentration (iCi/cc)[(500 mREM CDE)/(CDETHY mREM)] x XRLS 500/ 1 .6E+05 X XRLS = 3.1 E-03 X XRLS 5000 mREM Thyroid CDE Noble Gas concentration (iCi/cc)X5000T = 10 X X500T Y Postulated Release Thyroid CDE Thresholds Isotope XEAB FGR-11I CDETHY XRLS X500T X5000T (jtCi/cc)

DCF (mREM) (jltCilcc) (jiCilcc)(mREMI jiCi)Kr-83m 2.8E-03 0.00E+00 0.0E+00 4.5E-01 I1.4E-03 I1.4E-02 Kr-85 4.8E-02 0.00E+00 0.0E+00 7.7E+00 2.4E-02 2.4E-01 Kr-85m 1.1IE-02 0.O0E+00 0.0E+00 1.8E+00 5.5E-03 5.5E-02 Kr-87 7.6E-03 0.00E+00 0.0E+00 I1.2E+00 3.7E-03 3.7E-02 Kr-88 2.2E-02 0.00E+00 0.0E+00 3.5E+00 1.1E-02 1.1E-01 Kr-89 6.9E-04 0.00E+00 0.0E+00 1.1 E-01 3.4E-04 3.4E-03 Xe-131 m 1.8E-02 0.00E+00 0.0E+00 2.9E+00 8.9E-03 8.9 E-02 Xe-133 1.5E+00 0.00E+00 0.0E+00 2.4E+02 7.4E-01 7.4E+00 Xe-133m 2.9E-02 0.00E+00 0.0E+00 4.6E+-00 1.4E-02 1.4E-01 Xe-I135 5.0E-02 0.00E+00 0.0E+00 7.9E+00 2.4E-02 2.4E-01 Xe-135m 2.8E-03 0.00E+00 0.0E+00 4.5E-01 1.4E-03 1.4 E-02 Xe-137 1.3E-03. 0.00E+00 0.0E+00 2.0E-01 6.1E-04 6.1E-03 Xe-i138 4.5E-03 0.00E+00 0.0E+00 7.2E-01 2.2E-03 2.2E-02 I-131 8.8E-05 1.08E+03 1.2E+05 I-132 1.4 E-04 6.44E+00 1.2E+'03 I-133 1.7E-04 1.80E+02 3.8 E+04 I-134 4.0E-05 1.07E+00 5.3E+01 1-135 1.2E-04 3.13E+01 4.7E+03 Total CDETHY =I1.6E+05 mREM Totals 8.3E-01 J.LCilcc 8.3E+00 IpCi/cc I I SM-SNC524602-001 ATCMN 3 HE 3-ATTACHMENT E3B SHEET E3B-1 SIG SRVs & ARVs Release Path TEDE & Thyroid CDECalculations (Core Damage)Postulated Release Activity XRLS -"Release Concentration XRLS =[Partition Factor x Xrcs (jiCi/g)]

x [pris (g/cc)]Partition Factors[Assumption

1. 5]Noble Gases: 1 .0 Iodine, liquid leakage to Auxiliary Building:

0.01 Iodine, primary coolant leakage to Containment building:

0.01 Iodine, primary coolant leakage to steam generator:

0.01 Iodine, SJAEs: 1.0E-04 Xrcs =RCS coolant activity (iC i/cc)Xrcs =RCS Equilibrium Activity (pCi/g) +[Release Fraction x Core Inventory (Ci) x (1 .0E+i06jiCi/1 Ci)]/MRcs (g)RCS Equilibrium Activity:

Design Input #14 Core Inventory:

Design Input #14 Release Fractions

[Assumption

1. 6]1.0 for Noble Gases (RG 1.183 Table 2, LOCA)0.4 for Iodine (RG 1.183 Table 2, LOCA)0 for no core damage MRCS = RCS coolant mass (Ibm)MRCS = 417,219 Ibm x (453.59 g/1 Ibm) [Design Input #11]MRcs = 1 .89E+08 g pris --Density of release fluid (g/cc)pris -' 1.00E+00 g/cc [Arbitrary Value]

SM-SNC524602-001 ATCMN 3 HE 3-ATTACHMENT E3B SHEET E3B-2 Isotope Core Core Xeq Xrcs (llCi/g) Partition XRLS Inventory Release (jlCilg) Factor (liCi/cc)(Ci) Fraction Kr-83m 9.70E+06 1.00 4.50E-01 5.1E+04 1.00 5.1E+04 Kr-85 7.20E+05 1.00 7.70E+00 3.8E+03 1.00 3.8E+03 Kr-85m 2.10E+07 1.00 1.80E+00 1.1E+05 1.00 1.1E+05 Kr-87 4.00E+07 1.00 1.20E+00 2.1IE+05 1.00 2.1E+05 Kr-88 5.70E+07 1.00 3.50E+00 3.0E+05 1.00 3.0E+05 Kr-89 6.90E+07 1.00 1.10E-01 3.6E+05 1.00 3.6E+05 Xe-131m 8.40E+05 1.00 2.90E+00 4.4E+03 1.00 4.4E+03 Xe-133 1.50E+08 1.00 2.40E+02 7.9E+05 1.00 7.9E+05 Xe-133m 4.80E+06 1.00 4.60E+00 2.5E+04 1.00 2.5E+04 Xe-135 3.50E+07 1.00 7.90E+00 1.8E+05 1.00 1.8E+05 Xe-135m 3.00OE+07 1.00 4.50 E-01 1.6 E+05 1.00 1.6 E+05 Xe-137 1.40E+08 1.00 2.00E-01 7.4E+05 1.00 7.4E+05 Xe-138 1.30E+08 1.00 7.20E-01 6.9E+05 1.00 6.9E+05 I-131 7.50E+07 0.40 1.40E+00 1.6E+05 0.01 1.6E+03 I-132 1.10E+08 0.40 2.30E+00 2.3E+05 0.01 2.3E+03 1-133 1.60E+08 0.40 2.70E+00 3.4E+05 0.01 3.4E+03 I-134 1.70E+08 0.40 6.30E-01 3.6E+05 0.01 3.6E+03 1-135 1.50E+08 0.40 1.90E+00 3.2E+05 0.01 3.2E+03 SM-SNC524602-001 SM-SNC52602-001ATTACHMENT E3BSHEEB-SHEET E3B-3 Postulated Release TEDE Calculations C C TEDE = Total Effective Dose Equivalent (mREM)TEDE = EDE + CEDE EDE = Effective Dose Equivalent (mREM) from external exposure EDE = DCFFGR-12 X XEAB X texp DCFFGR-12

= FGR-12 dose conversion factor [(mREM/hr)/(p,iCi/cc)]

3EDE = Committed Effective Dose Equivalent (mREM) from inhalation 3EDE = DCFFGR-11 X XEAB X BR x texp DCFFGR-11

= FGR-l11 dose conversion factor (mREM/p, Ci)XEAB = Radionuclide concentration at Exclusion Area Boundary (pCi/cc)XEAB = [QRLs (m^3/sec)]

x [X/Q (sec/m^3)]

x [XRLS (pCi/cc)]Qris -Release flow rate (mA3/sec)QRLS = 613,000 Ibm/hr x SVstm (cu ft/Ibm) x [1 hr/60 min] [Assur SVstrn = Specific Volume of Saturated Steam @ Patm SVstrn = 26.804 cu ft/Ibm [Assur QRLS = 2.74E+05 CFM x [1 mini60 sec] x [0.0283 m^3/ft^3]QRLS = 129.2 m^3/sec X/Q = Atmospheric dilution factor (sec/mA3)X/Q = 4.87E-05 :sec/m3 [Assur texp = Exposure time texp -1.0 hour0 days <br />0 hours <br />0 weeks <br />0 months <br /> [Assur BR = Breathing Rate (mA3/sec)BR = 3.47E-04 m^3/sec [Assur*BR = 1 .25E+06 cc/hr = m^3/sec x [(1 .0E6 cc)/(1 mA3)] x [3600 sec/I h nption #4]nption #8]nption #3]nption #1]nption #2]r]

SM-SNC524602-001 SM-SNC52602-OO1ATTACHMENT E3BSHEEB4 SHEET E3B-4 Isotope Release XEAB FGR-12 EDE FGR-11 CEDE Activity DCF (mREM) DCF (mREM)(mREM/hr)/ (mREM/(pCilcc) pCi)Kr-83m 5.1E+04 3.2E+02 2.00E+01 6.4E+03 O.00E+OO O.OE+OO Kr-85 3.8E+03 2.4E+01 1.59E+03 3.8E+04 O.00E+OO O.0E+00 Kr-85m 1.1E+05 7.0E+02 9.96E+04 7.0E+'07 O.OOE+OO O.OE+OO Kr-87 2.1E+05 1.3E+03 5.49E+05 7.3E+08 0.00E+00 O.OE+OO Kr-88 3.0E+05 1 .9E+03 I1.36E+06 2.6E+09 O.O0E+00O O.OE+00O Kr-89 3.6E+05 2.3E+03 O.00E+O0 0.OE+OO O.00E+00O 0.0E+00 Xe-131m 4.4E+03 2.8E+01 5.18E+03 1.4E+05 O.00E+OO O.OE+OO Xe-133 7.9E+05 5.0E+03 2.08E+04 1.0E+08 O.OOE+OO O.OE+00 Xe-133m 2.5E+04 1.6E+02 l.82E+04 2.9E+06 O.OOE+OO O.OE+OO Xe-135 1.8E+05 1.2E+03 l.59E+05 1.8E+08 O.OOE+00O 0.0E+00O Xe-135m 1.6E+05 1.0E+03 2.72E+05 2.7E+08 O.OOE+OO O.OE+00 Xe-I137 7.4E+05 4.7E+03 O.OOE+OO O.OE+OO O.OOE+OO O.OE+00 Xe-i138 6.9E+05 4.3E+03 7.69E+05 3.3E+'09 O.OOE+OO O.QE+OO 1-131 1.6E+03 1.0E+01 2.42E+05 2.4E+06 3.29E+01 4.1E+0-8 1-132 2.3E+03 1.5E+01 1.49E+06 2.2E+07 3.81E-01 7.0E+-06 1-133 3.4E+03 2.1E+01 3.92E+05 8.3E+06 5.85E+00 1.6E+08 1-134 3.6E+03 2.3E+01 1.73E+06 3.9E+07 1.31E-01 3.7E+06 1-135 3.2E+03 2.0E+01 1.06E+06 2.1E+07 1.23E+00 3.1E+'07 Total = 7.4E+09 mREM Total = 6.1E+08 mREM TEDE = EDE + CEDE EDE = 7.4E+09 mREM CEDE = 6.1E+08 mREM TEDE = 8.0E+09 mREM SM-SNC524602-001 ATCMN 3 HE 3-ATTACHMENT E3B SHEET E3B-5 100 & 1000 mREM TEDE Thresholds Xioo = 100 mREM TEDE Noble Gas concetration Xio0 = [(100 mREM)/(TEDE mREM)] x XRLS Xlooo =Xiooo =TEDE =I1.3E-08 1000 mREM 10 x ioo 8.0E+09 mREM X XRLS TEDE Noble Gas concetration Isotope XRLS Xioo Xiooo (piCilcc) (litCi/cc) (lpCilcc)Kr-83m 5.1 E+04 6.4E-04 6.4E-03 Kr-85 3.8E+03 4.8E-05 4.8E-04'Kr-85m 1.1E+05 1.4E-03 1.4E-02'Kr-87 2.1E+05 2.7E-03 2.7E-02 Kr-88 3.0E+05 3.8E-03 3.8E-02 Kr-89 3.6E+05 4.6E-03 4.6E-02 Xe-131 m 4.4 E+03 5.6E-05 5.6 E-04 Xe-133 7.9E+05 1.0E-02 1.0E-01 Xe-I133m 2.5E+04 3.2E-04 3.2E-03 Xe-135 1.8E+05 2.3E-03 2.3E-02 IXe-135m 1.6E+05 2.0E-03 2.0OE-02 Xe-I137 7.4E+05 9.3E-03 9.3E-02 Xe-I138 6.9E+05 8.6E-03 8.6E-02 Totals 4.6E-02 4.6E-01 J.LCiIcC pCi/cc SM-SNC524602-001 ATCMN 3 HE 3-ATTACHMENT E3B SHEET E3B-6 Thyroid CDE Calculations CDETHY = Thyroid Committed Dose Equivalent (mREM) from inhalation CDETHY = DCFFGR-11 X XEAB X BR x texp DCFFGR-11

=FGR-11I dose conversion factor (mREM/p#Ci/cc) texp -1 .00 hour0 days <br />0 hours <br />0 weeks <br />0 months <br /> BR = I1.25E+06 cc/hr Xsoom = 500 mREM Thyroid CDE Noble Gas concentration (p#Ci/cc)X500T = [(500 mREM CDE)/(CDETHY mREM)] x XRLS X500T = 500/ 1 .9E+1 0 X XRLS -2.6E-08 X XRLS X5000T = 5000 mREM Thyroid CDE Noble Gas concentration

(#iCi/cc)X5000T = 10 X XSOOT Postulated Release Thyroid CDE Thresholds Isotope XEAB FGR-11I CDETHY XRLS X500T X5000T (p.Ci/cc)

DCF (mREM) (lpCi/cc) (mREM/lpCi)Kr-83m 3.2E+02 0.00E+00 0.0E+00 5.1E+04 1.3E-03 1.3E-02 Kr-85 2.4E+01 0.00E+00 0.0E+00 3.8E+03 9.9E-05 9.9E-04 Kr-85m 7.0E+'02 0.00E+00 0.0E+00 1.1 E+05 2.9E-03 2.9E-02 Kr-87 1.3E+03 0.00E+00 0.0E+00 2.1IE+05 5.5E-03 5.5E-02 Kr-88 1.9E+03 0.00E+00 0.0E+00 3.0E+05 7.9E-03 7.9E-02 Kr-89 2.3E+03 0.00E+00 0.0E+00 3.6E+05 9.5E-03 9.5E-02 Xe-131 m 2.8E+01 0.00E+00 0.0E+00 4.4E+03 1.2E-04 1.2E-03 Xe-133 5.0E+03 0.00E+00 0.0E+00 7.9E+05 2.1E-02 2.1E-01 Xe-i133m 1 .6E+02 0.00E+00 0.0OE+00 2.5E+04 6.6 E-04 6.6 E-03 Xe-135 1.2E+03 0.00E+00 0.0E+00 1.8 E+05 4.8 E-03 4.8 E-02 Xe-135m 1.0E+03 0.00E+00 0.0E+00 1.6E+05 4.1E-03 4.1 E-02 Xe-137 4.7E+03 0.00E+00 0.0E+00 7.4E+05 1.9E-02 1.9E-01 Xe-138 4.3E+03 0.00E+00 0.0E+00 6.9E+05 1.8 E-02 1.8E-01 1-131 1.0E+01 1.08E+03 1.3E+10 I-132 1.5E+01 6.44E+00 1.2E+08 I-133 2.1E+01 1.80E+02 4.8 E+09 I-134 2.3E+01 1.07E+00 3.0E+07-352.0E+01 3.13E+01 7.8E+08 Total CDETHY =1.9E+10 mREM Totals 9 .5E-02 lpCi/cc 9.5E-01 lpCi/cc SM-SNC524602-001 SM-SNC52602-001ATTACHMENT E4ASHEEA-SHEET E4A-1 TDAFWP Exhaust Release Path TEDE & Thyroid CDE Calculations (No Core Damage)Postulated Release Activity XRLS -- Release Concentration XRLS = [Partition Factor x Xrcs i/g)] x [pris (glcc)]Partition Factors[Assumption

1. 5]Noble Gases: 1.0 Iodine, liquid leakage to Auxiliary Building:

0.01 Iodine, primary coolant leakage to Containment building:

0.01 Iodine, primary coolant leakage to steam generator:

0.01 Iodine, SJAEs: 1 .0E-04 Xrcs = RCS coolant activity (p.Ci/cc)Xrcs = RCS Equilibrium Activity (pCi/g) +[Release Fraction x Core Inventory (Ci) x (1 .0E+06p.Ci/1 Ci)]/MRcs (g)RCS Equilibrium Activity:

Design Input #14 Core Inventory:

Design Input #14 Release Fractions

[Assumption

1. 6]1.0 for Noble Gases (RG 1.183 Table 2, LOCA)0.4 for Iodine (RG 1.183 Table 2, LOCA)0 for no core damage MRCS = RCS coolant mass (Ibm)MRcs = 417,219 Ibm x (453.59 g/l Ibm) [Design Input #11]MRCS = 1 .89E+08 g prls = Density of release fluid (g/cc)prls = 1 .00E+00 g/cc [Arbitrary Value]

SM-SNC524602-001 SM-SNC52602-001ATTACHMENT E4ASHEE4-SHEET E4A-2 Isotope Core Core Xeq Xrcs i/g) Partition XRLS Inventory Release (lpCi/g) Factor (Ci) Fraction Kr-83rm 9,70E+06 0.00 4.50E-01 4,5E-01 1.00 4,5E-01 Kr-85 7.20E+05 0.00 7.70E+00 7.7E+00 1.00 7.7E+00 Kr-85m 2,10E+07 0.00 1.80E+00 1.8E+00 1.00 1.8 E+00 Kr-87 4.00E+07 0.00 1 .20E+00 1,.2E+00 1.00 1,.2E+00 Kr-88 5.70E+07 0.00 3.50E+00 3.5E+00 1.00 3.5E+00 Kr-89 6.90E+07 0.00 1.10E-01 1.1E-01 1.00 1.1E-01 Xe-131m 8.40E+05 0.00 2.90E+00 2.9E+00 1.00 2.9E+00 Xe-133 1.50E+08 0.00 2.40E+02 2.4E+02 1.00 2.4E+02 Xe-133m 4.80E+06 0.00 4.60E+00 4.6E+00 1.00 4.6E+00 Xe-135 3.50E+07 0.00 7.90E+00 7.9E+00 1.00 7.9E+00 Xe-135m 3.00E+07 0.00 4.50E-01 4.5E-01 1.00 4.5E-01 Xe-137 1.40E+08 0.00 2.00E-01 2.0E-01 1.00 2.0E-01 Xe-138 1.30E+08 0.00 7.20E-01 7.2E-01 1.00 7.2E-01 1-131 7.50E+07 0.00 1.40E+00 1.4E+00 0.01 1.4E-02 1-132 1.10E+08 0.00 2.30E+00 2.3E+00 0.01 2.3E-02 1-133 1.60E+08 0.00 2.70E+00 2.7E+00 0.01 2.7E-02 I-134 1.70E+08 0.00 6.30E-01 6.3E-01 0.01 6.3 E-03 1-135 1.50E+08 0.00 1.90E+00 1.9E+00 0.01 1.9E-02 SM-S NC524602-001 ATCMN 4 HE 4-ATTACHMENT E4A SHEET E4A-3 Postulated Release TEDE Calculations TEDE TEDE EDE EDE CEDE CEDE XEAB XEAB Qris QRLS QRLS QRLS texp texp BR BR BR= Total Effective Dose Equivalent (mREM)-EDE + CEDE= Effective Dose Equivalent (mREM) from external exposure= DCFFGR-12 x XEAB X texp DCFFGR-12

= FGR-1 2 dose conversion factor

-Committed Effective Dose Equivalent (mREM) from inhalation

= DCFFGR-11 X XEAB X BR x texp DCFFGR-11

= FGR-11I dose conversion factor (mREM/tCi)

= Radionuclide concentration at Exclusion Area Boundary (PCi/cc)= [QRLS (m^3/sec)]

x [X/Q (sec/m^3)]

x [XRLS (#iCi/cc)]

= Release flow rate (mA3/sec)= 26,106 Ibm/hr x SVstm (cu ft/Ibm) x [1 hr/GO min] [Design Input #221 SVstm = Specific Volume of Saturated Steam @ Patm SVstm = 26.804 cu ft/Ibm [Assumption

1. 8]= 1.1 7E+04 CFM x [1 min/GO sec] x [0.0283 mA3/ftA3]= 5.5 mA3/sec= Atmospheric dilution factor (sec/m^3)= 4.87E-05 sec/m3 [Assumption

1. 3]= Exposure time=1.0 hour0 days <br />0 hours <br />0 weeks <br />0 months <br /> [Assumption

1. 1]-Breathing Rate (mA3/sec)= 3.47 E-04 m^3/sec [Assumption

1. 2]= 1 .25E+06 cc/hr = mA3/sec x [(1 .0E6 cc)/(1 mA3)] x [3600 sec/i hr]

SM-SNC524602-001 SM-SNC52602-OO1ATTACHMENT E4ASHE 4-SHEET E4A-4 Isotope Release XEAB FGR-12 EDE FGR-11 CEDE Activity DCF (mREM) DCF (mREM)(JlCilcc) (m REM/hr)I (m REM/

IpCi)Kr-83m 4.5E-01 I1.2E-04 2.00E+01 2.4E-03 O.OOE+OO O.OE+OO Kr-85 7.7E+00 2.1E-03 1.59E+03 3.3E+00 O.OOE+OO O.0E+00O Kr-85m I1.8E+00O 4.8E-04 9.96E+04; 4.8E+01 O.OOE+00 O.OE+OO Kr-87 I1.2E+00 3.2E-04 5.49E+05 1 .8E+02 O.OOE+OO O.0E+OO Kr-88 3.5E+00 9.4E-04 I1.36E+06 I1.3E+03 0.00E+00O O.OE+OO Kr-89 1.1E-01 2.9E-05 O.OOE+OO O.OE+OO O.OOE+OO 0.0E+OO Xe-131m 2.9E+00 7.8E-04 5.18E+03 4.0E+00 O.OOE+00 O.OE+OO Xe-133 2.4E+i02 6.4E-02 2.08E+04 1.3E+03 0.00E+00 O.0E+O0 Xe-133m 4.6E+00 1.2E-03 1.82E+04 2.3E+01 0.00E+O0 0.0E+00 Xe-135 7.9E+00 2.1E-03 I.59E+05 3.4E+02 0.00E+00 0.0E+00 Xe-135m 4.5E-01 1.2E-04 2.72E+05 3.3E+01 O.OOE+OO 0.0E+O0 Xe-I137 2.0E-01 5.4E-05 O.00E+O0 O.0E+OO O.OOE+OO 0.0E+00 Xe-138 7.2E-O1 1.9E-04 7.69E+05 1.5E+02 O.OOE+OO O.OE+OO I-131 1.4 E-02 3.8 E-06 2.42 E+05 9.1IE-01 3.29E+01I I.5E+02 1-132 2.3E-02 6.2E-06 1.49E+06 9.2E+00 3.81E-01 2.9E+00 1-133 2.7E-02 7.2E-06 3.92E+05 2.8E+00 5.85E+00 5.3E+01 1-134 6.3E-03 I.7E-06 1.73E+06 2.9E+00 1.31E-01 2.8E-01 1-135 1.9E-02 5.1E-06 1.06E+06 5.4E+00 1.23E+00 7.8E+00 Total = 3.4E+03 mREM Total = 2.2E+02 mREM TEDE = EDE + CEDE EDE =CEDE =TEDE = 3.6E+03 3.4E+03 mREM 2.2E+02 mREM mREM SM-SNC524602-00 1 ATCMN 4 HE4-ATTACHMENT E4A SHEET E4A-5 100 & 1000 mREM TEDE Thresholds Xioo =100 mREM TEDE Noble Gas concetration

(#iCi/cc)Xioo = [(100 mREM)/(TEDE mREM)] x XRLS TEDE = 3.6E+03 mREM Xlioo -Xiooo =Xlooo -2.8E-02 1000 mREM 10 xXioo X XRLS TEDE Noble Gas concetration (aC i/cc)Isotope XRLS Xlo0 Xto00 (p.C i/cc) (lpCi/cc) Kr-83m 4.5E-01 1.2E-02 1.2E-01 Kr-85 7.7E+00 2.1 E-01 2.1 E+00 Kr-85m 1.8E+00 5.OE-02 5.0E-01 Kr-87 I1.2E+00 3.3 E-02 3.3E-01 Kr-88 3.5E+00 9.7E-02 9.7E-01 Kr-89 1.1 E-01 3.0E-03 3.OE-02 Xe-131m 2.9E+00 8.0E-02 8.0E-01 Xe-I133 2.4E+02 6.6E+00 6.6E+01 Xe-133rn 4.6E+00 1.3E-01 1.3E+00 Xe-I135 7.9E+00 2.2E-01 2.2E+00 Xe-135m 4.5E-01 1.2E-02 1.2E-01 Xe-I137 2.0E-01 5.5E-03 5.5E-02 Xe-138 7.2E-01 2.0E-02 2.OE-01 Totals 7.5E+00 7.5E+01 pCi/cc pCi/cc SM-S NC524602-001IATCMN 4 HE 4-ATTACHMENT E4A SHEET E4A-6 Thyroid CDE Calculations CDETHY = Thyroid Committed Dose Equivalent (mREM) from inhalation CDETHY = DCFFGR-11 X XEAB X BR x texp DCFFGR-11

= FGR-11I dose conversion factor (mREM/tCi/cc); "Thyroid" texp = 1.00 hour0 days <br />0 hours <br />0 weeks <br />0 months <br /> BR = 1 .25E+06 cc/hr X5oom = 500 mREM Thyroid CDE Noble Gas concentration

(#tCi/cc)XS00T = [(500 mREM CDE)/(CDETHY mREM)] x XRLS X500T = 500/ 6.9E+03 x XRLS -- 7.2E-02 x XRLS X5000T = 5000 mREM Thyroid CDE Noble Gas concentration (pCi/cc)X5000T = 1 0 X X500T Y Postulated Release Thyroid CDE Thresholds Isotope XEAB FGR-11I CDETHY XRLS X500T X5000T DCF (mREM) (mREM/piCi)Kr-83m 1.2E-04 0.00E+00 0.0E+00 4.5E-01 3.2E-02 3.2E-01 Kr-85 2.1E-03 0.00OE+00 0.0E+00 7.7E+00 5.5E-01 5.5E+00 Kr-85m 4.8 E-04 0.00E+00 0.0E+00 1 .8E+00 1 .3E-01 1 .3E+00 Kr-87 3.2E-04 0.00E+00 0.0E+00 1.2E+00 8.6E-02 8.6E-01 Kr-88 9.4E-04 0.00E+00 0.0E+00 3.5E+00 2.5E-01 2.5E+00 Kr-89 2.9 E-05 0.00E+00 0.0E+00 1.1IE-01 7.9E-03 7.9 E-02 Xe-131 m 7.8 E-04 0.00E+00 0.0E+00 2.9E+00 2.IE-01 2.1E+00 Xe-133 6.4E-02 0.00E+00 0.0E+00 2.4E+02 1.7E+01 1.7E+02 Xe-133m 1.2 E-03 0.0OE+00 0.0E+00 4.6E+00 3.3E-01 3.3E+00 Xe-135 2.1 E-03 0.O0E+00 0.0E+00 7.9E+00 5.7E-01 5.7E+00 Xe-135m 1.2E-04 0.00E+00 0.0E+00 4.5E-01 3.2E-02 3.2E-01 Xe-137 5.4E-05 0.00E+00 0.0E+00 2.0E-01 1.4E-02 1.4E-01 Xe-138 1.9E-04 0.00E+00 0.0E+00 7.2E-01 5.2 E-02 5.2E-01 1-131 3.8E-06 1.08E+03 5.1E+03 I-132 6.2E-06 6.44E+00 5.0E+01 I-133 7.2 E-06 1 .80E+02 1 .6E+03 I-134 1.7E-06 1.07E+00 2.2E+00 1-135 5.1E-06 3.13E+01 2.0E+02 Total CDETHY " 6.9E+03 mREM Totals 2.0E+01 2 .0E+02 iC i/cc a SM-SNC524602-001 ATCMN 4 HE 4-ATTACHMENT E4B SHEET E4B-1 TDAFWP Exhaust Release Path TEDE & Thyroid CDE Calculations (Core Damage)Postulated Release Activity XRLS --- Release Concentration (jiCi/cc)XRLS = [Partition Factor x Xrcs (pCi/g)] x [pris (glcc)]Partition Factors[Assumption

1. 5]Noble Gases: 1.0 Iodine, liquid leakage to Auxiliary Building:

0.01 Iodine, primary coolant leakage to Containment building:

0.01 Iodine, primary coolant leakage to steam generator:

0.01 Iodine, SJAEs: 1 .0E-04 Xrcs = RCS coolant activity Xrcs = RCS Equilibrium Activity (jiCi/g) +[Release Fraction x Core Inventory (Ci) x (1 .0E+06gCi/1 Ci)]/MRcs (g)RCS Equilibrium Activity:

Design Input #14 Core Inventory:

Design Input #14 Release Fractions

[Assumption

1. 6]1.0 for Noble Gases (RG 1.183 Table 2, LOCA)0.4 for Iodine (RG 1.183 Table 2, LOCA)0 for no core damage MRCS = RCS coolant mass (Ibm)MRcs " .417,219 Ibm x (453.59 g/l Ibm) [Design Input #11]MRCS =1.89E+I08 g pris " Density of release fluid (g/cc)pris = 1 .00E+00 g/cc [Arbitrary Value]

SM-SNC524602-001IATCMN 4 HE 4-ATTACHMENT E4B SHEET E4B-2 Isotope Core Core Xeq Xrcs (l4Cilg) Partition XRLS Inventory Release (jliCilg)

Factor (JlCi/cc)(Ci) Fraction Kr-83m 9.70E+06 1.00 4.50E-01 5.1E+04 1.00 5.1E+04 Kr-85 7.20E+05 1.00 7.70E+00 3.8 E+03 1.00 3,8 E+03 Kr-85m 2.10E+07 1.00 1.80E+00 1.1E+05 1.00 1.1E+05 Kr-87 4.00E+07 1.00 1.20E+00 2.1E+05 1.00 2.1E+05 Kr-88 5.70E+07 1.00 3.50E+00 3.0E+05 1.00 3.0E+05 Kr-89 6.90 E+07 1.00 1.10E-01 3.6 E+05 1.00 3.6 E+05 Xe-131 m 8.40 E+05 1.00 2.90E+00 4.4 E+03 1.00 4.4 E+03 Xe-133 1.50E+08 1.00 2.40E+02 7.9E+05 1.00 7.9E+05 Xe-133m 4.80E+06 1.00 4.60E+00 2.5E+04 1.00 2.5E+04 Xe-135 3.50E+07 1.00 7.90E+00 1.8E+05 1.00 1.8E+05 Xe-135m 3.00E+07 1.00 4.50E-01 1.6E+05 1.00 1.6E+05 Xe-137 1.40E+08 1.00 2.00E-01 7.4E+05 1.00 7.4E+05 Xe-138 1.30E+08 1.00 7.20E-01 6.9E+05 1.00 6.9E+05 1-131 7.50E+07 0.40 1.40E+00 1.6E+05 0.01 1.6E+03 I-132 1.10E+08 0.40 2.30E+00 2.3 E+05 0.01 2.3E+03 1-133 1.60E+08 0.40 2.70E+00 3.4E+05 0.01 3.4E+03 I-134 1.70E+08 0.40 6.30E-01 3.6E+05 0.01 3.6E+03 1-135 1.50E+08 0.40 1.90E+00 3.2E+05 0.01 3.2E+03 SM-SNC524602-001 SM-5N52460-0O IATTACHMENT E4BSHEEB3 SHEET E4B-3 Postulated Release TEDE Calculations TEDE = Total Effective Dose Equivalent (mREM)TEDE = EDE + CEDE EDE = Effective Dose Equivalent (mREM) from external exposure EDE = DCFFGR-12 x XEAB X texp DCFFGR-12

= FGR-12 dose conversion factor [(mREMIhr)/(jiCi/cc)]

CEDE = Committed Effective Dose Equivalent (mREM) from inhalation CEDE = DCFFGR-11 x XEAB X BR x texp DCFFGR-11

= FGR-11I dose conversion factor (mREM/p#Ci)

XEAB = Radionuclide concentration at Exclusion Area Boundary (jiCi/cc)XEAB = [QRLS (m^3/sec)]

x [X/Q (sec/mA3)]

x [XRLS (j, Ci/cc)]Qris = Release flow rate (m^3/sec)QRLS = 26,106 Ibm/hr x SVstm (cu ft/Ibm) x [1 hr/60 min] [Design Input #22]SVstrn = Specific Volume of Saturated Steam @ Patrn SVstm = 26.804 cu ft/Ibm [Assumption

1. 8]QRLS = 1.1 7E+04 CFM x [1 min/60 sec] x [0.0283 m^3/ft^3]QRLS = 5.5 m^3/sec X/Q = Atmospheric dilution factor (sec/m^3)X/Q = 4.87E-05 sec/m3 [Assumption

1. 3]texp = Exposure time texp =1.0 hour0 days <br />0 hours <br />0 weeks <br />0 months <br /> [Assumption

1. 1]BR = Breathing Rate (mA3/sec)BR = 3.47E-04 mA3/sec [Assumption

1. 2]BR =. 1.25E+06 cc/hr = m^3/sec x [(1 .0E6 cc)/(1 m^3)] x [3600 sec/ilhr]

SM-SNC524602-001 SM-SNC52602-OO1ATTACHMENT E4BSHEE44 SHEET E4B-4 Isotope Release XEAB FGR-12 EDE FGR-11 CEDE Activity (J.Ci/cc)

DCF (mREM) DCF (mREM)(jxCilcc) (mREM/hr)/ (mREMI (p.Cilcc)

IpCi)Kr-83m 5.1 E+04 1.4E+01 2.00E+01 2.7E+02 O.OOE+O0 O.OE+O0 Kr-85 3.8E+03 I1.0E+00 1 .59E+03 1 .6E+03 0.OOE+OO O.OE+OO Kr-85m 1.1 E+05 3.0E+01 9.96E+04 3.0E+06 0.00E+00O O.OE+OO Kr-87 2.1E+05 5.7E+01 5.49E+05 3.1E+i07 O.OOE+00 O.0E+00 Kr-88 3.0E+05 8.1E+01 1.36E+06 1.1E+08 O.OOE+00 0.0E+00 Kr-89 3.6E+05 9.8E+01 0.00E+O0 O.OE+00 O.OOE+00 0.0E+OO Xe-131m 4.4E+03 1.2E+00 5.18E+03 6.2E+03 O.OOE+00 0.0E+00 Xe-133 7.9E+05 2.1E+02 2.08E+04 4.4E+06 O.OOE+OO O.OE+OO Xe-133m 2.5E+04 6.8E+00 1.82E+04 1.2E+05 0.00E+00O O.OE+OO Xe-135 1.8E+05 5.0E+01 1.59E+05 7.9E+06 O.OOE+OO O.OE+OO Xe-135m 1.6E+05 4.2E+01 2.72E+05 1.2E+07 O.OOE+OO O.OE+OO Xe-I137 7.4E+05 2.0E+02 0.OOE+OO O.0E+O0 O.OOE+OQ 0.OE+00 Xe-138 6.9E+05 I.8E+02. 7.69E+05 1.4E+08 O.OOE+OO O.OE+00 1-131 1.6E+03 4.2E-01 2.42E+05 1.0E+05 3.29E+01 1.7E+07 1-132 2.3E+03 6.2E-01 1.49E+06 9.3E+05 3.81E-01 3.0E+05 1-133 3.4E+03 9.1E-01 3.92E+05 3.5E+05 5.85E+00 6.6E+06 1-134 3.6E+03 9.6E-01 I.73E+06 1.7E+06 I.31E-01 1.6E+05 1-135 3.2E+03 8.5E-01 1.06E+06 9.0E+05 1.23E+00 1.3E+06 Total = 3.1 E+08 mREM Total = 2.6E+07 mREM h TEDE = EDE + CEDE EDE = 3.1E+08 mREM CEDE = 2.6E+07 mREM TEDE = 3.4E+08 rnREM SM-SNC524602-001 SM-SN52460-00 IATTACHMENT E4BSHEE4-SHEET E4B-5 100 & 1000 mREM TEDE Thresholds Xioo = 100 mREM TEDE Noble Gas concetration (jiCi/cc)Xioo = [(100 mREM)/(TEDE mREM)] x XRLS Xloo =Xlooo =TEDE = 3.4E+08 mREM 2.9E-07 x XRLS 1000 mREM TEDE Noble Gas concetration

(#C i/cc)10 x ioo Isotope XRLS Xl00 Xl000i/cc) (jiC i/cc) (!pCi/cc)Kr-83m 5.IE+04 1.5E-02 1.5E-0l Kr-85 3.8E+03 I.1IE-03 I.IE-02 Kr-85m 1.1IE+05 3.3E-02 3.3E-01 Kr-87 2.1E+05 6.2E-02 6.2E-01 Kr-88 3.0E+05 8.9E-02 8.9E-01 Kr-89 3.6E+05 1.1 E-01 1.1 E+00 Xe-131m 4.4E+03 1.3E-03 I.3E-02 Xe-I133 7.9E+05 2.3E-01 2.3E+00 Xe-I133m 2.5E+04 7.5E-03 7.5E-02 Xe-135 I.8 E+05 5.5 E-02 5.5E-01 Xe-135m I.6E+05 4.7E-02 4.7E-01 Xe-I137 7.4E+05 2.2E-01 2.2E+00 Xe-I138 6.9E+05 2.0E-01 2.0E+00 Totals 1.1 E+00 1.1 E+01 p~CiIcc i~Ci/cc SM-SNC524602-001 ATCMN 4 HE 4-ATTACHMENT E4B SHEET E4B-6 Thyroid CDE Calculations CDETHY = Thyroid Committed Dose Equivalent (mREM) from inhalation CDETHY -DCFFGR-11 X XEAB X BR x texp DCFFGR-11

= FGR-11I dose conversion factor "Thyroid" texp = 1.00 hour0 days <br />0 hours <br />0 weeks <br />0 months <br /> BR = 1 .25E+06 cc/hr XS00T = 500 mREM Thyroid CDE Noble Gas concentration (pCi/cc)X500T = [(500 mREM CDE)/(CDETHY mREM)] x XRLS XS00T -- 500/ 8.2E+08 x XRLS =X500T =" 5000 mREM Thyroid CDE Noble Gas X5000T = 10 X X500m 6.1E-07 XXRLS concentration V Postulated Release Thyroid CDE Thresholds Isotope XEAB FGR-11I CDETHY XRLS X500T X5000T DCF (mREM) (jltCi/cc)(mREMI jtC i)Kr-83m 1.4E+01 0.00E+00 0.0E+00 5.1E+04 3.1E-02 3.1E-01 Kr-85 I1.0E+00 0.00E+00 0.0E+00 3.8E+03 2.3E-03 2.3E-02 Kr-85m 3.0E+01 0.00E+-00 0.0E+00 1.1IE+05 6.8 E-02 6.8E-01 Kr-87 5.7E+01 0.00E+00 0.0E+00 2.1E+05 1.3E-01 1.3E+00 Kr-88 8.IE+01 0.00E+00 0.0E+00 3.0E+05 1.8E-01 1.8E+00 Kr-89 9.8E+01 0.00E+00 0.0E+00 3.6E+05 2,2E-01 2.2E+00 Xe-131 m 1.2 E+00 0.00E+00 0.0OE+00 4.4E+03 2.7E-03 2.7 E-02 Xe-133 2.1E+02 0.00E+00 0.0E+00 7.9 E+05 4.9 E-01 4.9E+00 Xe-I133m 6.8E+00 0.00E+00 0.0E+00 2.5E+04 1 .6E-02 1 .6E-01 Xe-135 5.0E+01 0.00E+00 0.0E+00 1.8E+05 I.IE-01 1.1E+00 Xe-135m 4.2E+01 0.00E+-00 0.0E+00 1.6E÷05 9.7E-02 9.7E-01 Xe-1 37 2.OE+02 0.00E+00 0.0E+00 7.4E+05 4.5E-01 4.5E+00 Xe-I138 1 .8E+02 0.O0E+00 0.0E+00 6.9E+05 4.2 E-01 4.2E+00 1-131 4.2E-01 1.08E+03 5.7E+08 I-132 6.2E-01 6.44E+00 5.0E+06 I-133 9.1E-01 1.80E+02 2.0E+08 I-134 9.6E-01 1.07E+00 1.3E+06 1-135 8.5E-01 3.13E+01 3.3E+07 Total CDETHY =8.2E+08 mREM Totals 2.2E+00 2.2E+01 1 iCi/cc&

Southern Nuclear Design Calculation IPlant: Farley Unit: 1&2 ICalculation Number: SM-SNC524602-001 Sheet: F-I Attachment F -Shielding Calculations DescrptionNumber Descrptionof Pages F1 -Water Shielding Properties 5 F2 -Modification of VEGP SFP Dose Rate vs. Depth Analysis for Farley 18 F3 -Operating Deck Dose Rates for Reduced RPV Water Level 3 F4 -Seal Table Room Dose Rate Evaluation 2 4 4 4 4 4 4 4 4 Total Number of Pages including Cover Sheeti 29 Southern Nuclear Design Calculation SPlant: Farley Unit: 1&2 Calculation Number: SM-SNC524602-001 Sheet: Fl-1I Attachment F1 -Water Shielding Parameters Several shielding evaluations are performed in support of this calculation, using existing analyses.

The associated shielding parameters are available in tables in nuclear engineering reference books as functions of gamma energy. The energies in the tables do not align with the energies of the spent fuel gamma source terms used in Vogtle calc X6CDE.01 or Farley calc SM-SNC467144-001.

Linear interpolation of the tabulated values is a time consuming option. However, these parameters are non-linear functions of gamma energy, so additional error is introduced by linear interpolation.

Curvilinear regression can be performed on these parameters using the Data Analysis Regression tool in Microsoft Excel. The following on-line references provide guidance for using this tool:* Cameron, "EXCEL 2007: Multiple Regression," Department of Economics, University of California

-Davis, 2009 (http ://ca mero n .eco n. u cd avis.ed u/excel/ex6l multiplerepqression .html)*"A Quick Guide to Using Excel 2007's Regression Analysis Tool," Fuqua School of Business, Duke University, 2009 (https://facu lty~fupua.d uke~ed u/~pecklu nd/ExcelReView/Use%20Excel%202007%20Rep res sion.pdf)The regression is judged as adequate based on the following.

• The Multiple Correlation Coefficient, R 2 or R Square, is a measure of amount of reduction in variability in the dependent variable.

It varies from zero to one. A R Square approaches one, the regression fit improves.*The relative error of the regression is calculated as the difference between the regression value and the tabulated value divided by the tabulated value at each value of the dependent variable (gamma energy in this case). As the relative error approaches zero, the accuracy of the regression improves.Curvilinear regressions on several water shielding parameters are documented in the Excel spreadsheet comprising the remainder of this attachment.

SM-SNC524602-001 Attachment Fl -Water Shielding Parameters Taylor Exposure Buildup Factor Coefficient (a2 for Water Curvilinear regression performed using Excel Data Analysis ToolPak ( =Ko + [Ki x El + [Ki x (E^2)] + [K3 x (E^3)] + [K4IE] + [K5/(E^2)]

+ [KeI(E^3)]

Sheet Fl-I S aCr2-tab af2-reg Error MeV ____(%)0.3 -0.0871 -0.0871 0.006%0.4 -0.0605 -0.0605 -0.043%0.6 -0.0386 -0.0387 0.183%1.0 -0.0182 -0.0180 -0.880%1.5 -0.0036 -0.0038 6.796%2.0 0.0041 0.0043 4.137%3.0 0.0151 0.0151 -0.286%4.0 0.0366 0.0366 0.021%

Reference:

Table 5.2, ANSI/ANS-6.4.3-1 991 Ey,= 4.0 MeV0.0366 Ko = -5.94E-02 Ki = 7.01 E-02 K2 = -2.51E-02 K3 = 3.42 E-03 K4 = -7.87E-03 K5 = 1 .87E-03 1K6= -1.11E-03 Regression Statistics Multiple R 1.0000 R Square 1.0000 Standard Error 0.0003 Observations 8 Water Taylor Exposure Buildup Factor Coefficient (a2 0.0 U ,,. 0.004 .... .... ....*" -0.o5 ----- ----- -....... ..0.0i oo I-0.15 ....m ...E....r..

y (M .....e. ..* Tabulated Regression SM-SNC524602-001 Attachment F1 -Water Shielding Parameters Water Mass Attenuation Coefficient Curvilinear regression performed using Excel Data Analysis ToolPak pidp = Ko + [Ki x E] + [K2 x (E^2)] + [K3 x (E^3)] + [K4/E] + [K5/(E^2)]

+ [Ke/(E^3)](cmA2/g)Sheet F1-2 E7pip Error MeV Table Rgrssn 0.1 0.1670 0.1670 0.01%0.2 0.1360 0.1356 -0.26%0.3 0.1180 0.1188 0.70%0.4 0.1060 0.1061 0.08%0.5 0.0966 0.0965 -0.12%0.6 0.0896 0.0890 -0.64%0.8 0.0786 0.0782 -0.57%1.0 0.0706 0.0705 -0.20%1.5 0.0575 0.0579 0.73%2.0 0.0493 0.0499 1.26%3.0 0.0396 0.0398 0.41%4.0 0.0339 0.0336 -0.88%5.0 0.0301 0.0297 -1.25%6.0 0.0275 0.0273 -0.75%8.0 0.0240 0.0246 2.36%10.0 0.0219 0.0217 -0.87%E7 10.0 MeV UP = 0.0217 cm^2/g Ko =Ki =K2=K3 =K4 =K5 =Ke =5.26E-02-1 .13E-02 1.41 E-03-6.21 E-05 3.14E-02-3.75E-03 1 .77E-04 Regression Statistics Multiple R 1.0000 R Square 0.9999 Standard Error 0.0005 Observations 16

Reference:

Table 11.4, pager68 aMarshs A Introduction toefNuclearvs Engnerigy Water Mass Attenuation Coefficient vs. Energy...0.20 E So.15 0.0~0.00 U)I'4 4=4 -Table3 5 6Rersso 7 8 9 10* Table --Regressioo SM-SNC524602-001 Attachment F1 -Water Shielding Parameters Taylor Exposure Buildup Factor Coefficient Ai for Water Curvilinear regression performed using Excel Data Analysis ToolPak Ai = Ko + [Ki x E] + [K2 x (E^2)] + [K3 x (E^3)] + [K4/E] + [K5/(E^2)]

+ [KO/(E^3)]

Sheet F1-3Al-tab Al-reg Error MeV ___ ____ (%)0.3 226.726 226.731 0.002%0.4 103.797 103.771 -0.025%0.6 72.516 72.586 0.097%1.0 54.278 54.119 -0.293%1.5 39.009 39.252 0.622%2.0 32.003 31 .835 -0.526%3.0 22.738 22.781 0.188%4.0 11.703 11.695 -0.064%

Reference:

Table 5.2, ANSI/ANS-6.4.3-1991 Ey, =A1i=K0 =Ki =I2=K3 =K4 =K5 =K6=4.0 11.695-2.73E+02 1 .22E+02-2 .45E+01 1 .64E+00 3.68E+02-1.71 E+02 3.07E+01 MeV Regression Statistics Multiple R 1.0000 R Square 1.0000 Standard Error 0.3465 Observations 8 250'~200 IL.0.o 150lo 00 uJ 1,,.,. s Water Taylor Exposure Buildup Factor Coefficient Ai 0 0.0 0.5 1.0 1.5 2.0 2.5 3.0 3. 40 45 Gamma Energy (MeV)3.5 4.0 4.5* Tabulated

---

Regression SM-SNC524602-001 Attachment F1 -Water Shielding Parameters Taylor Exposure Buildup Factor Coefficient (ai for Water Curvilinear regression performed using Excel Data Analysis ToolPak cti = Ko + [Ki x E] + [K2 x (E^2)] + [K3 x (E^3)l + [K4/E] + [K5/(EA2)]

+ [Ke/(E^3)]

Sheet F1-4 E a Ol-tab (al-reg Error MeV ___ ____ (%)0.3 -0.1084 -0.1084 -0.002%0.4 -0.0975 -0.0975 0.009%0.6 -0.0763 -0.0763 -0.032%1.0 -0.0506 -0.0507 0.109%1.5 -0.0357 -0.0356 -0.235%2.0 -0.0274 -0.0275 0.213%3.0 -0.0194 -0.0194 -0.076%4.0 -0.0226 -0.0226 0.01 2%

Reference:

Table 5.2, ANSI/ANS-6.4.3-1 991 E7= 1.5 MeV ( = -0.0356 Ko = 6.52E-02 Ki = -4.58E-02 K2 = 1 .53E-02 K3 = -1 .95E-03 K4 = -1.04E-01 K5 = 2.26E-02 K =I -1.75E-03 Regression Statistics Multiple R 1.0000 R Square 1.0000 Standard Error 0.0001 Observations 8 Water Taylor Exposure Buildup Factor Coefficient a1 0.00 ___ ___ ___o. -oo-4.a 0 0. -0.05 0 ..I. .......Ga4a Eery (eV* Tabulated -Regression Southern Nuclear Design Calculation SPlant: Farley Unit: 1&2 Calculation Number: SM-SNC524602-001 ISheet: F2-1 Attachment F2 -Modification of VEGP SFP Dose Rate vs. Depth Analysis for Farley Introduction Appendix 0 of VEGP calculation X6CDE.01 determined dose rate vs. SFP water depth over a full core (193 fuel assemblies) discharged at 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> after shutdown.

The core was modeled as an equivalent disc source with a water shield.These results may be used to estimate water surface dose rate vs. water depth above fuel in the Farley reactor vessel at 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> after shutdown subject to the following modifications.

Source Strenaqth To account for the greater spacing between fuel assemblies in the SFP racks, the VEGP volumetric source terms (MeV/cc-sec) were multiplied by 0.72 (sheet 04). The water surface dose rate is proportional to the water surface gamma flux, which in turn is proportional to source strength.

Multiplying the dose rates in X6CDE.01 by 1.39 (~1/0.72) will normalize them back to the source strength above an irradiated core in the reactor vessel.Source Radius The VEGP discharged core was modeled as a disc source (SA y/cm 2-sec) of radius R feet overlaid with a slab water shield of thickness d feet similar to the disc source described on pages 487-488 of _--l"Introduction to Nuclear Engineering.

" The shield thickness d corresponds to the water iT' r depth above the core and the radius R is one half of P the effective cylinder diameter 13.7 feet on page 04 in X6CDE.01.

Disc Sed source The buildup flux at the water surface is calculated as shown on page 488 of "Introduction to Nuclear Engineering":

• sfc = (SA/2) x {A1*{E1[(1

+

-Ei[(1 + al)*Ji*d*sec 0]) +2*E[1+ cx2)*p.*d]

-Ei[(1 + cL2)*lI*d*sec 0]} (1)where Ai, hA, Qi1, & G(2 = Coefficients for Taylor Buildup Factor; functions of gamma energy (pages 481-482 of "Introduction to Nuclear Engineering")

Southern Nuclear Design Calculation SPlant: Farley Unit: 1&2 Calculation Number: SM-SNC524602-001 ISheet: F2-2 Attachment F2 -Modification of VEGP SFP Dose Rate vs. Depth Analysis for Farley The angle 0 is a function of water depth d and source radius R: tan = R/d 0 = tan-'(R/d)

The effective diameter of the Farley core is 9.975 feet (= 1 foot/i12 inches x 119.7 inches [Table 3-1, U-735579, "Farley Radiation Analysis Design Manual"]).

Thus, for a given water depth the angle 0) will differ between Vogtle and Farley.Per page 483 of "Introduction to Nuclear Engineering," the exponential function Ei(X) can be approximated by Ei(X) = [exp(-X)]*{[1/(X

+ 1)] + [1/(X + 1)3]} for X > 14. For X = 10, the error is 0.11%; the smallest value of X used in this evaluation is ~8; any error due to this approximation is negligible.

Equation (1) is modified and simplified for Farley and Vogtle as follows: 41F/(SAI 2) = A1*[E1 (XFll) -- E1 (XFi2)] + A2*[Ei (XF21) -- E1(XF22)]

(2)XFli = (1 + oal)*,,*d (2a)XFi2 = XF11*sec OF (2b)XF21 = (1 + ax2)*Ji*d (2C)XF22 = XF2i*sec OF (2d)OF = tan-'(RF/d)

(2e)*v/(SA/2) = Ai*[Ei (Xv1i) -E1(Xv12)]

+ A2*[E1 (Xv21) -Ei (Xv22)] (3)Xvii = (1 + ox1)*,t*d (3a)Xv12 = Xvli*sec Ov (3b)Xv21 = (1 +I ct2)*li*d (3c)Xv22 = Xv2i*sec Ov (3d)Ov = tarn-(Rv/d)

(3e)Equation (2) is divided by equation (3) as follows: CF/(SA/2) A1*[E1(XFli)

-E1(XF12)]

+ A2*[E1(XF21)

-E1(XF22)]

(4)4v/(SA/2)

Ai*[E1(Xwli)

-E1(Xwi2)]

+ A2*[E1(Xv2i)

-Ei(Xv22)]CFA1*[E1 (XF11) -- E1 (XFi2)] + A2*[E1 (XF2i) -- E1 (XF22)] (5)4v Ai*[E1 (Xw11) -E1 (Xw12)] + A2*[E1 (Xv21) -E1 (Xv22)]Since dose rates is proportional to gamma flux, DRF A1*[E1(XF¶1)

-E1(XF12)]

+ A2*[E1(XF21)

-Ei(XF22)]

(6)DRv A1*[E1(Xvll)

-- E1(Xvl2)]

+ A2*[E1(Xv21)

-E1(Xv22)]

Southern Nuclear Design Calculation SPlant: Farley Unit: 1&2 Calculation Number: SM-SNC524602-001 lSheet: F2-3 Attachment F2 -Modification of VEGP SFP Dose Rate vs. Depth Analysis for Farley The above dose correction factor is calculated for each energy and depth listed in Attachment D to X6CDE.01 in the Excel spreadsheet that comprises the remainder of this attachment.

The dose rate calculated in Attachment D of X600E.01 for each energy and depth [DRv(E,d)]

is modified to generate a dose rate for Farley at the same energies and depths [DRF(E,d)]

as follows: DRF(E,d) = DRv(E,d) x FNORM X [DRF/DRv]where FNORM = 1/0.72 = 1.39 The results are summarized below E Depth = 8' Depth = 10' Depth = 11.1'(MeV) Vogtle Farley Vogtle Farley Vogtle Farley 0.90 6.3E+02 8.4E+02 1 .0E+01 1 .3E+01 1.1 E+00 1 .4E+00 1.35 3.8E+02 5.0E+02 1.2E+01 1.4E+01 1.7E+00 2.1E+00 1.80 8,6E+03 1.IE+04 4.OE +02 4.9 E+02 7.5E+01 8.9E+01 2.20 9.4E+02 1.2E+03 5.4E+01 6.4E+01 1.1IE+01 1.3E+01 2.60 2,0E+03 2.4E+03 1.4E+02 1.7E+02 3.4E+01 3.8E+01 3.00 6.0E+01 7.1E+01 5,2E+00 5.9E+00 1.3E+00 1.5E+00 4.00 7.7E+01 8.9E+01 9.2E+00 1 .0E+01 2.8E+00 3.0E+00 TOTALS 1 .3E+04 1 .6E+04 6.4E+02 7.6E+02 1 .3E+02 I1.5E+02 mREM/hr mREM/hr mREMIhr mREMIhr mREMIhr mREMIhr E Depthl= 2' Depthl= 4' Depthl=B1'(MeV) Vogtle Farley Vogtle Farley Vogtle Farley 0.90 1 .6E-01 1 .9E-01 2,7E-03 3.3E-03 4.6E-05 5.4E-05 1.35 3.2E-01 3.8E-01 9.8E-03 1.1IE-02 3.3 E-04 3.7 E-04 1.80 1.7E+01 2.0E+01 8.2E-01 9.2E-01 3.9E-02 4.3E-02 2.20 2.8E+00 3.2E+00 1 .6E-01 1 .8E-01 9.5E-03 1 .0E-02 2.60 9.41E+00 1.0E+01 6.7E-01 7.2E-01 4.9E-02 5.IE-02 3.00 4.1E-01 4.5E-01 3.5E-02 3.7E-02 3.1E-03 3.1E-03 4.00 1 .0E+00 1 .0E+00 1 .2E-01 1 .2E-01 1 .4E-02 1 .4E-02 TOTALS 3.1 E+01 mREMIhr 3.6E+01 mREM/hr 1.8E+00 mREM/hr 2.0E+00 mREMIhr 1.2E-01 mREMIhr 1.2E-01 mREMIhr mREMIhr mREMIhr mREMIhr mREMIhr mREM/hr Southern Nuclear Design Calculation SPlant: Farley Unit: 1&2 Calculation Number: SM-SNC524602-O01 F2 Attachment F2 -Modification of VEGP SFP Dose Rate vs. Depth Analysis for Farley The dose rates vs. depth are plotted below for comparison.

Dose Rate vs. Water Depth 1 .0E+04 ---~1.0E+03 1.0E+01 -~-- ~ -~ -* ---1 .OE+00_____

11 .0 E -0 1 .................................... ....................................rr 8 9 10 11 12 13 14 15 15 Water Depth (feet),-,-Vogtle

-,-,--Farley SM-SNC524602-001IATCMN 2SETF-ATTACHMENT F2 SHEET F2-5 Calculations Input Parameters Water Shielding Parameters E I~p p A1ih A2l X2 (aeV) (cm^21g) (llcm) ____0.90 0.0740 0.0730 58.3145 -57.3145 -0.0554 -0.0221 1.35 0.0610 0.0602 42.6872 -41.6872 -0.0391 -0.0073 1.80 0.0528 0.0520 34.2498 -33.2498 -0.0303 0.0015 2.20 0.0474 0.0467 29.8353 -28.8353 -0.0251 0.0066 2.60 0.0432 0.0426 26.3424 -25.3424 -0.0215 0.0106 3.00 0.0398 0.0392 22.7808 -21.7808 -0.0194 0.0151 4.00 0.0336 0.0331 11.6955 -10.6955 -0.0226 0.0366 pi/P = Ko + [Ki x E] + [K2 x (E^2)] + [K3 x (EA3)] + [K4/E] + [K5/(EA2)]

+ [K6/(EA3)]

= (p)x p p = Water density (g/cm^3)p = 61.55 Ibm/cu ft[Design In put 26]p = 0.986 g/cmA3 = Ibm/cu ft x [(0.016018463 g/cc)/(1 Ibm/cu ft)]Ai = Ko + [Ki x E]A2= I -Ai= Ko +[K x E]cL2 = Ka + [Ki x E]+ [K(2 x (EA2)] + [K(3 x (EA3)] + [K4/E] + [K5/(E^2)]

+ [K6/(EA3)]

[page 481, Lamarsh "Introduction to Nuclear Engineering"]

+ [K2 x (E^2)] + [K3 x (E^3)] + [K4/E] + [K5/(E^2)]

+ [K6/(E^3)]

+ [K(2 x (EA2)] + [K(3 x (E^3)] + [K4/E] + [K5/(E^2)]

+ [K6/(E^3)]

pip Ko =K2 =K3 =K4 =Ks5=K6 =0.05261 -2.73E+02 0.0652 -0.0594-0.01131 1.22E+02 -0.0458 0.0701 0.00141 -2.45E+01 0.0153 -0.0251-0.00006 1 .64E+00 -0.0020 0.0034 0.03138 3.68E+02 -0.1043 -0.0079-0.00375 -1.71 E+02 0.0226 0.0019 0.00018 3.07E+01 -0.0018 -0.0011 From Attachment Fl of this calculation SM-SNC524602-001 ATCMN 2SETF-ATTACHMENT F2 SHEET F2-6 Farley Source Geometry DF = Farley core effective diameter DF = 119.7 inches RF = Farley effective radius (ft)RE = 1/2 X DF X (1 ft/12 in)REF= 4.988 ft Vogtle Source Geometry Dv = Vogtle cylindrical source effective diameter Dv= 13.7 ft RE = Vogtle cylindrical source effective radius Rv = 1/2 xDv Rv = 6.850 ft Source Strength Re-Normalization Fnorm = 1/Vogtle source strength adjustment Fnorrm 1.39 Vogtle Dose Rates vs. Depth E Depth Depth Depth Depth Depth Depth (MeV) 8ft 10ft 11.1lft 12ft 14ft 16ft 0.90 6.335E+02 1.031 E+01 1 .082E+-00 1.551 E-01 2.736E-03 4.569E-05 1.35 3.848E+02 1.156E+01 1.687E+'00 3.179E-01 9.808E-03 3.305E-04 1.80 8.601E+03 4.038E+02

!7.523E+01 1.733E+01 8.218E-01 3.933E-02 2.20 9.403E+02 5.407E+01 1.125E+01 2.834E+00 1.637E-01 9.471E-03 2.60 2.000E+03 1 .435E+02 3.368E+01 9.374E+00 6.749E-01 4.870E-02 3.00 5.971E+01 5.174E+00 1.347E+'00 4.081E-01 3.546E-02 3.086E-03 4.00 7.71 7E+01 9.1 87E+00 2.847E+00 9.956E-01 1.1 89E-01 1 .423E-02 TOTALS 1 .270E+04 6.375E+02 1.271 E+02 3.141 E+01 1 .827E+00 1.1 52E-01 NOTE: All significant figures on sheets spreadsheet.

D-7 thru D-9 of X6CDE.01 entered into this SM-SNC524602-001IATCMN 2SETF-ATTACHMENT F2 SHEET F2-7 Depth Dependent Adjustment Factors d = Water depth d = 8 feet d = 243.84 cm Farley RF =OF =sec OF =4.988 0.557 1.178 feet radians = arctan(RF/d)

Ey XFII XFI2 XF2I XF22 MeV __ _ _ __ _ _0.90 16.808 19.807 17.401 20.506 1.35 14.098 16.613 14.564 17.163 1.80 12.304 14.499 12.707 14.974 2.20 11.111 13.094 11.473 13.520 2.60 10.159 11.971 10.492 12.364 3.00 9.374 11.047 9.703 11.435 4.00 7.896 9.304 8.374 9.868 Ey EI(XFII) EI(XFI2) EI(XF2I) EI(XF22)MeV 0.90 2.83E-09 1.20E-10 1.51E-09 5.79E-11 1.35 5.02E-08 3.47E-09 3.05E-08 1 .94E-09 1.80 3.43E-07 3.27E-08 2.22E-07 1 .97E-08 2.20 1.24E-06 1.47E-07 8.40E-07 9.30E-08 2.60 3.50E-06 4.90E-07 2.43E-06 3.21 E-07 3.00 8.26E-06 1.33E-06 5.76E-06 8.75E-07 4.00 4.24E-05 8.92E-06 2.49E-05 4.81 E-06 SM-SNC524602-001 ATCMN 2SETF-ATTACHMENT F2 SHEET F2-8 Vogtle Rv =Ov =sec Ov =8 6.850 0.708 1.316 feet feet radians = arctan(RF/d)Xvli1 Xvl 2 Xv21 Xv22 MeV 0.90 16.808 22.128 17.401 22.909 1.35 14.098 18.560 14.564 19.174 1.80 12.304 16.198 12.707 16.728 2.20 11.111 14.628 11.473 15.104 2.60 10.159 13.374 10.492 13.813 3.00 9.374 12.341 9.703 12.775 4.00 7.896 10.395 8.374 11.024 Ey Ei(Xvii) EI(Xv12) EI(Xvwl) EI(Xv22)MeV 0.90 2.83E-09 1.06E-11 1.51 E-09 4.71 E-12 1.35 5.02 E-08 4.46 E-10 3.05E-08 2.34E-10 1.80 3.43E-07 5.39E-09 2.22E-07 3.07E-09 2.20 1 .24 E-06 2.85E-08 8.40E-07 1 .72 E-08 2.60 3.50E-06 1 .09E-07 2.43E-06 6.80E-08 3.00 8.26E-06 3.29E-07 5.76E-06 2.07E-07 4.00 4.24E-05 2.71 E-06 2.49E-05 1 .37E-06 Ey DRy Fnorm DRF DRF MeV mREMIhr DRv ____0.90 6.3E+02 1.39 0.96 8.4E+02 1.35 3.8E+02 1.39 0.93 5.0OE+02 1.80 8.6E+03 1.39 0.91 1.1IE+04 2.20 9.4E+02 1.39 0.89 1 .2E+03 2.60 2.0E+03 1.39 0.88 2.4E+03 3.00 6.0E+01 1.39 0.86 7.1E+01 4.00 7.7E+01 1.39 0.83 8.9E+01 TOTAL = 1 .3E+04 mREM/hr TOTAL = 1 .6E+04 mREM/hr SM-SNC524602-001 ATCMN 2SETF-ATTACHMENT F2 SHEET F2-9 10 304.8 feet cm Farley RF = 4.988 OF = 0.463 sec OF=" 1.117 feet radians = arctan(RF/d)

EyXFII XF12 XF~t XF22 MeV 0.90 21.010 23.478 21.752 24.307 1.35 17.622 19.693 18.205 20.344 1.80 15.380 17.186 15.884 17.749 2.20 13.889 15.521 14.341 16.026 2.60 12.698 14.190 13.116 14.656 3.00 11.718 13.094 12.129 13.554 4.00 9.870 11.029 10.467 11.697 E'y EI (XF1I) Ei (XFI2) EI (XF2I) E I(XF22)MeV 0.90 3.42E-11 2.60E-12 1.57E-11 1.10E-12 1.35 1.20E-09 1.36E-10 6.48E-10 6.86 E-11 1.80 1.28E-08 1.90E-09 7.52E-09 1.05E-09 2.20 6.27 E-08 1.10E-08 3.87E-08 6.46 E-09 2.60 2.24E-07 4.55E-08 1.43E-07 2.77E-08 3.00 6.45E-07 1.47E-07 4.14E-07 8.97E-08 4.00 4.80E-06 1.36E-06 2.50E-06 6.59E-07 SM-SNC524602-001ATAHETFSETF21 ATTACHMENT F2 SHEET F2-10 Vogtle Rv=" Ov =sec 0v =10 6.850 0.601 1.212 feet feet radians = arctan(RF/d)

Ey' Xv ii Xvi 2 Xv~i Xv22 MeV 0.90 21.010 25.467 21.752 26.365 1.35 17.622 21.360 18.205 22.067 1.80 15.380 18.642 15.884 19.253 2.20 13.889 16.836 14.341 17.383 2.60 12.698 15.392 13.116 15.898 3.00 11.718 14.203 12.129 14.702 4.00 9.870 11.963 10.467 12.688 Ey Ei(Xvii) Et(Xv12) EI(Xv21) E I(Xv22)MeV 0.90 3.42 E-11 3.29E-13 1.57E-11 1.30E-13 1.35 1.20E-09 2.37E-11 6.48E-10 1.13E-11 1.80 1.28 E-08 4.09E-10 7.52E-09 2.15E-10 2.20 6.27E-08 2.74E-09 3.87E-08 1 .54E-09 2.60 2.24E-07 1 .27E-08 1 .43E-07 7.40E-09 3.00 6.45E-07 4.48E-08 4.14E-07 2.63E-08 4.00 4.80E-06 4.95E-07 2.50E-06 2.27E-07 E7DRy Fnorm DR F DRF MeV mREM/hr DRv 0.90 1.0E+01 1.39 0.93 1.3E+01 1.35 1.2E+01 1.39 0.90 1.4E+01 1.80 4.0E+02 1.39 0.87 4.9E+02 2.20 5.4E+01 1.39 0.85 6.4E+01 2.60 1.4E+02 1.39 0.84 1.7E+02 3.00 5.2E+00 1.39 0.82 5.9E+00 4.00 9.2E+00 1.39 0.79 1.0E+01 TOTAL = 6.4E+02 mREM/hr TOTAL = 7.6E+02 mREM/hr SM-SNC524602-001 ATCMN 2SETF-ATTACHMENT F2 SHEET F2-11 d= 11.1 feet d = 338.328 cm Farley RF=-OF sec OF =4.988 0.422 1.096 feet radians =arctan(RF/d)

E XF11 XFI2 XF2I XF22 MeV___ _0.90 23.321 25.567 24.144 26.470 1.35 19.561 21.445 20.208 22.154 1.80 17.071 18.715 17.631 19.329 2.20 15.417 16.902 15.918 17.452 2.60 14.095 15.453 14.558 15.960 3.00 13.007 14.259 13.463 14.760 4.00 10.955 12.010 11.619 12.738 Ey E1(XFII) E1(XF12) EI(XF21) EI(XF22)MeV__ _ _ __ _ _0.90 3.06E-12 2.97E-13 1.30E-12 1.16E-13 1.35 1.56E-10 2.17E-11 7.91E-11 1.03E-11 1.80 2.14E-09 3.79E-10 1.19E-09 1.99E-10 2.20 1 .23E-08 2.56E-09 7.24E-09 1 .43E-09 2.60 5.03 E-08 1.19E-08 3.07E-08 6.93E-09 3.00 1.61E-07 4.22E-08 9.88E-08 2.48E-08 4.00 1.47 E-06 4.70 E-07 7.17E-07 2.15E-07 SM-SNC524602-001ATAHETFSETF21 ATTACHMENT F2 SHEET F2-12 Vogtle d=Rv =Ov =sec Ov =11.1 6.850 0.553 1.175 feet feet radians = arctan(Rv/d)

E'y Xv1i Xvi2 Xv2i Xv22 MeV 0.90 23.321 27.405 24.144 28.372 1.35 19.561 22.986 20.208 23.746 1.80 17.071 20.060 17.631 20.718 2.20 15.417 18.117 15.918 18.706 2.60 14.095 16.563 14.558 17.107 3.00 13.007 15.284 13.463 15.821 4.00 10.955 12.873 11.619 13.653 Ey Ei(Xv1i) E1(Xvl2) EI(Xv21) EI(Xv22)MeV 0.90 3.06E-12 4.42E-14 1.30E-12 1.63E-14 1.35 1.56E-10 4.35E-12 7.91E-11 1.97E-12 1.80 2.14E-09 9.23E-11 1.19E-09 4.64E-11 2.20 1.23E-08 7.11E-10 7.24E-09 3.83E-10 2.60 5.03E-08 3.66E-09 3.07E-08 2.06E-09 3.00 1.61 E-07 1.42 E-08 9.88 E-08 8.03E-09 4.00 1.47E-06 1.86E-07 7.17E-07 8.06 E-08 Ey DRy Fnorm DR F DRF MeV mREM/hr DRyv ___0.90 1 .08E+'00 1.39 0.91 1 .4E+00 1.35 1.69E+00 1.39 0.88 2.1E+00 1.80 7.52E+01 1.39 0.85 8.9E+01 2.20 1.12E+01 1.39 0.83 1.3E+01 2.60 3.37E+'01 1.39 0.82 3.8E+01 3.00 1 .35E+00 1.39 0.80 1 .5E+00 4.00 2.85E+00 1.39 0.77 3.0E+00 TOTAL = 1 .27E+02 m REM/hr TOTAL = 1 .5E+02 mREM/hr SM-SNC524602-001ATAHETFSETF21 ATTACHMENT F2 SHEET F2-13 d = 12 feet d = 365.76 cm Farley RF = 4.988 feet OF =sec OF =0.394 1.083 radians = arctan(RF/d)

Ey, XF11 XF12 XF21 XF22 MeV 0.90 25.212 27.303 26.102 28.267 1.35 21.147 22.901 21.846 23.658 1.80 18.456 19.986 19.060 20.641 2.20 16.667 18.049 17.209 18.636 2.60 15.238 16.502 15.739 17.044 3.00 14.061 15.227 14.555 15.762 4.00 11.843 12.826 12.561 13.603 Ey EI(XF11) EI(XF12) EI(XF2I) EI(XF22)MeV 0.90 4.29E-13 4.91E-14 1.70E-13 1.81E-14 1.35 2.96E-11 4.75E-12 1.43E-11 2.16E-12 1.80 4.98E-10 9.98E-11 2.64E-10 5.03E-11 2.20 3.28E-09 7.63E-10 1.85 E-09 4.12E-10 2.60 1.49E-08 3.91 E-09 8.76E-09 2.20E-09 3.00 5.22 E-08 1.51 E-08 3.08 E-08 8.55E-09 4.00 5.63E-07 1.96E-07 2.60E-07 8.51 E-08 SM-SNC524602-001ATAHETFSETF21 ATTACHMENT F2 SHEET F2-14 Vogtle Rv =Ov=sec Ov =12 6.850 0.519 1.151 feet feet radians = arctan(Rv/d)

E'y Xv Ii Xv12 Xv2l Xv22 MeV 0.90 25.212 29.031 26.102 30.055 1.35 21.147 24.350 21.846 25.155 1.80 18.456 21.251 19.060 21.947 2.20 16.667 19.192 17.209 19.816 2.60 15.238 17.546 15.739 18.122 3.00 14.061 16.191 14.555 16.760 4.00 11.843 13.637 12.561 14.463 E', Ei(Xvt1) Ei(Xvi2) EI(Xvzi) E1(Xv22)MeV 0.90 4.29 E-13 8.22 E-15 1.70E-13 2.85E-15 1.35 2.96E-11 1.05E-12 1.43E-11 4.55 E-13 1.80 4.98E-10 2.66E-11 2.64E-10 1.28E-11 2.20 3.28E-09 2.30E-10 1.85E-09 1.19E-10 2.60 1.49E-08 1.30E-09 8.76E-09 7.07E-10 3.00 5.22E-08 5.43E-09 3.08E-08 2.97E-09 4.00 5.63E-07 8.20E-08 2.60E-07 3.40E-08 E', DRv Fnorm DR.__F DRF MeV mREM/hr DRy 0.90 1.55E-01 1.39 0.90 1.94E-01 1.35 3.18E-01 1.39 0.87 3.82E-01 1.80 1.73E+01 1.39 0.84 2.02E+01 2.20 2.83E+00 1.39 0.82 3.22E+00 2.60 9.37E+00 1.39 0.80 1 .04E+01 3.00 4.08E-01 1.39 0.79 4.45E-01 4.00 9.96E-01 1.39 0.76 1.05E+00 TOTAL = 3.14E+01 mREM/hr TOTAL = 3.59E+01 mREM/hr SM-SNC524602-001ATAHETFSETF21 ATTACHMENT F2 SHEET F2-15 d = 14 feet d = 426.72 cm Farley RF =OF =seC'OF =4.988 0.342 1.062 feet radians = arctan(RF/d)

E'y XF11 XF12 XF21 XF22 MeV 0.90 29.414 31 .225 30.452 32.327 1.35 24.671 26.190 25.488 27.057 1.80 21.531 22.857 22.237 23.606 2.20 19.445 20.642 20.077 21.313 2.60 17.778 18.872 18.362 19.492 3.00 16.405 17.415 16.981 18.026 4.00 13.817 14.668 14.654 15.557 Ey E1(XF11) EI(XFI2) E1(XF2I) E1(XF22)MeV 0.90 5.53E-15 8.54E-16 1.89E-15 2.74E-16 1.35 7.53E-13 1.56E-13 3.22E-13 6.34E-14 1.80 1.98E-11 4.97E-12 9.49E-12 2.28E-12 2.20 1.76E-10 5.02E-11 9.07E-11 2.49E-11 2.60 1.02 E-09 3.21 E-10 5.49E-10 1.68E-10 3.00 4.33 E-09 1.49 E-09 2.35E-09 7.82 E-10 4.00 6.77E-08 2.73E-08 2.77E-08 1 .06E-08 SM-SNC524602-001ATAHETFSETF21 ATTACHMENT F2 SHEET F2-16 Vogtie d=Rv =Ov =sec Ov =14 6.850 0.455 1.113 feet feet radians = arctan(Rv/d)

E'y Xvii1 Xv1 2 Xv21 Xv22 MeV 0.90 29.414 32.747 30.452 33.902 1.35 24.671 27.466 25.488 28.375 1.80 21.531 23.971 22.237 24.756 2.20 19.445 21.648 20.077 22.352 2.60 17.778 19.791 18.362 20.442 3.00 16.405 18.263 16.981 18.905 4.00 13.817 15.383 14.654 16.315 Ey Ei(Xvi1) Ei(Xvi2) Ei(Xvzi) EI(Xv22)MeV 0.90 5.53E-15 1.78E-16 1.89 E-15 5.42 E-17 1.35 7.53E-13 4.15E-14 3.22E-13 1.62E-14 1.80 1.98E-11 1.56E-12 9.49 E-12 6.89E-13 2.20 1.76E-10 1.75E-11 9.07E-11 8.42E-12 2.60 1.02E-09 1.22E-10 5.49E-10 6.19E-11 3.00 4.33 E-09 6.09 E-10 2.35E-09 3.10E-10 4.00 6.77E-08 1.28E-08 2.77E-08 4.76E-09 Ey DRy Fnorm DRF DRF MeV mREM/hr DRy 0.90 2.7E-03 1.39 0.87 3.3E-03 1.35 9.8E-03 1.39 0.83 1.1E-02 1.80 8.2E-01 1.39 0.81 9.2E-01 2.20 1.6E-01 1.39 0.79 1.8E-01 2.60 6.7E-01 1.39 0.77 7.2E-01 3.00 3.5E-02 1.39 0.76 3.7E-02 4.00 1.2E-01 1.39 0.73 1.2E-01 TOTAL = 1,.8E+00O mREM/hr TOTAL = 2.0E+00 mREMIhr SM-SNC524602-001ATAHETFSETF27 ATTACHMENT F2 SHEET F2-17 d = 16 feet d = 487.68 cm Farley RF =OF =sec OF =4.988 0.302 1.047 feet radians = arctan(RF/d)

Ey XF1I XFI2 XF2I XF22 MeV 0.90 33.62 35.21 34.80 36.45 1.35 28.20 29.53 29.13 30.51 1.80 24.61 25.78 25.41 26.62 2.20 22.22 23.28 22.95 24.03 2.60 20.32 21.28 20.98 21.98 3.00 18.75 19.64 19.41 20.33 4.00 15.79 16.54 16.75 17.54 Ey E1 (XF11) E1(XF12) E1(XF21) E1 (XF22)MeV 0.90 7.3E-17 1.4E-17 2.1E-17 3.9E-18 1.35 1.9E-14 4.9E-15 7.4E-15 1.8E-15 1.80 8.0OE-13 2.4E-13 3.5E-13 1.0E-13 2.20 9.6E-12 3.2E-12 4.5E-12 1.5E-12 2.60 7.1E-11 2.6E-11 3.5E-11 1.2E-11 3.00 3.7E-10 1.4E-10 1.8E-10 7.0E-11 4.00 8.3E-09 3.7E-09 3.0E-09 1.3E-09 SM-SNC524602-001ATAHETFSETF21 ATTACHMENT F2 SHEET F2-18 Vogtle d=Rv=Ov =sec Ov =16 6.850 0.405 1.088 feet feet radians = arctan(Rv/d)

E Xv Ii Xvl 2 Xv~l Xv22 MeV___ _0.90 33.62 36.57 34.80 37.86 1.35 28.20 30.67 29.13 31.69 1.80 24.61 26.77 25.41 27.64 2.20 22.22 24.17 22.95 24.96 2.60 20.32 22.10 20.98 22.83 3.00 18.75 20.39 19.41 21.11 4.00 15.79 17.18 16.75 18.22 E7 E1(Xvii) Ei(Xv12) EI(Xv2i) Ew(Xv22)MeV 0.90 7.3E-17 3.5E-18 2.1E-17 9.3E-19 1.35 1.9E-14 1.5E-15 7.4E-15 5.3E-16 1.80 8.0E-13 8.5E-14 3.5E-13 3.4E-14 2.20 9.6E-12 1.3E-12 4.5E-12 5.6E-13 2.60 7.1E-11 1.1E-11 3.5E-11 5.1E-12 3.00 3.7E-10 6.5E-11 1.8E-10 3.1E-11 4.00 8.3E-09 1.9 E-09 3.0OE-09 6.4E-10 EyDRy Fnorm DR._.F DRF MeV mREM/hr DRy 0.90 4.6E-05 1.39 0.84 5.4E-05 1.35 3.3E-04 1.39 0.81 3.7E-04 1.80 3.9E-02 1.39 0.78 4.3E-02 2.20 9.5E-03 1.39 0.76 1.0OE-02 2.60 4.9E-02 1.39 0.75 5.1IE-02 3.00 3.1IE-03 1.39 0.73 3.1IE-03 4.00 1.4E-02 1.39 0.71 1.4E-02 TOTAL =1.2E-01 mREMIhr TOTAL = 1.2E-01 mREM/hr Southern Nuclear Design Calculation SPlant: Farley Unit: 1&2 Calculation Number: SM-SNC524602-001 ISheet: F3-1 Attachment F3 -Operating Deck Dose Rates for Reduced RPV Water Level Introduction The purpose of this evaluation is to determine the dose rates at the Containment operating deck area radiation monitors, RE0002 and RE0027A/B, that correspond to RPV water level elevations of 121 '-0" (3' above TOAF) and 11 8'-0" (TOAF).Evaluation Dose Rate at Water Surface or TOAF The dose rate vs. graph in Attachment F2 does not extend down to zero feet of water depth.The Farley dose rate vs. depth data are used to generate another graph, and the line is extended down to fuel uncovery as shown below: Farley RPV Dose Rate vs. Water Depth 12 Water Depth Above TOAF (feet)At an RPV water level elevation corresponding to 3 feet above TOAF (EL 121'-0"), the dose rate at the surface of the water is 3.0E+07 mREM/hr, or 3.0E+i04 REM/hr At an RPV water level corresponding to fuel uncovery, the dose rate is 3.0E+09 mREM/hr, or 3.0E+06 REM/hr Southern Nuclear Design Calculation IPlant: Farley IUnit: 1&2 ICalculation Number: SM-SNC524602-001 ISheet: F3-2 Attachment F3 -Operating Deck Dose Rates for Reduced RPV Water Level Operatincq Deck Reflected Dose Rate Based on a study of instrument location drawings D175148 and D205148, the containment operating deck (RE0002 and RE0027A/B) area radiation monitors do not have a direct view of the irradiated fuel. They are located 5' above the operating deck (EL 155'0"; Design Input #8)at EL 1 60'0" and against a wall. They do "see" gammas that reflect off the containment dome.The operating deck dose rate due to these reflected gammas is given by the following equation from Davisson, "Gamma Ray Dose Albedos," (copy in Attachment C1): DRmon/DRsfc

= (cos 0)*(A/r 2)*(a where DRmon = reflected dose rate at area radiation monitor (mREM/hr)DRsfc = dose rate at surface of water above irradiated fuel (mREM/hr)0 = incident angle = 0°A = reflecting area (sq ft)r = distance from reflecting surface to receptor a= dose albedo; dependent upon incident angle, gamma energy, reflected angle, and reflecting surface Rearranging the above equation to solve for the dose rate at the area radiation monitor yields DRmon = DRsfc x [(COS 0)*(A/r 2The containment geometry is shown to '-/i; '=",, right (from Assumption

1. 11). ,\, 0 = 0-> cos0e= 1.00 " //A = area of reflecting surface (sq ft)/,,/ \ , A=F1 D 2/4 //t\,'D = 13.083 ft [Design Input #12] ___A =fl[(13.083) 2/4 =134.4 sqfft7a \ / : ",, r = hypotenuse of right triangle \ '**+ x --y = 287'-0" -1 60'-0" y= 127ft x = 65 ft ....r = SQRT[x 2 + yl] = SQRT [(65)2 + (127)2] 'r= 143ft ... ....LContalnment dimensions:

Ueslgn Input Southern Nuclear Design Calculation SPlant: Farley Unit: 1&2 Calculation Number: SM-SNC524602-001 Sheet: F3-3 Attachment F3 -Operating Deck Dose Rates for Reduced RPV Water Level The containment has a carbon steel liner, so the dose albedo for iron is used. For an incident angle of 00, a range of emerging angles of 00 to ~~30°, and the predominant gamma energy (-2 MeV based a review of the dose rate data in Attachment E2), ct = -0.005 based on a review of the table on sheet C1-10 of this calculation.

DRmon = DRsfc x {(1 .00)*[134.4/(1432)]*(0.005)}

DRmon = 3.29E-05 x DRsfc Operatingi Deck Reflected Dose Rate -RPV Water Level (, TOAF The Containment operating deck dose rate due to an source dose rate of 3.0E+09 mREM/hr is therefore DRmon = 3.29E-05 x (3.0E+09 mREM/hr)DRmon = 9.86E+04 mREM/hr DRmon --100 REM/hr Southern Nuclear Design Calculation Plant: Farley Unit: 1&2 ICalculation Number: SM-SNC524602-001 Isheet: F4-1 Attachment F4 -Seal Table Room Dose Rate Evaluation Introduction The purpose of this evaluation is to determine the dose rates at the seal table room area radiation monitor, RE0007, that correspond to the operating deck dose rates calculated in Attachment F3 of this calculation.

Evaluation The dose rate is proportional to the gamma flux, DR oa 4, (page 442, Lamarsh, "Introduction to Nuclear Engineering"), so the dose rate in the seal table room (DRstr) may be estimated by modeling the reflected gamma flux at the operating deck as a monodirectional planar source at the back of a concrete shield. The gamma flux in the seal table room (4str) is the buildup flux passing through the operating deck (equation 10.26, page 484, "Introduction to Nuclear Engineering"):

4str = (4od/2) X {AiE1[(1 + a1) x p, x aod] + A2E1[(1 + (a2) x X aod]}*str/jod = 1/2 X {AiEi[(1 + oai) X !i X aod] + A2E1[(1 + ca2) x ji x aod]}DRstr/DRod

= % x {AiEi[(1 + ai) x p. x aod] + A2E1[(1 + oa2) x p. x aod]}A review of the data in Attachment F2 indicates that 2 MeV gammas are predominant; the evaluation will be based on 2 MeV gammas to estimate the overall effect on dose rate.Where, for 2 MeV gammas A1 = 18.089 [Table 10.3, page 482, "Introduction to Nuclear Engineering"]

A2 = 1 -Ai [page 481, "Introduction to Nuclear Engineering"]

A2 = -1 7.089 o1= -0.04250 [Table 10.3, page 482, "Introduction to Nuclear Engineering"]

cx2 = 0.00849 [Table 10.3, page 482, "Introduction to Nuclear Engineering"]

p.= (p/)x p (p./p) = 0.0445 cm 2/g [Table 11.4, page 648, "Introduction to Nuclear Engineering"]

p = 2.40 g/cm 3 [Table 11.4, page 648, "Introduction to Nuclear Engineering"]

p.= (0.0445 cm 2/g) x (2.40 g/cm 3)p. = 0.1068 cm-1 aod = operating deck thickness aod = 3 ft X (30.48 cm/i ft) [Design Input #8]aod = 91.44 cm Southern Nuclear Design Calculation SPlant: Farley Unit: 1&2 ICalculation Number: SM-SNC524602-001 Sheet: F4-2 Attachment F4 -Seal Table Room Dose Rate Evaluation Per equation 10.24 on page 483 of "Introduction to Nuclear Engineering," for X > 14 the function Ei(X) may be approximated as: Ei[X] = [exp(-X)]

x {[l/(X + 1)] + [I/(X +1)]Xi = (1 + oci) x !L x aod = (1 -- 0.04250) X (0.1068 cm-1) x (91.44 cm) = 9.3507 X2 = (1 + cL2) x JI x aod = (1 + 0.00849) X (0.1068 cm-') x (91.44 cm) = 9.8487 For X = 10, the error is 0.11%; the values of X used in this evaluation is are sufficiently close to 10 that any error due to this approximation is negligible.

For Xi = 9.3507: Ei[Xi] = [exp(-9.3507)]

x {[1I(9.3507

+ 1)] + [1/(9.3507

+1)]Ei [Xi] = 8.4739E-06 For X2 = 9.8487: E1[X2] = [exp(-9.8487)]

x {[1/(9.8487

+ 1)] + [1 /(9.8487 +1)]Ei[Xi] = 4.9097E-06 Therefore DRstr/DRod

= 1/2 x [(1 8.089)x(8.4739E-06)

+ (-1 7.089)x(4.9097E-06)]

DRstr/DRod

= % x [1 .532E-04 -8.390E-05]

DRstr/DRod

= 3.47E-.05 DRstr = (3.47E-.05) x DRod For RPV water level EL 11 8'-0" (TOAF), DRod = 9.86E+04 mREM/hr (Attachment F3): DRstr = (3.47E-05) x (9.86E+04 mREM/hr)DRstr = 3.42 mREM/hr DRstr = -3 mREMIhr Purpose: The purpose of this calculation is to provide emergency action level thresholds for use in the development of the Farley Nuclear Plant Emergency Action Levels using NEI 99-01 Rev 6 guidelines.

This calculation includes the thresholds for three fission product barrier EALs; Fuel Clad Barrier Loss 3.A, RCS Barrier Loss 3.A, and Containment Barrier Potential Loss 3.A.Criteria: The calculation performed will support the development of guidelines for NE! 99-01 EALs numbers AA2 (EAL3), AA2 (EAL4), FC(EAL5), RCS(EAL4), CTMT(EAL2), CTMT(EAL5), and SS5(EAL 1).1. Declaration of an emergency, when such a declaration is not required, involves risk to the public as does the failure to make such a declaration, should one be warranted.

Therefore, this calculation shall develop a 'best estimate" value for the dose rates or curie concentrations sensed at the monitors chosen for the Emergency Action Level (EAL) set points. When judgments are necessary, these judgments shall be as close to anticipated conditions as possible.2. If a particular monitor is to be used for an EAL, then the dose rate or curie concentration set point developed for that specific monitor shall be within the range of the monitor, or the monitor shall not be cited as applicable for the EAL.3. In accordance with the guidance of Regulatory Guide 1 .97, Revision 2, post-accident radiation monitors must read within a factor of 2 of actual radiation conditions.

Therefore, changes in the set points of this revision that are within a factor of 2 of the previous revision's set point for the same EAL do not invalidate the previous set point.It is up to the ultimate user of these calculations to determine if change to the EAL set point guidance document(s) is warranted.

4. Methods and Assumptions shall comply with the guidance of NEI 99-01 Rev. 6.

==

Conclusions:==

The results of the calculations of the radiation analysis for the fission product barrier EALs are presented below.EAL Monitor Monitor Range Set Point Containment Barrier , 5 Potential Loss 4.B *55 FulCa BrirRE-0027A&B 1 E+00 to 1 E+07 R/hr 600 R/hr Loss 3.A RE-0002 1 E-04 to 1 E+01 R/hr 1 R/hr RCS Barrier Loss 3.A Or Or RE-0007 I1E-04 to 1 E+01 R/hr 0.5R/hr Cotinet arir RE-0027A&B 1 E+00 to 1 E+07 R/hr 8,000R/hr PotentialLoss_3.A

__________

__________

__ ________**These values are not reported in this calculation.

The evaluation was performed in calculation SM-95-0754-001 and this information can be found there. This calculation provides the supportating rational for the established set point.

Design Inputs: 1. Per RG1 .195 page 14 Table 3, we will only consider groups for radionuclide of XE, Kr, and I.2. The Reactor Coolant Fission Product Specific Activity is taken from WCAP-1 4722 Table 7.6-6 page 7.6-52.3. The ICRP30 inhalation dose conversion factors are obtained from NUREG/CR-5106 pg E-19. Per ESAR page 3A-1.195-1 ICRP 30 dose conversion factors should be used with RG1 .1.95. The dose conversion factors also are available in Table G.6 of Faw & Shultis"Radiological Assesment" 4. The isotope 1-127 & 129 is considered a stable isotope per Chart of Nuclides and will not be part of this analysis.5. The Geometric Correction Factor in Sections V, VI, and VII of 768 was obtained from SM-94-0466-001 page 30.6. Per RG1.195 page 12 and 13 section 3.2 and table 2: The core inventory release fractions for non-LOCA events where only cladding is breached, the release fractions in table 2 should be considered.

1-131 is 0.08, Kr-85 is 0.10, Other Noble Gases 0.05, Other lodines 0.05.The RG1 .195 Table I shows release fractions when the fuel melted as well as cladding when Table 2 is only when the cladding failed. The NEI 99-01 page 5-F-19 section 6 described the IC as 20% failed cladding, therefore it is more appropriate to use Table 2 release fractions when only cladding failed.7. Dose Equivalent 1-131 is defined as that concentration of 1-131 (uCi/gm) which alone would produce the same thyroid dose as the quantity and isotopic mixture of 1-131, I-132, 1-133, 1-134, 1-135 (NUREG-1301 page 6).8. The radiation monitor RE-0027A&B operating range is i to 1E:7 R/hr (page 3-16 of Al181015).

9. The radiation monitor RE-0002 operating range is 1 E-4 to 1 El rads per hour (page 3-5 of A181015).10.The radiation monitor RE-0007 operating range is 1E-4 to 1E1 rads per hour (page 3-12 of Al181 015).11 .Technical Specification 3.4.16 limits the RCS activity to 0.5pCi/gm dose equivalent I-131.12. RCS mass is 417,219 Ibm (page 4.1-3 WCAP 15097).

Assumptions:

1. The assumptions used in the radiation monitor response analysis performed in SCS Calculation SM-94-0466-O01 are correct and proper for this analysis except as noted in the calculation.

2. It is assumed that the dose field seen by RE-0027 radiation detector sensitivity calculated in SM-94-0466-OO1 is applicable to RE-0002. It is a conservative assumption because per D205148 both detectors are located at same height of EL 160 feet.

References:

1. Deleted 2. Deleted 3. SCS Calculation SM-95-0754-001 Ver 7.0 "Severe Accident Management Guidelines (SAM G)" 4. U206196 Vl.0 was superseded by U279877 V3.0 "R.H. General Arrangement" 5. D176540 V12.0, "Section 18 Concrete Auxiliary Building" 6. SCS Calculation SM-96-1064-001 V9.0 "Fuel Handling Accident Doses" 7. TACT5 Users Manual, NUREG/CR-5106 June 1988 8. AlA list, Westinghouse Letter ALA-95-756, 12/15/95 "Joseph M Farley Nuclear Plant Units 1 and 2 Power Uprate Project Analysis Input Assumption List and Matrix Revision 2." 9. SCS Nuclear Support Calculation F-86-03, Rev. 3, GRODEC Verification.

10. SCS Calculation SM-94-0466-001 V0.0, "Containment Dose Rate" 11. U 735579 VI1.0 "Radiation Analysis Design Manual for FNP", 4/72 12. D175149 V18.0, "Inst Loc CTMT & Fuel Hand" 13. U21 7359 V2.0, "ICCMS Technical Manual Volume II (Electronics)" 14. NEI 99-01 Rev 6 "Methodology for Development of Emergency Action Levels" 15. Deleted 16. Deleted 17. Shultis and Faw "Fundamentals of Nuclear Science and Engineering."2002 ISBN0-8247-0834-2

18. SM-97-1 638-002 V3.0 "Steam Generator Replacement

-Containment Pressure and Temperature Analysis" & CCN-F-10-0001 V3.0 19. Faw and Shultis "Radiological Assessment:

Sources and Doses" 1999, ISBN: 0-89448-455-9 20.A181015 V14.0 "Functional System Description Radiation Monitoring System" 21 .FNP Technical Specifications 198/194 22. Deleted.23. SNC Calculation 006.03 V0.0 "Analytical Procedures" 24. D1 76200, 15.0 "Floor Plan At EL. I105'6" Concrete -Containment" 25. "Engineering Compendium on Radiation Shielding", 1968 26. Etherington "Nuclear Engineering Handbook" McGraw 1958. Selected pages copy is attached to this calculation.

27. RG 1.195 "Methods and assumptions for evaluating radiological consequences of design bases accidents at Light-Water Nuclear Power Reactors." May 2003

28. WCAP14722 VI1.0 "Power Uprate Project NSSS Engineering Report." 29. Lockheed Martin 2002, "Chart of Nuclides and Isotopes" Ed 1 6 th.30. NUREG-1 301 "Offsite Dose Calculation Manual Guidance:

Standard Radiological Effluent Controls for Pressurized Water Reactors." Generic Letter 89-01, Supplement No. 1.31 .RG1 .97 R2 "Instrumentation for light-water-cooled nuclear power plants to assess plant and environs conditions during and following an accident." 32. NUREG-1228 "Source Estimations During Incident Response to Severe Nuclear Power Plant Accidents" 1988 33. U264698 V0.2 "RE/RI27 INS;TRUCTION MANUAL VI SYS 875-SUPERSEDES U447940 SUPERCEDES:U447940" 34. Deleted 35. WCAP 15097 VI.0 "REPLACEMENT STEAM GENERATOR PROGRAM NSSS ENGINEERING REPORT FOR FNP UNITS 1 AND 2 REVISION 1" Method of solutions:

Three related fission product barrier thresholds are calculated with the same method in this calculation.

The nuclide inventory for the RCS is taken from WCAP14722 and scaled to the prescribed activities of 0.5 pCi/cc, and 300 pCi/cc for representing a failure of the RCS barrier and the fuel clad barrier respectively.

For the case of potential containment failure, values from WCAP14722 for the full core are scaled based on gap release fractions, assumed 20% failed fuel, and power rating. The resulting nuclide inventories are dispersed evenly in the free volume of containment, binned by energy level in GRODEC, multiplied by dose conversion factors and a geometric factor to determine the containment radiation monitor response.The development of the values in this calculation were performed using various computer codes which were previously developed and verified for their particular application related to this calculation.

All codes were verified to be operating properly on their respective PC used in the calculation by running the test cases used in the verification of the code and comparing the results with the original verification calculation.

Details of the codes used are contained in the specific sections of the calculation.

Southern Nuclear 0perating Cornpanylant FNPSM-SNC524602-OO1 SOUTHERA Plnit: FNPil:NE 90 A Cluain Atcmn COMPN nit:1&2Tite:

NI 9-01 AL alclatins ttahmenT G-Body of Calculation:

Containment Barrier Potential Loss 4.B NEI 99-01 Rev 6 pg 119 "The existence of an explosive mixture means, at a minimum, that the containment atmospheric hydrogen concentration is sufficient to support a hydrogen burn (i.e., at the lower deflagration limit). A hydrogen burn will raise containment pressure and could result in collateral equipment damage leading to a loss of containment integrity.

It therefore represents a potential loss of the Containment Barrier." Existence of an explosive mixture of hydrogen and oxygen indicates a potential loss of containment integrity.

Per calculation SM-95-0754-001 pg 9, a hydrogen concentration above 6% is potentially explosive.

Since the accuracy of the hydrogen monitor is +/-0.5% in the range of 0-10% hydrogen, use 5.5%. Per calculation SM-95-0754-001 page 12 the concentration of >6% would support a burn throughout containment.

Fuel Clad Barrier Loss 3.A Containment radiation monitor RE-0027A&B (Q1 D21 RE0027A&B, Q2D21 RE0027A&B) can be read to one significant digit (page 15 of U264698), thus the value of 640.06R/hr is conservatively rounded off to 600R/hr (The revision 1 of this calculation had 80R/hr). The range of this monitor is 1Ito R/hr (page 3-16 of A181015).NEI 99-01 Rev 6 pg 105 "The radiation monitor reading corresponds to an instantaneous release of all reactor coolant mass into the containment, assuming that reactor coolant activity equals 300pCi/gm dose equivalent 1-131.Reactor coolant activity above this level is greater than that expected for iodine spikes and corresponds to an approximate range of 2% to 5% fuel clad damage. Since this condition indicates that a significant amount of fuel clad damage has occurred, it represents a loss of the Fuel Clad Barrier. " The monitor reading is calculated assuming the instantaneous release and dispersal of the reactor coolant noble gas inventory associated with a concentration of 300pCi/gm of dose equivalent 1131 into the containment atmosphere.

Concentration of this magnitude is several times larger than the maximum technical specification RCS concentration and is therefore indicative of fuel clad damage. Halogens and particulates are assumed to be largely retained by the water and/or removed via other physical processes (e.g. plateout and settling) and not dispersed throughout the containment.

This yields a slightly lower (conservative) radiation monitor reading.

The Reactor Coolant System fission products concentrations are taken from WCAP14722 Table 7.6-6, while all these isotopes are scaled to match DEl of 3001pCi/gm.

NUREG/CR-5106 pg E-1 9 ICRP Publication 30 (Ref 7) provides the inhalation dose conversion factor (REM/Ci)for 1-129 and 1-132. The isotope 1-127 is considered a stable isotope per Chart of Nuclides and will not be part of this analysis.

The rest of inhalation dose conversion factors for ICRP Publication 30 are listed in Faw Shultis "Radiological Assessment" Table G.6 in units of (Sv/Bq).The converstion factor of Sv/Bq to Rem/Ci is as follows: Ci :=3.7. 010 *Bq jpCi :=10- *.Ci Sv REM:=-100 page 5 of Faw, Shultis "Radiological Assesment" page 14 of Faw, Shultis "Radiological Assesment" note 5.Sv 102REM 1---=3.7x 1 Bq Ci MathCAD internal conversion The following excell worksheet was developed as follows:

= Activity. " k-) " Factor" (1i Factor. = Factor.

• LD3.7. *0 2(j Activity~'

'C m Activity'*

i/'.m 106"C-i 1 Relative Dose Conversion Weighted_____

Activity Factor Factor Activity Factor Activity (R/gm)(uCi/gm) (R/Ci) (Sv/Bq) (Ci/gm) (R/Ci)WCAP14722 NUREG- Faw,Shultis Table 7.6-6 5106 1-131 1.400E+i-00_____

2.90E-07 1.400E-06 1.073E+06 1.502E+00 1-132 2.300E+O0 6.30E+03 2.300E-06 6.300E+03 1.449E-02 1-133 2.700E+00 4.90E-08 2.700E-06 1.813E+05 4.895E-01 1-134 6.300E-01

______ 2.90E-10 6.300E-07 1.073E+03 6.760E-04 1-135 1.900E+00 8.50E-09 1.900E-06 3.145E+04 5.976E-02 SUM 2.07E+i00 And Ci :=3.7. 010 *Bq Ci p.Ci :=DOSeDEI :=2.07. 100.R-gm gm Do s CDEI RatioDEy to_1.131 .-=- 1.38_ Dose 1.131 MaSSRCS : 417219. lb = 1.892 x 108gm lib =453.592gm This statement defines the unit of Curies, since Becquerels are defined in MathCAD, while Curies are not. Reference is page 102 of Shultis Fundamentals of Nuclear Science and Engineering.

The sum in table above generated this number.The dose was generated in the table above.The RCS mass was obtained from WCAPI15097 page 4.1-3 MathCAD internal conversion and rounding to six sig. fig.The iodine gas activity as compaired to WCAP14722 is calculated below ActivityLl 3 1 := 1.4- 10-6. C-~gm.. .300. C.*Ratioiodine

.g = 155.28 RatioDEt to_1. 131 "Activityl.

1 3 1 The isotopes activity WCAP14722 table 7.6-6 was multiplied by 155.28, which was calculated above. The activity related to Xe and Kr was assumed to have 100% release as indicated in the NEI99-01 problem statement.

The activities related to Xe and Kr were obtained from WCAP14722 table 7.6-6.

18 gm The RCS mass was obtained from MaSSRCS := 417219- lb = 1.892 x 1gm WCAP 15097 page 4.1-3 lib =453.592gm MathCAD internal cornversion and rounding to two sig fig.The isotopes activities in next excell spreadsheet are calculated as follows: Isotope _________FC-EAL5 Activity (uCi/gm) Containment

______ WCAP14722 Activity (Ci)1-129 2.70E-08 7.93E-04 1-130 2.20E-02 6.46E+02 1-131 1.400E+00 4.11E+04 1-132 2.300E+00 6.76E+04 1-133 2.700E+00 7.93E+04 1-134 6.300E-01 1.85E+04 1-135 1.900E+00 5.58E+04 Kr-83m 4.500E-01 1.32E+04 Kr-85 7.700E+00 2.26E+05 Kr-85m 1.800E+00 5.29E+04 Kr-87 1.200E+00 3.53E+04 Kr-88 3.500E+00 1.03E+05 Kr-89 1.100E-01 3.23E+03 Xe-131m 2.900E+00 8.52E+04 Xe-133 2.400E+02 7.05E+06 Xe-133m 4.600E+00 1.35E+05 Xe-135 7.900E+00 2.32E+05 Xe-135m 4.500E-01 1.32E+i04 Xe- 137 2. O00E-01 5.88E+03 Xe-138 7.200E-01 2.12E+04 This activity was multiplied by 155.28, and multiplied by 10^-6 to convert from uCi to Ci, and mul ti Plied by gram ms RCS mass 1._892E8 .1-129 isotope is a Stable isotope. It will be dropPed f~rom -the m odel................................I The activities in the above table were entered into the GRODEC computer program (F-86-03 Ref.9) to convert the activity to specific energy groups which are used to estimate the detector response.

The volume of 5.66E1 0cc was used in GRODEC. Note: GRODEC was installed on a computer DELL SN#CYC7LS1 that was running Windows XP. To verify the program proper operation nine test cases were executed and output results were matched to the verification files listed on pages G1-G26 CALC F-86-03. The GRODEC input and output files can be found in GRODEC section of this calculation.

Containment volume: lff3 = 2.832 x 104 mL MathCAD internal converstion CC : lmL Volumnecontainment

= 2. 106.* if 3 Containment volume obtained from SM-97-1638-002 page A-8.Volumecontainment

= 5.66 x 101 cc The GRODEC results were entered into the EXCEL spread sheet below. The Dose Conversion Factors were obtained from SM-94-0466-001 page 32. A copy of these conversion factors is also attached to this calculation (reference Table 3 Etherington "Nuclear Engineering Handbook").

The geometric correction factor 768 was obtained from SM-94-0466-001 page 30.Dose Rate (/hr) = Source (MeV/cc-sec) x Geometric Factor + Dose Conversion Factor (MeV/cc-sec per I Rad/hr)Group Dose Cony GRDODEC FC EAL5 Energy Factor Source Dose Rate (MeV) (R/H per (MeV/cc- (R/h)Me V/cc- sec)sec)0.1 5.900E+05 1.358E+05 1.767E+02 0.3 5.540E+05 4.394E+04 6.091E+01 0.5 5.430E+05 1.621E+04 2.292E+01 0.7 5.490E+05 6.403E+04 8.957E+01 1 S.770E+05 5.842E+04 7.776E+01 1.5 6.270E+05 5.418E+04 6.637E+01 2 6.810E+05 5.294E+04 5.970E+01 2.5 7.350E+05 6.760E+04 7.063E+O1 3 7.890E+05 1.591E+i04 1.549E+01 Total Dose Rate (Rad/h) 640.06 Containment Barrier Potential Loss 3.A Containment radiation monitor RE-0027A&B (QI D21 RE0027A&B, Q2D21 RE0027A&B) can be read to one significant digit (page 15 of U264698), thus the value of 7,969R/hr is rounded off to 8,000R/hr (The revision 1 of this calculation had 3,000R/hr).

This rounding is acceptable because per RG1 .97 the instrument accuracy is expected to be within a factor of 2 or +/-50%.The range of this monitor is 1Ito R/hr (page 3-16 of Al181 015).NEI 99-01 Rev 6 pg 116 "The radiation monitor reading corresponds to an instantaneous release of all reactor coolant mass into the containment, assuming that 20% of the fuel cladding has failed. This level of fuel clad failure is well above that used to determine the analogous Fuel Clad Barrier Loss and RCS Barrier Loss thresholds.

NUREG-1228, Source Estimations During Incident Response to Severe Nuclear Power Plant Accidents, indicates the fuel clad failure must be greater than approximately 20%in order for there to be a major release of radioactivity requiring offsite protective actions. For this condition to exist, there must already have been a loss of the RCS Barrier and the Fuel Clad Barrier. It is therefore prudent to treat this condition as a potential loss of containment which would then escalate the emergency classification level to a General Emergency." A major release of radioactivity requiring offsite protective actions from core damage is not possible unless a major failure of fuel cladding allows radioactive material to be released from the core into the reactor coolant. Regardless of whether containment is challenged, this amount of activity in containment, if released could have such severe consequences that it is prudent to treat this as a potential loss of containment.

NUREG-1 228, "Source Estimations During Incident Response to Severe Nuclear Power Plant Accidents," indicates that such conditions do not exist when the amount of clad damage is less than 20%, which is the value used for this analysis.

The activity for isotopes can be found as follows: ActivitYisotope

= CoreInventoryisotope*

PowerDBAcorecton Release_Fraction

• MeltedFuel%

PowerDBAeoreto

= 102% =1.02 WCAP 14722 Table 7.6-1 Releaseaae 0 ion131 := 0.08 These release fractions come from RG1.195 Table 2.Reeseto Kr85 :=0.10 ReleasehactionOtherNobleGases

= 0.05 Releasefration_Othrlodines

= 0.05 MeltedFuel%

= 20% = 0.2 This value comes from NEI99-01 page 5-F15.The Core Inventory is listed in WCAP14722 Table 7.6-5. Per RG1 .195 Table 3 we only consider Xe, Kr, and Idoine isotopes.

Per RG1.195 page 12 and 13 section 3.2 and table 2: The core inventory release fractions for non-LOCA events where only cladding is breached, the release fractions in table 2 should be considered:

1-131 is 0.08, Kr-85 is 0.10, Other Noble Gases 0.05, Other Iodines 0.05. The power DBA correction factor is 1.02 (102%) per WCAP14722 Table 7.6-1 page 7.6-10. Per NUREG1301 DEl definition on page 6 the DEl is based on I-I131,1I-132,1I-133,1I-134, and I-135, so only these five Iodine isotopes were considered.

The following Excel Sheet is developed with the criteria listed above.

Isotope WCAP14722 PowerDBA T Release % failed CTMTEAL6 Table 7.6-5 Fraction fuel_______ ____________

RGi. 195 ____ _ _ _ _ ______ (ci) ______I_____

_____(ci)i..................

i..............

I I + I I 1-131 7.50E+07 1.02 0.08 0.2 1. 224E+06 1-132 1.10E+08 1.02 0.05 0.2 1.122E+06

....1-133 1.60E+08 1.02 0.05 0.2 1.632E+06__

1-134 1.70E+08 1.02 0.05 0.2 1.734E+I06 1-135 1.50E+08 1.02 0.05 0.2 1.530E+06 Kr-83m 9.70E+06 1.02 0.05 0.2 9.894E+04

_Kr-85 7.20E+05 1.02 0.10 0.2 1.469E+04 Kr-85m 2.10E+07 1.02 0.05 0.2 2.142E+05 Kr-87 4.00E+07 1.02 0.05 0.2 4.080E+05 Kr-88 5.70E+07 1.02 0.05 0.2 5.814E+05 Xe-131m 8.40E+05 1.02 0.05 0.2 8.568E+03

_Xe-133 1.50E+08 1.02 0.05 0.2 1.530E+06__

Xe-133m 4.80E+06 1.02 0.05 0.2 4.896E+04 Xe-135 3.50E+07 1.02 0.05 0.2 3.570E+05__

Xe-135m 3.00E+07 1.02 0.05 0.2 3.060E+05__

Xe-137 1.40E+08 1.02 0.05 0.2 1.428E+06__

Xe-138 1.300E+08 1.02 0.05 0.2 1.326E+i06 J i J f 1 i t!..........

.............

1. The activities in the above table were entered into the GRODEC computer program (F-86-03 Ref.9) to convert the activity to specific energy groups which are used to estimate the detector response.

The volume of 5.66E1 0cc was used in GRODEC. Note: GRODEC was installed on a computer DELL SN#CYC7LS1 that was running Windows XP. To verify the program proper operation nine test cases were executed and output results were matched to the verification files listed on pages G1-G26 CALC F-86-03. The GRODEC input and output files can be found in GRODEC section of this calculation.

Containment volume: ift3 2.832 x 104 mL MathCAD internal converstion cc :=lmL Volumecontaimet

=2. 106. ft 3 Containment volume obtained from SM-97-1638-002 page A-8.Volumecontainment

=5.66 x 101 cc The GRODEC results were entered into the EXCEL spread sheet below. The Dose Conversion Factors were obtained from SM-94-0466-001 page 32. A copy of these conversion factors is also attached to this calculation (reference Table 3 Etherington "Nuclear Engineering Handbook").The geometric correction factor of 768 was obtained from SM-94-0466-001 page 30.Dose Rate (R/hr) = Source (MeV/cc-sec) x (MeV/cc-sec per I Rad/hr).Group Dose Cony GRDODEC FC EAL5 Energy Factor Source Dose Rate (MeV) (R/hr per (MeV/cc- (R/hr)Me V/cc- sec)se C)0.1 5.900E+05 3.131E+04 4.076E+01 0.3 5.540E+05 1.424E+05 1.974E+02 0.5 5.430E+05 3.740E+i05 5.290E+02 0.7 5.490E+05 1.205E+06 1.685E+03 1 5.770E+05 1.417E+06 1.886E+03 1.5 6.270E+05 1.555E+'06 1.905E+03 2 6.810E+05 8.608E+05 9.707E+02 2.5 7.350E+05 5.353E+05 5.594E+02 3 7.890E+05 2.012E+05 1.959E+02 Total Dose Rate (Rad/h) 7.969E+03 Geometric Factor -Dose Conversion Factor RCS Barrier Potential Loss 3.A The containment radiation monitor RE-0002 (NI D21 RE0002, N2D21 RE0002) was calculated as 1.07 R/hr and can be conservatively down rounded to 1 R/hr (The revision 1 value for this monitor was 0.1 R/hr). Per A181015 page 3-5 the instrument range is 1E-4 to 1IE1 rads per hour.Or The containment radiation monitor RE-0007 (Ni D21 RE0007, N2D21 RE0007) was calculated as 0.54 R/hr and can be conservatively down rounded to 0.5 R/hr (The revision 1 value for this monitor was 0.2 R/hr). Per A181015 page 3-12 the instrument range is 1E-4 to 1E1 rads per hour.NEI 99-01 Rev 6 pg 111 "The reading should be determined assuming the instantaneous release and dispersal of the reactor coolant noble gas and iodine inventory, with RCS activity at Technical Specification allowable limits, into the containment atmosphere.

Using RCS activity at Technical Specification allowable limits aligns this threshold with IC SU3. Also, RCS activity at this level will typically result in containment radiation levels that can be more readily detected bycontainment radiation monitors, and more readily differentiated from those caused by piping or component "shine" sources. If desired, a, plant may use a lesser value of RCS activity for determining this value." This reading is calculated assuming the instantaneous release and dispersal of the reactor: coolant noble gas and iodine inventory associated with normal operating concentrations (i.e., within technical specification limits) into the containment atmosphere.

It is indicative of an RCS leak only without significant clad damage.Technical Specification 3.4.16 limits the RCS activity to 0.5 pCi/gm dose equivalent 1131.NUREG/CR-5106 pg E-19 ICRP Publication 30 (Ref 7) provides the inhalation dose conversion factor (REM/Ci) for 1-132. The rest of inhalation dose conversion factors for ICRP Publication 30 are listed in Faw Shultis "Radiological Assessment" Table G.6 in units of (Sv/Bq). The RCS design basis activity is listed on page 7.6-52 of WCAP14722 Table 7.6-6.Per NUREG1301 DEl definition on page 6 the DEl is based on 1-131, 1-132, 1-133, 1-134, and I-135, so only these five Iodine isotopes were considered.

The converstion factor of Sv/Bq to Rem/Ci is as follows: Ci :=3.7.1010

• Bq lLCi :=10- *.Ci_Sv REM:=-100 page 5 of Faw, Shultis "Radiological Assesment" page 14 of Faw, Shultis "Radiological Assesment" note 5.1*-Sv = .x112 REM Bq Ci MathCAD intemnal conversion The following excell worksheet was developed as follows: Activity Activity Factor" 'R---i Factor. = Factor- 3.7. 02

= Activity

• g* '0°(Relative Dose Conversion Weighted _____Activity Factor Factor Activity Factor Activity (R/gin)(uCi/gm) (R/Ci) (Sv/Bq) (Ci/gm) (R/Ci)WCAP14722 NUREG- Faw, Shultis Table 7.6-6 5106 Table G.6 1-131 1.400E+00 2.900E-07 1.400E-06 1.073E+06 1.502E+00 1-132 2.300E+00 6.300E+03

______2.300E-06 6.300E+03 1.449E-02 1-133 2.700E+00

_____ 4.900E-08 2.700E-06 1.813E+05 4.895E-01 1-134 6.300E-01

_____ 2.900E-10 6.300E-07 1.073E+03 6.760E-04 1-135 1.900E+00

_____ 8.500E-09 1.900E-06 3.145E+04 5.976E-02 SUM 2.07E+00 Ci :=3.7- 101 *Bq Ci 1 iCi := --6 DOSeDET := 2.07. 100 -gm Dose 1 1 3 1 :=1.50. 100.R gm Do s eDEL RatioDET to_1.131 :=. .1.38_ DOSel.1 3 1 MassRCS : 417219. lb =1.892 x 108 gm lib = 453.592 gm This statement defines the unit of Curies, since Becquerels are defined in MathCAD, while Cunes are not. Reference is page 102 of Shultis Fundamentals of Nuclear Science and Engineering.

The sum in table above generated this number.The dose was generated in the table above.The RCS mass was obtained from WCAP 15097 page 4.1-3 MathCAD internal conversion.

The iodine gas activity as compaired to WCAP 14722 is calculated below:-6 Ci Activityi.

1 3 1 :=1.4. 10 gm 0.5. ptCi RatlOiodines

.- g = 0.259 RatioDEl to 1.131 "ActivitYI.

1 3 1 The activity from WCAP14722 Table 7.6-6 was multiplied by 0.259, which was calculated above. The activity was also multiplied by 1 0^-6 for Ci/gm vs uCi/gm unit conversion and multiplied by 1 .892E8gm to account for RCS mass. The table was calculated for Iodines and Noble Gases.

Isotope IRCSEAL4 Activity (uCi/gm)WCAP14722 Conainen I + -. _______________________________

This activity was multiplied by 0.259, and multiplied by 10^-6 to convert from uCi to Ci, and multiplied by g~ramms of RCS mass 1.892E8 1 11-129 isotope is a stable isotope. It will be 1-129 2.70E-08j 1.32E-06f dropped from the model.1-130 2. 20E-02 1.08 E+00 1-131 1.400E+O0 6. 86E+01 1-132 2. 300E+00 1. 13E+02 1-133 2.700E+00 1.32E+02 1-134 6.300E-01 3.09E+01 1-135 1.900E+00 9.31E+01 Kr-83m 4.500E-01!

2.21E+01 Kr-85 7.700E+00' 3.77E+02 Kr-85m 1.800E+00 8.82E+01 Kr-87 1.200E+O0 5.88E+01 Kr-88 3.500E+00 1.72E+02 Kr-89 1.100E-O1 5.39E+00 Xe-131m 2.900E+00 1.42E+02 Xe-133 2.400E+02 1.18E+04 Xe- 133 m 4.600E+i00 2.25 E+02 Xe-135 7.900E+00 3.87E+02 Xe-135m 4.500E-01 2.21E+401 Xe-137 2.000E-01 9.80E+003 Xe-138 7.200E-01 3.53E+01.4 The activities in the above table were entered into the GRODEC computer program (F-86-03 Ref.9) to convert the activity to specific energy groups which are used to estimate the detector response.

The volume of 5.66E1 0cc was used in GRODEC. Note: GRODEC was installed on a computer DELL SN#CYC7LS1 that was running Windows XP. To verify the program proper operation nine test cases were executed and output results were matched to the verification files listed on pages G1-G26 CALC F-86-03. The GRODEC input and output files can be found in GRODEC'section of this calculation.

Containment volume: lff3 = 2.832 x 104mL, MathCAD internal converstion cc :=lmL Volumecontainment

=2. 106. -ft 3 Containment volume obtained from SM-97-1638-002 page A-8.Volumecontainment

=5.66 x 101 cc The GRODEC results were entered into the EXCEL spread sheet below. The GRODEC input and output file "RCSEAL4" are listed below. The Dose Conversion Factors were obtained from SM-94-0466-001 page 32. A copy of these conversion factors is also attached to this calculation (reference Table 3 Etherington "Nuclear Engineering Handbook").The geometric correction factor of 768 was obtained from SM-94-0466-001 page 30. The use of this geometric factor for R-2 radiation sensor is a good approximation because RE-0027 and RE-0002 are at the same height in the containment of 160'0" (D205148).

Dose Rate (R/hr) = Source (MeV/cc-sec) x Geometric Factor -Dose Conversion Factor (MeV/cc-sec per 1 Rad/hr).Group Dose GRDODE RCS EAL4 Energy Conv C Source Dose (MeV) Factor (MeV/cc- Rate (R/hr per sec) (R/hr)Me V/cc-se c) ____0.1 5.90E+05 2.27E+02 2.96E-O1 0.3 5.54E+05 7.33E+01 1.02E-01 0.5 5.43E+05 2.70E+01 3.82E-02 0.7 5.49E+05 1.07E+02 1.49E-01 1 5.77E+05 9.76E+01 1.30E-01 1.5i 6.27E+05 9.04E+01 1.11E-01 2 6.81E+05 8.84E+01 9.97E-O2 2.5 7.35E+05 1.13E+02 1.18E-0l 3 7.89E+05 2.65E+01 2.58E-02 Total Dose Rate (Rad/h) 1.07 RE-0007 is located near the seal table at elevation 133'-6" (Reference (D 175149 Zone C11).The containment volume visible to the monitor is shown on the following three sheets. This is modeled as a cylinder approximately 33' high with a radius of 31'. Using the methodology as described in Reference (SM-94-0466-001 page 26 -30) and is developed below.EL_RE00O7

=133.5

• ft ELplattnlnn=

137- ft The approximate elevation for RE-0007 is listed at 0175149 Zone B12.The platform elevation is listed in D205068 zone F5.hI = Lplffrm- ELRE0007 = 106.68 cm Height niodel "= 33

• ft The approximation assumption is 33feet. This approximation is shown on the folowing three sheets of this calculation.

h =Height model --h = 899.16ecm Rcontainment

"=6 5 *ft ..1 2 4 V 1 := -- Reontainment

• Height_model

=7.3.x 104 ft3 6 V 2:= 2.88"104 ft3 diameter is 65feet per 0176200., As shown on one of the three provided below markups, the pie section represents approximately six's of the presented volume.This volume was developed on the third marked up page. This page is provided below.R2 Volumecylinde

7E -R height Radius Heihtmoel

31.336ft S*Higt moe Calulating the cylinder equivalent radius that will be used for this model.-0.112 Radius--= 0.941 Radius Per table 6.4-3 page 382 of"Engineering Compendium on Radiation Shielding Vol. 1" the function (I) can be found. Liniar interpolation was also used.Linear Interpolation (X,-- x 1)(Y 3-- Yi)-0.112 Radius-___ 0.941 Radius 4)I (0.112 -0.1) -(1.34-- 1.68) +16 (0.2 -0.1)4)AI =1.64 (0.941 -0.4) -(0.628 4) A2 : 1.03)___+ 1.03 (1.0 -0.4)4 A2 =0.668 Equation 6.4-20 page 381 of"Engineering Cmpendium on Radiation Shielding:

h:=106.68cm h:=899.16cm Radius := 31.336ft 955.121 cm SV 4) .X -(h. 4 A1 + h. -)A2),)aaoo2 := --(h. ")A1 + h 2-4)A So 387.543 cm The viariable Sv was dropped out in this equiation line to calculate the ratio, and the Sv variable reinserted in the boxed equation.RE0007 = Sv .387.4 387.5 R R 4)RE0002 '= -- .1.07--- = 0.54-768 hr hr Thus the monitor R-7 response to the release is 387.5/768 times the R-2 monitor response, 0.54R/hr.

1.o~ ~.~ta*

W 1(.4*cOt.s1 fA ~A.Y7T~$ ~3

V~&N Ar ;. rVATION 129'-&'

a I* .I* i ----:* ... , E~:r:% 2'Y(ING '~5~

GRODEC FC_EAL_5 Input File 1 19 60,1 .32e+04,0 61 ,2.26e+05,0 62,5.29e+04,0 63,3.53e+I04,0 64,1 .03e+05,0 65,3.23e+03,0 1 40,6.46e+02,0 141,4.1 le+04,0 1 42,6.76e+04,0 1 43,7.93e+04,0 144,1 .85e+04,0 145,5.58e+04,0 1 46,8.52e+04,0 I147,7.05e+06,0 148,1 .35e+05,0 1 49,2.32e+05,0 150,1 .32e+04,0 151 ,5.88e+03,0 152,2.1 2e+04,0 FC_EAL_5.G_0 Output file OUTPUT OF GRODEC CALCULATION OPERATING IN MODE 1 DATA FILE NAME:FCEAL_5 INPUT DATA LISTING ISOTOPE INITIAL ADDITION ACTIVITY(CI)

RATE(CI/HR)-

KR-83M I1.320E+04 0.000E+00 KR-85 2.260E+05 0.000E+00 KR-85M 5.290E+04 0.000E+00 KR-87 3.530E+04 0.000E+00 KR-88 I1.030E+i05 0.000E+00 KR-89 3.230E+03 0.000E+00 I-130 6.460E+02 0.000E+00 1-131 1-132 1-133 1-134 1-135 XE-I131M XE-I133 XE-I133M XE-i135 XE-I135M XE-I137 XE-1 38 4.110OE+04 6.760E+'04 7.930E+04 1 .850E+04 5.580E+04 8.520E+04 7.050E+06 I1.350E+'05 2 .320E+05 I1.320E+04 5.880E+03 2.1 20E+04 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 WHAT ARE THE START, STOP, AND INTERVAL TIMES 1.00 1.00 1.00 TIME THIS INCREMENT

=1.000000 HOURS TOTAL ACTIVITY = 8144320.000000 CURIES ISOTOPE ISOTOPE NUMBER NAME INITIAL ACT(C I)ADDITION RATE(CI/HR)

ACTIVITY (CI)60 61 62 63 64 65 75 76 77 84 140 141 142 143 144 145 146 KR-83M KR-85 KR-85M KR-87 KR-88 KR-89 RB-87 RB-88 RB-89 SR-89 1-130 1-131 I-132 1-133 1-134 1-135 XE-131M 1 .320E+04 0.000E+00 9.094E+03 2.260E+05 0.000E+00 2.260E+05 5.290E+04 0.000E+00 4.519E+'04 3.530E+04 0.000E+00 2.043E+04 I1.030E+05 0.000E+00 8.042E+04 3.230E+03 0.000E+00 6.770E-03 0.000E+'00 0.000E+00 4.478E-11I 0.000E+00 0.000E+00 7.880E+'04 0.000E+00 0.000E+00 5.650E+-01 0.000E+00 0.000E+00 1 .238E-01 6.460E+02 0.000E+00 6.106E+02 4.110E+04 0.000E+00 4.095E+04 6.760E+04 0.000E+00 4.975E+04 7.930E+04 0.000E+00 7.664E+04 1.850E+04 0.000E+00 8.316E+03 5.580E+04 0.000E+00 5.030E+04 8.520E+04 0.000E+00 8.509E+04 147 XE-133 7.050E+06 0.000E+00 7.013E+06 148 XE-133M 1.350E+05 0.000E+00 1.333E+05 149 XE-135 2.320E+05 0.000E+00 2.193E+05 150 XE-135M 1.320E+04 0.000E+00 9.184E+02 151 XE-137 5.880E+03 0.000E+00 1.378E-01 152 XE-138 2.120E+04 0.000E+00 1.970E+03 161 CS-I135 0.000E+00 0.000E+00 5.946E-06 163 CS-137 0.000E+00 0.000E+'00 1.453E-03 164 CS-138 0.000E+00 0.000E+00 4.594E+03 171 BA-137M 0.000E+00 0.000E+00 1.453E-03 START OF MESS RUN ISOTOPES NOT INCLUDED IN MESS RUN NAME ACTIVITY (CI)RB-87 4.477765E-11I I-130 610.609700 CS-I135 5.945921 E-06 WHAT IS THE SOURCE VOLUME (CC)5.660000E+1 0 WHAT IS THE SOURCE DENSITY (GM/CC)1 .000000E-03 START EXECUTION OF THE MESS SUBROUTINE, ID NUMBERS ARE MESS ID NUMBERS,NOT MAIN PROGRAM IDS.THE NUMBER OF ENERGY GROUPS INPUT: 10 THE MAXIMUM ENERGY OF EACH GROUP: ENERGY MAXIMUM GROUP ENERGY 1 1 .000000E-01 2 3.000000E-01 3 5.000000E-01 4 7.000000E-01 5 1 .000000E+-00 6 1 .500000E+00 7 2.000000E+00 8 2.500000E+00 9 3.000000E+00 10 I.000000E+01 MESS INPUT DATA: SOURCE DENSITY (GM/CC) = 1.000000E-03 SOURCE VOLUME (CC) = 5.660000E+10 ISOTOPE ID NO.UC/GM SOURCE STRENGTH UC/CC CI KR 83M 45 KR 85 47 KR 85M 46 KR 87 48 KR 88 49 KR 89 50 KR 89 51 RB 88 67 RB 89 68 SR 89 21 1131 4 I132 5 I133 6 I134 7 I135 8 XEI131M 53 XE 133 54 XEI133M 55 XE 135 56 XEI137M 57 XE 137 58 XE 138 59 CS 137 35 CS 138 36 BAI137M 78 1 .606748E+0; 3.9929 10E+03 7.98431 8E+0;3.609242E+02 1 .420800E+03 1.196137 E-04 1 .196137 E-04 1 .392279E+03 9.981931 E-01 2.1 87626 E-03 7.235484E+02 8.789404E+02 1 .354038E+03 1 .469265E+02 8.8871 59E+02 1 .503393E+0 1 .238983E+05 2.354879E+0 3.873833E+03 1.622541 E+0 2.433959E-03 3.481 397E+01 2.567481 E-05 8.11 5789E+01 2.567368 2 1.606748E-01 3.992910OE+00 2 7.984319E-01 3.609242E-01 1 .420800E+00 1 .196137 E-07 1 .196137 E-07 1 .392279E+00 9.981 932E-04 2.187626 E-06 7.235484E-01 4 8.789405E-01 4 1.354038E+00 7 1 .469265E-01 8 8:887159E-01 5)3 1.503393E+00 1 .238983E+02

)3 2.354879E+00 3.873833E+00

)1 1.622541E-02 2.433959E-06 3.481397 E-02 2.567481 E-08 8.1 15789 E-02 5 2.567368E-08 9.0941 94E+03 2 .259987E+05 4.5191 24E+04 2.042831 E+04 8.04 1727E+04 6.770 134E-03 6.7701 34E-03 7.880300E+04 5.649773E+01 1.2381 97E-01.095284E+04

.974803E+04 T.663855E+04

.316039 E+03.0301 32E+04 8.509204E+04 7.01 2643E+06 1.332861 E+05 2.1 92590 E+05 9.1 83580E+02 1.377621 E-01 1.970471 E+03 1 .453194E-03 4.593537E+03 1.4531 30E-03 MESS OUTPUT DATA: ENERGY MAXIMUM SOURCE STRENGTH GROUP ENERGY (MEV/CC-SEC)(GAMMAS PER SEC)1 2 3 4 5 6 7 8 1 .000000E-01 3.000000E-01 5.000000E-01 7.000000E-01 1 .000000E+00 1 .500000E+00 2.000000E+00 2.500000E+00 1 .357539E+05 4.394020E+04 1 .620586E+04 6.402692E+04 5.842256E+04 5.41 8294E+04 5.2941 09E+04 6.759647E+04 7.683671 E+1 6 8.290051 E+15 1 .834504E+

15 5.1 77034 E+ 15 3.30671 7E+1 5 2.044503E+1 5 1 .498233E+

15 1 .530384E+

15 9 3.000000E+O0 1.591065E+04 3.001810E+14 10 1.000000E+O01 O.O00000E+O0 O.O00000E+O0 CTMTEAL6 Input File 1 17 60,9.894e+04,0 61,1 .469e+04,0 62,2.142e+05,0 63,4.080e+05,0 64,5.81 4e+05,0 141,1 .224e+I06,0 142,1 .122e+06,0 143,1 .632e+06,0 144,1 .734e+06,0 145,1 .530e+06,0 146,8.568E+03,0 147,1 .530e+06,0 148,4.896e+04,0 1 49,3.570e+05,0 I150,3.060e+i05,0 151,1 .428e+06,0 152,1 .326e+'06,0 CTMTEAL6 Output File OUTPUT OF GRODEC CALCULATION OPERATING IN MODE 1 DATA FILE NAME:CTMTEAL6 IN PUT DATA LISTING ISOTOPE INITIAL ADDITION ACTIVITY(Cl)

RATE(CI/HR)

KR-83M 9.894E+04 O.OOOE+OO KR-85 1 .469E+04 O.000E+OO KR-85M 2.142 E+05 0.000OE+OO KR-87 4.080E+05 O.OOOE+00 KR-88 5.814E+05 O.OOOE+OO I-131 1.224E+06 O.OO0E+OO I-132 1.122E+06 0.O00E+00 I-!133 1.632E+06 O.O00E+0O I-134 1 .734E+06 O.O00E+OO I-135 1 .530E+06 0.00OE+00O XE-131M 8.568 E+03 0.O00E+00 XE-133 1.530E+06 0.000E+00 XE-I133M 4.896E+04 0.000E+00 XE-I135 3.570E+05 0.000E+00 XE-I135M 3.060E+05 0.000E+00 XE-I137 1 .428E+06 0.000E+00 XE-138 1.326E+06 0.000E+00 WHAT ARE THE START, STOP, AND INTERVAL TIMES 1.00 1.00 1.00 TIME THIS INCREMENT

=1.000000 HOURS TOTAL ACTIVITY = 9649019.000000 CURIES ISOTOPE ISOTOPE NUMBER NAME INITIAL ADDITION ACT(CI) RATE(CI/HR)

ACTIVITY (Cl)60 61 62 63 64 75 76 141 142 143 144 145 146 147 148 149 150 151 152 161 163 164 171 KR-83M KR-85 KR-85M KR-87 KR-88 RB-87 RB-88 1-131 I-132 1-133 I-134 I-135 XE-131M XE-I133 XE-I133M XE-I135 XE-I135M XE-i137 XE-i138 CS-I135 CS-137 CS-I138 BA-I137M 9.894E+04 0.000E+00 6.817E+04 I1.469E+-04 0.000E+00 I1.469E+04 2.142E+05 0.000E+00 1.830E+05 4.080E+05 5.814E+05 0.000E+00 0.000E+00 1 .224E+06 1 .122E+06 I1.632E+06 1 .734E+06 I1.530E+06 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.361E+05 4.539E+05 5.175E-1 0 4.448E+05 I1.220E+06 8.257E+05 I1.577E+06 7.795E+05 I1.379E+06 8.568E+03 0.000E+00 1.153E+04 I1.530E+06 0.000E+00 1.531 E+06 4.896E+04 0.000E+00 4.834E+04 3.570E+05 0.000E+00 4.447E+05 3.060E+05 0.000E+00 2.129E+04 I1.428E+06 0.000E+00 3.346E+01 I1.326E+06 0.000E+00 I1.232E+05 0.000E+00 0.000E+00 I1.064E-05 0.000E+00 0.000E+00 3.529E-01 0.000E+00 0.000E+00 2.873E+05 0.000E+00 0.000E+00 3.529E-01 Southern Nuclear 0peratinl Cornpany SOUTHERNAAjL Plant: FNP SM-SNC524602-001I COMPANYt Unit: 1 &2 Title: NEI 99-01 EAL Calculations Attachment G START OF MESS RUN ISOTOPES NOT INCLUDED IN MESS RUN NAME RB-87 CS-I135 ACTIVITY (Cl)5.175433 E-10 1 .064398E-05 WHAT IS THE SOURCE VOLUME (CC)5.660000E+1-I0 WHAT IS THE SOURCE DENSITY (GM/CC)I1.000000E-03 START EXECUTION OF THE MESS SUBROUTINE, ID NUMBERS ARE MESS ID NUMBERS,NOT MAIN PROGRAM IDS.THE NUMBER OF ENERGY GROUPS INPUT: 10 THE MAXIMUM ENERGY OF EACH GROUP: ENERGY MAXIMUM GROUP ENERGY I 2 3 4 5 6 7 8 9 10 1 .000000E-01 3.000000E-01 5.000000E-01 7.000000E-01 I1.000000E+'00 I1.500000E+00 2.000000E+00 2.500000E+00 3.000000E+00 1 .000000E+01 MESS INPUT DATA: SOURCE DENSITY (GM/CC) = 1.000000E-03 SOURCE VOLUME (CC) = 5.660000E+-10 ISOTOPE ID NO.UC/GM KR 83M 45 1.20 KR 85 47 2.595 SOURCE STRENGTH UC/CC CI'4331 E+03 1.204331 E+00 6.816512E+04

$645E+02 2.595645E-01 1.4691 35E+04 KR 85M 46 KR 87 48 KR 88 49 RB 88 67 1131 4 I132 5 I133 6 I134 7 I135 8 XE 131M 53 XE 133 54 XEI133M 55 XE 135 56 XEI137M 57 XE 137 58 XE 138 59 CS 137 35 CS 138 36 BA 137M 78 3.232970E+03 3.232970E+00 1.829861 E+05 4.171 588 E+03 8.01 9932E+03 7.858942E+03 2.154801 E+04 1 .458833E+04 2.786620E+04 1.377138 E+04 2.436802E+04 2.037676E+O 2.704368E+04 8.540360E+O 7.856226E+03 3.761 344E+O 5.911 043E-01 2.177516E+03 6.235311 E-03 5.0761 96E+03 6.235037E-0:

4.171588 E+00 8.01 9933E+00 7.858943E+00 2.154801 E+01 1 .458833E+01 2.786621E+01 1.3771 38E+01 2.436802E+01

)2 2.037676E-01 I.2.704368E+01

'2 8.540360E-01

'2 3.761345E-01 5.91 1044 E-04 2.177516E+00 6.2353 12E-06 S5.076197E+00 3 6.235037E-06 2.36111 9E+05 4.539282E+05 4.4481 62E+05 1.219617E+06 8.256995E+05 1 .577227E+06 7.79460 1E+05 1 .379230E+06 1.1 53325E+04 I1.530672E+06 4.833844E+04 4.446624E+05 2.128921 E+04 3.345651 E+01 1 .232474E+05 3.5291 86E-01 2.8731 27E+05 3.529031 E-01 MESS OUTPUT DATA: ENERGY MAXIMUM GROUP ENERGY 1 1.000000E-01 2 3.000000E-01 1 3 5.000000E-01 ,C 4 7.000000E-01 I 5 1.000000E+00 6 1.500000E+00 7 2.000000E+00 8 2.500000E+00 9 3.000000E+00 10 1.000000E+01 SOURCE STRENC (MEV/CC-SEC)(GAMMAS PER SEC)3.131267E+04

!.424045E+05 3.740096E+05 1.204571 E+06 I1.41 691 6E+06 1 .555426E+06 8.607784E+05 5.353415E+05 2.0121 73E+05 0.000000E+00 1 .772297E+16 2.686697E+16 4.233789E+1 6 9.73981 8E+16 8.01 9742E+16 5.869141 E+16 2.436003E+1 6 1.21 201 3E+'16 3.796299E+1 5 0.000000E+00 RCSEAL4 Input File 1 19 60,2.21 e+01 ,0 61 ,3.77e+02,0 62,8.82e+01

,0 63,5.88e+01

,0 64,1 .72e+02,0 65,5.39e+00,0 140,1 .O8e+00,0 141 ,6.86e+01

,0 142,1 .13e+02,0 143,1 .32e+02,0 144,3.09e+01

,0 145,9.31e+01

,0 146, 1.42e+02,0 147, 1.18e+04,0 1 48,2.25e+02,0 1 49,3.87e+02,0 150,2.21 e+01 ,0 151 ,9.80e+00,0 1 52,3.53e+01

,0 RCSEAL4 Output File OUTPUT OF GRODEC CALCULATION OPERATING IN MODE DATA FILE NAME:RCSEAL4 1 INPUT DATA LISTING ISOTOPE INITIAL ADDITION ACTIVITY(CI)

RATE(CI/HR)

KR-83M 2.210E+01 0.000E+00 KR-85 3.770E+02 0.000E+00 KR-85M 8.820E+01 0.000E+00 KR-87 5.880E+01 0.000E+00 KR-88 1 .720E+02 0.000E+00 KR-89 5.390E+00 0.O00E+00 I-130 1.080E+00 0.000E+00 I-131 6.860E+01 0.OOE+00 1-132 1.130E+02 0.000E+00 I-133 1 .320E+02 0.000E+00 I-134 I-135 XE-i131M XE-I133 XE-i133M XE-1 35 XE-i135M XE-I137 XE-I138 3.090E+01 9.310OE+01 1 .420E+02 1.1 80E+04 2.250E+02 3.870E+02 2.210OE+01 9.800E+00 3.530E+01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 WHAT ARE THE START, STOP, AND INTERVAL TIMES 1.00 1.00 1.00 TIME THIS INCREMENT

=1.000000 HOURS TOTAL ACTIVITY = 13625.140000 CURIES ISOTOPE ISOTOPE NUMBER NAME INITIAL ACT(C I)ADDITION RATE(CI/HR)

ACTIVITY (CI)60 61 62 63 64 65 75 76 77 84 140 141 142 143 144 145 146 147 148 149 KR-83M KR-85 KR-85M KR-87 KR-88 KR-89 RB-87 RB-88 RB-89 SR-89 1-130 1-131 1-132 1-133 1-134 I-135 XE-131M XE-1 33 XE-I133M XE-I135 2.210OE+01 3.770E+02 8.820E+01 5.880E+01 1 .720E+02 5.390E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1 .080E+00 6.860E+01 1 .130E+02 1 .320E+02 3.090E+01 9.310OE+01 O.O00E+OC O.O00E+O0 O.O00E+OC O.O00E+O0 O.O00E+O0 0.O00E+O0 0.O00E+O0 0.OO0E+O0 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00]1.523E+01 3.770E+02]7.535E+01 3.403E+01 1 .343E+02 1 .1 30E-05 7.459E-1 4 1 .316E+02 9.428E-02 2.066E-04 1.021 E+00 6.835E+01 8.31 6E+01 1 .276E+02 1 .389E+01 8.393E+01 1 .420E+02 0.000E+00 1.41 8E+02 1.180E+04 0.000E+00 1.174E+04 2.250E+02 0.000E+00 2.221E+02 3.870E+02 0.000E+00 3.658E+02 150 XE-135M 2.210E+01 0.000E+00 1.538E+00 151 XE-I137 9.800E+00 0.000E+00 2.296E-04 152 XE-138 3.530E+01 0.000E+00 3.281E+00 161 CS-135 0.000E+00 0.000E+00 9.918E-09 163 CS-137 0.000E+00 0.000E+00 2.422E-06 164 CS-I138 0.000E+00 0.000E+00 7.649E+00 171 BA-I137M 0.000E+00 0.000E+00 2.422E-06 START OF MESS RUN ISOTOPES NOT INCLUDED IN MESS RUN NAME ACTIVITY (CI)RB-8"7 7.458713E-14 I-130 1.020834 CS-135 9.918468 E-09 WHAT IS THE SOURCE VOLUME (CC)5.660000E+1 0 WHAT IS THE SOURCE DENSITY (GM/CC)I1.000000E-03 START EXECUTION OF THE MESS SUBROUTINE, ID NUMBERS ARE MESS ID NUMBERS,NOT MAIN PROGRAM IDS.THE NUMBER OF ENERGY GROUPS INPUT: 10 THE MAXIMUM ENERGY OF EACH GROUP: ENERGY MAXIMUM GROUP ENERGY 1 1.000000E-01 2 3.000000E-01 3 5.000000E-01 4 "7.000000E-01 5 1.000000E+00 6 1.500000E+00 7 2.000000E+00 8 2.500000E+00 9 3.000000E+00 10 1.000000E+01 MESS INPUT DATA:

SOURCE DENSITY (GM/CC) = 1.000000E-03 SOURCE VOLUME (CC) = 5.660000E+10 ISOTOPE ID NO.UC/GM SOURCE STRENGTH UC/CC ,Cl KR 83M 45 KR 85 47 KR 85M 46 KR 87 48 KR 88 49 KR 89 50 KR 89 51 RB 88 67 RB 89 68 SR 89 21 1131 4 I132 5 1133 6 1134 7 I135 8 XE 131M 53 XE 133 54 XEI133M 55 XE 135 56 XE 137M 57 XE 137 58 XE 138 59 CS 137 35 CS 138 36 BAI137M 78 2.690086E-0' 6.660739E+0O 1 .331223E+O 6.01 1994E-01 2.372598E+00 1 .996030E-07 1 .996030E-07 2.32497 1 E+00 1 .665715E-03 3.650559E-06 1 .207675E+00 1 .469235E+00 2.253884E+00 2.454069E-01 1 .482786E+00 2.505659E+(2.073757E+0", 3.924798E+(6.46201 5E+0(2.71 6527E-0 4.056599E-06 5.796855E-02 4.2791 36E-08 1.351 355 E-01 4.278947E-0 1 2.690086E-04 p 6.660739E-03

'0 1.331223E-03 6.01 1995E-04 S2.372598E-03 1 .996030E-10 1 .996030E-10) 2.324971 E-03 1.66571 6E-06 3.650559E-09 1 .207675E-03 6 1 .469235E-03 8 2.253884E-03 1 2.454069E-04 1.1 .482786E-03 8 00 2.505659E-03 2 2.073757E-01

)0 3.924798E-03) 6.462015E-03

'2 2.716527E-05 4.056599E-09 S4.279136E-11 1.351 355E-04'8 4.278947E-11I 1 .522589E+01 3.769978E+02 7.534721 E+01 3.402789E+01 1 .342890E+02 I1.129753E-05 1 .129753E-05 1.31 5934E+02 9.427950E-02 2.0662 17E-04 1.835438E+01

.315868E+01

.275698E+02

.389003E+01

.392568E+'01 1 .418203E+02 1 .173746 E+04 2.221 436E+02 3.657500E+02 1 .537554E+00 2.296035E-04 3.281 020E+00 2.421991 E-06 7.648672E+00 2.421 884E-06 MESS OUTPUT DATA: ENERGY MAXIMUM SOURCE STRENGTH GROUP ENERGY (MEV/CC-SEC)(GAMMAS PER SEC)1 2 3 4 5 6 7 8 9 10 1 .000000E-01 3.000000E-01 5.000000E-01 7.000000E-01 I1.000000E+00 I1.500000E+00 2.000000E+00 2.500000E+00 3.000000E+00 1 .000000E+01 2.2721 89E+02 7.329755E+01 2.703011E+01 1 .068445E+02 9.759991 E+'01 9.042906E+01 8.837747E+01 I1.128665E+02 2.651 560E+I01 0.000000E+00 1 .286059E+14 1 .382880E+13 3.059809E+1 2 8.6391 37E+12 5.524155E+12 3.4121 90E+1 2 2.501 082E+1 2 2.555298E+1 2 5.002609E+11I 0.000000E+00

Southern Nuclear Operatin9 Cornpany,"

SOUTHE~RNA Plant: FNP TteNE990EACacliosAttachment G COMPANY' Unit: 1&2 TteNl901ELCcuain I SHEET G-42 , (... I/ NUCLEARl ENGINEERING HANDBOOK..

/J HAROLD ETHERtINGTON, Editor S!""Vice President Nuclear Producie--frc~o, Divis ion of ACfF Inusutries D)irector 2 Naval and Reactor Engineering Diviaione Argonnem National Laboratory

FIRST EDITION New York Toronto London McGRA.W-ItILL BOOK COMPANY, INO.1958 7-66 RADIATION RADIOLOGICAL PROTECTION

[SEC. 7 Table 3. Flux for Unit Tissue Dose*Eo. Photon flux ior Energy flux for photon energy, I rad/hr, I read/hr, Mev m-9 8ee-1 Mevf(re') (aeo)0.1 3O .90 X 10° 5.90 X 10'0.15 3.88 X t0' 3.82 X 10'0.20 2.91 X tO' 5.82 X 10'0.30 1.847 X 10' 3.54 X (0'0.40 1.357 X lO' 5.43 X (0'0.50 1.085 X 108 5.425 X 0.60 9.065 X 10' 5.44 X IC'0.90 6.98 X 10' 5.58 X 10'1,0 5.77 X I0' 5,77 X IC'1.25 4.77 X l10' 5.96 X JO'1.5 4.18 X I0' 5.27 X 10'2.0 3.4fi5 X tO' 6.6( X 10'3.0 2.63 X I1(1 7.89 X 10'4.0 2.10 >1 ID' 8.41 X 10'5.0 1.80 )( 1os 9.00 X 10'6.0 I.577 X I0' 9.46 X 108 8.0 1.2704X ID' 1.022X I0'10.0 1.067 X 1.067 X (0'* Ct'.ceitzt-.ot1 Croiii It'if, 4.where B,(pi) is the dose-rate build-uji f.ct~or chosen fromt Tab~les 4 and 5 for source energy B, per photon, material of shileldl, thniekeni:.

of shield 1,it, atcenuation coeitcient for source energy It, ond geometry isot~ropie or plane c~ollimated source--see below).For more conipli;ated source configurations it, is uneeessnry to integrate this expres-sion over the sources, sines doses from d iffercnt sources must, be radded to obtain total dose at a point.The build-up facotms in Tables 4 and 5 are ca~lculated on the. assumption that the dose is to be determined in air. They arc ade~quate for dose in t~issue, since the mass attenuat~ion cocfli<.ielt8 are very niearly tlhe s0m.fl~For convenience, Table 6 is given, which shows the number of curies of Go6° and Cs'" i'-ray sources whieh are adequately shielded in lead shields of different thicknesses.

1.33 Calculations of *{eating Due to y Rays. 'the rate of heatt deposition in the shield from scatte~red plus unscatltered y radlilt-io, at, a distance 1R from the source with t em or shield intervening is given by H(~t =1.02X I°(, ergs/(sec) (g)(5)where B 0 (t = energy ab~sorption build-up factor, elhosen for photon energy Bo, material, and umbe~cr of relaxation lengths in the shield pi (Table 7)// = energy ahsorption mass at, t, nuat~ion coefficient for the shield material, cm2/gni (from Table 2)1.4 Factors Affecting Calculational Method The use of the foregoing article and the accompanying tables is dependent upon the conditions of the problem. In most instances a judicious choice must be made with some compromise in accuracy.

The recommendations which follow are designed to give conservative estimates of dose rate with a minimum of complication.

More sophisticated approaches yielding more accurate results can be found in the references.

1.41 Choice of "Point Isotropic" (Table 4) or "Plane Collimated" (Table 5) Build-up Factors. If the source is embedded in or immediately adjacent to the shield, the"point isotropic" build-up factor is to be used (Fig. 3a). If a small (in linear extent)

SEc. 7-31 NUCLEAR RADIATION SHIELDING 7--115 Table 26. Physical Properties of Concretes Conm-at l..bn hik Expels- Specific Condoc-prieRupture" Ea.Ulhodhrn-son, heat, t~ivity, Diffu-, Conorete*

Lh/[t' Baga/ydi strengt~h, modulhs, modules--strength, age, %" in./(in.)

Bte/ Btu/(hr) ity jupsi psit (X l0-')t pst('I) (lb)('F) (I t){oF) fts/hr Cony. C15) 153 .-.5.0 4.960 630 4.6 ... 0.04! 5.5 0.23 1.50 0.042 Q (16) 154 9.0 8.870 1,005 5.9 900 0.012 P (16) 185 9.0 5,865 700 4.4 970 0.021 0 (17) 210 6.53 4,640 516 5.0 1,396 0.023 5.6 0.20 1.20 0.030 M (15) 226 5.!I 6,130 445 4.3 ... 0.029 10 0.157 0.884 0.025 L (15) 230 5.0 3.340 630 3.7 ... 0.029 10 0.146 0.867 0.026 K' (17) 224 7.0 5.780 684 4.3 1,423. 0.018 5.7 0.21 1.68 0.034 F (17) 273 6.55 3.180 406 5.4 1.266 0.013 5.9 0.18 2.75 0.056*Concrete composition is similar to that given in table of concrotes, except for K', which ha~s 46-lb limonite and 0.6-Lb fixed water per cubio loot. COny, is Grand Coulee concrete.

Placement method is given in Table 25. The liomonite used was from Michigan; the barite was from Nevada; specific gravity ofro agnetite was 4.4.t Strength ,values are for moist cured specimens, 28 dayo old.so~asce: H. 8. Davis, Ref. 33.Table 27. Concrete Shield Cost s Coat. dollars /yd5 ConceteType

_____________Total cost/lb.Concete ypecents Forms Conerete Ordiuiary struntural

.......................

45 25 1. 7 Ordinary .......................

Q 60 40 2.4 High density .................

Kor N 100 120 3.7 High density ..................

0 300 250 9.5 High deneity ..................

F 600 500 15.5 snvaca: H. S. Davia, _Nucieon~ce.

Ref. 33.REFERENCES

1. Faun, U.: Gamma-ray Attenuation, Nuc.Zeonic, 11(1): 8 (August, 1953); 11(2): 55 (September, 1953).2. Goldstein, H., and 3. E. Wilkins: "Calculations of the Penetration of Gamma Rays," NYO-8075, June 30, 1954 (available from the Office of Technical Services, Depart-ment of Commerce, Washington).

3. "Reactor Handbook," Vol. I., chap. 2.3, Technical Information Service, U.S. Atomic Energy Commission, 1955.4. Grodatein, Gladys White: "I Ray Attenuation Coefficients from 10 Key to 100 Mev," N~aU~. Bur. Ci'c. 583, April, 1957.5. Davisson, C. M., and R. D. Evans: Rena. Mod. Phyj., 24: 79 (1952).6. Nelms, A,: Graphs of the Compton Energy--Angle Relationship and the Kelei-Nishina Formula from 10 Key to 500 Mev, NaIL. Rur. ,Standards Cire. 542.7. Gamble. R. L,: "'Prompt Fission Gamma Rays from Uranium 235," Dissertation, University of Texas, Austin, Tex., June, 1955, 8a. Hollander, 3. M., I. Perlman, and G. T. Seaborg; Table of Isotopes, Revs. MPod. Phyao., 258: 469 (1953).b. Clark, F. H.: "Decay of Fission Product Gammas," NDA-27-39, Dec. 30, 1954.c. Moteff, John: "Fission Product Decay Gamma Energy Spectrum," APEX-134, June, 1953.d. Way, K4., et al. "Nuclear Data,"' NaIl. Hur. Stassdarda Circ. 499 and Supplements 1 and 2.e. Supplements and Nuclear Data Compilations in NSA.9, Rockwell, T. (ed.): "Reactor Shielding Design Manual," TID-7004, March, 1956.

SM-SNC524602-001 Attachment I ENERCON Calculation for E-HU1 SHEET I-2 CALC NO. SNC024-CALC-003

~jEN E R CON CALCULATION REV. 0 oy REVISION STATUS SHEET PAGE NO. 2 of 8 CALCULATION REVISION STATUS REVISION DATE DESCRIPTION 0 1010712015 Initial Submittal PAGE REVISION STATUS PAGE NO. REVISION PAGE NO. REVISION 1-8 0 APPENDIXIATTACHMENT REVISION STATUS APPENDIX NO. NO. OF REVISION ATTACHMENT NO. OF REVISION PAGES NO. NO. PAGES NO.

SM-SNC524602-001 Attachment I ENERCON Calculation for E-HU1 SHEET I-3 CALC NO. SNC024-CALC-003 IE NE R CON TABLE OF CONTENTS REV. 0 Excellence--Evey propecK Fv¢y PAGE NO. 3 of 8 Section 1.0 2.0 3.0 4.0 5.0 6.0 7.0 8.0 Purpose and Scope Summary of Results and Conclusions References Assumptions Design Inputs Methodology Calculations Computer Software Page No.4 4 5 5 6 7 8 8 SM-SN C524602-001 Attachment I SHEET I-4_________________

ENERCON Calculation for E-HU1 CALC NO. SNC024-CALC-003 FNP DETERMINATION OF -____________

EMERGENCY ACTION LEVEL REV. 0 SE N E R C 0 N FOR INITIATING CONDITION E-PAGE NO. Page 4of 8 1.0 Purpose and Scope The purpose of this calculation is to determine the emergency action level (EAL)thresholds for the initiating condition (IC) E-HU1, which is defined as damage to the confinement boundary of a storage cask containing spent fuel, as described in NEI 99-01 Rev. 6 [1]. The IC is defined as an "on-contact' radiation reading greater than two times the allowable dose readings as specified in the technical specifications listed in the cask's Certificate of Compliance (CoC). A dose rate reading greater than EAL threshold value indicates that there is degradation in the level of safety of the spent fuel cask.This calculation is performed under guidance from NEI 99-01 Rev. 6 [1], which describes development of a site-specific emergency classification scheme.2.0 Summary of Results and Conclusions The emergency action levels for initiating condition E-HU1 are calculated based on the HI-STORM 100 and HI-TRAC 125 cask system technical specification for spent fuel cask surface dose rates [2]. An elevated cask surface dose rate is indicative of degradation of the cask confinement barrier. The calculated elevated dose rates used as emergency action level thresholds are provided in Table 2-1.

SM-SNC524602-001 Attachment I IFNFRfln\I(3N iilIdtinn fnr F-HI-llI SHEET I-5 CALC NO. SNCO24-CALC-003 FNP DETERMINATION OF EMERGENCY ACTION LEVEL REV. 0~jE N E R C 0 N FOR INITIATING CONDITION E-..

ay. HU1I PAGE NO. Page 5 of 8 Table 2-1 Emergency Action Level Spent Fuel Cask Surface (Neutron + Gamma) Dose Rates for IC E-HU1 Location1 EA__________________________ (mrem/hr)HI-TRAC 125 _ ____Side -Mid -height 1 1360 Top J 260 HI-STORM 100 Side -60 inches below mid-height 340 Side -Mid -height 350 Side -60 inches above mid-height 170 Top -Center of lid 50 Top -Radially centered 60 Inlet duct 460 Outlet duct 160 3.0 References

1. NEI 99-01, Rev. 6, "Development of Emergency Action Levels for Non-Passive Reactors." Nuclear Energy Institute.

November 2012.2. FNP 10 CFR 72.212 Report. Docket Number 72-42, Version 12.4.0 Assumptions There are no assumptions made in this calculation.

SM-SNC0524602-001 Attachment I IFNI:PC'.fNI I.lrlIlllfinn far !:::_,I! II SHEET I-6 CALC NO. SNC024-CALC-003 FNP DETERMINATION OF EMERGENCY ACTION LEVEL REV. 0E N E R C 0 N FOR INITIATING CONDITION E-Eoy pwoJ.c,. £~ery,,o HUI1 PAGE N O. Page 6 of 8 5.0 Design Inputs 1. The contact dose rates from the HI-STORM 100 and HI-TRAC 125 cask system technical specification

[2, Table 6.2-3] are provided below in Table 5-1. These source values are scaled to develop the emergency action levels for initiating condition E-HU1.Table 5-1 Technical Specification Dose Rate Limits (Neutron + Gamma) for HI-STORM 100 and HI-TRAC 125 LoatonNumber of Technical Specification jMeasurements j Limit (mrem/hr)HI-TRAC 125 __________

Side -Mid -height 4 680.3 Top 4 ________129.4 HI-STORM 100 Side -60 inches below mid-height 4 171.8 Side -Mid -height 4 177.0 Side -60 inches above mid-height 4 84.7 Top -Center of lid 1 27.1 Top -Radially centered 4 30.0 Inlet duct 4 231.8 Outlet duct 4 82.2 SM-SNC524602-001 Attachment I

fnr II SHEET I-7 CALC NO. SNCO24-CALC-003 FNP DETERMINATION OF EMERGENCY ACTION LEVEL REV. 0 IIE N E R C 0 N FOR INITIATING CONDITION E-Ex e~ydj.0. HU1 PAGE NO. Page 7 of 8 6.0 Methodology The "on-contact" dose rates from the technical specification for the HI-STORM 100 and HI-TRAC 125 cask system are scaled by a factor of 2, as specified in NEI 99-01 Rev. 6[1], for use in initiating condition E-HU1.

SM-SNC524602-001 Attachment I ENERCON Calculation for E-HU1 SHEET I-8 CALC NO.SNC024-CALC-003 ENERCON FNP DETERMINATION OF EMERGENCY ACTION LEVEL FOR INITIATING CONDITION E-HU1 REV. 0 PAGE NO.Page 8 of 8 7.0 Calculations The dose rates in Table 5-1 are multiplied by 2 in order to calculate the EAL dose rate limits. These calculations are presented below in Table 7-1.Table 7-1 Dose Rate Scaling Calculations for EAL Limits (Neutron + Gamma)TTechnical LoainSpecification Scaling Calculated Value EAL LoainLimit Factor (mrem/hr) (mrem/hr)__________________________ (mrem/hr)

__ ___ __________

_______________ ______ _______ ______HI-TRAC 125 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _Side -Mid -height T 680.3 2 1360.6 J 1360 Top j 129.4 ] 2 258.8 J 260 Side -60 inches below mid-height Side -Mid -height Side -60 inches above mid-height Top -Center of lid Top -Radially centered Inlet duct Outlet duct 343.6 340 354 350 169.4 170 54.2 50 60 60 463.6 460 164.4 160 8.0 Computer Software Microsoft WORD 2013 is used in this calculation for basic multiplication.

SM-SNC524602-001 Attachment I ENFR(]fON (Th].lnultinn fnr F-H!!1 I SHEET I-9 CALC NO. SNCO24-CALC-003 CALCULATION PREPARATION REV. 0 F -i E NE R CON CHECKLIST NO. PagelIof 8 CHECKLIST ITEMS 1 YES NO N/A GENERAL REQUIREMENTS

1. If the calculation is being performed to a client procedure, is the procedure being used the latest revision?Client procedure is not used in this calculation.

ENERCON QA procedures used throughout this El El [project.2. Are the proper forms being used and are they the latest revision?

[] [ ] El 3. Have the appropriate client review forms/checklists been completed?T Clen roeur s o uedi ti clulton EECO A rceuesusdthoghuEti

__[][Cletproedueicotsdi.sclulto.EECNQ rcdre sdtruhu hsE 4. Are all pages properly identified with a calculation number, calculation revision and page number consistent with the requirements of the client's procedure?

Client procedure is not used in this calculation.

ENERCON QA procedures used throughiout thifs [] El [project.5. Is all information legible and reproducible?

[] ElE 6. Is the calculation presented in a logical and orderly manner?. [] El El 7. Is there an existing calculation that should be revised or voided?This calculation does not replace any ENERCON produced calculation.

Information generated El[][by this calculation will be used by SNC to update their Farley Nuclear Power Plant EAL report. l l _8. Is it possible to alter an existing calculation instead of preparing a new calculation for this situation?

No current ENERCON calculations exist that are similar to this calculation for addressing the El [] El SNC Farley EAL update.9. If an existing calculation is being used for design inputs, are the key design inputs, T assumptions and engineering judgments used in that calculation valid and do they [ ][apply to the calculation revision being performed.

SM-SNC524602-001 Attachment I IlkIIJC'C'lMl IPi4I I SHEET 1-10k.Jai~l,~LAII{A;LILjI I I..JI L----I CALC NO. SNC024-CALC-003 CALCULATION PREPARATION REV. 0 SEN E R CON CHECKLIST NO. Page 2of 8 No ENERCON design inputs or outputs are affected by this calculation.

This calculation will affect the Farley EAL evaluation.

12. Can the calculation logic, methodology and presentation be properly understood

[ ][without referring back to the originator for clarification?

OBJECTIVE AND SCOPE 13. Does the calculation provide a clear concise statement of the problem and objective of Ell the calculation?

[ ][14. Does the calculation provide a clear statement of quality classification?

[] El El 15. Is the reason for performing and the end use of the calculation understood?

[] El Li 16. Does the calculation provide the basis for information found in the plant's license basis?~The plant's license basis is not applied in this evaluation.

{] El El 17. If so, is this documented in the calculation?T The plant's license basis is not applied in this evaluation.

{] El El 18. Does the calculation provide the basis for information found in the plant's design basis documentation?

The plant's license basis is not applied in this evaluation.

[ ][19. If so, is this documented in the calculation?T The plant's license basis is not applied in this evaluation.

{] El El SM-SNC524602-001 SM-SN0524602-OO IAttachment I SETIi SHEET I-11___ __ __ __ ___ __ __ __ _ 'AI' J LsUI I,..i::IU

-!!.UII IUI! r--F--U CALC NO. SNCO24-CALC.-003 CALCULATION PREPARATION REV. 0 E ; E NE R CON CHECKLIST

<oy PAGE NO. Page 3of 8 CHECKLIST ITEMS 1 YES NO NIA 20. Does the calculation otherwise support information found in the plant's design basis documentation?

Calculation is applied in the development of the Farley Nuclear Power Plant EAL evaluation, LI LII [not the plant license basis.21. If so, is this documented in the calculation?

Calculation is applied in the development of the Farley Nuclear Power Plant EAL evaluation, [ ][not the plant license basis.22. Has the appropriate design or license basis documentation been revised, or has the change notice or change request documents being prepared for submittal?

Calculation is applied in the development of the Farley Nuclear Power Plant EAL evaluation, LI []I [not the plant license basis.DESIGN INPUTS 23. Are design inputs clearly identified?

[] [24. Are design inputs retrievable or have they been added as attachments?

I]Iu 1 []25. If Attachments are used as design inputs or assumptions are the Attachments traceable and verifiable?

Attachments are not included in this calculation.

LII 0][26. Are design inputs clearly distinguished from assumptions?

I ] [1010 DESIGN INPUTS (Continued)

27. Does the calculation rely on Attachments for design inputs or assumptions?

If yes, are the attachments properly referenced in the calculation?

Attachments are not included in this calculation.

0] [] 0 28. Are input sources (including industry codes and standards) appropriately selected and 00 are they consistent with the quality classification and objective of the calculation?

[ ][

SM-SNC524602-001 Attachment I ENERCON Calculation for E-l-SHEET 1-12 U1 CALC NO. SNC024-CALC-003 CALCULATION PREPARATION REV. 0 F E N ER CON CHECKLISTy PAGE NO. Page 4of 8 CHECKLIST ITEMVS' YES NO N/A 29. Are input sources (including industry codes and standards) consistent with the plant's design and license basis? [ ][30. If applicable, do design inputs adequately address actual plant conditions?

[ ][31. Are input values reasonable and correctly applied? El[][32. Are design input sources approved?

[ ][33. Does the calculation reference the latest revision of the design input source? [ ][34. Were all applicable plant operating modes considered?

[] El El ASSUMPTIONS

35. Are assumptions reasonable/appropriate to the objective?

[] El El 36. Is adequate justification/basis for all assumptions provided?

[ ][37. Are any engineering judgments used? El [] LI 38. Are engineering judgments clearly identified as such?No engineering judgments were applied in this evaluation.

LI [][39. If engineering judgments are utilized as design inputs, are they reasonable and can they be quantified or substantiated by reference to site or industry standards, engineering principles, physical laws or other appropriate criteria?

[ ][No engineering judgments were applied in this evaluation.

_METHODOLOGY

40. Is the methodology used in the calculation described or implied in the plant's licensing basis? [ ][

SM-SNC524602-001 Attachment I SHEET 1-13_________________

ENERCON Calculation for E-HU!CALC NO. SNCO24-CALC-003 CALCULATION PREPARATION REV. 0~~E N E RC(0N CHECKLIST NO. Page 5of 8 CHECKLIST ITEM~S 1 YES NO N/A 41. If the methodology used differs from that described in the plant's licensing basis, has the appropriate license document change notice been initiated?

Plant licensing basis was not affected by thjis evaluation.

LI LI []42. Is the methodology used consistent with the stated objective?

0] I 43. Is the methodology used appropriate when considering the quality classification of the 0 calculation and intended use of the results? [ ][BODY OF CALCULATION

44. Are equations used in the calculation consistent with recognized engineering practice 0] L [and the plant's design and license basis? ___45. Is there reasonable justification provided for the use of equations not in common use? T Equations applied in this evaluation are in common use in the industry.

{] LIL 0 46. Are the mathematical operations performed properly and documented in a logical 0 L fashion? [ ][47. Is the math performed correctly?

LI III[48. Have adjustment factors, uncertainties and empirical correlations used in the analysis z been correctly applied? [ ][49. Has proper consideration been given to results that may be overly sensitive to very small changes in input?Results generated by calculations performed in this evaluation are not significantly affected by LI LI 0]minor perturbations of variables.

SOFTWARE/COMPUTER CODES I__ __50. Are computer codes or software languages used in the preparation of the calculation?

Only basic functions and operations in Microsoft Word 2013 were applied in this calculation.

{ L LI 0]

SM-SNC524602-001 SM-SNC52602AttacHEETnt-I ENERCON Calculation for El-SHEET 1-14 LU1 CALCULATION PREPARATION REV.0 0E NE R CON CHECKLIST

£v,ry doy.PG O ae6o CHECKLIST ITEMS 1 YES NO N/A 51. Have the requirements of CSP 3.09 for use of computer codes or software languages, including verification of accuracy and applicability been met?.Only basic functions and operations in Microsoft Word 2013 were applied in this calculation.

El E0 SOFTWAREICOMPUTER CODES (Continued)

52. Are the codes properly identified along with source vendor, organization, and revision 0][][level?53. Is the computer code applicable for the analysis being performed?

El El 0]54. If applicable, does the computer model adequately consider actual plant conditions'?

El El 0]55. Are the inputs to the computer code clearly identified and consistent with the inputs and El El 0]assumptions documented in the calculation?

56. Is the computer output clearly identified?

Only basic functions and operations in Microsoft Word 2013 were applied in this calculation.

El El 0]57. Does the computer output clearly identify the appropriate units?Only basic functions and operations in Microsoft Word 2013 were applied in this calculation.

El El 0]58. Are the computer outputs reasonable when compared to the inputs and what was expected?Only basic functions and operations in Microsoft Word 2013 were applied in this calculation.

El l 0 59. Was the computer output reviewed for ERROR or WARNING messages that could invalidate the results?Only basic functions and operations in Microsoft Word 2013 were applied in this calculation.

l ll E T RESULTS AND CONCLUSIONS

60. Is adequate acceptance criteria specified?

This calculation provides results for the SNC Farley Nuclear Power Plant EAL evaluation.

No acceptance criteria required for this evaluation.

SM-SNC524602-001 Attachment I ENERCON Calculation for E-HU1 SHEETI1-15 CALC NO. SNC024-CALC-003 CALCULATION PREPARATION REV. 0 FIEN E R CON CHECKLISTE NO. Page 7of 8 CHECKLIST ITEM~S 1 YES NO N!A 61. Are the stated acceptance criteria consistent with the purpose of the calculation, and intended use?This calculation provides results for the SNC Farley Nuclear Power Plant EAL evaluation.

No El [] [acceptance criteria required for this evaluation.

62. Are the stated acceptance criteria consistent with the plants design basis, applicable licensing commitments and industry codes, and standards?

This calculation provides results for the SNC Farley Nuclear Power Plant EAL evaluation.

No El E] [acceptance criteria required for this evaluation.

63. Do the calculation results and conclusions meet the stated acceptance criteria?This calculation provides results for the SNC Farley Nuclear Power Plant EAL evaluation.

No acceptance criteria required for this evaluation.

64. Are the results represented in the proper units with an appropriate tolerance, if applicable?

[ ][65. Are the calculation results and conclusions reasonable when considered against the stated inputs and objectives?

[ ][66. Is sufficient conservatism applied to the outputs and conclusions?

El[][67. Do the calculation results and conclusions affect any other calculations?

No ENERCON calculations are affected by this evaluation.

Results are provided to SNC Farley [ ][Nuclear Power Plant for input into the Farley EAL evaluation.F1

68. If so, have the affected calculations been revised?No ENERCON calculations are affected by this evaluation.

Results are provided to SNC Farley [ ][Nuclear Power Plant for input into the Farley EAL evaluation.I Tl SM-SNC524602-001I Attachment I ENERCON Calculation for E-HUI SHEETI1-16 CALC NO. SNCO24-CALC-003 CALCULATION PREPARATION REV. 0EN E R CON CHECKLIST....

NO. Page 8of 8 CHECKLIST ITEMS 1 YES NO N/A 69. Does the calculation contain any conceptual, unconfirmed or open assumptions requiring later confirmation?

Calculation is based on design input and assumption data provided and used by client in their 10 El [] El CFR 72.2 12 Report. Parameters maintained for consistency.

70. If so, are they properly identified?

No open assumptions applied in this evaluation.

Assumptions have basis based on information El l provided by the client.DESIGN REVIEW 71. Have alternate calculation methods been used to verify calculation results? El[][Note: 1. Where required, provide clarificationfjustification for answers to the questions in the space provided below each question.

An explanation is required for any questions answered as "No' or "N/A".Originator:

/ v and Sign r Date SM-SN C524602-001I Attachment H ENERCON Calculation for RAI SHEET H-I"CALC NO. SNC024-CALC-001 E N ER C ON CALCULATION COVER Excelence--E ,yp oape E eiy day S H EET REV. 0 PAGE NO. I of 10 Title: Farley EALs RA1 Threshold to Address NEI Item Cover Sheet Items Yes No t Does this calculation contain any open assumptions, including preliminary

[] [information, that require confirmation? (If YES, identify the assumptions.)_________

2 Does this calculation serve as an "Alternate Calculation"? (If YES, identify the ][design verified calculation.)

____Design Verified Calculation No.__________

3 Does this calculation supersede an existing Calculation? (If YES, identify the El [design verified calculation.)

____Superseded Calculation No.__________

Scope of Revision: Initial Issue Revision Impact on Results: Initial Issue Study Calculation El Final Calculation

[]Safety-Related El Non-Safety-Related

[](Print Name and Sign)Originator:

David Hartmangruber

.4Date: I 23zO/I5/Design Reviewer Dominic Napolitano, Ph. D L/ _" Date: ~ , Approver:

Jay Maisler, CHiP# Digitally signed I Ia. J. M'aisler, CHPn~l... I,, I PunIl~ t'I

• f ;7" --,-..)'" ,-ounail~jmaisler@enercon.com, c=US 4/

16:45:56 -04'00' SM-SNC524602-001 Attachment H ENERCON Calculation for RA1 SHEET H-2 CALC NO. SNC024-CALC

-001 IIE N ER CO N CALCULATION0 Fxco, .....-Every project. &'ery day REVISION STATUS SHEET RV PAGE NO. 2 of 10 CALCULATION REVISION STATUS REVISION DATE DESCRIPTION 0 10/23/2015 Initial Issue PAGE REVISION STATUS PAGE NO. REVISION PAGE NO. REVISION 1-10 0 APPENDIX/ATTACHMENT REVISION STATUS APPENDIX NO. NO. OF REVISION ATTACHMENT NO. OF REVISION PAGES NO. NO. PAGES NO.

SM-SNC524602-001 Attachment H ENERCON Calculation for RA1 SHEET H-3 CALC NO. SNC024-CALC-001EN E RC ON TABLE OF CONTENTS REV. 0 Excellenc'--Every project. Frety doy/PAGE NO. 3 of 10 Section 1.0 Purpose and Scope.......................................................

2.0 Summary of Results and Conclusions

.....................................

3.0 References................................................................

4.0 Assumptions..............................................................

5.0 Design Inputs..............................................................

6.0 Methodology..............................................................

7.0 Calculations

..............................................................

8.0 Computer Software........................................................

9.0 Results and Conclusion

...................................................

Page No.4 5 6 6 7 8 8 9 10 SM-SNC524602-001 Attachment H SHEET H-4 ENERCON Calculation for RA1 CALC NO. SNC024-CALC-001 Farley EAL RA1 Threshold SEN E R CON to Address NEI 99-01 REV. 0Revision 6 PAGE NO. 4 ofl10 1.0 Purpose and Scope The purpose of this calculation is to calculate the Emergency Action Level (EAL)thresholds for the update of the RAI calculation in the Southern Nuclear (SNC) Design Calculation SM-96-1076-002 (Reference

1) in response to the changes made to the Initiating Condition (IC) AAI in Revision 6 of NEI 99-01 (Reference 2). Calculation RA1 is meant to address the IC AA1 (Section 4.1 of NEI 99-01 Revision 6 states "R may be used in lieu of A" for this recognition category provided the change is carried through for all the associated IC identifiers).

Revision 6 of NEI 99-01 IC AAI identifies an EAL threshold for a release of gaseous or liquid radioactivity resulting in an offsite dose to a member of the public greater than 10 mrem Total Effective Dose Equivalent (TEDE) or 50 mrem thyroid Committed Dose Equivalent (CDE). IC AA1 is applicable to all operating modes and there are 4 EALs outlined in NEI 99-01 for IC AAI.1. Reading of site specific radiation monitors greater than threshold values that would generate a dose rate greater than the dose criterion established in IC AA1 in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. Reading must be shown for 15 minutes or longer.2. Dose assessment using actual meteorology indicates doses greater than 10 mrem Total Effective Dose Equivalent (TEDE) or 50 mrem thyroid Committed Dose Equivalent (CDE) at or beyond site boundary 3. Analysis of a liquid effluent sample indicates a concentration or release rate that would result in doses greater than 10 mrem TEDE or 50 mrem thyroid CDE at or beyond site boundary for one hour of exposure.4. Field survey results indicate either of the following at or beyond site boundary.

A closed window dose rate greater than 10 mR/hr expected to continue for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or longer an analyses of field survey samples indicates a thyroid CDE greater than 50 mrem for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> of inhalation.

SM-SNC524602-001 Attachment H ENERCON Calculation for RA1 SHEET H-5 CALC NO. SNC024-CALC-001 Farley EAL RA1 Threshold jE N ER C ON to Address NEI 99-01 REV. 0...

Revision 6 PAGE NO. 5 ofl10 The scope of this calculation is to determine site specific instrument readings for the RAl EAL 1 threshold.

The IC RA1 EAL 2, 3, and 4 are not evaluated in this calculation.

The quality rating of this calculation is non-safety related due to results only being used to generate a revised set of EALs for submission by the Farley nuclear power plant (FNP).2.0 Summary of Results and Conclusions The instrument readings that indicate an EAL threshold value has been reached for IC RAl are calculated in this calculation.

IC RAI is the release of gaseous or liquid radioactivity resulting in offsite dose to a member of the public greater than 10 mrem TEDE or 50 mrem thyroid ODE.The RA1 EAL 1 is the valid reading on one or more of the following radiation monitors that exceeds or is expected to exceed the reading shown in Table 2-1.Table 2-1 Radiation Monitor RA1 EAL Threshold Values

' '"Monitor Reading RE0015C Steam Jet Air Ejector (SJAE) 1.3 R/hr RE0029B Plant Vent Stack 0.008 pCi/cm 3 RE0060A/B/C S/G Atmospheric Relief Valves 0.005 R/hr (ARVs) & Safety Relief Valves (SRVs)RE0060D Turbine Driven Auxiliary 0.11 R/hr Feedwater Pump (TDAFW)Turbine Exhaust SM-SNC524602-001 Attachment H SHEET H-6___________________

ENERCON Calculation for RA1 ________CALC NO. SNC024-CALC-OO1 Farley EAL RAI Threshold 0 EN E R CON to Address NEI 99-01 REV. 0.... E e ro y Revision 6 PAGE NO. 6 ofl10 3.0 References

1. SM-96-1 076-002 Rev 5, NEI 99-01 EAL Calculations, Southern Company, September 25 2015.2. NEI 99-01 Rev 6, Development of Emergency Action Levels for Non-Passive Reactors, November 2012, Nuclear Energy Institute.

4.0 Assumptions

Based on the analysis of the methodology of Reference 1, the following assumption is consistent with the previously performed calculations, but were not included in the listed assumptions of Reference 1.4.1 Perfect Monitor Response This assumption is also applied to be consistent with the calculations performed in Attachment E of Reference

1. It is assumed in this calculation that the monitors at the end of each pathwaY are not energy dependent or that the monitor response accounts for the relative energy spectrum associated with the thresholds determined in this calculation based on the expected proportion of each isotope in the overall concentration.

This is a simplifying assumption applied due to the limited information provided about the monitoring equipment.

SM-SNC524602-001 Attachment H ENERCON Calculation for RA1 SHEET H-7 CALC NO. SNC024-CALC-001 Farley EAL RA1 Threshold~jE NE R CON to Address NEI 99-01 REV. 0 Fler-ce-Eer pr.

t eery day Revision 6 PAGE NO. 7 of 10 5.0 Design Inputs 5.1 FarleylIndication and RS1 EAL 1 Thresholds SM-96-1076-002 (Reference

1) addresses the IC RS1, which is based on the release of gaseous radioactivity resulting in offsite dose to a member of the public greater than 100 mrem TEDE or 500 mrem thyroid CDE. SM-96-1076-002 evaluates four release pathways and determines the monitor readings that would indicate an EAL threshold value has been reached for IC RS1. The monitor readings that would indicate an EAL threshold value for IC RS1 are provided in Table 5-1.The indicating ranges for the radiation monitors are also provided in Table 5-1 and the ranges are based on Design Input I on Sheet 27 of Reference

1. These values are used to calculate the IC RAI EAL threshold values.Table 5-1 Radiation Monitor RS1 EAL Threshold Values Monitor Vent Path ,,o..

Reading ,Indicating RE0015C Steam Jet Air Ejector (SJAE) 13 R/hr 10- o 102 R/hr RE0029B Plant Vent Stack 0.08 pCi/cm 3 10-7 to 10 5 pCi/cm 3 RE0060A/B/C SIG Atmospheric Relief 0.05 R/hr 10-5 to~ 10 hr Valves (AR\Is) & Safety Relief Valves (SR\Is)RE0060D Turbine Driven Auxiliary 1.1 R/hr 10-5 to R0Phr Feedwater Pump (TDAFWV)Turbine Exhaust SM-SNC524602-001 Attachment H SHEET H-8___________________

ENERCON Calculation for RA1 ________CALC NO. SNC024-CALC-001 Farley EAL RA1 Threshold SEN ER C ON to Address NEI 99-01 REV. 0 en e ono. Revision 6 PAGE NO. 8 oflO0 6.0 Methodology In the SM-96-1076-002 (Reference

1) RSI evaluation, EAL 1 thresholds were set based on readings of radiation monitoring equipment for several effluent pathways.

The thresholds are shown in Table 5-1 of this calculation.

The calculations for dose rate estimates is linear, therefore the RSI readings are scaled down by a factor of 10 (multiple of 0.1) for the RA1 evaluation performed in this calculation resulting in EAL I threshold values reflecting an offsite dose to a member of the public greater than 10 mrem Total Effective Dose Equivalent (TEDE) or 50 mrem thyroid Committed Dose Equivalent (ODE). The calculation of the RA1 EAL I threshold values is provided in Section 7.0.7.0 Calculations As discussed in Section 6.0, the values provided in Table 5-1 are multiplied by a scaling factor of 0.1 for the RA1 EAL I thresholds.

The resultant threshold values for RA1 EAL 1 are shown in Table 7-1. All threshold values are within the indicating range of the radiation monitors.

SM-SN C524602-001 Attachment H ENERCON Calculation for RA1 SHEET H-9 CALC NO. SNC024-CALC-001 Farley EAL RA1 Threshold IEN ER C ON to Address NEI 99-01 REV. 0 Exo,...

Revision 6 PAGE NO. 9 ofl10 Table 7-1 Radiation Monitor RA1 Threshold Values Radiation

i'"Vent Path ".. ,Scaled' Resuiltant Indicating...

Monitor" ,........ o ,Factor Monitor Range ,... .. , : ...... .. ..... " .. .R eading :,, .. .o .. .. , ,R eading .. ... '. .. " RE0O15C Steam Jet Air Ejector 13 R/hr 0.1 1.3 R/hr 10-5 to 10 2 R/hr (SJAE)RE0029B Plant Vent Stack 0.08 pCi/cm 3 0.1 0.008 pCi/cm 3 10 toi0 5 pCi/cm 3 RE0060AIB/C SIG Atmospheric 0.05 R/hr 0.1 0.005 Rfhr 10 to 10 R/hr Relief Valves (ARVs)& Safety Relief Valves (SRVs)RE00600 Turbine Driven 1.1 R/hr 0.1 0.11 Rfhr 10-5 to 103 R/hr Auxiliary Feedwater Pump (TDAFW)Turbine Exhaust 8.0 Computer Software No computer software was used in the creation of this calculation.

SM-SNC524602-001 Attachment H ENERCON Calculation for RA1 SHEET H-10 CALC NO. SNC024-CALC-001 Farley EAL RAI Threshold F,'I: EN E R CON to Address NEI 99-01 REV. 0

£E'ey doa Revision 6 PAGE NO. 10 ofl10 9.0 Results and Conclusion The purpose of this calculation is to calculate the EAL thresholds for the RAl calculation in the SNC Design Calculation SM-96-1076-002 (Reference

1) for the Farley nuclear power plant for use in development of an EAL submittal based on NEI 99-01 Revision 6.Table 2-1 contains the threshold values associated with the RAl EAL 1. These values will be applied to the FNP Emergency Action Level Scheme developed using the guidance of NEI 99-01 Revision 6.

SM-SNC524602-001 Attachment H ENERCON Calculation for RAl SHEET H-Il CALCULATION PREPARATION REV.0 CHECKLIST ITEMS 1 YES NO NIA GENERAL REQUIREMENTS

1. If the calculation is being performed to a client procedure, is the procedure being used the latest revision?Client procedure is not used in this calculation.

ENERCON QA procedures used thi'oughout LI El 0]3. Have the appropriate client review forms/checklists been completed?

Client procedure is not used in this calculation.

ENERCON QA procedures used throughout

[] iii [this project.4. Are all pages properly identified with a calculation number, calculation revision and page number consistent with the requirements of the client's procedure?

Client procedure is not used in this calculation.

ENERCON QA procedures used throughout EJ LI 0]this project.5. Is all information legible and reproducible?

0] []i 6. Is the calculation presented in a logical and orderly manner? 0] LI LI 7. Is there an existing calculation that should be revised or voided?This calculation does not replace any ENERCON produced calculation.

Information generated

[] 0][by this calculation will be used by SNC to update their Farley Nuclear Power Plant EAL report. _ _ _8. Is it possible to alter an existing calculation instead of preparing a new calculation for this situation?

No current ENERCON calculations exist that are similar to this calculation for addressing the LI 0] LI SNC Farley EAL update.9. If an existing calculation is being used for design inputs, are the key design inputs, 1 assumptions and engineering judgments used in that calculation valid and do they 101 ] [apply to the calculation revision being performed.____________

SM-SNC524602-001 Attachment H SHEET H-12___________________

ENERCON Calculation for RA1 CALC NO. SNCO24-CALC-OO1 CALCULATION PREPARATION REV. 0 SE NE R CON CHECKLIST...

E NO. Page 2 of 8 CHECKLIST

'TEIMS 1 YES NO I NIA 10. Is the format of the calculation consistent with applicabl e procedures and expectations 9 I[ -i} [11. Were design input/output documents properly updated to reference this calculation?

No ENERCON design inputs or outputs are affected by this calculation.

This calculation will affect the Farley EAL evaluation.

12. Can the calculation logic, methodology and presentation be properly understood without referring back to the originator for clarification?

______ _____OBJECTIVE AND SCOPE 13. Does the calculation provide a clear concise statement of the problem and objective of Lii the calculation?

[ ][14. Does the calculation provide a clear statement of quality classification?

[] Li Li 15. Is the reason for per-forrning and the end use of the calculation understood?

[] EJ Li 16. Does the calculation provide the basis for information found in the plant's license basis?The plant's license basis is not applied in this evaluation.

Li [] [17. If so, is this documented in the calculation?

The plant's license basis is not applied in this evaluation.

Li Li [18. Does the calculation provide the basis for information found in the plant's design basis documentation?

The plant's license basis is not applied in this evaluation.

[ ][19. If so, is this documented in the calculation?

The plant's license basis is not applied in this evaluation.

Li [] [

SM-SNC524602-001 Attachment H ENERCON Calculation for RA1 SHEET H-13 CALC NO. SNC024-CALC-001 CALCULATION PREPARATION REV. 0~:E N E RC ON CHECKLISTE NO. Page 3 of 8 CHECKLIST ITEMS 1 YES NO N/A 20. Does the calculation otherwise support information found in the plant's design basis documentation?

Calculation is applied in the development of the Farley nuclear power plant EAL evaluation, LI L] [not the plant license basis.21. If so, is this documented in the calculation?

Calculation is applied in the development of the Farley nuclear power plant EAL evaluation, [ ][not the plant license basis.22. Has the appropriate design or license basis documentation been revised, or has the change notice or change request documents being prepared for submittal?

Calculation is applied in the development of the Farley nuclear power plant EAL evaluation, [] [] [not the plant license basis.DESIGN INPUTS 23. Are design inputs clearly identified?

[ ][24. Are design inputs retrievable or have they been added as attachments?

t]L u I iii 25. If Attachments are used as design inputs or assumptions are the Attachments traceable and verifiable?

Attachments are not included in this calculation.

"] III [26. Are design inputs clearly distinguished from assumptions?

[ ][27. Does the calculation rely on Attachments for design inputs or assumptions?

If yes, are the attachments properly referenced in the calculation?

Attachments are not included in this calculation.

1] [ ]28. Are input sources (including industry codes and standards) appropriately selected and I L are they consistent with the quality classification and objective of the calculation?

[ ][29. Are input sources (including industry codes and standards) consistent with the plant's LI[][design and license basis?

SM-SNC524602-001 Attachment H ENERCON Calculation for RA1 SHEET H-14 CALC NO. SNC024-CALC-001 CALCULATION PREPARATION REV. 0~jE N ER CON CHECKLIST...

NO. Page 4 of 8 CHECKLIST ITEMVS 1 YES NO NIA 30. If applicable, do design inputs adequately address actual plant conditions?

] [31. Are input values reasonable and correctly applied? [] LI I [32. Are design input sources approved?

[] L] I 33. Does the calculation reference the latest revision of the design input source? 0] ii ii 34. Were all applicable plant operating modes considered?

] Li LI ASSUMPTIONS

35. Are assumptions reasonable/appropriate to the objective?

0] LI El 36. Is adequate justification/basis for all assumptions provided?

0] L]I izi 37. Are any engineering judgments used? [] 0 Ii 38. Are engineering judgments clearly identified as such?No engineering judgments were applied in this evaluation.

Li [][39. If engineering judgments are utilized as design inputs, are they reasonable and can they be quantified or substantiated by reference to site or industry standards, engineering principles, physical laws or other appropriate criteria?

[ ][No engineering judgments were applied in tris evaluation.

METHODOLOGY

40. Is the methodology used in the calculation described or implied in the plant's licensing 0 L 41. If the methodology used differs from that described in the plant's licensing basis, has the appropriate license document change notice been initiated?

Plant licensing basis was not affected by this evaluation.

LI [][

SM-SNC524602-001I Attachment H ENERCON Calculation for RA1 SHEET H-15 CALC NO. SNC024-CALC-001 CALCULATION PREPARATION REV. 0 jE N E R CON CHECKLIST....

NO. Page 5 of 8 CHECKLIST ITEMS 1 YES NO N/A 42. Is the methodology used consistent with the stated objective?

[ ][43. Is the methodology used appropriate when considering the quality classification of the I~I mm calculation and intended use of the results? j] J' J BODY OF CALCULATION

44. Are equations used in the calculation consistent with recognized engineering practice LI [] [and the plant's design and license basis? ___45. Is there reasonable justification provided for the use of equations not in common use?Equations applied mn this evaluation are in common use mn the industry.

LI LI [46. Are the mathematical operations performed properly and documented in a logical [] ] I [fashion?I 47. Is the math performed correctly?.

] I L-i I [48. Havebe corcladjustmentaplidfactors, uncertainties and empirical correlations used in the analysis [] ] I [49. Has proper consideration been given to results that may be overly sensitive to very small changes in input?Results generated by calculations performed in this evaluation are not significantly affected by LI LI [minor perturbations of variables.

SOFTWARE/COMPUTER CODES ___50. Are computer codes or software languages used in the preparation of the calculation?

-I___No software languages or codes were used in the development of this calculation.

LI [] LI including verification of accuracy and applicability been met?I No software languages or codes were used in the development of this calculation.I SM-.SNC524602-001 Attachment H ENERCON Calculation for RA1 SHEET H-16 CALC NO. SNC024-CALC-0O1 CALCULATION PREPARATION REV. 0 SE NE R CON CHECKLISTE NO. Page 6 of B CHECKLIST ITEMS 1 YES NO NIA SOF'IWAREICOMPUTER CODES (Continued)

52. Are the codes properly identified along with source vendor, organization, and revision level?No software languages or codes were used in the development of this calculation.

~L 53. Is the computer code applicable for the analysis being performed?T No software languages or codes were used in the development of this calculation.

El {] LI 54. If applicable, does the computer model adequately consider actual plant conditions?

No software languages or codes were used in the development of this calculation.

[] Li 0 55. Are the inputs to the computer code clearly identified and consistent with the inputs and assumptions documented in the calculation?

No software languages or codes were used in the development of this calculation.

{ ] [j []56. Is the computer output clearly identified?

No software languages or codes were used in the development of this calculation.

0][][57. Does the computer output clearly identify the appropriate units?No software languages or codes were used in the development of this calculation.

I] Li 0]58. Are the computer outputs reasonable when compared to the inputs and what was expected?Li}Li0[No software languages or codes were used in the development of this calculation.

59. Was the computer output reviewed for ERROR or WARNING messages that could invalidate the results?No software languages or codes were used in the development of this calculation.Li i 0 I .

SM-SNC524602-001 Attachment H ENERCON Calculation for RA1 SHEET H-17 CALC NO. SNC024-CALC-001 CALCULATION PREPARATION REV. 0 SEN E R CON CHECKLIST

£v'ey, da PAGE NO. Page 7 of 8 CHECKLIST ITEMS 1 YES NO N/A RESULTS AND CONCLUSIO NS 60. Is adequate acceptance criteria specified?

This calculation provides results for the SNC Farley nuclear power plant EAL evaluation.

No acceptance criteria required for this evaluation.

61. Are the stated acceptance criteria consistent with the purpose of the calculation, and intended use?This calculation provides results for the SNC Farley nuclear power plant EAL evaluation.

No El El 0]acceptance criteria required for thifs evaluation.

62. Are the stated acceptance criteria consistent with the plant's design basis, applicable licensing commitments and industry codes, and standards?

This calculation provides results for the SNC Farley nuclear power plant EAL evaluation.

No El El 0]acceptance criteria required for this evaluation.

63. Do the calculation results and conclusions meet the stated acceptance criteria?This calculation provides results for the SNC Farley nuclear power plant EAL evaluation.

No ~ E acceptance criteria required for this evaluation.

64. Are the results represented in the proper units with an appropriate tolerance, if 0 l E applicable?

[ ][65. Are the calculation results and conclusions reasonable when considered against the 0 Ell stated inputs and objectives?

[ ][66. Is sufficient conservatism applied to the outputs and conclusions?

] El El 67. Do the calculation results and conclusions affect any other calculations?

No ENERCON calculations are affected by this evaluation.

Results are provided to SNC El l 0 Parley nuclear power plant for input into the Parley EAL evaluation.

68. If so, have the affected calculations been revised?No ENERCON calculations are affected by this evaluation.

Results are provided to SNC El l 0 Parley nuclear power plant for input into the Farley EAL evaluation.

SM-SNC524602-001 Attachment H ENERCON Calculation for RA1 SHEET H-18 CALC NO. SNC024-CALC-001 CALCULATION PREPARATION REV. 0 SEN E R CON CHECKLIST&c0,0lc-n 0,e Eve0i eay. dyPAGE NO. Page 8of 8 69. Does the calculation contain any conceptual, unconfirmed or open assumptions requiring later confirmation.?

Calculation is based on design input and assumption data provided and used by client in their El [] El ODCM and current EAL evaluation.

Parameters maintained for consistency.

70. If so, are they properly identified?T No open assumptions applied in this evaluation.

Assumptions have basis based on information El El 10 provided by the client.DESIGN REVIEW 71. Have alternate calculation methods been used to verify calculation results? t] []T []Note: 1. Where required, provide clarificationljustification for answers to the questions in the space provided below each question.

An explanation is required for any questions answered as 'No' or "NIA°.Originator:

David Hartmangruber Print Name and Sign Date SM-SNC524602-001I Attachment I ENERCON Calculation for E-HU1 SHEET I-1 CALC NO.SNCO24-CALC-003 FJENERCON gxceI~ence--Every project, Eoerydoy.CALCULATION COVER SHEET REV. 0 PAGE NO.1 of 8 Til:Level for Initiating Condition E-HU1 rjc dntfe:5C2 Item Cover Sheet Items Yes No 1 Does this calculation contain any open assumptions, including preliminary D][information, that require confirmation? (If YES, identify the assumptions.)

2 Does this calculation serve as an "Alternate Calculation"? (If YES, identify the design [][verified calculation.)

Design Verified Calculation No. __________

3 Does this calculation supersede an existing Calculation? (If YES, identify the design []" [verified calculation.)

____Superseded Calculation No. __________

Scope of Revision: Initial Issue Revision Impact on Results: Initial Issue Study Calculation Final Calculation IX Safety-Related

[] Non-Safety-Related (Print Name and Sign)J Originator:

Andrew Blackwell Date: toU2LS Design Reviewer:

Curt Lindner Date: -i/is.Date: 10/9/2015 Approver:

Jay Maisler, CliP SM-SNC524602-001 ATCMN 2SET0-ATTACHMENT C2 SHEET C2-5 CRTD-Vol.

58 ASME INTERNATIONAL STEAM TABLES FOR INDUSTRIAL USE Second Edition Based on the IAPWS Industrial Formulation 1997 for the Thermodynamic Properties of Water and Steam (IAPWS-1F97)

Prepared by WILLIAM T. PARRY General Electric Company JAMES C. BELLOWS Siemens Energy, Inc.JOHN S, GALLAGHER Retired ALLAN H. HARVEY National Institute of Standards and Technology on behalf of ASME Research and Technology Committee on Water and Steam in Thermal Systems, Subcommittee on Properties of Steam THE AMERICAN SOCIETY OF MECHANICAL ENGINEERS Three Park Avenue em New York, N.Y. 10016 SM-SNC524602-001 ATTACHMENT 02 SHEET C2-6 Table U-2. Properties of Saturated Water and Steam (Pressure) p -I Volume, ir/lb., J Enthalpy, B tu/lbm, Entropy, BtuI(lb,..*R)

{p_p ~ t ("F) v L Av v h IL Ah h v si As s v Ip s!..0.1 0.12 0.14 11.16 0.2 0.25 0.3 0.35 04 0.45 0,5 0.6 0.7 0.8 0.9 1.0 1.2 1.4 1.6 1.8 2.0 2.2 2.4 2.6 2.3 3.0 3.5 4.0 4.5 5.0 5.5 6.0 6..5 7.0 7.5 3.0 8.5 9.0 9.5 10.0 10.5 11.0 11.5 12.0 12.5 13.0 13.5 14.0 14.066 15 16 17 18 19 20 21 22 23 24 25 35.1105 39.632 43.620 47.134 53,132 59.293 64.452 68.906 72.834 76.355 79.549 85.180 90.046 94.342 98.195 1 01.694 107.869 113.212 117.934 122. 174 126.027 129.563 132.835 135 .881I 138.734 141.418 147.515 152.913 157 .767 162.184 166.243 170.002 173.505 176.790 179.883 182.807 185.582 188.224 190.746 193.160!195.475 197 .700 199.842 201.908 203.904 205.834 207.704 209.517 211J.954 212.988 216.273 2 19.392 222.363 225.201I 227.9 18 230.526 233.034 235.450 237.781 240.034 0(116(020 2945.0 0.016 020 2476.9 (0.016020 2139.9 0.016 022 1885.3 0.016 027 1525.9 (1.016 034 1235.2 0.016 042 1039.4 0.016 050 898.40 0.016057 791.84 0.016 065 708.43 0.016073 641.31 0.016 087 539.89 0.016 100 466.80 0.016 113 411.56 0.016 125 368.30 0.016 137 333.49 0.0 16 158 280.87 0.0 16 178 242.93 0.016 196 214.25 0.016214 191.79 0.016 230 173.70 0.016 245 158.82 0.016 260 146.35 0.016 273 135.75 0.016 287 126.63 0.016 299 118.69 0.016 329 102.70 0.016 356 90.612 0.016 382 81.137 0.016 406 73.507 0.016 428 67.226 0.016 449 61.963 0.0 16 469 57.487 0.0 16 488 53.632 0.016 507 50.277 0.016 524 47.328 0.016 541 44.717 0.0 16 558 42.387 0.0 16 573 40.295 0.016 589 38.406 0.016604 36.692 0.016618 35.128 0.016 632 33.697 0.016 646 32.381 0.016659 31.167 0.016 672 30.04.4 0.0 16 685 29.002 0.016 697 28.031 0.016 714 26.787 0.016 721 26.278 0.016 745 24.738 0.016 767 23.374 0.016788 22.156 0.016 809 21.063 0.016 829 20.075 0.016849 19.179 0.016 868 18.361 0.016886 17.613 0.016 904 16.924 0.016 922 16.289 2945.0 2476.9 2139.9 1885.3 1525.9 1235.2 1039.4 898.41 791.86 708.44 64 1.32 539.90 466.81I 411.57 368.32 333.51 280.89 242.95 214.27 191.80 173.72 158.84 146.37 135.77 126.65 118.70 102.72 90.628 81.154 73.523 67.242 61.979 57.503 53.649 50.293 47.345 44.733 42.404 40.3 12 38.423 36.708 35.145 33.7 14 32.398 31.184 30.06 1 29.018 28.048 26.804 26.295 24.755 23.390 22.173 21.079 20.092 19.196 18.378 17.629 16.941I 16.306 3.009 7.662 11.668 15. 193 21.204 27.37 I 32.532 36.985 40.911 44.428 47.618 53.242 58. 110 62.389 66.236 69.728 75.892 8 1.225 85.939 90. 172 94.019 97.551 100.82 103.86 106.71 109.39 115.49 120.89 125.74 130.16 134.23 137.99 141 .50 144.79 147.90 150.83 153.61 156.27 158.80 161.22 163.55 165.79 167.94 170.02 172.03 173.97 175.85 177.68 180.13 181.18 184.49 1 87.63 190.63 193.50 196.25 198.88 201.42 203.86 206.23 208.51 1073.5 1076.5 1070.9 1078.5 1068.6 1080.3 1066.6 1081.8 1063.2 1084.4 1059.8 1087.1I 1056.8 1089.4 1054.3 1091.3 1052.1 1093.0 1050.1I 1094,5 1048.3 1095.9 1045.1 1098.3 1042.3 1100.4 1039.9 1102.3 1037.7 1103.9 1035.7 1105.4 1032.2 1108.1 1029.1 110.3 1026.4 112.3 1024.0 114.1 1021.7 115.8 1019.7 117.2 1017.8 118.6 1016.0 119.9 1014.4 1121.1 1012.8 1122.2 1009.2 1124.7 1006.1 1126.9 1003.2 1128.9 1000.6 1130.7 998.14 1132.4 995.90 1133.9 993.79 1135.3 991.81 1136.6 989.94 1137.8 988.17 1139.0 986.48 1140.1 934.87 1141.1 983.32 1142.1 981.84 1143.1 980.42 1144.0 979.04 1144.8 977.71 1145.7 976.43 1146.4 975.19 1147.2 973.93 1148.0 972.81 1148.7 971.67 1149.4 970.14 1150.3 969.48 1150.7 967.40 1151.9 965.42 1153.1 963.52 1154.2 961.70 1155.2 959.95 1156.2 958.26 1157.1I 956.63 1158.0 955.05 1158.9 953.52 1 159.7 952.04 1160.5 0.0061 0.0155 0.0235 0.0304 0.0422 0.0542 0.0641 0.0725 0.0799 0.0865 0.0925 0.1028 0.1117 0.1195 0.1264 0.1326 0.1435 0. 1529 0. 1611I 0. 1684 0. 1750 0. 1810 0.1865 0. 1916 0. 1964 0.2009 0.2110 0.2 198 0.2277 0.2349 0.2414 0.2474 0.2529 0.2581 0.2630 0.2675 0.2719 0.2760 0.2799 0.2836 0.2871I 0.2905 0.2938 0.2969 0.3000 0.3029 0.3057 0.3084 0.3121 0.3 137 0.3 136 0.3232 0.3276 0.33 18 0.3358 0.3396 0.3433 0.3468 0.3502 0.3534 2.1701 2.1447 2.,1233 2.1046 2.0734 2.0421 2.0 164 1.9947 1.9758 1.959 I 1.9441I 1.9 182 1.8962 1.8770 1.8601 1.8450 1.8187 1.7964 1.7770 1.7599 1.7445 1.7305 1.7178 1.7060 1,6951I 1.6849 1.6621 1.6423 1.6247 1.6090 1.5947 1.5816 1.5695 1.5583 1.5479 1.5381 1.5288 1.52.01!.5118 1.5040 1.4965 1.4393!.4825 1.4759 1.4696 1.4635 1.4577 1.4520 1.4445 i.44 13 1.43 12 1.4217 1.4127 i1.4042 1.3961 1.3884 1.38 10 1.3739 1.3671I 1.3606 2.1762 2.1602 2.1467 2.1351 2.1156 2.0962 2.0805 2.0672 2.0557 2.0456 2.0366 2.02 10 2.0079 1.9965 1.9865 1.9776 1.9623 1.9493 1.938 I 1.9283 1.9 195 1.9115 1.9043 1.8977 1.89 15 1.8858 1.8731 1.8621 1.8525 1.8438 1.8361 1.8290 1.8224 1.8164 i1.8 108 1.8056 1.8007 1.7961 1.7917 1.7875 1.7836 1.7799 1.7763 1.7728 1.7696 1.7664 1.7634 1.7605 1.7566 1.7549 1.7497 1.744.9 1.7403 1.7360 1.7319 1.7280 1.7243 1.7207 1.7 173 1.7 141 0.1 0.12 0.14 0.16 0.2 0.25 0.3 0.35 0.4 0.45 0.5 0.6 0.7 0.8 0.9 1.0 1.2 1.4 1.6 1.8 2.0 2.2 24 2.6 2.8 3.0 3.5 4.0 4.5 5.0 5.5 6.0 6.5 7.0 7.5 8.0 9.0 9.5 10.0 10.5 11.0 11.5 12.0 12.5 13.0 13.5 14.0 14.696 15 16 17 13 19 20 21 22 23 24 25 174 SM-SNC524602-001 ATTACHMENT C2 SHEET C2-7 Table U-3 (continued).

Properties of Superheated Steam and Compressed Water (0) 14 psia (ht, 1.= 209.52 0 F) 15psia (t,., = 21.9 °F) 1 psia (4,., = 216,27 (F)Sal. Liq. 0.016697 177.68 0.3084 0.016721 181.18 0.3137 0.016745 184.49 0.3186 Sal. Liq.Sai. Yap. 28.048 1149.4 1.7605 26.295 I150.7 1.7549 24.755 1151.9 1.7497 Sal. Yap.32 0.016021 0.024 0.0000 0.016 021 0.027 0.0000 0.016021I 0.030 0.0000 32 40 0.016019 8.073 0.0162 0.016 019 8.076 0.0162 0.016019 8.079 0.0162 40 SO 0.016023 18.106 0.0361 0.016023 18,109 0.0361 0.016023 18.112 0.0361 SO 60 0.016034 28,118 0.0555 0.016034 28.120 0.0555 0.016034 28.123 0.0555 60 70 0.016051 38.116 0.0746 0.016051 38.119 0.0746 0.016 051 38.122 0.0746 70 80 0.016 073 48.106 0.0933 0.016073 48.109 0.0933 0.016 073 48.111 0.0933 80 90 0.016 100 58.090 0.1116 0.016 100 58.093 0,1116 0.016 100 58.096 0.1I116 90 100 0.016 131 68.071 0.1296 0.016 130 68.074 0.1296 0.016 130 68.077 0.1296 100 110 0.016 165 78.052 0.1473 0.016 165 78.054 0.1473 .0.016 165 78.057 0.1473 110 120 0.016204 88.033 0.1647 0.016 204 88.036 0.1646 0.016 204 88.038 0.1646 120 130 0.016246 98.017 0.1817 0.016246 98.019 0.1817 0.016246 98.022 0.1817 130 140 0.016292 108.00 0.1985 0.016292 108.01 0.1985 0.016292 108.01 0.1985 140 150 0.016 341 118.00 0.2151 0.016 341 118.00 0.2150 0.016 341 118.00 0.2150 150 160 0.016393 128.00 0.2313 0.016393 128.00 0.2313 0,016393 128.00 0.2313 160 170 0.016449 138.01 0.2473 0.016449 138.01 0.2473 0.016448 138.01 0.2473 170 180 0.016 507 148.03 0.2631 0.016 507 148.03 0.2631 0.016 507 148.03 0.2631 180 190 0,016569 158.06 0.2787 0.016568 158.06 0.2787 0.016568 158.06 0.2787 190 200 0.016633 168.10 0.2940 0.016633 168.11 0.2940 0.016633 168.11 0.2940 200 210 28.070 1149.6 1.7608 0.016701 178.17 0.3092 0.016701 178.17 0.3092 210 220 28.521 1154.5 1.7681 26.591 1154.1 1.7601 24.903 1153.7 1.7525 220 230 28.969 1159.4 1.7752 27.012 1159.0 1.7672 25.299 1158.7 1.7597 230 240 29.415 1164.2 1.7822 27.430 1163.9 1.7742 25.692 1163.6 1.7667 240 250 29.860 1169.0 1.7890 27.846 1168.7 1.7811 26,084 1168.4 1.7736 250 260 30.303 1173.8 1.7958 28.26 I 1173.6 1.7878 26.474 1173.3 1.7804 260 270 30.744 1178.6 1.8023 28.674 1178.4 1.7945 26.862 1178. I 1.7871 270 280 31. 185 1183.4 1.8088 29.086 1183.1I 1.801I0 27.249 I1182.9 1.7936 280 290 31.624 1188.1I 1.8152 29.497 1 187.9 1.8074 27.635 1 187.7 1.8000 290 300 32.062 1192.9 1.8215 29.906 1192.7 1.8137 28.020 1192.4 1.8063 300 310 32.499 1197.6 1.8277 30.315 1197.4 1.8199 28.405 1197.2 1.8125 310 320 32.935 1202.3 1.8338 30.723 1202.1 1,8260 28.788 1202.0 1.8187 320 330 33.371 1207.1I 1,8398 3I. 131 1206.9 1.8320 29. 170 1206.7 1.8247 330 340 33.806 1211.8 1.8457 31.537 1211.6 1.8380 29.552 1211.4 1.8307 340 350 34.240 1216.5 1.8516 31.943 1216.3 1.8438 29.933 1216.2 1.8366 350 360 34.674 1221.2 1.8574 32.349 1221.1I 1.8496 30.314 1220.9 1.8424 360 370 35.107 1225.9 1.8631 32.754 1225.8 1.8554 30.694 1225.6 1.8481 370 350 35.540 1230.6 1.8688 33.158 1230.5 1.8610 31.074 1230.4 1.8538 380 390 35.972 1235.4 1.8743 33.562 1235.2 1.8666 31.453 1235.1 "1.8594 390 400 36.404 1240.1I 1.8799 33.966 1239.9 1.8721 31.832 1239.8 1.8649 400 410 36.836 1244.8 1.8853 34.369 1244.7 1.8776 32.210 1244.5 1.8704 410 420 37.267 1249.5 1,8907 34,772 1249.4 1.8830 32.588 1249.3 1.8758 420 430 37.698 1254.2 1.8961 35.174 12.54.1I 1.8884 32.966 1254.0 1.8811 430 440 38.129 1259.0 1.9013 35.577 1 258.9 1.8936 33.344 1258.7 1.8864 440 450 38.559 1263.7 1.9066 35.979 1263.6 1.8989 33.721 1263.5 1.8917 450 460 38.990 1268.4 1.9117 36.381 1268.3 1.904 1 34.098 1268.2 1.8969 460 470 39.420 1273.2 1.9169 36.782 1273.1 1.9092 34.475 1273.0 1.9020 470 480 39.849 1277.9 1.9220 37,184 1277.8 1.9143 34.851 1277.7 1.9071 480 490 40.279 1282.7 1.9270 37.585 1282.6 !.9193 35.228 1282.5 1.9121 490 500 40.708 1287.4 1.9320 37.986 1287.3 1.9243 35.604 1287.2 1.9171 500 510 41. 137 1292.2 1.9369 38.387 1292.1I 1.9292 35.980 1292.0 1.9220 510 520 41.567 1297.0 1.9418 38.787 1296.9 1.9341 36.356 1296.8 1.9269 520 530 41i.995 1301.7 1.9466 39.188 1301.6 1.9390 36.732 1301!.6 1.9318 530 540 42.424 1306.5 1.9514 39.588 1306.4 1.9438 37.107 1306.4 1.9366 540 550 42.853 1311.3 1.9562 39.989 1311.2 1.9485 37.483 1311I.1 1.9414 550 560 43.281 1316 1 1.9609 40.389 1316.0 1.9533 37.858 1315.9 1.9461 S60 570 43.710 1320.9 1.9656 40.789 1320.8 1.9580 38.233 1320.7 1.9508 570 580 44.138 1325.7 1.9703 4I. 189 1325.6 1.9626 38.608 1325.6 1.9554 580 590 44.566 1330.5 1.9749 41.589 1330.4 1.9672 38.983 1330.4 1.9601 590 600 44.994 1335.3 1.9794 41.988 1335.3 1.9718 39.358 1335.2 1.9646 600 UNITS: i' in ft 3/1b., ; h in Btu/1bm ; s in Btul(ibm'"R) 198 SM-SNC524602-001 ATTACHMENT C2 SHEET C2-8 Table U-3 (continued).

Properties of Superheated Steam and Compressed Water 1800 palQ, = 623.07"F) 2eoo a,, =635.85 F) 2Nm ala,, 1 9.= -____ ____F_____________

__________

s_____ h s t('F)Sat. L.q.Sat. Vip.32 40 50 60 70 80 90 110 120 130 140 IS0 160~170 180 150 200 210 220 230 240 230 260 270 280 290 300 310 320 330 340 350 360 370 38O 390 400 410 420 430 440 450 460 470 480 490 O00 510 520 530 S40O 560 570 580 590 0.024 73 0.2184 0.015 923 0.015 923 0,015931 0.015 944 0.015 962 0`015 936 0.016 013 0.016 044 0,016 079 0.016 118 0`016 360 0.0I6 205 0.016 253 0.016 304 0.016 356 0.016415 0.016 475 0.016 537 0.036 603 0.016 6713 0.016 742 0.016 836 0.016 893 0.036 973 0.037 056 0.017 142 0.017 23!0037 324 0.037 420 0.017 539 0.017 623 0.037 730 0.037 841 0.017 956 0.0350 76 0.031320 0.01i8 329 0.013 464 0.0183604 0.011 749 0.018 902 0.039061 0`039 227 0.019 402 0.0I9 585 0.019 7781 0.039 983 0.020 395 0.020 422 0.020 663 0.020 921 0.023 196 0.021 492 0.0218133 0.022 362 0.022 545 0.022 970 0.023 448 648.27 1150.7 5.367 13.333 23.232 33,3"4 43.053 52.960 62.868 72.776 82.687 92.6013 302.52 332.44 322.37 132.33I 342.26 352.22 362.39 372.17 382.36 392.37/20'2.20 232.25 222.31I 232.40 242.50 252.64 262.60 272.98 283.20 293.45 303.73 334.05 324.43!334.83 345.26 355.76 366.33 376.92 38"7.60 398.34 409.35 420.04 4313.02 442.09 453.27 464.56 475.96 487.51 499.20 511.06 523.10 535.35 547.84 560.59 573.66 587.10 600.97 635.39 0.8415S 1.3063 0.o010 0.0161 0.03581 0.0O550 0.0739 0.0925 0.1106 0.1285 0.1461 0.13633 0. 1803 0.1970 0.21334 0.2296 0.2455i 0.2632 0.2766 0.2939 0.3069 0.3238 0 3364 0.3509 0.3652 0.3793 0.3932 0.40"70 0.4206 0.4341I 0.4475 0.4607 0.4738 0.4863 0.4997 0.5125 0.5251 0.53770.5626 0.5750 0.5873 0.5995 0.6337 0.6233 0.6359 0.6480 0.6603 0.6721 0.6842 0.6963 0.7085 0.7207 0.733 3 0.7455 07533 0.7706 0.7338 0.7971 0,.8107 0,025 63 0.1882 0.0315932 0.035933 0.035 923 0.015 934 0.035 953 0.035 976 0.0316003 0.016 035 0.0!6070 0.036 108 0.036 350 0.036 395 0.036 243 0.016 294 0.016 348 0.036 405 0.036464 0.0136 527 0.036 592 0.0136660 O0.06 733 0.036805 0.016 833 0.036 961 0.037044 0.037 329 0.037 2131 0.037 310 0.037406 0.037 505 0.017607 0.037 713 0.037 824 0.037 938 0.0183057 0.031 3810 0.013309 O0103442 0.018 531 0.0313726 0.033 876 0.019 034 0,019 399 0.039371 0.0I9 552 0.0139 743 0.039943 0.020 154 0.020 378 0.020 615 0.020 867 0.0213137 0.023 427 0.021 739 0,022 078 0.022 450 0.022 359 0.023 317 671.80 11336.5 5.960 13.894 23.802 33.703 43.603 53,501 63.400 73.303 83.205 93,112 303.02 1 12.94 322.86 132.80 342.74 352.69 162.65 372.62 382.63 392.62 202.64 232.67 222.73 232,81 242.93 253.03 263.38 273.36 283.56 293.80 304.07 314.38 324733 335.32 345.56 356.04 366.58 377.37 387.83 3981.55 409.34 420.23 433.16 442.23 453.35 464.60 475.98 487.48 499.32 5130.93 522.31 535.09 547.49 560.35 73,13'586.41 600.13 634.33 0.8622 1.2864 0.0001 0.013613 0,035"7 0.0550 0.0739 0.0924 0.13105 0.3284 0. 1459 0. 1632 0.13803 0.1968 0.2332 0.2294 0.2453 0.2610 0.2764 0.2917 0.3O67 0.3215S 0.3363 0.35O6 0.3649 03790 0.3929 0.4067 0.4203 0.4338 0.4473 0.4604 0.4735 0.4864 0.4993 0.5120 0.5247 0.5373 0.5497 0.5623 0.5744 0.5867 0.5989 0.633i3 0.6232 0.6352 0.6473 0.6593 0.67 14 0.6834 0.6955 0.7076 0.71398 0.7320 0.7444 0.7568 0.7695 0.73123 0,7954 0.8089 0.026 68 0.I1627 0.015 901 0.035 903 0.015 930 0.0 15 924 0.015 943 0.035 966 0.035 994 0.0 36 025 0.036 060 0.016099 0.036 341 0.016 336 0.0136 234 0.0136 284 0.036 338 0.016 395 0.016 454 0.0136 5813 0.016 649 0.016 720 0.016 793 0.0136 870 0.016 949 0.037 031 0,017 3316 0.0137 205 0.037 296 0.037 39t 0.037 490 0.0317 592 0,037 697 0.03730 0.017 921I 0.018 039 0.013 363 0.0 13 289 0.0181421 0.018 559 0.018 702 0.0181 853 0.039 007 0.019 373 0.019 343I 0.039 520 0.0319 708 0.019 906 0.020 314 0.020 334 0.020 567 0.020335 0.021 080 0.021 363 0.021 668 0.02f 3581 0.022 754 0.023 193 695.09 1120.4 6.553 14.475 24.370 34.262 44.1351 54.o413 63.932 73.825 83.721 93.62 3 303.53 133344 323.35 333.28 343.23 353.36 363.33 173.08 383.06 393.06 203.07 233.30 223.35 233.22 243.31 253.43 263.57 273.74 283.93 294.36 304.42 3134.72 325.06 335A3 345.35 356.32 366.85 377.42 388.06 398.76 409.53 420.33 431.31 442.33 453.44 464.66 476.00 43'7.46 499.06 530.81 522.73 534.85 547.138 559.75 572.59 535.76 599.31 633.33 0.8825 3,2659 0.0001 0,01363 0.0357 0.0549 0.0738 0.0923 0.1104 0. 1283 0.1458 0.31630 0.31800 0.31966 0.2330 0.2292 0.2451 0.2607 0.2762 02934 0.3064 0.3233 0.3359 0.`3503 0.3646 0.3787 0.3926 0.4064 0.4200 0A433S 0.4468 0.4600 0.4731 0.4860 0.4989 0.511 6 0.5242 0.5363 0.5492 0.,56136 0.5739 033862 0.5983 0.6305 0.622.5 0.6346 0.6466 0.6586 0.67/06 0`6326 0.6946 0.7/067 0,7388 0.7330 0.7433 0.7556 0.768I2 0.7809 0.7939 0.8071 Sat, L~iq.Sat. Vap.32 40 50 60 70 80 90 100 110 120 130 140 150 160 170 180 390 200 210 220 230 240 250 260 270 230 290 300 310 320 340 350 370 380 390 400 410 420 430 450 460 470 48I0 490 520 530 S4O 560'7..590 400 UNITS: v ia ; h in Btu/3b, ; in 8tu/(Ib.-°R) 238 SM-SNC524602-001 ATTACHMENT 02 SHEET C2-9 Table U-3 (continued).

Properties of Superheated Steam and Compressed Water... 2400sIma ( = 662.16'F) 2600 pIta (t:n 673 98 *F) 2800 pita 685.03 0 F)t (W) 'f '" A : J ' h v " h ____(°F Sai. Liq.Sai Vdp.32 40 50 60 70 80 90 100 110 120 13O 140 150 160 370 180 190 200 210 22.0 230 240 250 240O 270 280 290 300 310 320 330 340 350 360 380 400 430 420 440 450 460 470 480 500 530 540 550 560 600 0.027 89 0.1407 0.015 890 0.0)589 0.015 900 0.015 914 0,015 933 0.015 957 0.015 985 0.016016 0016 051 0.0 16 090 0016 131 0.016 176 0016 224 0.016 275 0.016 328 0.016 385 0,016 444 0.016 506 0,016 571 0.016 638 0.016 7/09 0.016 782 0.016858 0.1116 937 0,017 103 007191 0,017 283 0.017 377 0.017 475 0O0I7 576 0017 681 0017 790 0.017 903 0.018021 0.018 142 0.018 269 0.018 400 0,018 536 0.018 679 0.018 827 0,018 981 0.019 343 0.0193 12 0.019 488 0.019 674 0.0!9 869 0.020 074 0.020 291 0.020 521 0.020 764 0.021 024 0-021 30)0.021 599 014)23 921 0.022 653 0.023 076 718,67 1101.9 7.141 15.054 24.938 34.8 19 44.700 54.581 64.464 74.349 84.238 94.131 104.03 11393 123.14 133,76 143.69 153.63 163.57 173.54 183,51I 193.50 203.51 213.53 223.57 233.63 243.72 253,82 263.96 274.11 284.30 294.52 304.77 315.06 325.38 335.75 346.15 356h61 367.12 377.68 388.30 398.91 409,73 420.55 431.46 442,45 453.54 464 72 476.02 487.45 499.00 510.71 522.58 534.63 546.88 559.37 572.11 585.16 598.56 612.38 0.9O27 1.2443 0,1001I 0.0161 0.0357 0,0549 0.0737 0.0922 0.1103 0.1281 0 1457 0. 1629 0.1798 0.1965 0.2128 0.2290 0.2449 0.2605 0.2760 0,39)2 0.3062 0.32)0 0 3356 0.3500 0.3643 03784 0.392.3 0.4060 0.4196 0.4331 0.4464 0.4596 0.4727 0,4856 0.4985 0.5112 0.5238 0.5363 0.5488 0.5611 0.5734 0.5856 0.5978 0.6099 0.62 19 0.6339 0.6459 0.6579 0.6699 0.68 18 0,6938 0,7058 0.7179 0.7300 0.7422 0.7545 0.7669 0.'7795 0.7924 0,8055 0.029 38 0.1211 0-015 880 0.015 882 0.015 890 0.015 905 0.015 924 0.015 947 0,015 975 0,016007/0,1116042 0.016 080 0.016 122 0.016 167/0.016 214 0.016 265 0.016 319 0 0)6 375 0.016 434 0,016 496 0.016 560 0.016 628 0,016 698 0.016 771 0.016 846 0.016 925 0.0)7 006 0.017091 0.0)7 178 0.0)7 269 0.017 363 0.017 460 0.017 56)I 0.0 17 666 0.017 774 0.0)7 886 0.018 003 0.018 123 0.018 249 0.018 379 0.018 515 0.018 656 0,018 802 0.0)8 955 0.0)9 !15 0,019 282 0.019 457 0.019641 0,019 833 0.020036 0.020 249 0.020 475 0.0207)5 0.020 970 0.021 24)0.02) 533 0.02) 847 0.022 186 0.022 557 0.022 965 743,27 1060.'2 7.730 15.632 25.505 35,376 45.247 55.120 64.995 74.873 84.754 94 .640 10453 11[4.43 124.33 134.24 144.16 154.10 164.04'73.99 183.96 193.94 203.94 2 13.96 223.99 234.05 244.12 254.22 264,34 274.49 284.67 294,.88 305.12 315.39 325.71t 336.06 346.46 356.90 367.39 377.93 388.53 399.20 ,409.93 420.7'3 431.61 442.58 453.64 464,79 476.06 487.44 498.96 510.62 522.43 534.42 546.61 559.01 571.66 584.60 597.87 611.52 0.9236 1.2208 0.0001 0.0 161 0.0356 0.0548 0.07/36 0.0921 0.1102 0.1210 0.1455 0. 1627 0.1796 0. 1963 0.2127 0.2288 0.2447 0.2603 0.27/57 0.2909 0.3059 0.3207 0.3353 0.3498 (1.3640 0.378)0.3920 0,405"7 0.4193 0.43211 0.446!0.4593 0.4723 0.4852 0.4980 0.5106 0.5234 0.5359 0.5483 0.5606 0.5729 0.5851 0.5972 0.6093 0.6213 0.6333 0.6453 0.6572 0.6691 0.681 I 0.6930 0.7049 0.7169 0.7290 0.7411 0.7534 0.7657/0.7782 0.7909 0.5039 0,031 34 0.,1029 0.015 869 0.015 872 0.0)5 880 0.0)5 895 0.015 914 0.015 938 0.015 966 0-015 997 0.016 032 0.016071 0.0)6 113 0.016 157 0.016 205 0.016 255 0.0)6 309 0.0)6 365 0.0! 6 424 0,016 485 0.016 550 0.016 6)7 0.016 687 0.016 759 0.016 835 0.016 913 0.0)6 994 0.017078 0.017 165 0.0)7 255 0.0)7 349 0.0)7 446 0.0 17 546 0-017 650 0.0)7 758 0.017 869 0,017 985 0.018 105 0.018 229 0.01I8 359 0,018 493 0.0)8 633 0.018 17"8 04)18 930 0.019068 0.019 254 0.0)9 426 0.0 19 608 0.019 798 0.0!9 998 0.020 208 0.020 431 0.020 666 0.020 917 0.021 183 0.02) 468 0.021 7/75 0.022 l0S 0.022 465 0.022 859 770.20 1053A 8.317 16.2 10 26.07)35.932 45.794 55.658 65 .525 7 5.396 85.270 95,149 105.03 114.92 124.82 134,73 144.64 154.56 164.50 174.45 184.41 194.39 204.33 214.39 224.4)I 234.46 244.53 254.62 26473 274 .87 285.04 295.24 305.47 315.73 326.04 336.38 346.76 35"/.19 367.66 378.19 388.7/8 399.42 4 10,.13 420.92 431.77 442,7/)453.7/4 464.87 476.10 487.45 498.92 5)0.54 522.30 534.23 546.35 558.68 571.24 584.08 597.22 610,72 0.9462 1.1936 0.0)60 0.0356 0.0547 0.0735 0.0920 0. 1t01 o.1279 0. 1454 0.1626 0.1795 0.1961 0.2 125 0.2286 0.2445 0.2601 0,2755 0.2907/0.305'7 0. 3205 0.335)0.3 495 0-3637 0 .3778 0.3917 0.4054 0.4 190 0.4324 0.4457 0.4589 0.47i19 0.4848 0.4976 0.5 103 0.5229 0.5354 0.5478 0.5601 0.5724 0,5846 0.5967 0.6087 0.62O7 0.6327 0.6446 0.6565 0.6684 0.6803 0,6922 O.704)0.7 160 0.7280 0.7401 0.7522 0.7645 0.7769 0.7595 0.8023 Sal. Lzq Sal. Yap 32 40 50 60 70 80 90 100 110 120 1.30 140 ISO 160 170 180 190 200 2)0 220 230 240 250 260 270 280 290 300 310 320 330 340 350 360 370 310 390 400 410 420 430 440 460 470 4,9 500 520 540 550 560 6OO UNITS: p, in h in £ in BluJ(lbm'R) 240 Southern Nuclear Design Calculation IPlant: Farley Unit: 1&2 ICalculaton Number: SM-SNC524602-o01 Sheet: D-1 I Attachment D -Water Level Elevations Corresponding to Fuel Uncovery Several EALs are based on the water level elevations that correspond to uncovery of irradiated fuel in the reactor vessel, the spent fuel pool, and the spent fuel transfer canal during refueling operations.

RPV Level at 6" Below Bottom ID of RCS LOOD Hot Leg Centerline Elevation-'Ax I D =-1/2 x29" Elevation

@ bottom of loop 6-inch level reduction= 122'-9" = 121'-21"= -0'-14.5"[Design Input #9][Design Input #9]= 121 '-6.5" (= 121 '-21" -0'-14.5")Elevation

@ 6" below bottom of loop = 121'-0.5" =-121'Cold Leg Centerline Elevation-1/2 x ID =1/2x 27.5" Elevation

@ bottom of loop 6-inch level reduction-122'-9" = 121'-21"--0'-1 3.75"= 121'-7.25"[Design Input #9][Design Input #9]Elevation

@ 6" below bottom of loop = 1 20'-1 .25" = -121'Top of Active Fuel (TOAF) in Reactor Vessel The elevation of the top of the irradiated fuel in the reactor vessel is determined by referencing reactor vessel dimensions from drawings U168878 & U206587 to the centerline of the cold and hot leg nozzle centerline elevation as shown to the right.The upper core plate elevation is the CL/HL centerline elevation (122'-9";

Design Input #9) plus the distance to the reactor vessel mating surface (82.437";

Design Input #9) then minus the distance from the mating surface to the upper core plate (124.687";

Design Input #9): ELucP = 122.75 ft + [(82.437 in -124.687 in) x (1 ft/12 in)]ELucP = 122.75 ft -3.53 ft ELucp = -119 ft Mating Surface A A 32.437" I (uieaa7a &I U2OUUJ CL&HL* EL 122'S" 124.667" (U1671 &U206667)Upper Core Plate The elevation of TOAF (ELTOAF) is approximately 1 foot below this elevation (Assumption

1. 10): ELTOAF =-118' = 119' -1' Southern Nuclear Design Calculation IPlant: Farley U nit: I 2 ICalculationNumber:

SM-SN0524602-00O1 Sheet: D-2 I Attachment D -Water Level Elevations Corresponding to Fuel Uncovery Spent Fuel Pool The bottom elevation of the Spent Fuel Pool is 1 14'-5" (Design Input #6). The top of the spent fuel rack is 14'-5.375" (Design Input #7) above this as shown to the right.The elevation corresponding to a water level at the top Ak.lZ L of the spent fuel racks is ELsFP = 1 14'-5" + 14'-5.375" ELsFP = 128'-10.375" ELsFP = -129 ft The fuel transfer tube centerline elevation is 11 5'-101/=" (Design Inputs #6 & 8). A fuel assembly is 8.426" on a side (Design Input #11). Thus, the elevation corresponding to just covering the fuel assembly is ELXFR = 1 15'-101/2" + (8.426"/2)

= 1 15'-101/2" + 4.213" ELxFR = 1 15'-14.71 3" ELXFR = '-116 ft Southern Nuclear Design Calculation SPlant: Farley Unit: 1 &2 Calculation Number: SM-SNC524602-001I Sheet: E-l Attachment E -TEDE & Thyroid CDE Dose Calculations Description of Pages El -Plant Vent Stack TEDE & Thyroid ODE Calculations 6 E2A -SJAE Release Path TEDE & Thyroid CDE Calculations 6 (No Core Damage)E2B -SJAE Release Path TEDE & Thyroid ODE Calculations 6 (Core Damage)E3A -SIG ARV & SRV Release Path TEDE & Thyroid ODE Calculations 6 (No Core Damage)E3B -SIG ARV & SRV Release Path TEDE & Thyroid ODE Calculations 6 (Core Damage)E4A -TDAFWP Exhaust Release Path TEDE & Thyroid ODE Calculations 6 (No Core Damage)E4B -TDAFWP Exhaust Release Path TEDE & Thyroid ODE Calculations 6 (Core Damage)Total Number of Pages Including Cover Sheet 4 43 SM-SNC524602-001 ATCMN lSETE-ATTACHMENT E1 SHEET E1-1 Plant Vent Stack Release Path TEDE & Thyroid CDE Calculations Postulated Release Activity XRLS -- Release Concentration (pCi/cc)XRLS = [Partition Factor x Xrcs (p#Ci/g)]

x [pris (g/cc)]Partition Factors[Assumption

1. 5]Noble Gases: 1.0 Iodine, liquid leakage to Auxiliary Building:

0.01 Iodine, primary coolant leakage to Containment building:

0.01 Iodine, primary coolant leakage to steam generator:

0.01 Iodine, SJAEs: 1 .0E-04 RCS coolant activity (piCi/cc)RCS Equilibrium Activity (p.Ci/g) +[Release Fraction x Core Inventory (Ci) x (1 Ci)]/MRcs (g)Xrcs =Xrcs =RCS Equilibrium Activity:

Design Input #14 Core Inventory:

Design Input #14 Release Fractions

[Assumption

1. 6]1.0 for Noble Gases (RG 1.183 Table 2, LOCA)0.4 for Iodine (RG 1.183 Table 2, LOCA)0 for no core damage MRCS = RCS coolant mass (Ibm)MRcs = 417,219 Ibm x (453.59 g/1 Ibm) [Design Input #11]MRCS = 1 .89E+08 g pris = Density of release fluid (g/cc)pris = 1 .00E+00 g/cc [Arbitrary Value]

SM-SNC0524602-001 ATCMN lSETE-ATTACHMENT E1 SHEET E1-2 Isotope Core Core Xeq Xrcs (jtC ilg) Partition XRLS Inventory Release (.iCilg) Factor (JllCi/cc)(Ci) Fraction Kr-83m 9,70E+06 1.00 4.50E-01 5.IE+04 1.00 5.1E+04 Kr-85 7.20E+05 1.00 7.70E+00 3.8E+i03 1.00 3.8 E+03 SKr-85m 2.10E+07 1.00 1.80E+00 1.1IE+05 1.00 1.1IE+05 Kr-87 4.00E+07 1.00 1.20E+00 2.1E+05 1.00 2.1E+05 Kr-88 5.70E+07 1.00 3.50E+00 3.0E+05 1.00 3.0E+05 Kr-89 6.90E+07 1.00 1.10E-01 3.6E+05 1.00 3.6E+05;Xe-131 m 8.40 E+05 1.00 2.90E+00 4.4E+03 1.00 4.4 E+03 Xe-133 1.50E+08 1.00 2.40E+02 7.9E+05 1 oo 7.9E+05 Xe-133m 4.80E+06 1.00 4.60E+00 2.5E+04 1.00 2.5E+04 Xe-135 3.50E+07 1.00 7.90E+00 1.8E+05 1.00 1.8E+05 Xe-135m 3.00E+07 1.00 4.50E-01 1.6E+05 1.00 1.6E+05 Xe-137 1.40E+08 1.00 2.00E-01 7.4E+05 1.00 7.4E+05 Xe-138 1.30E+08 1.00 7.20E-01 6.9E+05 1.00 6.9E+05 1-131 7.50E+07 0,40 1,40E+00 1.6E+05 0,01 1.6E+03 I-132 1.10E+08 0.40 2.30E+00 2.3E+05 0.01 2.3E+03 I-133 1.60E+08 0.40 2.70E+00 3.4E+05 0.01 3.4E+03 1-134 1.70E+08 0.40 6.30E-01 3.6E+05 0.01 3.6E+03 I-135 1.50E+08 0.40 1.90E+00 3.2E+05 0.01 3.2E+03 SM-SNC524602-001 TAHETElSETE-ATTACHMENT E1 SHEET E1-3 Postulated Release TEDE Calculations TEDE =Total Effective Dose Equivalent (mREM)TEDE =EDE + CEDE EDE =Effective Dose Equivalent (mREM) from external exposure EDE =DCFFGR-12 X XEAB X texp DCFFGR-12

= FGR-12 dose conversion factor [(mREM/hr)/(pCi/cc)]

CEDE --Committed Effective Dose Equivalent (mREM) from inhalation CEDE --DCFFGR-11 x XEAB X BR X texp DCFFGR-11

= FGR-11I dose conversion factor (mREM/iCi)

XEAB =Radionuclide concentration at Exclusion Area Boundary (pCi/cc)XEAB =[QRLS (m^3/sec)]

X [X/Q (sec/m^3)]

x [XRLS (pCi/cc)]Qris =Release flow rate (m^3/sec)Qris = 150,000 CFM x [1 mini60 sec] x [0.0283 mA3/ft^3]

[Design Input #21]Qris "-70.8 mA3/sec X/Q =Atmospheric dilution factor (sec/m^3)X/Q = 4.87E-05 sec/m3 [Assumption

1. 3]texp Exposure time texp =I1.0 hour0 days <br />0 hours <br />0 weeks <br />0 months <br /> [Assumption

1. 1]BR =Breathing Rate (m^3/sec)BR = 3.47E-04 m^3/sec [Assumption

1. 2]BR 1 1.25E+06 cc/hr = m^3/sec x [(1 .0E6 cc)/(1 mA3)] x [3600 sec/i hr]

SM-SNC524602-001 ATCMN lSETE-ATTACHMENT E1 SHEET E1-4 Isotope Release XEAB FGR-12 EDE FGR-11 CEDE Activity DCF (mREM) DCF (mREM)(1.+/-Cilcc) (mREM/hr)/ (mREM/(j4Ci/cc) Kr-83m 5.1IE+04 1.8E+02 2.00E+O1 3.5E+03 0.OOE+O0 O.OE+OO Kr-85 3.8E+03 l.3E+Ol l.59E+03 2.1 E+04 O.OOE+OO O.OE+OO Kr-85m 1.1 E+05 3.8E+02 9.96E+04 3.8E+07 O.OOE+00 O.OE+OO Kr-87 2.1 E+05 7.3E+02 5.49E+05 4.OE+08 O.O0E+OO O.OE+OO Kr-88 3.0E+05 I1.0E+03 I1.36E+06 I1.4E+09 O.OOE+OO O.QE+OO Kr-89 3.6E+05 I1.3E+03 O.OOE+OO O.OE+OO O.OOE+OO O.OE+OQ Xe-131m 4.4E+03 1.5E+01 5.18E+03 7.9E+04 O.OOE+OO O.OE+OO Xe-I133 7.9E+05 2.7E+03 2.08E+04 5.7E+07 O.OOE+OO O.OE+OO Xe-133m 2.5E+04 8.7E+01 1.82E+04 1.6E+06 O.OOE+OO O.OE+OO Xe-135 1.8E+05 6.4E+02 I.59E+05 1.0E+08 O.OOE+OO O.OE+OO Xe-135m 1.6E+05 5.5E+02 2.72E+05 1.5E+08 O.OOE+OO O.OE+OO Xe-i137 7.4E+05 2.6E+03 O.OOE+00 O.OE+OO O.O0E+OO O.OE+OO Xe-138 6.9E+05 2.4E+03 7.69E+05 1.8E+09 O.OOE+OO O.OE+OO 1-131 1.6E+03 5.5E+00 2.42E+05 1.3E+06 3.29E+01 2.2E+08 1-132 2.3E+03 8.0E+00 1.49E+06 1.2E+07 3.81E-01 3.8E+06 1-133 3.4E+03 1.2E+01 3.92E+05 4.6E+06 5.85E+00 8.5E+07 1-134 3.6E+03 1.2E+01 1.73E+06 2.1E+07 1.31E-01 2.OE+06 ,1-135 3.2E+03 1.1E+01 1.06E+06 1.2E+07 1.23E+00 1.7E+07 Total = 4.0E+09 mREM Total = 3.3E+08 mREM TEDE = EDE + CEDE EDE.=CEDE =TEDE = 4.4E+09 4.0E+09 mREM 3.3E+08 mREM mREM SM-SNC524602-001 SM-SNC52602-001ATTACHMENT El1HETE-SHEET E1-5 100 & 1000 mREM TEDE Thresholds Xioo = 100 mREM TEDE Noble Gas concetration (jFCi/cc)Xioo = [(100 mREM)/(TEDE mREM)] x XRLS TEDE = 4.4E+09 mREM Xioo =2.3E-08 x XRLS Xiooo = 1000 mREM TEDE Noble Gas concetration (FtCi/cc)Xiooo =l0 x Xoo Isotope XRLS X100 Xio00 (ltC i/cc) (jiC i/cc) (lpCi/cc)SKr-83m 5.IE+04 1.2E-03 1.2E-02 Kr-85 3.8E+03 8.7E-05 8.7E-04 Kr-85m 1.1 E+05 2.5E-03 2.5E-02 Kr-87 2.1E+05 4.8E-03 4.8E-02 Kr-88 3.0E+05 6.9E-03 6.9E-02 Kr-89 3.6E+05 8.4E-03 8.4E-02 Xe-I131rm 4.4E+03 1 .0E-04 I1.OE-03 Xe-133 7.9E+05 1.8E-02 1.8 E-0I Xe-I133m 2.5E+04 5.8E-04 5.8E-03 Xe-I135 1 .8E+05 4.2E-03 4.2E-02 Xe-I135m i .6E+05 3.6E-03 3.6E-02 Xe-137 7.4E+05 1.7E-02 l.7E-01 Xe-138 6.9E+05 1.6E-02 1.6E-01 Totals 8.3E-02 1 4C i/cc Ci/cc SM-SNC524602-001 ATCMN lSETE-ATTACHMENT E1 SHEET E1-6 Thyroid CDE Calculations CDETHY = Thyroid Committed Dose Equivalent (mREM) from inhalation CDETHY -DCFFGR-11 X XEAB X BR x texp DCFFGR-11

= FGR-11I dose conversion factor (mREM/pFCi/cc) texp = 1.00 hour0 days <br />0 hours <br />0 weeks <br />0 months <br /> BR = 1 .25E+06 cc/hr X500T = 500 mREM Thyroid CDE Noble Gas concentration (liCi/cc)X500T = [(500 mREM CDE)/(CDETHY mREM)] x XRLS X500T=- 500/ 1.1E+10 x XRLS=- 4.8E-08 X XRLS X5000T = 5000 mREM Thyroid CDE Noble Gas concentration (pzCi/cc)X5000T = 10 x X500m Postulated Release Thyroid CDEThresholds Isotope XEAB FGR-11I CDETHY XRLS X500T X5000T DCF (mREM) (pCi/cc)(mREM/pCi)Kr-83m 1.8E+02 0.00E+00 0.0E+00 5.1E+04 2.4E-03 2.4E-02 Kr-85 I1.3E+01 0.00E+00 0.0E+O0 3.8E+03 I1.8E-04 1 .8E-03 Kr-85m 3.8 E+02 0.00E+00 0.0E+00 1.1 E+'05 5.3 E-03 5.3E-02 Kr-87 7.3E+02 0.00E+00 0.0E+00 2.1E+05 1.0E-02 1.0E-01 Kr-88 1 .0E+03 0.00E+00 0.0E+00 3.0E+05 1 .4 E-02 I.4E-01 Kr-89 I1.3E+03 0.00E+00 0.0E+00 3.6E+05 1 .7E-02 1 .7E-01 Xe-131 m 1.5E+01 0.00E+00 0.0E+00 4.4E+03 2.1E-04 2.1E-03 Xe-i133 2.7E+03 0.00E+00 0.0E+00 7.9E+05 3.8E-02 3.8E-01 Xe-133m 8.7E+01 0.00E+00 0.0OE+00 2.5E+04 1.2 E-03 1.2 E-02 Xe-135 6.4E+02 0.00E+00 0.0E+00 1.8E+05 8.8E-03 8.8E-02 Xe-135m 5.5 E+02 0.00E+00 0.0E+00 1.6E+05 7.5 E-03 7.5E-02 Xe-137 2.6E+03 0.00E+00 0.0E+00 7.4E+05 3.5E-02 3.5E-01 Xe-I138 2.4E+03 0.00E+00 0.0E+00 6.9E+05 3.3E-02 3.3E-01 1-131 5.5E+00 1.08E+03 7.4E+09 I-132 8.0E+00 6.44E+00 6.4E+07 I-133 1.2E+01 1.80E+02 2.6E+09 I-134 1 .2E+01 I1.07E+00 I1.6E+07 I-135 1.1IE+01 3.13E+01 4.3E+08 Total CDETHY " 1.1 E+10 mREM Totals 1.7E-01 lpCi/cc 1 .7E+00 pCilcc SM-SNC524602-001 SM-SNC52602-001ATTACHMENT E2ASHEEA-SHEET E2A-1 SJAE Release Path TEDE & Thyroid CDE Calculations (No Core Damage)Postulated Release Activity XRLS "-Release Concentration (pCi/cc)XRLS =[Partition Factor x Xr~cs (p.Cij/g)]

x [pris (g/cc)]Partition Factors[Assumption

1. 51 Noble Gases: 1.0 Iodine, liquid leakage to Auxiliary Building:

0.01 Iodine, primary coolant leakage to Containment building:

0.01 Iodine, primary coolant leakage to steam generator:

0.01 Iodine, SJAEs: 1.0E-04 Xrcs " RCS coolant activity Xrcs --RCS Equilibrium Activity +[Release Fraction x Core Inventory (Ci) x (1 .0E+06pFCi/1 Ci)]/MRcs (g)RCS Equilibrium Activity:

Design Input #14 Core Inventory:

Design Input #14 Release Fractions

[Assumption

1. 6]1.0 for Noble Gases (RG 1.183 Table 2, LOCA)0.4 for Iodine (RG 1.183 Table 2, LOCA)0 for no core damage MRCS = RCS coolant mass (Ibm)MRCS = 417,219 Ibm x (453.59 g/1 Ibm) [Design Input #11]MRcs = 1.89E+08 g pris -"Density of release fluid (g/cc)pris 1 1.00E+00 g/cc [Arbitrary Value]

SM-SNC524602-001 ATCMN 2 HE 2-ATTACHMENT E2A SHEET E2A-2 Isotope Core Core Xeq Xrcs ilg) Partition XRLS Inventory Release Factor (jiCi/cc)(Ci) Fraction Kr-83m 9.70E+06 0.00 4.50E-01 4.5E-01 1.00 4.5E-01 Kr-85 7.20E+05 0.00 7.70E+00 7.7E+00 1.00 7.7E+00 Kr-85m 2.10E+07 0.00 1.80E+00 1.8E+00 1.00 1.8E+00 Kr-87 4.00E+07 0.00 1 .20E+00 1 .2E+00 1.00 1 .2E+00 Kr-88 5.70E+07 0.00 3.50E+00 3.5E+00 1.00 3.5E+00 Kr-89 6.90E+07 0.00 1.10E-01 1.1E-01 1.00 1.1E-01 Xe-131m 8.40E+05 0.00 2.90E+00 2.9E+00 1.00 2.9E+00 Xe-133 1.50E+08 0.00 2.40E+02 2.4E+02 1.00 2.4E+02 Xe-I133m 4.80E+06 0.00 4.60E+00 4.6E+00 1.00 4.6E+00 Xe-135 3.50E+07 0.00 7.90E+00 7.9E+00 1.00 7.9E+00 Xe-I 35m 3.00E+07 0.00 4.50E-01 4.5E-01 1.00 4.5E-01 Xe=137 1.40E+08 0.00 2.00E-01 2.0E-01 1.00 2.0E-01 Xe-138 1.30E+08 0.00 7.20E-01 7.2E-01 1.00 7.2 E-01 1-131 7.50E+07 0.00 1.40E+00 1.4E+00 1.00E-06 1.4E-06 I-132 1.10E+08 0.00 2.30E+00 2.3E+00 1.00E-06 2.3E-06 I-133 1.60E+08 0.00 2.70E+00 2.7E+00 1.00E-06 2.7E-06 I-134 1.70E+08 0.00 6.30E-01 6.3E-01 1.00E-06 6.3E-07 1-135 1.50E+08 0.00 1.90E+00 1.9E+00 1.00E-06 1.9E-06 SM-SNC524602-001 SM-SNC52602-001ATTACHMENT E2ASHEE2-SH EET E2A-3 Postulated Release TEDE Calculations TEDE = Total Effective Dose Equivalent (mREM)TEDE = EDE + CEDE EDE = Effective Dose Equivalent (mREM) from external exposure EDE = DCFFGR-12 X XEAB X texp DCFFGR-12

= FGR-12 dose conversion factor [(mREM/hr)I(jpCilcc)]

CEDE = Committed Effective Dose Equivalent (mREM) from inhalation CEDE = DCFFGR-11 X XEAB X BR x texp.DCFFGR-11

= FGR-1 1 dose conversion factor (mREM/pCi)

XEAB = Radionuclide concentration at Exclusion Area Boundary (j#Ci/cc)XEAB = [QRLS (m^3/sec)]

x [XIQ (sec/m^3)]

x [XRLS (pCi/cc)]Qris = Release flow rate (m^3/sec)Qris = 1,060 CFM x [1 mini60 sec] x [0.0283 mA3/ftA3]

[Design Input #20]Oris = 0.50 mA3/sec X/Q = Atmospheric dilution factor (sec/mA3)X/Q = 4.87E-05 sec/m3 [Assumption

1. 3]texp = Exposure time texp = 1 .0 hour0 days <br />0 hours <br />0 weeks <br />0 months <br /> [Assumption

1. 1]BR = Breathing Rate (mA3/sec)BR = 3.47 E-04 mA3/sec [Assumption

1. 2]BR = 1 .25E+06 cc/hr = mA3/sec x [(1 .0E6 cc)/(1 mA3)] x [3600 sec/I hr]

SM-SNC524602-001 SM-SNC52602-OO1ATTACHMENT E2ASHEEA4 SHEET E2A-4 Isotope Release XEAB FGR-12 EDE FGR-11 CEDE Activity (1 iCi/cc) DCF (mREM) DCF (mREM)i/cc) i(m REMIh r)/ (m RE M/(p.Ci/cc) Kr-83m 4.5E-01 1.1IE-05 2.O0E+O1 2.2E-04 O.OOE+OO O.OE+O0 Kr-85 7.7E+00 1.9E-04 1.59E+03 3.0E-01 O.OOE+OO O.OE+OO Kr-85m I1.8E+O0 4.4E-05 9.96E+04 4.4E+00 O.OOE+O0 O.OE+OO Kr-87 I1.2E+O0 2.9E-05 5.49E+05 I1.6E+O1 O.OOE+OO O.OE+OO Kr-88 3.5E+00 8.5E-05 1.36E+06 1.2E+02 O.OOE+OO 0.0E+00 Kr-89 1.1 E-O1 2.7E-06 O.OOE+OO O.OE+OO O.OOE+O0 O.OE+0O Xe-131m 2.9E+00 7.lE-05 5.18E+03 3.7E-01 O.OOE+OO O.OE+OO Xe-133 2.4E+02 5.8E-03 2.08E+04 1.2E+02 O.OOE+OO O.OE+OO Xe-133m 4.6E+00 1.1E-04 1.82E+04 2.0E+OO O.OOE+OO O.OE+OO Xe-135 7.9E+O0 1.9E-04 1.59E+05 3.1 E+01 O.OOE+OO O.OE+OO Xe-135m 4.5E-01 1.1E-05 2.72E+05 3.OE+00 O.OOE+OO O.OE+OO Xe-I137 2.0E-01 4.9E-06 O.OOE+OO O.OE+OO O.OOE+OO O.OE+OO Xe-138 7.2E-01 1.8E-05 7.69E+05 1.3E+01 O.OOE+OO O.OE+OO 1-131 1.4E-06 3.4E-11 2.42E+05 8.3E-06 3.29E+01 1.4E-03 1-132 2.3E-06 5.6E-11 1.49E+06 8.4E-05 3.81E-01 2.7E-05 1-133 2.7E-06 6.6E-11 3.92E+05 2.6E-05 5.85E+00 4.8E-04 1-134 6.3E-07 1.5E-11 1.73E+'06 2.7E-05 1.31E-01 2.5E-06 1-135 1.9E-06 4.6E-11 1.06E+06 4.9E-05 1.23E+00 7.1E-05 Total = 3.1 E+02 mREM Total = 2.0E-03 mREM TEDE = EDE + CEDE EDE =CEDE =TEDE = 3.1E+02 3.1E+02 mREM 2.0E-03 mREM mREM SM-SNC524602-001 ATCMN 2 HE 2-ATTACHMENT E2A SHEET E2A-5 100 & 1000 mREM TEDE Thresholds Xioo = 100 mREM TEDE Noble Gas concetration Xioo = [(100 mREM)/(TEDE mREM)] x XRLS Xiooo =Xlooo =TEDE =3.3E-01 1000 mREM 10 xXioo 3.1E+02 mREM X XRLS TEDE Noble Gas concetration (pCi/cc)Isotope XRLS Xi00 Xi000(lpCi/cc)Kr-83rn 4.5E-01 1 .5E-01 I1.5E+00 Kr-85 7.7E+00 2.5E+00 2.5E+01 Kr-85m I1.8E+00 5.9E-01 5.9E+00 Kr-87 1.2E+-00 3.9E-0I 3.9E+00 Kr-88 3.5E+i00 I.1E+i00 1.1E+01 Kr-89 1.1IE-01 3.6 E-02 3.6E-01 Xe-131 m 2.9E+00 9.4 E-0I 9.4E+00 Xe-I133 2.4E+02 7.8E+01 7.8E+02 Xe-133m 4.6E+00 1.5E+00 1.5E+01 Xe-135 7.9E+00 2.6E+00 2.6E+01 Xe-135m 4.5E-01 1.5E-01 1.5E+00 Xe-137 2.0E-01 6.5E-02 6.5E-01 Xe-I138 7.2E-01 2.3E-01 2.3E+00 Totals 8.8E+01 8.8E+02 pCiIcc pC i/cc a SM-SNC524602-001 SM-SNC52602-001ATTACHMENT E2ASHEEA6 SHEET E2A-6 Thyroid CDE Calculations CDETHY = Thyroid Committed Dose Equivalent (mREM) from inhalation CDETnY = DCFFGR-11 X XEAB X BR x texp DCFFGR-11

= FGR-11I dose conversion factor (mREM/tCi/cc) texp = 1.00 hour0 days <br />0 hours <br />0 weeks <br />0 months <br /> BR = 1 .25E+06 cc/hr xS00T = 500 mREM Thyroid CDE Noble Gas concentration

(#iCi/cc)X5O0T = [(500 mREM CDE)/(CDETHY mREM)] x XRLS X500T = 500/ 6.3E-02 X XRLS = 7.9E+03 x XRLS X5000T = 5000 mREM Thyroid CDE Noble Gas concentration

(#iCi/cc)X5000T = 10 X X500T Postulated Release Thyroid CDE Thresholds Isotope XEAB FGR-11I CDETHY XRLS X500T X5000T (piCilcc)

DCF (mREM) (mREM/piCi)Kr-83m 1.1IE-05 0.00E+00 0.0E+00 4.5E-01t 3.6E+03 3.6E+04 Kr-85 1.9E-04 0.00E+00 0.0E+00 7.7E+00 6.1E+04 6.1E+05 Kr-85m 4.4E-05 0.00E+00 0.0E+00 1 .8E+00 1 .4E+04 1 .4E+05 Kr-87 2.9E-05 0.00E+00 0.0E+00 1.2E+00 9.5E+03 9.5E+04 Kr-88 8.5E-05 0.00E+00 0.0E+00 3.5E+00 2.8E+04 2.8E+05 Kr-89 2,7E-06 0.00E+00 0.0E+00 1.1E-01 8.7E+02 8.7E+03 Xe-131 m 7.1E-05 0.00E+00 0.0OE+00 2.9E+00 2.3 E+04 2.3 E+05 Xe-133 5.8E-03 0.00E+00 0.0E+00 2.4E+02 1.9E+06 1.9E+07 Xe-133m 1.1E-04 0.00E+00 0.0E+00 4.6E+00 3.6E+04 3.6E+05 Xe-135 1.9E-04 0.00E+00 0.0E+00 7.9E+00 6.3E+04 6.3E+05 Xe-135m 1.1 E-05 0.00E+00 0.0E+00 4.5E-01 3.6E+03 3.6E+04 Xe-137 4.9E-06 0.00E+00 0.0E+00 2.0E-0I 1.6E+03 1.6E+04 Xe-138 1.8E-05 0.00E+00 0.0E+00 7.2E-01 5.7E+03 5.7E+04 1-131 3.4E-11 '1.08E+03 4.6E-02 1-132 5.6E-11 6.44E+00 4.5E-04 I-133 6.6E-11 1.80E+02 1.5E-02 I-134 1 .5E-1 1 1 .07E+00 2.0E-05 1-135 4.6E-11 3.13E+01 1.8E-03 Total CDETHY =-6.3E-02 mREM Totals 2.2E+06 2.2E+07 lpCi/cc SM-SNC524602-001 ATCMN 2 HE 2-ATTACHMENT E2B SHEET E2B-1 SJAE Release Path TEDE & Thyroid CDE Calculations (Core Damage)Postulated Release Activity XRLS = Release Concentration (iC i/cc)XRLS = [Partition Factor x Xrcs x [prls (glcc)]Partition Factors[Assumption

1. 5]Noble Gases: 1.0 Iodine, liquid leakage to Auxiliary Building:

0.01 Iodine, primary coolant leakage to Containment building:

0.01 Iodine, primary coolant leakage to steam generator:

0.01 Iodine, SJAEs: 1.0E-04 Xrcs = RCS coolant activity (p, Ci/cc)Xrcs = RCS Equilibrium Activity (pCi/g) +[Release Fraction x Core Inventory (Ci) x (1 .0E+061iCi/1 Ci)]/MRcs (g)RCS Equilibrium Activity:

Design Input #14 Core Inventory:

Design Input #14 Release Fractions

[Assumption

1. 6]1.0 for Noble Gases (RG 1.183 Table 2, LOCA)0.4 for Iodine (RG 1.183 Table 2, LOCA)0 for no core damage MRCS = RCS coolant mass (Ibm)MRcs = 417,219 Ibm x (453.59 g/1 Ibm) [Design Input #11]MRCS = 1 .89E+08 g prls = Density of release fluid (g/cc)prls = 1 .00E+00 g/cc [Arbitrary Value]

SM-SNC524602-001 ATCMN 2 HE 2-ATTACHMENT E2B SHEET E2B-2 Isotope Core Core Xeq Xrcs (.LC ig) Partition XRLS Inventory Release Factor (jtCi/cc)(Ci) Fraction SKr-83m 9.70E+06 1.00 4,50E-01 5.1E+04 1.00 5,1E+04 Kr-85 7,20E+05 1.00 7.70E+00 3.8E+03 1.00 3.8 E+'03 Kr-85m 2.10E+07 1.00 1.80E+00 1.I E+05' 1.00 1,1IE+05 Kr-87 4.00E+07 1.00 1.20E+00 2.1E+05 1.00 2.IE+05 Kr-88 5,70E+07 1.00 3.50E+00 3.OE+05 1.00 3.0E+05 Kr-89 6.90E+07 1.00 1.10E-01 3.6E+05 1.00 3.6E+05 Xe-131 m 8.40 E+05 1.00 2.90 E÷00 4.4E+03 1.00 4.4E+03 Xe-133 1.50E+08 1.00 2.40E+02 7.9E+05 1.00 7.9E+05 Xe-133m 4.80E+06 1.00 4.60E+00 2.5E+04 1.00 2.5E+04 Xe-135 3.50E+07 1.00 7.90E+00 1.8E+05 1.00 1.8E+05 Xe-135m 3.00E+07 1.00 4.50E-01 1.6E+05 1.00 1.6E+05 Xe-137 1.40E+08 1.00 2.00E-01 7.4E+05 -1.00 7.4E+05 Xe-138 1.30E+08 1.00 7.20E-01 6.9E+05 1.00 6.9E+05 1-131 7.50E+07 0.40 1 40E+00 I 6E+05 I .OE-06 I 6E-01 I-132 1.10E+08 0.40 2.30E+00 2.3E+05 1.00E-06 2.3 E-01 1-133 1.60E+08 0.40 2.70E+00 3.4E+i05 1.00E-06 3.4E-01 1-134 1 .70E+08 0.40 6.30E-01 3.6E+05 1 .00E-06 3.6E-01 1-135 1.50E+08 0.40 l.90E+00 3.2E+05 1.00E-06 3.2E-01 SM-SNC524602-001 SM-SNC52602-001ATTACHMENT E2BSHEE23 SHEET E2B-3 Postulated Release TEDE Calculations TEDE = Total Effective Dose Equivalent (mREM)TEDE = EDE + CEDE EDE = Effective Dose Equivalent (mREM) from external exposure EDE = DCFFGR-12 x XEAB x texp DCFFGR-12

-FGR-12 dose conversion factor [(mREM/hr)/(j, Cilcc)]CEDE = Committed Effective Dose Equivalent (mREM) from inhalation CEDE = DCFFGR-11 x XEAB X BR x texp DCFFGR-11

= FGR-1 1 dose conversion factor (mREM/pCi)

XEAB = Radionuclide concentration at Exclusion Area Boundary (pCi/cc)XEAB = [QRLS (m^3/sec)]

x [X/Q (sec/m^3)]

x [XRLS (pCi/cc)]Qris = Release flow rate (mA3/sec)Qris = .1,060 CFM x [1 min/60 sec] x [0.0283 mA3/ft^3]

[Design Input #201 Qris = 0.50 mA3/sec X/Q = Atmospheric dilution factor (sec/m*3)X/Q = 4.87E-05 sec/m3 [Assumption

1. 3]texp =Exposure time texp = 1.0 hour0 days <br />0 hours <br />0 weeks <br />0 months <br /> [Assumption

1. 1]BR = Breathing Rate (mA3/sec)BR = 3.47E-04 mA3/sec [Assumption

1. 2]BR = 1 .25E+06 cc/hr = m^3/sec x [(1 .0E6 cc)/(1 m*3)] x [3600 sec/Ilhr]

SM-SNC524602-001 SM-SNC52602-OO1ATTACHMENT E2BSHEE24 SHEET E2B-4 Isotope Release XEAB FGR-12 EDE FGR-11 CEDE Activity (1DCF (mREM) DCF (mREM)(mREM/hr)l (mREMI Kr-83m 5,1E+04 1.2E+00 2.00E+01 2.5E+01 O.OOE+OO O.QE+OO Kr-85 3.8E+03 9,3E-02 1,.59E+03 1 .5E+02 O.OOE+OO O.OE+OO Kr-85m 1,1E+05. 2.7E+00 9.96E+04 2,7E+05 O,00E+OO O,0E+OO Kr-87 2,1E+05 5,1E+00 5,49E+05 2.8E+06 O.OOE+OO O.OE+OO Kr-88 3,0E+05 7.3E+00 1,.36E+06 I1,0E+07 0.OOE+OO O.OE+00 Kr-89 3,6E+05 8,9E+00 O,00E+OO O.OE+O0 0.OOE+OO O,0E+00 Xe-131m 4,4E+03 1.1E-01 5.18E+03 5,6E+02 0,00E+00 O.OE+OO Xe-133 7.9E+05 1,9E+01 2,08E+04 4.0E+05 O,00E+OO 0.0E+00 Xe-133m 2,5E+04 6.2E-01 1.82E+04 1,1E+04 O,00E+OO O,0E+OO Xe-135 1.8E+05 4,5E+00 1,59E+05 7.1E+05 O,00E+OO O.OE+O0 Xe-135m 1,6E+05 3.9E+00 2.72E+05 1,0E+06 0,00E+00 O,0E+00 Xe-137 7,4E+05 1,8E+01 0,00E+00 O,0E+OO O,00E+00 O,0E+00 Xe-138 6,9E+05 1.7E+01 7,69E+05 1,3E+07 0,00E+00 0,0E+00 1-131 1.6E-01 3.9E-06 2.42E+05 9.4E-01 3.29E+0-1 1.6E+02 1-132 2.3E-01 5.7E-06 1.49E+06 8.5E+00 3.81E-01 2.7E+00 1-133 3.4E-01 8.2E-06 3.92E+05 3.2E,+00 5.85E+00 6.0E+01 1-134 3.6E-01 8.8E-06 1.73E+06 1.5E+01 1.31E-01 1.4E+00 1-135 3.2E-01 7.7E-06 1.06E+06 8.2E+00 1.23E+00 1.2E+01 Total = 2.8E+07 mREM Total = 2.3E+02 mREM TEDE = EDE + CEDE EDE = 2.8E+07 mREM CEDE = 2.3E+02 mREM TEDE = 2.8E+07 mREM SM-SNC524602-001 SM-SNC52602-001ATTACHMENT E2BSHEE2-SHEET E2B-5 100 & 1000 mREM TEDE Thresholds Xioo =100 mREM TEDE Noble Gas concetration (jiCi/cc)Xioo =[(100 mREM)/(TEDE mREM)] x XRLS TEDE = 2.8E+07 mREM Xl000 =Xl000 -3.6E-06 1000 mREM 10 xXioo x XRLS TEDE Noble Gas concetration (gCi/cc)Isotope XRLS Xi00 Xi000i/cc) i/cc) Kr-83m 5.1 E+04 1.8 E-01 1.8E+00 Kr-85 3.8E+03 1 .4E-02 1 .4E-01 Kr-85m 1.1E+05 3.9 E-01 3..9E+00 Kr-87 2.1 E+05 7.5E-01 7.5E+00 Kr-88 3.0E+05 1.1IE+00 1.1 E+01 Kr-89 3.6E+05 1 .3E+00 1 .3E+01 Xe-131 m 4.4E+03 1.6E-02 1.6E-01 Xe-i133 7.9E+05 2.8E+'00 2.8E+01 Xe-133m 2.5E+'04 9,0E-02 9.0E-01 Xe-135 1.8 E+05 6.6E-01 6.6 E+00 Xe-135m 1.6E+05 5.6E-01 5.6 E+00 Xe-I137 7.4E+05 2.6E+00 2.6E+01 Xe-i138 6.9E+05 2.4E+00 2.4E+01 Totals 1.3E+01 1.3E+02 pCilcc pCi/cc SM-SNC524602-001 SM-SN052602-001ATTACHMENT E2BSHEE26 SHEET E2B-6 Postulated Release Thyroid CDE Calculations CDETHY = Thyroid Committed Dose Equivalent (mREM) from inhalation CDETHY = DCFFGR-11 X XEAB X BR X texp DCFFGR-I1

= FGR-11I dose conversion factor (mREM/tCi/cc) texp -1.00 hour0 days <br />0 hours <br />0 weeks <br />0 months <br /> BR = 1 .25E+06 cc/hr X5OOT = 500 mREM Thyroid ODE Noble Gas concentration X500T = [(500 mREM CDE)/(CDETHY mREM)] x XRLS X5OOT = 500/ 7.4E+03 x XRLS = 6.7E-02 x XRLS X5000T = 5000 mREM Thyroid ODE Noble Gas concentration (pCi/cc)X5000T = 10 x X500T Postulated Release Thyroid CDE Thresholds Isotope XEAB FGR-11I CDETHY XRLS X500T X5000T (jxCilcc)

DCF (mREM) (jtCi/cc) (jiCi/cc) (mREMI pCi)Kr-83m 1.2E+00 0.00E+00 0.0E+00 5.1E+04 3.5E+03 3.5 E+04 Kr-85 9.3E-02 0.00E+00 0.0E+00 *3.8E+03 2.6E+02 2.6E+03 Kr-85m 2.7E+00 0.00E+00 0.0OE+00 1.1IE+05 7.5E+03 7.5E+04 Kr-87 5.1E+00 0.00E+'00 0.0E+00 2.1E+05 1.4E+04 1.4E+05 Kr-88 7.3E+00 0.00E+00 0.0E+00 3.0E+05 2.0E+04 2.0E+05 Kr-89 8.9E+I00 0.00E+00 0.0E+00 3.6E+05 2.5E+04 2.5E+05 Xe-131 m 1.1E-01 0.O0E+00 0.0OE+00 4.4E+03 3.0OE+02 3.0E+i03 Xe-133 1.9E+01 0.OOE+00 0.0E+00 7.9E+05 5.3E+04 5.3E+05 Xe-133m 6.2E-01 0.00E+00 0.0E+00 2.5E+04 1.7E+03 1.7E+04 Xe-135 4.5E+00 0.00E+00 0.0E+00 1.8E+05 1.2E+04 1.2E+05 Xe-135m 3.9E+00 0.00E+00 0.0E+00 1.6E+05 1.IE+04 1.1E+05 Xe-137 1.8E+01 0.00OE+00 0.0E+00 7.4E+05 5.0OE+04 5.0E+05 Xe-138 1.7E+01 0.00E+00 0.0E+00 6.9E+05 4.6E+04 4.6E+05 I-131 3.9E-06 1.08E+03 5.2 E+03 I-132 5.7E-06 6.44E+00 4.6E+01 I-133 8.2E-06 1.80E+02 1.9E+03 I-134 8.8E-06 1.07E+00 1.2E+01 1-135 7.7E-06 3.13E+01 3.0E+02 Total CDETHY " 7.4E+03 mREM Totals 2.4E+05 ipCilcc 2.4E+06 SM-SNC524602-001IATCMN 3 HE 3-ATTACHMENT E3A SHEET E3A-1 SIG SRVs & ARVs Release Path TEDE & Thyroid CDECalculations (No Core Damage)Postulated Release Activity XRLS = Release Concentration (FiCi/cc)XRLS = [Partition Factor x Xrcs (jiCi/g)]

x [prls (g/cc)]Partition Factors[Assumption

1. 5]Noble Gases: 1.0 Iodine, liquid leakage to Auxiliary Building:

0.01 Iodine, primary coolant leakage to Containment building:

0.01 Iodine, primary coolant leakage to steam generator:

0.01 Iodine, SJAEs: 1 .0E-04 Xrcs = RCS coolant activity (p.Ci/cc)Xrcs = RCS Equilibrium Activity +[Release Fraction x Core Inventory (Ci) x (1 .0E+06 pCi/I Ci)]IMRcs (g)RCS Equilibrium Activity:

Design Input #14 Core Inventory:

Design Input #14 Release Fractions

[Assumption

1. 6]1.0 for Noble Gases (RG 1.183 Table 2, LOCA)0.4 for Iodine (RG 1.183 Table 2, LOCA)0 for no core damage MRCS = RCS coolant mass (Ibm)MRcs = 417,219 Ibm x (453.59 g/1 Ibm) [Design Input #111 MRcs- =1I.89E+08 g prls = Density of release fluid (g/cc)pris = 1 .00E+00 g/cc [Arbitrary Value]

SM-SNC524602-001 ATCMN 3 HE 3-ATTACHMENT E3A SHEET E3A-2 Isotope Core Core Xeq Xrcs ilg) Partition XRLS Inventory Release (jxCilg) Factor (Ci) Fraction Kr-83m 9.70E+06 0.00 4,50E-01 4,5E-01 1.00 4.5E-01 Kr-85 7.20E+05 0.00 7,70E+00 7.7E+00 1.00 7.7E+00 Kr-85m 2.10E+07 0.00 1.80E+00 1.8E+00 1.00 1.8E+00 Kr-87 4.00E+07 0.00 1 .20E+00 1 .2E+00 1.00 1 .2E+00 Kr-88 5.70E+07 0.00 3.50E+00 3.5E+00 1.00 3.5E+00 Kr-89 6.90E+07 0.00 1.10E-01 1.1E-01 1.00 1.1E-01 Xe-131 m 8,40 E+05 0.00 2.90E+00 2,9 E+00 1.00 2,9 E+00 Xe-133 1.50E+08 0.00 2.40E+02 2.4E+02 1.00 2.4E+02 Xe-133m 4.80E+06 0.00 4,60E+00 4.6E+00 1.00 4.6E+00 Xe-135 3.50E+07 0.00 7,90E+00 7.9E+00 1.00 7,9E+00 Xe-135m 3.00E+07 0.00 4.50E-01 4.5E-01 1.00 4,5E-01 Xe-137 1.40E+08 0.00 2,00E-01 2.0E-01 1.00 2.0E-01 Xe-138 1.30E+08 0.00 7,20E-01 7.2 E-01 1.00 7.2E-01 I-131 7.50E+07 0.00 1.40E+00 1.4E+00 0.01 1.4E-02 I-132 1.I0E+08 0.00 2.30E+00 2.3E+00 0.01 2.3E-02 1-133 1.60E+08 0.00 2.70E+00 2.7E+00 0.01 2.7E-02 I-134 1.70E+08 0.00 6.30E-01 6.3E-01 0.01 6.3E-03 1-135 1.50E+08 0.00 1.90E+00 1.9E+00 0.01 1.9E-02 SM-SNC524602-001 SM-SNC52602-001ATTACHMENT E3ASHEE33 SHEET E3A-3 Postulated Release TEDE Calculations TEDE = Total Effective Dose Equivalent (mREM)TEDE = EDE + CEDE EDE = Effective Dose Equivalent (mREM) from external exposure EDE = DCFFGR-12 x XEAB X texp DCFFGR-12

= FGR-12 dose conversion factor [(mREM/hr)/(pfCi/cc)]

CEDE = Committed Effective Dose Equivalent (mREM) from inhalation CEDE = DCFFGR-11 X XEAB X BR x texp DCFFGR-11

-FGR-11I dose conversion factor (mREM/jiCi)

XEAB "- Radionuclide concentration at Exclusion Area Boundary (!tCi/cc)XEAB = [QRLS (m^3/sec)]

X [X/Q (sec/m^3)]

x [XRLS (jtCi/cc)]

Oris = Release flow rate (m^3/sec)QRLS = 613,000 Ibm/hr x SVstm (cu ft/Ibm) x [1 hr/60 mini [Assumption

1. 4]SVstm = Specific Volume of Saturated Steam @ Patrm SVstm = 26.804 cu ft/Ibm [Assumption

1. 8]QRLS "- 2.74E+05 CFM x [1 min/60 sec] x [0.0283 m^3/ft^3]QRLs = 129.2 mA3/sec X/Q = Atmospheric dilution factor (sec/m^3)X/Q = 4.87E-05 sec/m3 [Assumption

1. 3]texp = Exposure time texp -1.0 hour0 days <br />0 hours <br />0 weeks <br />0 months <br /> [Assumption

1. 1]BR = Breathing Rate (mA3/sec)BR = 3.47E-04 mA3/sec [Assumption

1. 2]BR = 1 .25E+06 cc/hr = m^3/sec x [(1 .0E6 cc)/(1 mA3)] x [3600 sec/i hr]

SM-SNC524602-001 SM-SNC52602-OOIATTACHMENT E3ASHEE3-SHEET E3A-4 Isotope Release XEAB FGR-1 2 EDE FGR-11I CEDE Activity (jltCilcc)

DCF (mREM) DCF (mREM)(JlCilcc) (mREM/hr)l (mREMI pCi)Kr-83m 4.5E-01 2.8E-03 2.00E+01 5.7E-02 O.OOE+OO O.OE+OO Kr-85 7.7E+00 4.8E-02 1 .59E+03 7.7E+01 0.OOE+OO O.OE+OO Kr-85m 1.8E+00 1.IE-02 9.96E+04 1.1E+'03 0.OOE+00 0.OE+00O Kr-87 1.2E+00 7.6E-03 5.49E+05 4.1E+03 O.OOE+OO O.OE+OO Kr-88 3.5E+00 2.2E-02 I1.36E+06 3.0E+04 O.OOE+00 O.OE+OO Kr-89 1.1E-01 6.9E-04 0.OOE+OO 0.0E+00O O.OOE+OO 0.0E+00 Xe-131m 2.9E+00 1.8E-02 5.18E+03 9.5E+01 O.00E+OO O.OE+OO Xe-133 2.4E+02 I.5E+00 2.08E+04 3.1E+04 O.OOE+OO 0.0E+00O Xe-133m 4.6E+00 2.9E-02 1.82E+04 5.3E+02 O.O0E+OO 0.OE+00 Xe-135 7.9E+00 5.0E-02 1.59E+05 7.9E+03 O.OOE+00 O.OE+O0 Xe-I135m 4.5E-01 2.8E-03 2.72E+05 7.7E+I02 0.OOE+OO O.OE+OO Xe-137 2.0E-01 I.3E-03 O.OOE+OO O.OE+O0 O.OOE+OO O.OE+OO Xe-I138 7.2E-01 4.5E-03 7.69E+05 3.5E+03 O.00E+OO O.QE+OO;I-131 1.4E-02 8.8E-05 2.42E+05 2.1E+01 3.29E+01 3.6E+03!1-132 2.3E-02 1.4E-04 1.49E+06 2.2E+02 3.81E-01 6.9E+01 1-133 2.7E-02 1.7E-04 3.92E+05 6.7E+01 5.85E+00 1.2E+03 1-134 6.3E-03 4.0E-05 1.73E+06 6.9E+01 I.31E-01 6.5E+00 1-135 I.9E-02 1.2E-04 1.06E+06 1.3E+02 1.23E+00 1.8E+02 Total = 8.0E+04 mREM Total = 5.1 E+03 mREM.5 TEDE = EDE + CEDE EDE =CEDE =TEDE = 8.5E+04 8.0E+04 mREM 5.1E+03 mREM mREM SM-SNC524602-001 ATCMN 3 HE 3-ATTACHMENT E3A SHEET E3A-5 100 & 1000 mREM TEDE Thresholds Xioo = 100 mREM TEDE Noble Gas concetration (pCi/cc)Xioo = [(100 mREM)/(TEDE mREM)] x XRLS TEDE = 8.5E+04 mREM Xioo = 1 .2E-03 X XRLS X1000 Xiooo-1000 mREM= 10 xXioo TEDE Noble Gas concetration (p.Ci/cc)Isotope XRLS Xioo Xi000 Kr-83m 4.5E-01 5.3E-04 5.3E-03 Kr-85 7.7E+00 9.1E-03 9.1E-02 Kr-85m 1.8E+00 2.1E-03 2.1IE-02 Kr-87 1 .2E+00 I1.4E-03 1 .4E-02 Kr-88 3.5E+00 4.1E-03 4.1E-02 Kr-89 1.1 E-01 1.3E-04 1.3E-03 Xe-131 m 2.9E+00 3.4 E-03 3.4 E-02 Xe-I133 2.4E+'02 2.8E-01 2.8E+00 Xe-I133m 4.6E+00 5.4E-03 5.4E-02 Xe-1 35 7.9E+00 9.3E-03 9.3E-02 Xe-i135m 4.5E-0I 5.3E-04 5.3E-03 Xe-I137 2.0E-0l 2.4E-04 2.4E-03 Xe-i138 7.2E-0I 8.5E-04 8.5E-03 Totals 3.2E-01 3.2E+00 pCi/cc pC ilc c SM-SNC524602-001 ATCMN 3 HE 3-ATTACHMENT E3A SH EET E3A-6 Thyroid CDE Calculations CDETHY = Thyroid Committed Dose Equivalent (mREM) from inhalation CDETHY = DCFFGR-11 X XEAB X BR x texp DCFFGR-11

= FGR-11I dose conversion factor (mREM/jiCi/cc)

X500T =XS00T =X500T =X5000T =texp " 1.00 hour0 days <br />0 hours <br />0 weeks <br />0 months <br /> BR 1 1.25E+06 cc/hr 500 mREM Thyroid CDE Noble Gas concentration (iCi/cc)[(500 mREM CDE)/(CDETHY mREM)] x XRLS 500/ 1 .6E+05 X XRLS = 3.1 E-03 X XRLS 5000 mREM Thyroid CDE Noble Gas concentration (iCi/cc)X5000T = 10 X X500T Y Postulated Release Thyroid CDE Thresholds Isotope XEAB FGR-11I CDETHY XRLS X500T X5000T (jtCi/cc)

DCF (mREM) (jltCilcc) (jiCilcc)(mREMI jiCi)Kr-83m 2.8E-03 0.00E+00 0.0E+00 4.5E-01 I1.4E-03 I1.4E-02 Kr-85 4.8E-02 0.00E+00 0.0E+00 7.7E+00 2.4E-02 2.4E-01 Kr-85m 1.1IE-02 0.O0E+00 0.0E+00 1.8E+00 5.5E-03 5.5E-02 Kr-87 7.6E-03 0.00E+00 0.0E+00 I1.2E+00 3.7E-03 3.7E-02 Kr-88 2.2E-02 0.00E+00 0.0E+00 3.5E+00 1.1E-02 1.1E-01 Kr-89 6.9E-04 0.00E+00 0.0E+00 1.1 E-01 3.4E-04 3.4E-03 Xe-131 m 1.8E-02 0.00E+00 0.0E+00 2.9E+00 8.9E-03 8.9 E-02 Xe-133 1.5E+00 0.00E+00 0.0E+00 2.4E+02 7.4E-01 7.4E+00 Xe-133m 2.9E-02 0.00E+00 0.0E+00 4.6E+-00 1.4E-02 1.4E-01 Xe-I135 5.0E-02 0.00E+00 0.0E+00 7.9E+00 2.4E-02 2.4E-01 Xe-135m 2.8E-03 0.00E+00 0.0E+00 4.5E-01 1.4E-03 1.4 E-02 Xe-137 1.3E-03. 0.00E+00 0.0E+00 2.0E-01 6.1E-04 6.1E-03 Xe-i138 4.5E-03 0.00E+00 0.0E+00 7.2E-01 2.2E-03 2.2E-02 I-131 8.8E-05 1.08E+03 1.2E+05 I-132 1.4 E-04 6.44E+00 1.2E+'03 I-133 1.7E-04 1.80E+02 3.8 E+04 I-134 4.0E-05 1.07E+00 5.3E+01 1-135 1.2E-04 3.13E+01 4.7E+03 Total CDETHY =I1.6E+05 mREM Totals 8.3E-01 J.LCilcc 8.3E+00 IpCi/cc I I SM-SNC524602-001 ATCMN 3 HE 3-ATTACHMENT E3B SHEET E3B-1 SIG SRVs & ARVs Release Path TEDE & Thyroid CDECalculations (Core Damage)Postulated Release Activity XRLS -"Release Concentration XRLS =[Partition Factor x Xrcs (jiCi/g)]

x [pris (g/cc)]Partition Factors[Assumption

1. 5]Noble Gases: 1 .0 Iodine, liquid leakage to Auxiliary Building:

0.01 Iodine, primary coolant leakage to Containment building:

0.01 Iodine, primary coolant leakage to steam generator:

0.01 Iodine, SJAEs: 1.0E-04 Xrcs =RCS coolant activity (iC i/cc)Xrcs =RCS Equilibrium Activity (pCi/g) +[Release Fraction x Core Inventory (Ci) x (1 .0E+i06jiCi/1 Ci)]/MRcs (g)RCS Equilibrium Activity:

Design Input #14 Core Inventory:

Design Input #14 Release Fractions

[Assumption

1. 6]1.0 for Noble Gases (RG 1.183 Table 2, LOCA)0.4 for Iodine (RG 1.183 Table 2, LOCA)0 for no core damage MRCS = RCS coolant mass (Ibm)MRCS = 417,219 Ibm x (453.59 g/1 Ibm) [Design Input #11]MRcs = 1 .89E+08 g pris --Density of release fluid (g/cc)pris -' 1.00E+00 g/cc [Arbitrary Value]

SM-SNC524602-001 ATCMN 3 HE 3-ATTACHMENT E3B SHEET E3B-2 Isotope Core Core Xeq Xrcs (llCi/g) Partition XRLS Inventory Release (jlCilg) Factor (liCi/cc)(Ci) Fraction Kr-83m 9.70E+06 1.00 4.50E-01 5.1E+04 1.00 5.1E+04 Kr-85 7.20E+05 1.00 7.70E+00 3.8E+03 1.00 3.8E+03 Kr-85m 2.10E+07 1.00 1.80E+00 1.1E+05 1.00 1.1E+05 Kr-87 4.00E+07 1.00 1.20E+00 2.1IE+05 1.00 2.1E+05 Kr-88 5.70E+07 1.00 3.50E+00 3.0E+05 1.00 3.0E+05 Kr-89 6.90E+07 1.00 1.10E-01 3.6E+05 1.00 3.6E+05 Xe-131m 8.40E+05 1.00 2.90E+00 4.4E+03 1.00 4.4E+03 Xe-133 1.50E+08 1.00 2.40E+02 7.9E+05 1.00 7.9E+05 Xe-133m 4.80E+06 1.00 4.60E+00 2.5E+04 1.00 2.5E+04 Xe-135 3.50E+07 1.00 7.90E+00 1.8E+05 1.00 1.8E+05 Xe-135m 3.00OE+07 1.00 4.50 E-01 1.6 E+05 1.00 1.6 E+05 Xe-137 1.40E+08 1.00 2.00E-01 7.4E+05 1.00 7.4E+05 Xe-138 1.30E+08 1.00 7.20E-01 6.9E+05 1.00 6.9E+05 I-131 7.50E+07 0.40 1.40E+00 1.6E+05 0.01 1.6E+03 I-132 1.10E+08 0.40 2.30E+00 2.3E+05 0.01 2.3E+03 1-133 1.60E+08 0.40 2.70E+00 3.4E+05 0.01 3.4E+03 I-134 1.70E+08 0.40 6.30E-01 3.6E+05 0.01 3.6E+03 1-135 1.50E+08 0.40 1.90E+00 3.2E+05 0.01 3.2E+03 SM-SNC524602-001 SM-SNC52602-001ATTACHMENT E3BSHEEB-SHEET E3B-3 Postulated Release TEDE Calculations C C TEDE = Total Effective Dose Equivalent (mREM)TEDE = EDE + CEDE EDE = Effective Dose Equivalent (mREM) from external exposure EDE = DCFFGR-12 X XEAB X texp DCFFGR-12

= FGR-12 dose conversion factor [(mREM/hr)/(p,iCi/cc)]

3EDE = Committed Effective Dose Equivalent (mREM) from inhalation 3EDE = DCFFGR-11 X XEAB X BR x texp DCFFGR-11

= FGR-l11 dose conversion factor (mREM/p, Ci)XEAB = Radionuclide concentration at Exclusion Area Boundary (pCi/cc)XEAB = [QRLs (m^3/sec)]

x [X/Q (sec/m^3)]

x [XRLS (pCi/cc)]Qris -Release flow rate (mA3/sec)QRLS = 613,000 Ibm/hr x SVstm (cu ft/Ibm) x [1 hr/60 min] [Assur SVstrn = Specific Volume of Saturated Steam @ Patm SVstrn = 26.804 cu ft/Ibm [Assur QRLS = 2.74E+05 CFM x [1 mini60 sec] x [0.0283 m^3/ft^3]QRLS = 129.2 m^3/sec X/Q = Atmospheric dilution factor (sec/mA3)X/Q = 4.87E-05 :sec/m3 [Assur texp = Exposure time texp -1.0 hour0 days <br />0 hours <br />0 weeks <br />0 months <br /> [Assur BR = Breathing Rate (mA3/sec)BR = 3.47E-04 m^3/sec [Assur*BR = 1 .25E+06 cc/hr = m^3/sec x [(1 .0E6 cc)/(1 mA3)] x [3600 sec/I h nption #4]nption #8]nption #3]nption #1]nption #2]r]

SM-SNC524602-001 SM-SNC52602-OO1ATTACHMENT E3BSHEEB4 SHEET E3B-4 Isotope Release XEAB FGR-12 EDE FGR-11 CEDE Activity DCF (mREM) DCF (mREM)(mREM/hr)/ (mREM/(pCilcc) pCi)Kr-83m 5.1E+04 3.2E+02 2.00E+01 6.4E+03 O.00E+OO O.OE+OO Kr-85 3.8E+03 2.4E+01 1.59E+03 3.8E+04 O.00E+OO O.0E+00 Kr-85m 1.1E+05 7.0E+02 9.96E+04 7.0E+'07 O.OOE+OO O.OE+OO Kr-87 2.1E+05 1.3E+03 5.49E+05 7.3E+08 0.00E+00 O.OE+OO Kr-88 3.0E+05 1 .9E+03 I1.36E+06 2.6E+09 O.O0E+00O O.OE+00O Kr-89 3.6E+05 2.3E+03 O.00E+O0 0.OE+OO O.00E+00O 0.0E+00 Xe-131m 4.4E+03 2.8E+01 5.18E+03 1.4E+05 O.00E+OO O.OE+OO Xe-133 7.9E+05 5.0E+03 2.08E+04 1.0E+08 O.OOE+OO O.OE+00 Xe-133m 2.5E+04 1.6E+02 l.82E+04 2.9E+06 O.OOE+OO O.OE+OO Xe-135 1.8E+05 1.2E+03 l.59E+05 1.8E+08 O.OOE+00O 0.0E+00O Xe-135m 1.6E+05 1.0E+03 2.72E+05 2.7E+08 O.OOE+OO O.OE+00 Xe-I137 7.4E+05 4.7E+03 O.OOE+OO O.OE+OO O.OOE+OO O.OE+00 Xe-i138 6.9E+05 4.3E+03 7.69E+05 3.3E+'09 O.OOE+OO O.QE+OO 1-131 1.6E+03 1.0E+01 2.42E+05 2.4E+06 3.29E+01 4.1E+0-8 1-132 2.3E+03 1.5E+01 1.49E+06 2.2E+07 3.81E-01 7.0E+-06 1-133 3.4E+03 2.1E+01 3.92E+05 8.3E+06 5.85E+00 1.6E+08 1-134 3.6E+03 2.3E+01 1.73E+06 3.9E+07 1.31E-01 3.7E+06 1-135 3.2E+03 2.0E+01 1.06E+06 2.1E+07 1.23E+00 3.1E+'07 Total = 7.4E+09 mREM Total = 6.1E+08 mREM TEDE = EDE + CEDE EDE = 7.4E+09 mREM CEDE = 6.1E+08 mREM TEDE = 8.0E+09 mREM SM-SNC524602-001 ATCMN 3 HE 3-ATTACHMENT E3B SHEET E3B-5 100 & 1000 mREM TEDE Thresholds Xioo = 100 mREM TEDE Noble Gas concetration Xio0 = [(100 mREM)/(TEDE mREM)] x XRLS Xlooo =Xiooo =TEDE =I1.3E-08 1000 mREM 10 x ioo 8.0E+09 mREM X XRLS TEDE Noble Gas concetration Isotope XRLS Xioo Xiooo (piCilcc) (litCi/cc) (lpCilcc)Kr-83m 5.1 E+04 6.4E-04 6.4E-03 Kr-85 3.8E+03 4.8E-05 4.8E-04'Kr-85m 1.1E+05 1.4E-03 1.4E-02'Kr-87 2.1E+05 2.7E-03 2.7E-02 Kr-88 3.0E+05 3.8E-03 3.8E-02 Kr-89 3.6E+05 4.6E-03 4.6E-02 Xe-131 m 4.4 E+03 5.6E-05 5.6 E-04 Xe-133 7.9E+05 1.0E-02 1.0E-01 Xe-I133m 2.5E+04 3.2E-04 3.2E-03 Xe-135 1.8E+05 2.3E-03 2.3E-02 IXe-135m 1.6E+05 2.0E-03 2.0OE-02 Xe-I137 7.4E+05 9.3E-03 9.3E-02 Xe-I138 6.9E+05 8.6E-03 8.6E-02 Totals 4.6E-02 4.6E-01 J.LCiIcC pCi/cc SM-SNC524602-001 ATCMN 3 HE 3-ATTACHMENT E3B SHEET E3B-6 Thyroid CDE Calculations CDETHY = Thyroid Committed Dose Equivalent (mREM) from inhalation CDETHY = DCFFGR-11 X XEAB X BR x texp DCFFGR-11

=FGR-11I dose conversion factor (mREM/p#Ci/cc) texp -1 .00 hour0 days <br />0 hours <br />0 weeks <br />0 months <br /> BR = I1.25E+06 cc/hr Xsoom = 500 mREM Thyroid CDE Noble Gas concentration (p#Ci/cc)X500T = [(500 mREM CDE)/(CDETHY mREM)] x XRLS X500T = 500/ 1 .9E+1 0 X XRLS -2.6E-08 X XRLS X5000T = 5000 mREM Thyroid CDE Noble Gas concentration

(#iCi/cc)X5000T = 10 X XSOOT Postulated Release Thyroid CDE Thresholds Isotope XEAB FGR-11I CDETHY XRLS X500T X5000T (p.Ci/cc)

DCF (mREM) (lpCi/cc) (mREM/lpCi)Kr-83m 3.2E+02 0.00E+00 0.0E+00 5.1E+04 1.3E-03 1.3E-02 Kr-85 2.4E+01 0.00E+00 0.0E+00 3.8E+03 9.9E-05 9.9E-04 Kr-85m 7.0E+'02 0.00E+00 0.0E+00 1.1 E+05 2.9E-03 2.9E-02 Kr-87 1.3E+03 0.00E+00 0.0E+00 2.1IE+05 5.5E-03 5.5E-02 Kr-88 1.9E+03 0.00E+00 0.0E+00 3.0E+05 7.9E-03 7.9E-02 Kr-89 2.3E+03 0.00E+00 0.0E+00 3.6E+05 9.5E-03 9.5E-02 Xe-131 m 2.8E+01 0.00E+00 0.0E+00 4.4E+03 1.2E-04 1.2E-03 Xe-133 5.0E+03 0.00E+00 0.0E+00 7.9E+05 2.1E-02 2.1E-01 Xe-i133m 1 .6E+02 0.00E+00 0.0OE+00 2.5E+04 6.6 E-04 6.6 E-03 Xe-135 1.2E+03 0.00E+00 0.0E+00 1.8 E+05 4.8 E-03 4.8 E-02 Xe-135m 1.0E+03 0.00E+00 0.0E+00 1.6E+05 4.1E-03 4.1 E-02 Xe-137 4.7E+03 0.00E+00 0.0E+00 7.4E+05 1.9E-02 1.9E-01 Xe-138 4.3E+03 0.00E+00 0.0E+00 6.9E+05 1.8 E-02 1.8E-01 1-131 1.0E+01 1.08E+03 1.3E+10 I-132 1.5E+01 6.44E+00 1.2E+08 I-133 2.1E+01 1.80E+02 4.8 E+09 I-134 2.3E+01 1.07E+00 3.0E+07-352.0E+01 3.13E+01 7.8E+08 Total CDETHY =1.9E+10 mREM Totals 9 .5E-02 lpCi/cc 9.5E-01 lpCi/cc SM-SNC524602-001 SM-SNC52602-001ATTACHMENT E4ASHEEA-SHEET E4A-1 TDAFWP Exhaust Release Path TEDE & Thyroid CDE Calculations (No Core Damage)Postulated Release Activity XRLS -- Release Concentration XRLS = [Partition Factor x Xrcs i/g)] x [pris (glcc)]Partition Factors[Assumption

1. 5]Noble Gases: 1.0 Iodine, liquid leakage to Auxiliary Building:

0.01 Iodine, primary coolant leakage to Containment building:

0.01 Iodine, primary coolant leakage to steam generator:

0.01 Iodine, SJAEs: 1 .0E-04 Xrcs = RCS coolant activity (p.Ci/cc)Xrcs = RCS Equilibrium Activity (pCi/g) +[Release Fraction x Core Inventory (Ci) x (1 .0E+06p.Ci/1 Ci)]/MRcs (g)RCS Equilibrium Activity:

Design Input #14 Core Inventory:

Design Input #14 Release Fractions

[Assumption

1. 6]1.0 for Noble Gases (RG 1.183 Table 2, LOCA)0.4 for Iodine (RG 1.183 Table 2, LOCA)0 for no core damage MRCS = RCS coolant mass (Ibm)MRcs = 417,219 Ibm x (453.59 g/l Ibm) [Design Input #11]MRCS = 1 .89E+08 g prls = Density of release fluid (g/cc)prls = 1 .00E+00 g/cc [Arbitrary Value]

SM-SNC524602-001 SM-SNC52602-001ATTACHMENT E4ASHEE4-SHEET E4A-2 Isotope Core Core Xeq Xrcs i/g) Partition XRLS Inventory Release (lpCi/g) Factor (Ci) Fraction Kr-83rm 9,70E+06 0.00 4.50E-01 4,5E-01 1.00 4,5E-01 Kr-85 7.20E+05 0.00 7.70E+00 7.7E+00 1.00 7.7E+00 Kr-85m 2,10E+07 0.00 1.80E+00 1.8E+00 1.00 1.8 E+00 Kr-87 4.00E+07 0.00 1 .20E+00 1,.2E+00 1.00 1,.2E+00 Kr-88 5.70E+07 0.00 3.50E+00 3.5E+00 1.00 3.5E+00 Kr-89 6.90E+07 0.00 1.10E-01 1.1E-01 1.00 1.1E-01 Xe-131m 8.40E+05 0.00 2.90E+00 2.9E+00 1.00 2.9E+00 Xe-133 1.50E+08 0.00 2.40E+02 2.4E+02 1.00 2.4E+02 Xe-133m 4.80E+06 0.00 4.60E+00 4.6E+00 1.00 4.6E+00 Xe-135 3.50E+07 0.00 7.90E+00 7.9E+00 1.00 7.9E+00 Xe-135m 3.00E+07 0.00 4.50E-01 4.5E-01 1.00 4.5E-01 Xe-137 1.40E+08 0.00 2.00E-01 2.0E-01 1.00 2.0E-01 Xe-138 1.30E+08 0.00 7.20E-01 7.2E-01 1.00 7.2E-01 1-131 7.50E+07 0.00 1.40E+00 1.4E+00 0.01 1.4E-02 1-132 1.10E+08 0.00 2.30E+00 2.3E+00 0.01 2.3E-02 1-133 1.60E+08 0.00 2.70E+00 2.7E+00 0.01 2.7E-02 I-134 1.70E+08 0.00 6.30E-01 6.3E-01 0.01 6.3 E-03 1-135 1.50E+08 0.00 1.90E+00 1.9E+00 0.01 1.9E-02 SM-S NC524602-001 ATCMN 4 HE 4-ATTACHMENT E4A SHEET E4A-3 Postulated Release TEDE Calculations TEDE TEDE EDE EDE CEDE CEDE XEAB XEAB Qris QRLS QRLS QRLS texp texp BR BR BR= Total Effective Dose Equivalent (mREM)-EDE + CEDE= Effective Dose Equivalent (mREM) from external exposure= DCFFGR-12 x XEAB X texp DCFFGR-12

= FGR-1 2 dose conversion factor

-Committed Effective Dose Equivalent (mREM) from inhalation

= DCFFGR-11 X XEAB X BR x texp DCFFGR-11

= FGR-11I dose conversion factor (mREM/tCi)

= Radionuclide concentration at Exclusion Area Boundary (PCi/cc)= [QRLS (m^3/sec)]

x [X/Q (sec/m^3)]

x [XRLS (#iCi/cc)]

= Release flow rate (mA3/sec)= 26,106 Ibm/hr x SVstm (cu ft/Ibm) x [1 hr/GO min] [Design Input #221 SVstm = Specific Volume of Saturated Steam @ Patm SVstm = 26.804 cu ft/Ibm [Assumption

1. 8]= 1.1 7E+04 CFM x [1 min/GO sec] x [0.0283 mA3/ftA3]= 5.5 mA3/sec= Atmospheric dilution factor (sec/m^3)= 4.87E-05 sec/m3 [Assumption

1. 3]= Exposure time=1.0 hour0 days <br />0 hours <br />0 weeks <br />0 months <br /> [Assumption

1. 1]-Breathing Rate (mA3/sec)= 3.47 E-04 m^3/sec [Assumption

1. 2]= 1 .25E+06 cc/hr = mA3/sec x [(1 .0E6 cc)/(1 mA3)] x [3600 sec/i hr]

SM-SNC524602-001 SM-SNC52602-OO1ATTACHMENT E4ASHE 4-SHEET E4A-4 Isotope Release XEAB FGR-12 EDE FGR-11 CEDE Activity DCF (mREM) DCF (mREM)(JlCilcc) (m REM/hr)I (m REM/

IpCi)Kr-83m 4.5E-01 I1.2E-04 2.00E+01 2.4E-03 O.OOE+OO O.OE+OO Kr-85 7.7E+00 2.1E-03 1.59E+03 3.3E+00 O.OOE+OO O.0E+00O Kr-85m I1.8E+00O 4.8E-04 9.96E+04; 4.8E+01 O.OOE+00 O.OE+OO Kr-87 I1.2E+00 3.2E-04 5.49E+05 1 .8E+02 O.OOE+OO O.0E+OO Kr-88 3.5E+00 9.4E-04 I1.36E+06 I1.3E+03 0.00E+00O O.OE+OO Kr-89 1.1E-01 2.9E-05 O.OOE+OO O.OE+OO O.OOE+OO 0.0E+OO Xe-131m 2.9E+00 7.8E-04 5.18E+03 4.0E+00 O.OOE+00 O.OE+OO Xe-133 2.4E+i02 6.4E-02 2.08E+04 1.3E+03 0.00E+00 O.0E+O0 Xe-133m 4.6E+00 1.2E-03 1.82E+04 2.3E+01 0.00E+O0 0.0E+00 Xe-135 7.9E+00 2.1E-03 I.59E+05 3.4E+02 0.00E+00 0.0E+00 Xe-135m 4.5E-01 1.2E-04 2.72E+05 3.3E+01 O.OOE+OO 0.0E+O0 Xe-I137 2.0E-01 5.4E-05 O.00E+O0 O.0E+OO O.OOE+OO 0.0E+00 Xe-138 7.2E-O1 1.9E-04 7.69E+05 1.5E+02 O.OOE+OO O.OE+OO I-131 1.4 E-02 3.8 E-06 2.42 E+05 9.1IE-01 3.29E+01I I.5E+02 1-132 2.3E-02 6.2E-06 1.49E+06 9.2E+00 3.81E-01 2.9E+00 1-133 2.7E-02 7.2E-06 3.92E+05 2.8E+00 5.85E+00 5.3E+01 1-134 6.3E-03 I.7E-06 1.73E+06 2.9E+00 1.31E-01 2.8E-01 1-135 1.9E-02 5.1E-06 1.06E+06 5.4E+00 1.23E+00 7.8E+00 Total = 3.4E+03 mREM Total = 2.2E+02 mREM TEDE = EDE + CEDE EDE =CEDE =TEDE = 3.6E+03 3.4E+03 mREM 2.2E+02 mREM mREM SM-SNC524602-00 1 ATCMN 4 HE4-ATTACHMENT E4A SHEET E4A-5 100 & 1000 mREM TEDE Thresholds Xioo =100 mREM TEDE Noble Gas concetration

(#iCi/cc)Xioo = [(100 mREM)/(TEDE mREM)] x XRLS TEDE = 3.6E+03 mREM Xlioo -Xiooo =Xlooo -2.8E-02 1000 mREM 10 xXioo X XRLS TEDE Noble Gas concetration (aC i/cc)Isotope XRLS Xlo0 Xto00 (p.C i/cc) (lpCi/cc) Kr-83m 4.5E-01 1.2E-02 1.2E-01 Kr-85 7.7E+00 2.1 E-01 2.1 E+00 Kr-85m 1.8E+00 5.OE-02 5.0E-01 Kr-87 I1.2E+00 3.3 E-02 3.3E-01 Kr-88 3.5E+00 9.7E-02 9.7E-01 Kr-89 1.1 E-01 3.0E-03 3.OE-02 Xe-131m 2.9E+00 8.0E-02 8.0E-01 Xe-I133 2.4E+02 6.6E+00 6.6E+01 Xe-133rn 4.6E+00 1.3E-01 1.3E+00 Xe-I135 7.9E+00 2.2E-01 2.2E+00 Xe-135m 4.5E-01 1.2E-02 1.2E-01 Xe-I137 2.0E-01 5.5E-03 5.5E-02 Xe-138 7.2E-01 2.0E-02 2.OE-01 Totals 7.5E+00 7.5E+01 pCi/cc pCi/cc SM-S NC524602-001IATCMN 4 HE 4-ATTACHMENT E4A SHEET E4A-6 Thyroid CDE Calculations CDETHY = Thyroid Committed Dose Equivalent (mREM) from inhalation CDETHY = DCFFGR-11 X XEAB X BR x texp DCFFGR-11

= FGR-11I dose conversion factor (mREM/tCi/cc); "Thyroid" texp = 1.00 hour0 days <br />0 hours <br />0 weeks <br />0 months <br /> BR = 1 .25E+06 cc/hr X5oom = 500 mREM Thyroid CDE Noble Gas concentration

(#tCi/cc)XS00T = [(500 mREM CDE)/(CDETHY mREM)] x XRLS X500T = 500/ 6.9E+03 x XRLS -- 7.2E-02 x XRLS X5000T = 5000 mREM Thyroid CDE Noble Gas concentration (pCi/cc)X5000T = 1 0 X X500T Y Postulated Release Thyroid CDE Thresholds Isotope XEAB FGR-11I CDETHY XRLS X500T X5000T DCF (mREM) (mREM/piCi)Kr-83m 1.2E-04 0.00E+00 0.0E+00 4.5E-01 3.2E-02 3.2E-01 Kr-85 2.1E-03 0.00OE+00 0.0E+00 7.7E+00 5.5E-01 5.5E+00 Kr-85m 4.8 E-04 0.00E+00 0.0E+00 1 .8E+00 1 .3E-01 1 .3E+00 Kr-87 3.2E-04 0.00E+00 0.0E+00 1.2E+00 8.6E-02 8.6E-01 Kr-88 9.4E-04 0.00E+00 0.0E+00 3.5E+00 2.5E-01 2.5E+00 Kr-89 2.9 E-05 0.00E+00 0.0E+00 1.1IE-01 7.9E-03 7.9 E-02 Xe-131 m 7.8 E-04 0.00E+00 0.0E+00 2.9E+00 2.IE-01 2.1E+00 Xe-133 6.4E-02 0.00E+00 0.0E+00 2.4E+02 1.7E+01 1.7E+02 Xe-133m 1.2 E-03 0.0OE+00 0.0E+00 4.6E+00 3.3E-01 3.3E+00 Xe-135 2.1 E-03 0.O0E+00 0.0E+00 7.9E+00 5.7E-01 5.7E+00 Xe-135m 1.2E-04 0.00E+00 0.0E+00 4.5E-01 3.2E-02 3.2E-01 Xe-137 5.4E-05 0.00E+00 0.0E+00 2.0E-01 1.4E-02 1.4E-01 Xe-138 1.9E-04 0.00E+00 0.0E+00 7.2E-01 5.2 E-02 5.2E-01 1-131 3.8E-06 1.08E+03 5.1E+03 I-132 6.2E-06 6.44E+00 5.0E+01 I-133 7.2 E-06 1 .80E+02 1 .6E+03 I-134 1.7E-06 1.07E+00 2.2E+00 1-135 5.1E-06 3.13E+01 2.0E+02 Total CDETHY " 6.9E+03 mREM Totals 2.0E+01 2 .0E+02 iC i/cc a SM-SNC524602-001 ATCMN 4 HE 4-ATTACHMENT E4B SHEET E4B-1 TDAFWP Exhaust Release Path TEDE & Thyroid CDE Calculations (Core Damage)Postulated Release Activity XRLS --- Release Concentration (jiCi/cc)XRLS = [Partition Factor x Xrcs (pCi/g)] x [pris (glcc)]Partition Factors[Assumption

1. 5]Noble Gases: 1.0 Iodine, liquid leakage to Auxiliary Building:

0.01 Iodine, primary coolant leakage to Containment building:

0.01 Iodine, primary coolant leakage to steam generator:

0.01 Iodine, SJAEs: 1 .0E-04 Xrcs = RCS coolant activity Xrcs = RCS Equilibrium Activity (jiCi/g) +[Release Fraction x Core Inventory (Ci) x (1 .0E+06gCi/1 Ci)]/MRcs (g)RCS Equilibrium Activity:

Design Input #14 Core Inventory:

Design Input #14 Release Fractions

[Assumption

1. 6]1.0 for Noble Gases (RG 1.183 Table 2, LOCA)0.4 for Iodine (RG 1.183 Table 2, LOCA)0 for no core damage MRCS = RCS coolant mass (Ibm)MRcs " .417,219 Ibm x (453.59 g/l Ibm) [Design Input #11]MRCS =1.89E+I08 g pris " Density of release fluid (g/cc)pris = 1 .00E+00 g/cc [Arbitrary Value]

SM-SNC524602-001IATCMN 4 HE 4-ATTACHMENT E4B SHEET E4B-2 Isotope Core Core Xeq Xrcs (l4Cilg) Partition XRLS Inventory Release (jliCilg)

Factor (JlCi/cc)(Ci) Fraction Kr-83m 9.70E+06 1.00 4.50E-01 5.1E+04 1.00 5.1E+04 Kr-85 7.20E+05 1.00 7.70E+00 3.8 E+03 1.00 3,8 E+03 Kr-85m 2.10E+07 1.00 1.80E+00 1.1E+05 1.00 1.1E+05 Kr-87 4.00E+07 1.00 1.20E+00 2.1E+05 1.00 2.1E+05 Kr-88 5.70E+07 1.00 3.50E+00 3.0E+05 1.00 3.0E+05 Kr-89 6.90 E+07 1.00 1.10E-01 3.6 E+05 1.00 3.6 E+05 Xe-131 m 8.40 E+05 1.00 2.90E+00 4.4 E+03 1.00 4.4 E+03 Xe-133 1.50E+08 1.00 2.40E+02 7.9E+05 1.00 7.9E+05 Xe-133m 4.80E+06 1.00 4.60E+00 2.5E+04 1.00 2.5E+04 Xe-135 3.50E+07 1.00 7.90E+00 1.8E+05 1.00 1.8E+05 Xe-135m 3.00E+07 1.00 4.50E-01 1.6E+05 1.00 1.6E+05 Xe-137 1.40E+08 1.00 2.00E-01 7.4E+05 1.00 7.4E+05 Xe-138 1.30E+08 1.00 7.20E-01 6.9E+05 1.00 6.9E+05 1-131 7.50E+07 0.40 1.40E+00 1.6E+05 0.01 1.6E+03 I-132 1.10E+08 0.40 2.30E+00 2.3 E+05 0.01 2.3E+03 1-133 1.60E+08 0.40 2.70E+00 3.4E+05 0.01 3.4E+03 I-134 1.70E+08 0.40 6.30E-01 3.6E+05 0.01 3.6E+03 1-135 1.50E+08 0.40 1.90E+00 3.2E+05 0.01 3.2E+03 SM-SNC524602-001 SM-5N52460-0O IATTACHMENT E4BSHEEB3 SHEET E4B-3 Postulated Release TEDE Calculations TEDE = Total Effective Dose Equivalent (mREM)TEDE = EDE + CEDE EDE = Effective Dose Equivalent (mREM) from external exposure EDE = DCFFGR-12 x XEAB X texp DCFFGR-12

= FGR-12 dose conversion factor [(mREMIhr)/(jiCi/cc)]

CEDE = Committed Effective Dose Equivalent (mREM) from inhalation CEDE = DCFFGR-11 x XEAB X BR x texp DCFFGR-11

= FGR-11I dose conversion factor (mREM/p#Ci)

XEAB = Radionuclide concentration at Exclusion Area Boundary (jiCi/cc)XEAB = [QRLS (m^3/sec)]

x [X/Q (sec/mA3)]

x [XRLS (j, Ci/cc)]Qris = Release flow rate (m^3/sec)QRLS = 26,106 Ibm/hr x SVstm (cu ft/Ibm) x [1 hr/60 min] [Design Input #22]SVstrn = Specific Volume of Saturated Steam @ Patrn SVstm = 26.804 cu ft/Ibm [Assumption

1. 8]QRLS = 1.1 7E+04 CFM x [1 min/60 sec] x [0.0283 m^3/ft^3]QRLS = 5.5 m^3/sec X/Q = Atmospheric dilution factor (sec/m^3)X/Q = 4.87E-05 sec/m3 [Assumption

1. 3]texp = Exposure time texp =1.0 hour0 days <br />0 hours <br />0 weeks <br />0 months <br /> [Assumption

1. 1]BR = Breathing Rate (mA3/sec)BR = 3.47E-04 mA3/sec [Assumption

1. 2]BR =. 1.25E+06 cc/hr = m^3/sec x [(1 .0E6 cc)/(1 m^3)] x [3600 sec/ilhr]

SM-SNC524602-001 SM-SNC52602-OO1ATTACHMENT E4BSHEE44 SHEET E4B-4 Isotope Release XEAB FGR-12 EDE FGR-11 CEDE Activity (J.Ci/cc)

DCF (mREM) DCF (mREM)(jxCilcc) (mREM/hr)/ (mREMI (p.Cilcc)

IpCi)Kr-83m 5.1 E+04 1.4E+01 2.00E+01 2.7E+02 O.OOE+O0 O.OE+O0 Kr-85 3.8E+03 I1.0E+00 1 .59E+03 1 .6E+03 0.OOE+OO O.OE+OO Kr-85m 1.1 E+05 3.0E+01 9.96E+04 3.0E+06 0.00E+00O O.OE+OO Kr-87 2.1E+05 5.7E+01 5.49E+05 3.1E+i07 O.OOE+00 O.0E+00 Kr-88 3.0E+05 8.1E+01 1.36E+06 1.1E+08 O.OOE+00 0.0E+00 Kr-89 3.6E+05 9.8E+01 0.00E+O0 O.OE+00 O.OOE+00 0.0E+OO Xe-131m 4.4E+03 1.2E+00 5.18E+03 6.2E+03 O.OOE+00 0.0E+00 Xe-133 7.9E+05 2.1E+02 2.08E+04 4.4E+06 O.OOE+OO O.OE+OO Xe-133m 2.5E+04 6.8E+00 1.82E+04 1.2E+05 0.00E+00O O.OE+OO Xe-135 1.8E+05 5.0E+01 1.59E+05 7.9E+06 O.OOE+OO O.OE+OO Xe-135m 1.6E+05 4.2E+01 2.72E+05 1.2E+07 O.OOE+OO O.OE+OO Xe-I137 7.4E+05 2.0E+02 0.OOE+OO O.0E+O0 O.OOE+OQ 0.OE+00 Xe-138 6.9E+05 I.8E+02. 7.69E+05 1.4E+08 O.OOE+OO O.OE+00 1-131 1.6E+03 4.2E-01 2.42E+05 1.0E+05 3.29E+01 1.7E+07 1-132 2.3E+03 6.2E-01 1.49E+06 9.3E+05 3.81E-01 3.0E+05 1-133 3.4E+03 9.1E-01 3.92E+05 3.5E+05 5.85E+00 6.6E+06 1-134 3.6E+03 9.6E-01 I.73E+06 1.7E+06 I.31E-01 1.6E+05 1-135 3.2E+03 8.5E-01 1.06E+06 9.0E+05 1.23E+00 1.3E+06 Total = 3.1 E+08 mREM Total = 2.6E+07 mREM h TEDE = EDE + CEDE EDE = 3.1E+08 mREM CEDE = 2.6E+07 mREM TEDE = 3.4E+08 rnREM SM-SNC524602-001 SM-SN52460-00 IATTACHMENT E4BSHEE4-SHEET E4B-5 100 & 1000 mREM TEDE Thresholds Xioo = 100 mREM TEDE Noble Gas concetration (jiCi/cc)Xioo = [(100 mREM)/(TEDE mREM)] x XRLS Xloo =Xlooo =TEDE = 3.4E+08 mREM 2.9E-07 x XRLS 1000 mREM TEDE Noble Gas concetration

(#C i/cc)10 x ioo Isotope XRLS Xl00 Xl000i/cc) (jiC i/cc) (!pCi/cc)Kr-83m 5.IE+04 1.5E-02 1.5E-0l Kr-85 3.8E+03 I.1IE-03 I.IE-02 Kr-85m 1.1IE+05 3.3E-02 3.3E-01 Kr-87 2.1E+05 6.2E-02 6.2E-01 Kr-88 3.0E+05 8.9E-02 8.9E-01 Kr-89 3.6E+05 1.1 E-01 1.1 E+00 Xe-131m 4.4E+03 1.3E-03 I.3E-02 Xe-I133 7.9E+05 2.3E-01 2.3E+00 Xe-I133m 2.5E+04 7.5E-03 7.5E-02 Xe-135 I.8 E+05 5.5 E-02 5.5E-01 Xe-135m I.6E+05 4.7E-02 4.7E-01 Xe-I137 7.4E+05 2.2E-01 2.2E+00 Xe-I138 6.9E+05 2.0E-01 2.0E+00 Totals 1.1 E+00 1.1 E+01 p~CiIcc i~Ci/cc SM-SNC524602-001 ATCMN 4 HE 4-ATTACHMENT E4B SHEET E4B-6 Thyroid CDE Calculations CDETHY = Thyroid Committed Dose Equivalent (mREM) from inhalation CDETHY -DCFFGR-11 X XEAB X BR x texp DCFFGR-11

= FGR-11I dose conversion factor "Thyroid" texp = 1.00 hour0 days <br />0 hours <br />0 weeks <br />0 months <br /> BR = 1 .25E+06 cc/hr XS00T = 500 mREM Thyroid CDE Noble Gas concentration (pCi/cc)X500T = [(500 mREM CDE)/(CDETHY mREM)] x XRLS XS00T -- 500/ 8.2E+08 x XRLS =X500T =" 5000 mREM Thyroid CDE Noble Gas X5000T = 10 X X500m 6.1E-07 XXRLS concentration V Postulated Release Thyroid CDE Thresholds Isotope XEAB FGR-11I CDETHY XRLS X500T X5000T DCF (mREM) (jltCi/cc)(mREMI jtC i)Kr-83m 1.4E+01 0.00E+00 0.0E+00 5.1E+04 3.1E-02 3.1E-01 Kr-85 I1.0E+00 0.00E+00 0.0E+00 3.8E+03 2.3E-03 2.3E-02 Kr-85m 3.0E+01 0.00E+-00 0.0E+00 1.1IE+05 6.8 E-02 6.8E-01 Kr-87 5.7E+01 0.00E+00 0.0E+00 2.1E+05 1.3E-01 1.3E+00 Kr-88 8.IE+01 0.00E+00 0.0E+00 3.0E+05 1.8E-01 1.8E+00 Kr-89 9.8E+01 0.00E+00 0.0E+00 3.6E+05 2,2E-01 2.2E+00 Xe-131 m 1.2 E+00 0.00E+00 0.0OE+00 4.4E+03 2.7E-03 2.7 E-02 Xe-133 2.1E+02 0.00E+00 0.0E+00 7.9 E+05 4.9 E-01 4.9E+00 Xe-I133m 6.8E+00 0.00E+00 0.0E+00 2.5E+04 1 .6E-02 1 .6E-01 Xe-135 5.0E+01 0.00E+00 0.0E+00 1.8E+05 I.IE-01 1.1E+00 Xe-135m 4.2E+01 0.00E+-00 0.0E+00 1.6E÷05 9.7E-02 9.7E-01 Xe-1 37 2.OE+02 0.00E+00 0.0E+00 7.4E+05 4.5E-01 4.5E+00 Xe-I138 1 .8E+02 0.O0E+00 0.0E+00 6.9E+05 4.2 E-01 4.2E+00 1-131 4.2E-01 1.08E+03 5.7E+08 I-132 6.2E-01 6.44E+00 5.0E+06 I-133 9.1E-01 1.80E+02 2.0E+08 I-134 9.6E-01 1.07E+00 1.3E+06 1-135 8.5E-01 3.13E+01 3.3E+07 Total CDETHY =8.2E+08 mREM Totals 2.2E+00 2.2E+01 1 iCi/cc&

Southern Nuclear Design Calculation IPlant: Farley Unit: 1&2 ICalculation Number: SM-SNC524602-001 Sheet: F-I Attachment F -Shielding Calculations DescrptionNumber Descrptionof Pages F1 -Water Shielding Properties 5 F2 -Modification of VEGP SFP Dose Rate vs. Depth Analysis for Farley 18 F3 -Operating Deck Dose Rates for Reduced RPV Water Level 3 F4 -Seal Table Room Dose Rate Evaluation 2 4 4 4 4 4 4 4 4 Total Number of Pages including Cover Sheeti 29 Southern Nuclear Design Calculation SPlant: Farley Unit: 1&2 Calculation Number: SM-SNC524602-001 Sheet: Fl-1I Attachment F1 -Water Shielding Parameters Several shielding evaluations are performed in support of this calculation, using existing analyses.

The associated shielding parameters are available in tables in nuclear engineering reference books as functions of gamma energy. The energies in the tables do not align with the energies of the spent fuel gamma source terms used in Vogtle calc X6CDE.01 or Farley calc SM-SNC467144-001.

Linear interpolation of the tabulated values is a time consuming option. However, these parameters are non-linear functions of gamma energy, so additional error is introduced by linear interpolation.

Curvilinear regression can be performed on these parameters using the Data Analysis Regression tool in Microsoft Excel. The following on-line references provide guidance for using this tool:* Cameron, "EXCEL 2007: Multiple Regression," Department of Economics, University of California

-Davis, 2009 (http ://ca mero n .eco n. u cd avis.ed u/excel/ex6l multiplerepqression .html)*"A Quick Guide to Using Excel 2007's Regression Analysis Tool," Fuqua School of Business, Duke University, 2009 (https://facu lty~fupua.d uke~ed u/~pecklu nd/ExcelReView/Use%20Excel%202007%20Rep res sion.pdf)The regression is judged as adequate based on the following.

• The Multiple Correlation Coefficient, R 2 or R Square, is a measure of amount of reduction in variability in the dependent variable.

It varies from zero to one. A R Square approaches one, the regression fit improves.*The relative error of the regression is calculated as the difference between the regression value and the tabulated value divided by the tabulated value at each value of the dependent variable (gamma energy in this case). As the relative error approaches zero, the accuracy of the regression improves.Curvilinear regressions on several water shielding parameters are documented in the Excel spreadsheet comprising the remainder of this attachment.

SM-SNC524602-001 Attachment Fl -Water Shielding Parameters Taylor Exposure Buildup Factor Coefficient (a2 for Water Curvilinear regression performed using Excel Data Analysis ToolPak ( =Ko + [Ki x El + [Ki x (E^2)] + [K3 x (E^3)] + [K4IE] + [K5/(E^2)]

+ [KeI(E^3)]

Sheet Fl-I S aCr2-tab af2-reg Error MeV ____(%)0.3 -0.0871 -0.0871 0.006%0.4 -0.0605 -0.0605 -0.043%0.6 -0.0386 -0.0387 0.183%1.0 -0.0182 -0.0180 -0.880%1.5 -0.0036 -0.0038 6.796%2.0 0.0041 0.0043 4.137%3.0 0.0151 0.0151 -0.286%4.0 0.0366 0.0366 0.021%

Reference:

Table 5.2, ANSI/ANS-6.4.3-1 991 Ey,= 4.0 MeV0.0366 Ko = -5.94E-02 Ki = 7.01 E-02 K2 = -2.51E-02 K3 = 3.42 E-03 K4 = -7.87E-03 K5 = 1 .87E-03 1K6= -1.11E-03 Regression Statistics Multiple R 1.0000 R Square 1.0000 Standard Error 0.0003 Observations 8 Water Taylor Exposure Buildup Factor Coefficient (a2 0.0 U ,,. 0.004 .... .... ....*" -0.o5 ----- ----- -....... ..0.0i oo I-0.15 ....m ...E....r..

y (M .....e. ..* Tabulated Regression SM-SNC524602-001 Attachment F1 -Water Shielding Parameters Water Mass Attenuation Coefficient Curvilinear regression performed using Excel Data Analysis ToolPak pidp = Ko + [Ki x E] + [K2 x (E^2)] + [K3 x (E^3)] + [K4/E] + [K5/(E^2)]

+ [Ke/(E^3)](cmA2/g)Sheet F1-2 E7pip Error MeV Table Rgrssn 0.1 0.1670 0.1670 0.01%0.2 0.1360 0.1356 -0.26%0.3 0.1180 0.1188 0.70%0.4 0.1060 0.1061 0.08%0.5 0.0966 0.0965 -0.12%0.6 0.0896 0.0890 -0.64%0.8 0.0786 0.0782 -0.57%1.0 0.0706 0.0705 -0.20%1.5 0.0575 0.0579 0.73%2.0 0.0493 0.0499 1.26%3.0 0.0396 0.0398 0.41%4.0 0.0339 0.0336 -0.88%5.0 0.0301 0.0297 -1.25%6.0 0.0275 0.0273 -0.75%8.0 0.0240 0.0246 2.36%10.0 0.0219 0.0217 -0.87%E7 10.0 MeV UP = 0.0217 cm^2/g Ko =Ki =K2=K3 =K4 =K5 =Ke =5.26E-02-1 .13E-02 1.41 E-03-6.21 E-05 3.14E-02-3.75E-03 1 .77E-04 Regression Statistics Multiple R 1.0000 R Square 0.9999 Standard Error 0.0005 Observations 16

Reference:

Table 11.4, pager68 aMarshs A Introduction toefNuclearvs Engnerigy Water Mass Attenuation Coefficient vs. Energy...0.20 E So.15 0.0~0.00 U)I'4 4=4 -Table3 5 6Rersso 7 8 9 10* Table --Regressioo SM-SNC524602-001 Attachment F1 -Water Shielding Parameters Taylor Exposure Buildup Factor Coefficient Ai for Water Curvilinear regression performed using Excel Data Analysis ToolPak Ai = Ko + [Ki x E] + [K2 x (E^2)] + [K3 x (E^3)] + [K4/E] + [K5/(E^2)]

+ [KO/(E^3)]

Sheet F1-3Al-tab Al-reg Error MeV ___ ____ (%)0.3 226.726 226.731 0.002%0.4 103.797 103.771 -0.025%0.6 72.516 72.586 0.097%1.0 54.278 54.119 -0.293%1.5 39.009 39.252 0.622%2.0 32.003 31 .835 -0.526%3.0 22.738 22.781 0.188%4.0 11.703 11.695 -0.064%

Reference:

Table 5.2, ANSI/ANS-6.4.3-1991 Ey, =A1i=K0 =Ki =I2=K3 =K4 =K5 =K6=4.0 11.695-2.73E+02 1 .22E+02-2 .45E+01 1 .64E+00 3.68E+02-1.71 E+02 3.07E+01 MeV Regression Statistics Multiple R 1.0000 R Square 1.0000 Standard Error 0.3465 Observations 8 250'~200 IL.0.o 150lo 00 uJ 1,,.,. s Water Taylor Exposure Buildup Factor Coefficient Ai 0 0.0 0.5 1.0 1.5 2.0 2.5 3.0 3. 40 45 Gamma Energy (MeV)3.5 4.0 4.5* Tabulated

---

Regression SM-SNC524602-001 Attachment F1 -Water Shielding Parameters Taylor Exposure Buildup Factor Coefficient (ai for Water Curvilinear regression performed using Excel Data Analysis ToolPak cti = Ko + [Ki x E] + [K2 x (E^2)] + [K3 x (E^3)l + [K4/E] + [K5/(EA2)]

+ [Ke/(E^3)]

Sheet F1-4 E a Ol-tab (al-reg Error MeV ___ ____ (%)0.3 -0.1084 -0.1084 -0.002%0.4 -0.0975 -0.0975 0.009%0.6 -0.0763 -0.0763 -0.032%1.0 -0.0506 -0.0507 0.109%1.5 -0.0357 -0.0356 -0.235%2.0 -0.0274 -0.0275 0.213%3.0 -0.0194 -0.0194 -0.076%4.0 -0.0226 -0.0226 0.01 2%

Reference:

Table 5.2, ANSI/ANS-6.4.3-1 991 E7= 1.5 MeV ( = -0.0356 Ko = 6.52E-02 Ki = -4.58E-02 K2 = 1 .53E-02 K3 = -1 .95E-03 K4 = -1.04E-01 K5 = 2.26E-02 K =I -1.75E-03 Regression Statistics Multiple R 1.0000 R Square 1.0000 Standard Error 0.0001 Observations 8 Water Taylor Exposure Buildup Factor Coefficient a1 0.00 ___ ___ ___o. -oo-4.a 0 0. -0.05 0 ..I. .......Ga4a Eery (eV* Tabulated -Regression Southern Nuclear Design Calculation SPlant: Farley Unit: 1&2 Calculation Number: SM-SNC524602-001 ISheet: F2-1 Attachment F2 -Modification of VEGP SFP Dose Rate vs. Depth Analysis for Farley Introduction Appendix 0 of VEGP calculation X6CDE.01 determined dose rate vs. SFP water depth over a full core (193 fuel assemblies) discharged at 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> after shutdown.

The core was modeled as an equivalent disc source with a water shield.These results may be used to estimate water surface dose rate vs. water depth above fuel in the Farley reactor vessel at 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> after shutdown subject to the following modifications.

Source Strenaqth To account for the greater spacing between fuel assemblies in the SFP racks, the VEGP volumetric source terms (MeV/cc-sec) were multiplied by 0.72 (sheet 04). The water surface dose rate is proportional to the water surface gamma flux, which in turn is proportional to source strength.

Multiplying the dose rates in X6CDE.01 by 1.39 (~1/0.72) will normalize them back to the source strength above an irradiated core in the reactor vessel.Source Radius The VEGP discharged core was modeled as a disc source (SA y/cm 2-sec) of radius R feet overlaid with a slab water shield of thickness d feet similar to the disc source described on pages 487-488 of _--l"Introduction to Nuclear Engineering.

" The shield thickness d corresponds to the water iT' r depth above the core and the radius R is one half of P the effective cylinder diameter 13.7 feet on page 04 in X6CDE.01.

Disc Sed source The buildup flux at the water surface is calculated as shown on page 488 of "Introduction to Nuclear Engineering":

• sfc = (SA/2) x {A1*{E1[(1

+

-Ei[(1 + al)*Ji*d*sec 0]) +2*E[1+ cx2)*p.*d]

-Ei[(1 + cL2)*lI*d*sec 0]} (1)where Ai, hA, Qi1, & G(2 = Coefficients for Taylor Buildup Factor; functions of gamma energy (pages 481-482 of "Introduction to Nuclear Engineering")

Southern Nuclear Design Calculation SPlant: Farley Unit: 1&2 Calculation Number: SM-SNC524602-001 ISheet: F2-2 Attachment F2 -Modification of VEGP SFP Dose Rate vs. Depth Analysis for Farley The angle 0 is a function of water depth d and source radius R: tan = R/d 0 = tan-'(R/d)

The effective diameter of the Farley core is 9.975 feet (= 1 foot/i12 inches x 119.7 inches [Table 3-1, U-735579, "Farley Radiation Analysis Design Manual"]).

Thus, for a given water depth the angle 0) will differ between Vogtle and Farley.Per page 483 of "Introduction to Nuclear Engineering," the exponential function Ei(X) can be approximated by Ei(X) = [exp(-X)]*{[1/(X

+ 1)] + [1/(X + 1)3]} for X > 14. For X = 10, the error is 0.11%; the smallest value of X used in this evaluation is ~8; any error due to this approximation is negligible.

Equation (1) is modified and simplified for Farley and Vogtle as follows: 41F/(SAI 2) = A1*[E1 (XFll) -- E1 (XFi2)] + A2*[Ei (XF21) -- E1(XF22)]

(2)XFli = (1 + oal)*,,*d (2a)XFi2 = XF11*sec OF (2b)XF21 = (1 + ax2)*Ji*d (2C)XF22 = XF2i*sec OF (2d)OF = tan-'(RF/d)

(2e)*v/(SA/2) = Ai*[Ei (Xv1i) -E1(Xv12)]

+ A2*[E1 (Xv21) -Ei (Xv22)] (3)Xvii = (1 + ox1)*,t*d (3a)Xv12 = Xvli*sec Ov (3b)Xv21 = (1 +I ct2)*li*d (3c)Xv22 = Xv2i*sec Ov (3d)Ov = tarn-(Rv/d)

(3e)Equation (2) is divided by equation (3) as follows: CF/(SA/2) A1*[E1(XFli)

-E1(XF12)]

+ A2*[E1(XF21)

-E1(XF22)]

(4)4v/(SA/2)

Ai*[E1(Xwli)

-E1(Xwi2)]

+ A2*[E1(Xv2i)

-Ei(Xv22)]CFA1*[E1 (XF11) -- E1 (XFi2)] + A2*[E1 (XF2i) -- E1 (XF22)] (5)4v Ai*[E1 (Xw11) -E1 (Xw12)] + A2*[E1 (Xv21) -E1 (Xv22)]Since dose rates is proportional to gamma flux, DRF A1*[E1(XF¶1)

-E1(XF12)]

+ A2*[E1(XF21)

-Ei(XF22)]

(6)DRv A1*[E1(Xvll)

-- E1(Xvl2)]

+ A2*[E1(Xv21)

-E1(Xv22)]

Southern Nuclear Design Calculation SPlant: Farley Unit: 1&2 Calculation Number: SM-SNC524602-001 lSheet: F2-3 Attachment F2 -Modification of VEGP SFP Dose Rate vs. Depth Analysis for Farley The above dose correction factor is calculated for each energy and depth listed in Attachment D to X6CDE.01 in the Excel spreadsheet that comprises the remainder of this attachment.

The dose rate calculated in Attachment D of X600E.01 for each energy and depth [DRv(E,d)]

is modified to generate a dose rate for Farley at the same energies and depths [DRF(E,d)]

as follows: DRF(E,d) = DRv(E,d) x FNORM X [DRF/DRv]where FNORM = 1/0.72 = 1.39 The results are summarized below E Depth = 8' Depth = 10' Depth = 11.1'(MeV) Vogtle Farley Vogtle Farley Vogtle Farley 0.90 6.3E+02 8.4E+02 1 .0E+01 1 .3E+01 1.1 E+00 1 .4E+00 1.35 3.8E+02 5.0E+02 1.2E+01 1.4E+01 1.7E+00 2.1E+00 1.80 8,6E+03 1.IE+04 4.OE +02 4.9 E+02 7.5E+01 8.9E+01 2.20 9.4E+02 1.2E+03 5.4E+01 6.4E+01 1.1IE+01 1.3E+01 2.60 2,0E+03 2.4E+03 1.4E+02 1.7E+02 3.4E+01 3.8E+01 3.00 6.0E+01 7.1E+01 5,2E+00 5.9E+00 1.3E+00 1.5E+00 4.00 7.7E+01 8.9E+01 9.2E+00 1 .0E+01 2.8E+00 3.0E+00 TOTALS 1 .3E+04 1 .6E+04 6.4E+02 7.6E+02 1 .3E+02 I1.5E+02 mREM/hr mREM/hr mREMIhr mREMIhr mREMIhr mREMIhr E Depthl= 2' Depthl= 4' Depthl=B1'(MeV) Vogtle Farley Vogtle Farley Vogtle Farley 0.90 1 .6E-01 1 .9E-01 2,7E-03 3.3E-03 4.6E-05 5.4E-05 1.35 3.2E-01 3.8E-01 9.8E-03 1.1IE-02 3.3 E-04 3.7 E-04 1.80 1.7E+01 2.0E+01 8.2E-01 9.2E-01 3.9E-02 4.3E-02 2.20 2.8E+00 3.2E+00 1 .6E-01 1 .8E-01 9.5E-03 1 .0E-02 2.60 9.41E+00 1.0E+01 6.7E-01 7.2E-01 4.9E-02 5.IE-02 3.00 4.1E-01 4.5E-01 3.5E-02 3.7E-02 3.1E-03 3.1E-03 4.00 1 .0E+00 1 .0E+00 1 .2E-01 1 .2E-01 1 .4E-02 1 .4E-02 TOTALS 3.1 E+01 mREMIhr 3.6E+01 mREM/hr 1.8E+00 mREM/hr 2.0E+00 mREMIhr 1.2E-01 mREMIhr 1.2E-01 mREMIhr mREMIhr mREMIhr mREMIhr mREMIhr mREM/hr Southern Nuclear Design Calculation SPlant: Farley Unit: 1&2 Calculation Number: SM-SNC524602-O01 F2 Attachment F2 -Modification of VEGP SFP Dose Rate vs. Depth Analysis for Farley The dose rates vs. depth are plotted below for comparison.

Dose Rate vs. Water Depth 1 .0E+04 ---~1.0E+03 1.0E+01 -~-- ~ -~ -* ---1 .OE+00_____

11 .0 E -0 1 .................................... ....................................rr 8 9 10 11 12 13 14 15 15 Water Depth (feet),-,-Vogtle

-,-,--Farley SM-SNC524602-001IATCMN 2SETF-ATTACHMENT F2 SHEET F2-5 Calculations Input Parameters Water Shielding Parameters E I~p p A1ih A2l X2 (aeV) (cm^21g) (llcm) ____0.90 0.0740 0.0730 58.3145 -57.3145 -0.0554 -0.0221 1.35 0.0610 0.0602 42.6872 -41.6872 -0.0391 -0.0073 1.80 0.0528 0.0520 34.2498 -33.2498 -0.0303 0.0015 2.20 0.0474 0.0467 29.8353 -28.8353 -0.0251 0.0066 2.60 0.0432 0.0426 26.3424 -25.3424 -0.0215 0.0106 3.00 0.0398 0.0392 22.7808 -21.7808 -0.0194 0.0151 4.00 0.0336 0.0331 11.6955 -10.6955 -0.0226 0.0366 pi/P = Ko + [Ki x E] + [K2 x (E^2)] + [K3 x (EA3)] + [K4/E] + [K5/(EA2)]

+ [K6/(EA3)]

= (p)x p p = Water density (g/cm^3)p = 61.55 Ibm/cu ft[Design In put 26]p = 0.986 g/cmA3 = Ibm/cu ft x [(0.016018463 g/cc)/(1 Ibm/cu ft)]Ai = Ko + [Ki x E]A2= I -Ai= Ko +[K x E]cL2 = Ka + [Ki x E]+ [K(2 x (EA2)] + [K(3 x (EA3)] + [K4/E] + [K5/(E^2)]

+ [K6/(EA3)]

[page 481, Lamarsh "Introduction to Nuclear Engineering"]

+ [K2 x (E^2)] + [K3 x (E^3)] + [K4/E] + [K5/(E^2)]

+ [K6/(E^3)]

+ [K(2 x (EA2)] + [K(3 x (E^3)] + [K4/E] + [K5/(E^2)]

+ [K6/(E^3)]

pip Ko =K2 =K3 =K4 =Ks5=K6 =0.05261 -2.73E+02 0.0652 -0.0594-0.01131 1.22E+02 -0.0458 0.0701 0.00141 -2.45E+01 0.0153 -0.0251-0.00006 1 .64E+00 -0.0020 0.0034 0.03138 3.68E+02 -0.1043 -0.0079-0.00375 -1.71 E+02 0.0226 0.0019 0.00018 3.07E+01 -0.0018 -0.0011 From Attachment Fl of this calculation SM-SNC524602-001 ATCMN 2SETF-ATTACHMENT F2 SHEET F2-6 Farley Source Geometry DF = Farley core effective diameter DF = 119.7 inches RF = Farley effective radius (ft)RE = 1/2 X DF X (1 ft/12 in)REF= 4.988 ft Vogtle Source Geometry Dv = Vogtle cylindrical source effective diameter Dv= 13.7 ft RE = Vogtle cylindrical source effective radius Rv = 1/2 xDv Rv = 6.850 ft Source Strength Re-Normalization Fnorm = 1/Vogtle source strength adjustment Fnorrm 1.39 Vogtle Dose Rates vs. Depth E Depth Depth Depth Depth Depth Depth (MeV) 8ft 10ft 11.1lft 12ft 14ft 16ft 0.90 6.335E+02 1.031 E+01 1 .082E+-00 1.551 E-01 2.736E-03 4.569E-05 1.35 3.848E+02 1.156E+01 1.687E+'00 3.179E-01 9.808E-03 3.305E-04 1.80 8.601E+03 4.038E+02

!7.523E+01 1.733E+01 8.218E-01 3.933E-02 2.20 9.403E+02 5.407E+01 1.125E+01 2.834E+00 1.637E-01 9.471E-03 2.60 2.000E+03 1 .435E+02 3.368E+01 9.374E+00 6.749E-01 4.870E-02 3.00 5.971E+01 5.174E+00 1.347E+'00 4.081E-01 3.546E-02 3.086E-03 4.00 7.71 7E+01 9.1 87E+00 2.847E+00 9.956E-01 1.1 89E-01 1 .423E-02 TOTALS 1 .270E+04 6.375E+02 1.271 E+02 3.141 E+01 1 .827E+00 1.1 52E-01 NOTE: All significant figures on sheets spreadsheet.

D-7 thru D-9 of X6CDE.01 entered into this SM-SNC524602-001IATCMN 2SETF-ATTACHMENT F2 SHEET F2-7 Depth Dependent Adjustment Factors d = Water depth d = 8 feet d = 243.84 cm Farley RF =OF =sec OF =4.988 0.557 1.178 feet radians = arctan(RF/d)

Ey XFII XFI2 XF2I XF22 MeV __ _ _ __ _ _0.90 16.808 19.807 17.401 20.506 1.35 14.098 16.613 14.564 17.163 1.80 12.304 14.499 12.707 14.974 2.20 11.111 13.094 11.473 13.520 2.60 10.159 11.971 10.492 12.364 3.00 9.374 11.047 9.703 11.435 4.00 7.896 9.304 8.374 9.868 Ey EI(XFII) EI(XFI2) EI(XF2I) EI(XF22)MeV 0.90 2.83E-09 1.20E-10 1.51E-09 5.79E-11 1.35 5.02E-08 3.47E-09 3.05E-08 1 .94E-09 1.80 3.43E-07 3.27E-08 2.22E-07 1 .97E-08 2.20 1.24E-06 1.47E-07 8.40E-07 9.30E-08 2.60 3.50E-06 4.90E-07 2.43E-06 3.21 E-07 3.00 8.26E-06 1.33E-06 5.76E-06 8.75E-07 4.00 4.24E-05 8.92E-06 2.49E-05 4.81 E-06 SM-SNC524602-001 ATCMN 2SETF-ATTACHMENT F2 SHEET F2-8 Vogtle Rv =Ov =sec Ov =8 6.850 0.708 1.316 feet feet radians = arctan(RF/d)Xvli1 Xvl 2 Xv21 Xv22 MeV 0.90 16.808 22.128 17.401 22.909 1.35 14.098 18.560 14.564 19.174 1.80 12.304 16.198 12.707 16.728 2.20 11.111 14.628 11.473 15.104 2.60 10.159 13.374 10.492 13.813 3.00 9.374 12.341 9.703 12.775 4.00 7.896 10.395 8.374 11.024 Ey Ei(Xvii) EI(Xv12) EI(Xvwl) EI(Xv22)MeV 0.90 2.83E-09 1.06E-11 1.51 E-09 4.71 E-12 1.35 5.02 E-08 4.46 E-10 3.05E-08 2.34E-10 1.80 3.43E-07 5.39E-09 2.22E-07 3.07E-09 2.20 1 .24 E-06 2.85E-08 8.40E-07 1 .72 E-08 2.60 3.50E-06 1 .09E-07 2.43E-06 6.80E-08 3.00 8.26E-06 3.29E-07 5.76E-06 2.07E-07 4.00 4.24E-05 2.71 E-06 2.49E-05 1 .37E-06 Ey DRy Fnorm DRF DRF MeV mREMIhr DRv ____0.90 6.3E+02 1.39 0.96 8.4E+02 1.35 3.8E+02 1.39 0.93 5.0OE+02 1.80 8.6E+03 1.39 0.91 1.1IE+04 2.20 9.4E+02 1.39 0.89 1 .2E+03 2.60 2.0E+03 1.39 0.88 2.4E+03 3.00 6.0E+01 1.39 0.86 7.1E+01 4.00 7.7E+01 1.39 0.83 8.9E+01 TOTAL = 1 .3E+04 mREM/hr TOTAL = 1 .6E+04 mREM/hr SM-SNC524602-001 ATCMN 2SETF-ATTACHMENT F2 SHEET F2-9 10 304.8 feet cm Farley RF = 4.988 OF = 0.463 sec OF=" 1.117 feet radians = arctan(RF/d)

EyXFII XF12 XF~t XF22 MeV 0.90 21.010 23.478 21.752 24.307 1.35 17.622 19.693 18.205 20.344 1.80 15.380 17.186 15.884 17.749 2.20 13.889 15.521 14.341 16.026 2.60 12.698 14.190 13.116 14.656 3.00 11.718 13.094 12.129 13.554 4.00 9.870 11.029 10.467 11.697 E'y EI (XF1I) Ei (XFI2) EI (XF2I) E I(XF22)MeV 0.90 3.42E-11 2.60E-12 1.57E-11 1.10E-12 1.35 1.20E-09 1.36E-10 6.48E-10 6.86 E-11 1.80 1.28E-08 1.90E-09 7.52E-09 1.05E-09 2.20 6.27 E-08 1.10E-08 3.87E-08 6.46 E-09 2.60 2.24E-07 4.55E-08 1.43E-07 2.77E-08 3.00 6.45E-07 1.47E-07 4.14E-07 8.97E-08 4.00 4.80E-06 1.36E-06 2.50E-06 6.59E-07 SM-SNC524602-001ATAHETFSETF21 ATTACHMENT F2 SHEET F2-10 Vogtle Rv=" Ov =sec 0v =10 6.850 0.601 1.212 feet feet radians = arctan(RF/d)

Ey' Xv ii Xvi 2 Xv~i Xv22 MeV 0.90 21.010 25.467 21.752 26.365 1.35 17.622 21.360 18.205 22.067 1.80 15.380 18.642 15.884 19.253 2.20 13.889 16.836 14.341 17.383 2.60 12.698 15.392 13.116 15.898 3.00 11.718 14.203 12.129 14.702 4.00 9.870 11.963 10.467 12.688 Ey Ei(Xvii) Et(Xv12) EI(Xv21) E I(Xv22)MeV 0.90 3.42 E-11 3.29E-13 1.57E-11 1.30E-13 1.35 1.20E-09 2.37E-11 6.48E-10 1.13E-11 1.80 1.28 E-08 4.09E-10 7.52E-09 2.15E-10 2.20 6.27E-08 2.74E-09 3.87E-08 1 .54E-09 2.60 2.24E-07 1 .27E-08 1 .43E-07 7.40E-09 3.00 6.45E-07 4.48E-08 4.14E-07 2.63E-08 4.00 4.80E-06 4.95E-07 2.50E-06 2.27E-07 E7DRy Fnorm DR F DRF MeV mREM/hr DRv 0.90 1.0E+01 1.39 0.93 1.3E+01 1.35 1.2E+01 1.39 0.90 1.4E+01 1.80 4.0E+02 1.39 0.87 4.9E+02 2.20 5.4E+01 1.39 0.85 6.4E+01 2.60 1.4E+02 1.39 0.84 1.7E+02 3.00 5.2E+00 1.39 0.82 5.9E+00 4.00 9.2E+00 1.39 0.79 1.0E+01 TOTAL = 6.4E+02 mREM/hr TOTAL = 7.6E+02 mREM/hr SM-SNC524602-001 ATCMN 2SETF-ATTACHMENT F2 SHEET F2-11 d= 11.1 feet d = 338.328 cm Farley RF=-OF sec OF =4.988 0.422 1.096 feet radians =arctan(RF/d)

E XF11 XFI2 XF2I XF22 MeV___ _0.90 23.321 25.567 24.144 26.470 1.35 19.561 21.445 20.208 22.154 1.80 17.071 18.715 17.631 19.329 2.20 15.417 16.902 15.918 17.452 2.60 14.095 15.453 14.558 15.960 3.00 13.007 14.259 13.463 14.760 4.00 10.955 12.010 11.619 12.738 Ey E1(XFII) E1(XF12) EI(XF21) EI(XF22)MeV__ _ _ __ _ _0.90 3.06E-12 2.97E-13 1.30E-12 1.16E-13 1.35 1.56E-10 2.17E-11 7.91E-11 1.03E-11 1.80 2.14E-09 3.79E-10 1.19E-09 1.99E-10 2.20 1 .23E-08 2.56E-09 7.24E-09 1 .43E-09 2.60 5.03 E-08 1.19E-08 3.07E-08 6.93E-09 3.00 1.61E-07 4.22E-08 9.88E-08 2.48E-08 4.00 1.47 E-06 4.70 E-07 7.17E-07 2.15E-07 SM-SNC524602-001ATAHETFSETF21 ATTACHMENT F2 SHEET F2-12 Vogtle d=Rv =Ov =sec Ov =11.1 6.850 0.553 1.175 feet feet radians = arctan(Rv/d)

E'y Xv1i Xvi2 Xv2i Xv22 MeV 0.90 23.321 27.405 24.144 28.372 1.35 19.561 22.986 20.208 23.746 1.80 17.071 20.060 17.631 20.718 2.20 15.417 18.117 15.918 18.706 2.60 14.095 16.563 14.558 17.107 3.00 13.007 15.284 13.463 15.821 4.00 10.955 12.873 11.619 13.653 Ey Ei(Xv1i) E1(Xvl2) EI(Xv21) EI(Xv22)MeV 0.90 3.06E-12 4.42E-14 1.30E-12 1.63E-14 1.35 1.56E-10 4.35E-12 7.91E-11 1.97E-12 1.80 2.14E-09 9.23E-11 1.19E-09 4.64E-11 2.20 1.23E-08 7.11E-10 7.24E-09 3.83E-10 2.60 5.03E-08 3.66E-09 3.07E-08 2.06E-09 3.00 1.61 E-07 1.42 E-08 9.88 E-08 8.03E-09 4.00 1.47E-06 1.86E-07 7.17E-07 8.06 E-08 Ey DRy Fnorm DR F DRF MeV mREM/hr DRyv ___0.90 1 .08E+'00 1.39 0.91 1 .4E+00 1.35 1.69E+00 1.39 0.88 2.1E+00 1.80 7.52E+01 1.39 0.85 8.9E+01 2.20 1.12E+01 1.39 0.83 1.3E+01 2.60 3.37E+'01 1.39 0.82 3.8E+01 3.00 1 .35E+00 1.39 0.80 1 .5E+00 4.00 2.85E+00 1.39 0.77 3.0E+00 TOTAL = 1 .27E+02 m REM/hr TOTAL = 1 .5E+02 mREM/hr SM-SNC524602-001ATAHETFSETF21 ATTACHMENT F2 SHEET F2-13 d = 12 feet d = 365.76 cm Farley RF = 4.988 feet OF =sec OF =0.394 1.083 radians = arctan(RF/d)

Ey, XF11 XF12 XF21 XF22 MeV 0.90 25.212 27.303 26.102 28.267 1.35 21.147 22.901 21.846 23.658 1.80 18.456 19.986 19.060 20.641 2.20 16.667 18.049 17.209 18.636 2.60 15.238 16.502 15.739 17.044 3.00 14.061 15.227 14.555 15.762 4.00 11.843 12.826 12.561 13.603 Ey EI(XF11) EI(XF12) EI(XF2I) EI(XF22)MeV 0.90 4.29E-13 4.91E-14 1.70E-13 1.81E-14 1.35 2.96E-11 4.75E-12 1.43E-11 2.16E-12 1.80 4.98E-10 9.98E-11 2.64E-10 5.03E-11 2.20 3.28E-09 7.63E-10 1.85 E-09 4.12E-10 2.60 1.49E-08 3.91 E-09 8.76E-09 2.20E-09 3.00 5.22 E-08 1.51 E-08 3.08 E-08 8.55E-09 4.00 5.63E-07 1.96E-07 2.60E-07 8.51 E-08 SM-SNC524602-001ATAHETFSETF21 ATTACHMENT F2 SHEET F2-14 Vogtle Rv =Ov=sec Ov =12 6.850 0.519 1.151 feet feet radians = arctan(Rv/d)

E'y Xv Ii Xv12 Xv2l Xv22 MeV 0.90 25.212 29.031 26.102 30.055 1.35 21.147 24.350 21.846 25.155 1.80 18.456 21.251 19.060 21.947 2.20 16.667 19.192 17.209 19.816 2.60 15.238 17.546 15.739 18.122 3.00 14.061 16.191 14.555 16.760 4.00 11.843 13.637 12.561 14.463 E', Ei(Xvt1) Ei(Xvi2) EI(Xvzi) E1(Xv22)MeV 0.90 4.29 E-13 8.22 E-15 1.70E-13 2.85E-15 1.35 2.96E-11 1.05E-12 1.43E-11 4.55 E-13 1.80 4.98E-10 2.66E-11 2.64E-10 1.28E-11 2.20 3.28E-09 2.30E-10 1.85E-09 1.19E-10 2.60 1.49E-08 1.30E-09 8.76E-09 7.07E-10 3.00 5.22E-08 5.43E-09 3.08E-08 2.97E-09 4.00 5.63E-07 8.20E-08 2.60E-07 3.40E-08 E', DRv Fnorm DR.__F DRF MeV mREM/hr DRy 0.90 1.55E-01 1.39 0.90 1.94E-01 1.35 3.18E-01 1.39 0.87 3.82E-01 1.80 1.73E+01 1.39 0.84 2.02E+01 2.20 2.83E+00 1.39 0.82 3.22E+00 2.60 9.37E+00 1.39 0.80 1 .04E+01 3.00 4.08E-01 1.39 0.79 4.45E-01 4.00 9.96E-01 1.39 0.76 1.05E+00 TOTAL = 3.14E+01 mREM/hr TOTAL = 3.59E+01 mREM/hr SM-SNC524602-001ATAHETFSETF21 ATTACHMENT F2 SHEET F2-15 d = 14 feet d = 426.72 cm Farley RF =OF =seC'OF =4.988 0.342 1.062 feet radians = arctan(RF/d)

E'y XF11 XF12 XF21 XF22 MeV 0.90 29.414 31 .225 30.452 32.327 1.35 24.671 26.190 25.488 27.057 1.80 21.531 22.857 22.237 23.606 2.20 19.445 20.642 20.077 21.313 2.60 17.778 18.872 18.362 19.492 3.00 16.405 17.415 16.981 18.026 4.00 13.817 14.668 14.654 15.557 Ey E1(XF11) EI(XFI2) E1(XF2I) E1(XF22)MeV 0.90 5.53E-15 8.54E-16 1.89E-15 2.74E-16 1.35 7.53E-13 1.56E-13 3.22E-13 6.34E-14 1.80 1.98E-11 4.97E-12 9.49E-12 2.28E-12 2.20 1.76E-10 5.02E-11 9.07E-11 2.49E-11 2.60 1.02 E-09 3.21 E-10 5.49E-10 1.68E-10 3.00 4.33 E-09 1.49 E-09 2.35E-09 7.82 E-10 4.00 6.77E-08 2.73E-08 2.77E-08 1 .06E-08 SM-SNC524602-001ATAHETFSETF21 ATTACHMENT F2 SHEET F2-16 Vogtie d=Rv =Ov =sec Ov =14 6.850 0.455 1.113 feet feet radians = arctan(Rv/d)

E'y Xvii1 Xv1 2 Xv21 Xv22 MeV 0.90 29.414 32.747 30.452 33.902 1.35 24.671 27.466 25.488 28.375 1.80 21.531 23.971 22.237 24.756 2.20 19.445 21.648 20.077 22.352 2.60 17.778 19.791 18.362 20.442 3.00 16.405 18.263 16.981 18.905 4.00 13.817 15.383 14.654 16.315 Ey Ei(Xvi1) Ei(Xvi2) Ei(Xvzi) EI(Xv22)MeV 0.90 5.53E-15 1.78E-16 1.89 E-15 5.42 E-17 1.35 7.53E-13 4.15E-14 3.22E-13 1.62E-14 1.80 1.98E-11 1.56E-12 9.49 E-12 6.89E-13 2.20 1.76E-10 1.75E-11 9.07E-11 8.42E-12 2.60 1.02E-09 1.22E-10 5.49E-10 6.19E-11 3.00 4.33 E-09 6.09 E-10 2.35E-09 3.10E-10 4.00 6.77E-08 1.28E-08 2.77E-08 4.76E-09 Ey DRy Fnorm DRF DRF MeV mREM/hr DRy 0.90 2.7E-03 1.39 0.87 3.3E-03 1.35 9.8E-03 1.39 0.83 1.1E-02 1.80 8.2E-01 1.39 0.81 9.2E-01 2.20 1.6E-01 1.39 0.79 1.8E-01 2.60 6.7E-01 1.39 0.77 7.2E-01 3.00 3.5E-02 1.39 0.76 3.7E-02 4.00 1.2E-01 1.39 0.73 1.2E-01 TOTAL = 1,.8E+00O mREM/hr TOTAL = 2.0E+00 mREMIhr SM-SNC524602-001ATAHETFSETF27 ATTACHMENT F2 SHEET F2-17 d = 16 feet d = 487.68 cm Farley RF =OF =sec OF =4.988 0.302 1.047 feet radians = arctan(RF/d)

Ey XF1I XFI2 XF2I XF22 MeV 0.90 33.62 35.21 34.80 36.45 1.35 28.20 29.53 29.13 30.51 1.80 24.61 25.78 25.41 26.62 2.20 22.22 23.28 22.95 24.03 2.60 20.32 21.28 20.98 21.98 3.00 18.75 19.64 19.41 20.33 4.00 15.79 16.54 16.75 17.54 Ey E1 (XF11) E1(XF12) E1(XF21) E1 (XF22)MeV 0.90 7.3E-17 1.4E-17 2.1E-17 3.9E-18 1.35 1.9E-14 4.9E-15 7.4E-15 1.8E-15 1.80 8.0OE-13 2.4E-13 3.5E-13 1.0E-13 2.20 9.6E-12 3.2E-12 4.5E-12 1.5E-12 2.60 7.1E-11 2.6E-11 3.5E-11 1.2E-11 3.00 3.7E-10 1.4E-10 1.8E-10 7.0E-11 4.00 8.3E-09 3.7E-09 3.0E-09 1.3E-09 SM-SNC524602-001ATAHETFSETF21 ATTACHMENT F2 SHEET F2-18 Vogtle d=Rv=Ov =sec Ov =16 6.850 0.405 1.088 feet feet radians = arctan(Rv/d)

E Xv Ii Xvl 2 Xv~l Xv22 MeV___ _0.90 33.62 36.57 34.80 37.86 1.35 28.20 30.67 29.13 31.69 1.80 24.61 26.77 25.41 27.64 2.20 22.22 24.17 22.95 24.96 2.60 20.32 22.10 20.98 22.83 3.00 18.75 20.39 19.41 21.11 4.00 15.79 17.18 16.75 18.22 E7 E1(Xvii) Ei(Xv12) EI(Xv2i) Ew(Xv22)MeV 0.90 7.3E-17 3.5E-18 2.1E-17 9.3E-19 1.35 1.9E-14 1.5E-15 7.4E-15 5.3E-16 1.80 8.0E-13 8.5E-14 3.5E-13 3.4E-14 2.20 9.6E-12 1.3E-12 4.5E-12 5.6E-13 2.60 7.1E-11 1.1E-11 3.5E-11 5.1E-12 3.00 3.7E-10 6.5E-11 1.8E-10 3.1E-11 4.00 8.3E-09 1.9 E-09 3.0OE-09 6.4E-10 EyDRy Fnorm DR._.F DRF MeV mREM/hr DRy 0.90 4.6E-05 1.39 0.84 5.4E-05 1.35 3.3E-04 1.39 0.81 3.7E-04 1.80 3.9E-02 1.39 0.78 4.3E-02 2.20 9.5E-03 1.39 0.76 1.0OE-02 2.60 4.9E-02 1.39 0.75 5.1IE-02 3.00 3.1IE-03 1.39 0.73 3.1IE-03 4.00 1.4E-02 1.39 0.71 1.4E-02 TOTAL =1.2E-01 mREMIhr TOTAL = 1.2E-01 mREM/hr Southern Nuclear Design Calculation SPlant: Farley Unit: 1&2 Calculation Number: SM-SNC524602-001 ISheet: F3-1 Attachment F3 -Operating Deck Dose Rates for Reduced RPV Water Level Introduction The purpose of this evaluation is to determine the dose rates at the Containment operating deck area radiation monitors, RE0002 and RE0027A/B, that correspond to RPV water level elevations of 121 '-0" (3' above TOAF) and 11 8'-0" (TOAF).Evaluation Dose Rate at Water Surface or TOAF The dose rate vs. graph in Attachment F2 does not extend down to zero feet of water depth.The Farley dose rate vs. depth data are used to generate another graph, and the line is extended down to fuel uncovery as shown below: Farley RPV Dose Rate vs. Water Depth 12 Water Depth Above TOAF (feet)At an RPV water level elevation corresponding to 3 feet above TOAF (EL 121'-0"), the dose rate at the surface of the water is 3.0E+07 mREM/hr, or 3.0E+i04 REM/hr At an RPV water level corresponding to fuel uncovery, the dose rate is 3.0E+09 mREM/hr, or 3.0E+06 REM/hr Southern Nuclear Design Calculation IPlant: Farley IUnit: 1&2 ICalculation Number: SM-SNC524602-001 ISheet: F3-2 Attachment F3 -Operating Deck Dose Rates for Reduced RPV Water Level Operatincq Deck Reflected Dose Rate Based on a study of instrument location drawings D175148 and D205148, the containment operating deck (RE0002 and RE0027A/B) area radiation monitors do not have a direct view of the irradiated fuel. They are located 5' above the operating deck (EL 155'0"; Design Input #8)at EL 1 60'0" and against a wall. They do "see" gammas that reflect off the containment dome.The operating deck dose rate due to these reflected gammas is given by the following equation from Davisson, "Gamma Ray Dose Albedos," (copy in Attachment C1): DRmon/DRsfc

= (cos 0)*(A/r 2)*(a where DRmon = reflected dose rate at area radiation monitor (mREM/hr)DRsfc = dose rate at surface of water above irradiated fuel (mREM/hr)0 = incident angle = 0°A = reflecting area (sq ft)r = distance from reflecting surface to receptor a= dose albedo; dependent upon incident angle, gamma energy, reflected angle, and reflecting surface Rearranging the above equation to solve for the dose rate at the area radiation monitor yields DRmon = DRsfc x [(COS 0)*(A/r 2The containment geometry is shown to '-/i; '=",, right (from Assumption

1. 11). ,\, 0 = 0-> cos0e= 1.00 " //A = area of reflecting surface (sq ft)/,,/ \ , A=F1 D 2/4 //t\,'D = 13.083 ft [Design Input #12] ___A =fl[(13.083) 2/4 =134.4 sqfft7a \ / : ",, r = hypotenuse of right triangle \ '**+ x --y = 287'-0" -1 60'-0" y= 127ft x = 65 ft ....r = SQRT[x 2 + yl] = SQRT [(65)2 + (127)2] 'r= 143ft ... ....LContalnment dimensions:

Ueslgn Input Southern Nuclear Design Calculation SPlant: Farley Unit: 1&2 Calculation Number: SM-SNC524602-001 Sheet: F3-3 Attachment F3 -Operating Deck Dose Rates for Reduced RPV Water Level The containment has a carbon steel liner, so the dose albedo for iron is used. For an incident angle of 00, a range of emerging angles of 00 to ~~30°, and the predominant gamma energy (-2 MeV based a review of the dose rate data in Attachment E2), ct = -0.005 based on a review of the table on sheet C1-10 of this calculation.

DRmon = DRsfc x {(1 .00)*[134.4/(1432)]*(0.005)}

DRmon = 3.29E-05 x DRsfc Operatingi Deck Reflected Dose Rate -RPV Water Level (, TOAF The Containment operating deck dose rate due to an source dose rate of 3.0E+09 mREM/hr is therefore DRmon = 3.29E-05 x (3.0E+09 mREM/hr)DRmon = 9.86E+04 mREM/hr DRmon --100 REM/hr Southern Nuclear Design Calculation Plant: Farley Unit: 1&2 ICalculation Number: SM-SNC524602-001 Isheet: F4-1 Attachment F4 -Seal Table Room Dose Rate Evaluation Introduction The purpose of this evaluation is to determine the dose rates at the seal table room area radiation monitor, RE0007, that correspond to the operating deck dose rates calculated in Attachment F3 of this calculation.

Evaluation The dose rate is proportional to the gamma flux, DR oa 4, (page 442, Lamarsh, "Introduction to Nuclear Engineering"), so the dose rate in the seal table room (DRstr) may be estimated by modeling the reflected gamma flux at the operating deck as a monodirectional planar source at the back of a concrete shield. The gamma flux in the seal table room (4str) is the buildup flux passing through the operating deck (equation 10.26, page 484, "Introduction to Nuclear Engineering"):

4str = (4od/2) X {AiE1[(1 + a1) x p, x aod] + A2E1[(1 + (a2) x X aod]}*str/jod = 1/2 X {AiEi[(1 + oai) X !i X aod] + A2E1[(1 + ca2) x ji x aod]}DRstr/DRod

= % x {AiEi[(1 + ai) x p. x aod] + A2E1[(1 + oa2) x p. x aod]}A review of the data in Attachment F2 indicates that 2 MeV gammas are predominant; the evaluation will be based on 2 MeV gammas to estimate the overall effect on dose rate.Where, for 2 MeV gammas A1 = 18.089 [Table 10.3, page 482, "Introduction to Nuclear Engineering"]

A2 = 1 -Ai [page 481, "Introduction to Nuclear Engineering"]

A2 = -1 7.089 o1= -0.04250 [Table 10.3, page 482, "Introduction to Nuclear Engineering"]

cx2 = 0.00849 [Table 10.3, page 482, "Introduction to Nuclear Engineering"]

p.= (p/)x p (p./p) = 0.0445 cm 2/g [Table 11.4, page 648, "Introduction to Nuclear Engineering"]

p = 2.40 g/cm 3 [Table 11.4, page 648, "Introduction to Nuclear Engineering"]

p.= (0.0445 cm 2/g) x (2.40 g/cm 3)p. = 0.1068 cm-1 aod = operating deck thickness aod = 3 ft X (30.48 cm/i ft) [Design Input #8]aod = 91.44 cm Southern Nuclear Design Calculation SPlant: Farley Unit: 1&2 ICalculation Number: SM-SNC524602-001 Sheet: F4-2 Attachment F4 -Seal Table Room Dose Rate Evaluation Per equation 10.24 on page 483 of "Introduction to Nuclear Engineering," for X > 14 the function Ei(X) may be approximated as: Ei[X] = [exp(-X)]

x {[l/(X + 1)] + [I/(X +1)]Xi = (1 + oci) x !L x aod = (1 -- 0.04250) X (0.1068 cm-1) x (91.44 cm) = 9.3507 X2 = (1 + cL2) x JI x aod = (1 + 0.00849) X (0.1068 cm-') x (91.44 cm) = 9.8487 For X = 10, the error is 0.11%; the values of X used in this evaluation is are sufficiently close to 10 that any error due to this approximation is negligible.

For Xi = 9.3507: Ei[Xi] = [exp(-9.3507)]

x {[1I(9.3507

+ 1)] + [1/(9.3507

+1)]Ei [Xi] = 8.4739E-06 For X2 = 9.8487: E1[X2] = [exp(-9.8487)]

x {[1/(9.8487

+ 1)] + [1 /(9.8487 +1)]Ei[Xi] = 4.9097E-06 Therefore DRstr/DRod

= 1/2 x [(1 8.089)x(8.4739E-06)

+ (-1 7.089)x(4.9097E-06)]

DRstr/DRod

= % x [1 .532E-04 -8.390E-05]

DRstr/DRod

= 3.47E-.05 DRstr = (3.47E-.05) x DRod For RPV water level EL 11 8'-0" (TOAF), DRod = 9.86E+04 mREM/hr (Attachment F3): DRstr = (3.47E-05) x (9.86E+04 mREM/hr)DRstr = 3.42 mREM/hr DRstr = -3 mREMIhr Purpose: The purpose of this calculation is to provide emergency action level thresholds for use in the development of the Farley Nuclear Plant Emergency Action Levels using NEI 99-01 Rev 6 guidelines.

This calculation includes the thresholds for three fission product barrier EALs; Fuel Clad Barrier Loss 3.A, RCS Barrier Loss 3.A, and Containment Barrier Potential Loss 3.A.Criteria: The calculation performed will support the development of guidelines for NE! 99-01 EALs numbers AA2 (EAL3), AA2 (EAL4), FC(EAL5), RCS(EAL4), CTMT(EAL2), CTMT(EAL5), and SS5(EAL 1).1. Declaration of an emergency, when such a declaration is not required, involves risk to the public as does the failure to make such a declaration, should one be warranted.

Therefore, this calculation shall develop a 'best estimate" value for the dose rates or curie concentrations sensed at the monitors chosen for the Emergency Action Level (EAL) set points. When judgments are necessary, these judgments shall be as close to anticipated conditions as possible.2. If a particular monitor is to be used for an EAL, then the dose rate or curie concentration set point developed for that specific monitor shall be within the range of the monitor, or the monitor shall not be cited as applicable for the EAL.3. In accordance with the guidance of Regulatory Guide 1 .97, Revision 2, post-accident radiation monitors must read within a factor of 2 of actual radiation conditions.

Therefore, changes in the set points of this revision that are within a factor of 2 of the previous revision's set point for the same EAL do not invalidate the previous set point.It is up to the ultimate user of these calculations to determine if change to the EAL set point guidance document(s) is warranted.

4. Methods and Assumptions shall comply with the guidance of NEI 99-01 Rev. 6.

==

Conclusions:==

The results of the calculations of the radiation analysis for the fission product barrier EALs are presented below.EAL Monitor Monitor Range Set Point Containment Barrier , 5 Potential Loss 4.B *55 FulCa BrirRE-0027A&B 1 E+00 to 1 E+07 R/hr 600 R/hr Loss 3.A RE-0002 1 E-04 to 1 E+01 R/hr 1 R/hr RCS Barrier Loss 3.A Or Or RE-0007 I1E-04 to 1 E+01 R/hr 0.5R/hr Cotinet arir RE-0027A&B 1 E+00 to 1 E+07 R/hr 8,000R/hr PotentialLoss_3.A

__________

__________

__ ________**These values are not reported in this calculation.

The evaluation was performed in calculation SM-95-0754-001 and this information can be found there. This calculation provides the supportating rational for the established set point.

Design Inputs: 1. Per RG1 .195 page 14 Table 3, we will only consider groups for radionuclide of XE, Kr, and I.2. The Reactor Coolant Fission Product Specific Activity is taken from WCAP-1 4722 Table 7.6-6 page 7.6-52.3. The ICRP30 inhalation dose conversion factors are obtained from NUREG/CR-5106 pg E-19. Per ESAR page 3A-1.195-1 ICRP 30 dose conversion factors should be used with RG1 .1.95. The dose conversion factors also are available in Table G.6 of Faw & Shultis"Radiological Assesment" 4. The isotope 1-127 & 129 is considered a stable isotope per Chart of Nuclides and will not be part of this analysis.5. The Geometric Correction Factor in Sections V, VI, and VII of 768 was obtained from SM-94-0466-001 page 30.6. Per RG1.195 page 12 and 13 section 3.2 and table 2: The core inventory release fractions for non-LOCA events where only cladding is breached, the release fractions in table 2 should be considered.

1-131 is 0.08, Kr-85 is 0.10, Other Noble Gases 0.05, Other lodines 0.05.The RG1 .195 Table I shows release fractions when the fuel melted as well as cladding when Table 2 is only when the cladding failed. The NEI 99-01 page 5-F-19 section 6 described the IC as 20% failed cladding, therefore it is more appropriate to use Table 2 release fractions when only cladding failed.7. Dose Equivalent 1-131 is defined as that concentration of 1-131 (uCi/gm) which alone would produce the same thyroid dose as the quantity and isotopic mixture of 1-131, I-132, 1-133, 1-134, 1-135 (NUREG-1301 page 6).8. The radiation monitor RE-0027A&B operating range is i to 1E:7 R/hr (page 3-16 of Al181015).

9. The radiation monitor RE-0002 operating range is 1 E-4 to 1 El rads per hour (page 3-5 of A181015).10.The radiation monitor RE-0007 operating range is 1E-4 to 1E1 rads per hour (page 3-12 of Al181 015).11 .Technical Specification 3.4.16 limits the RCS activity to 0.5pCi/gm dose equivalent I-131.12. RCS mass is 417,219 Ibm (page 4.1-3 WCAP 15097).

Assumptions:

1. The assumptions used in the radiation monitor response analysis performed in SCS Calculation SM-94-0466-O01 are correct and proper for this analysis except as noted in the calculation.

2. It is assumed that the dose field seen by RE-0027 radiation detector sensitivity calculated in SM-94-0466-OO1 is applicable to RE-0002. It is a conservative assumption because per D205148 both detectors are located at same height of EL 160 feet.

References:

1. Deleted 2. Deleted 3. SCS Calculation SM-95-0754-001 Ver 7.0 "Severe Accident Management Guidelines (SAM G)" 4. U206196 Vl.0 was superseded by U279877 V3.0 "R.H. General Arrangement" 5. D176540 V12.0, "Section 18 Concrete Auxiliary Building" 6. SCS Calculation SM-96-1064-001 V9.0 "Fuel Handling Accident Doses" 7. TACT5 Users Manual, NUREG/CR-5106 June 1988 8. AlA list, Westinghouse Letter ALA-95-756, 12/15/95 "Joseph M Farley Nuclear Plant Units 1 and 2 Power Uprate Project Analysis Input Assumption List and Matrix Revision 2." 9. SCS Nuclear Support Calculation F-86-03, Rev. 3, GRODEC Verification.

10. SCS Calculation SM-94-0466-001 V0.0, "Containment Dose Rate" 11. U 735579 VI1.0 "Radiation Analysis Design Manual for FNP", 4/72 12. D175149 V18.0, "Inst Loc CTMT & Fuel Hand" 13. U21 7359 V2.0, "ICCMS Technical Manual Volume II (Electronics)" 14. NEI 99-01 Rev 6 "Methodology for Development of Emergency Action Levels" 15. Deleted 16. Deleted 17. Shultis and Faw "Fundamentals of Nuclear Science and Engineering."2002 ISBN0-8247-0834-2

18. SM-97-1 638-002 V3.0 "Steam Generator Replacement

-Containment Pressure and Temperature Analysis" & CCN-F-10-0001 V3.0 19. Faw and Shultis "Radiological Assessment:

Sources and Doses" 1999, ISBN: 0-89448-455-9 20.A181015 V14.0 "Functional System Description Radiation Monitoring System" 21 .FNP Technical Specifications 198/194 22. Deleted.23. SNC Calculation 006.03 V0.0 "Analytical Procedures" 24. D1 76200, 15.0 "Floor Plan At EL. I105'6" Concrete -Containment" 25. "Engineering Compendium on Radiation Shielding", 1968 26. Etherington "Nuclear Engineering Handbook" McGraw 1958. Selected pages copy is attached to this calculation.

27. RG 1.195 "Methods and assumptions for evaluating radiological consequences of design bases accidents at Light-Water Nuclear Power Reactors." May 2003

28. WCAP14722 VI1.0 "Power Uprate Project NSSS Engineering Report." 29. Lockheed Martin 2002, "Chart of Nuclides and Isotopes" Ed 1 6 th.30. NUREG-1 301 "Offsite Dose Calculation Manual Guidance:

Standard Radiological Effluent Controls for Pressurized Water Reactors." Generic Letter 89-01, Supplement No. 1.31 .RG1 .97 R2 "Instrumentation for light-water-cooled nuclear power plants to assess plant and environs conditions during and following an accident." 32. NUREG-1228 "Source Estimations During Incident Response to Severe Nuclear Power Plant Accidents" 1988 33. U264698 V0.2 "RE/RI27 INS;TRUCTION MANUAL VI SYS 875-SUPERSEDES U447940 SUPERCEDES:U447940" 34. Deleted 35. WCAP 15097 VI.0 "REPLACEMENT STEAM GENERATOR PROGRAM NSSS ENGINEERING REPORT FOR FNP UNITS 1 AND 2 REVISION 1" Method of solutions:

Three related fission product barrier thresholds are calculated with the same method in this calculation.

The nuclide inventory for the RCS is taken from WCAP14722 and scaled to the prescribed activities of 0.5 pCi/cc, and 300 pCi/cc for representing a failure of the RCS barrier and the fuel clad barrier respectively.

For the case of potential containment failure, values from WCAP14722 for the full core are scaled based on gap release fractions, assumed 20% failed fuel, and power rating. The resulting nuclide inventories are dispersed evenly in the free volume of containment, binned by energy level in GRODEC, multiplied by dose conversion factors and a geometric factor to determine the containment radiation monitor response.The development of the values in this calculation were performed using various computer codes which were previously developed and verified for their particular application related to this calculation.

All codes were verified to be operating properly on their respective PC used in the calculation by running the test cases used in the verification of the code and comparing the results with the original verification calculation.

Details of the codes used are contained in the specific sections of the calculation.

Southern Nuclear 0perating Cornpanylant FNPSM-SNC524602-OO1 SOUTHERA Plnit: FNPil:NE 90 A Cluain Atcmn COMPN nit:1&2Tite:

NI 9-01 AL alclatins ttahmenT G-Body of Calculation:

Containment Barrier Potential Loss 4.B NEI 99-01 Rev 6 pg 119 "The existence of an explosive mixture means, at a minimum, that the containment atmospheric hydrogen concentration is sufficient to support a hydrogen burn (i.e., at the lower deflagration limit). A hydrogen burn will raise containment pressure and could result in collateral equipment damage leading to a loss of containment integrity.

It therefore represents a potential loss of the Containment Barrier." Existence of an explosive mixture of hydrogen and oxygen indicates a potential loss of containment integrity.

Per calculation SM-95-0754-001 pg 9, a hydrogen concentration above 6% is potentially explosive.

Since the accuracy of the hydrogen monitor is +/-0.5% in the range of 0-10% hydrogen, use 5.5%. Per calculation SM-95-0754-001 page 12 the concentration of >6% would support a burn throughout containment.

Fuel Clad Barrier Loss 3.A Containment radiation monitor RE-0027A&B (Q1 D21 RE0027A&B, Q2D21 RE0027A&B) can be read to one significant digit (page 15 of U264698), thus the value of 640.06R/hr is conservatively rounded off to 600R/hr (The revision 1 of this calculation had 80R/hr). The range of this monitor is 1Ito R/hr (page 3-16 of A181015).NEI 99-01 Rev 6 pg 105 "The radiation monitor reading corresponds to an instantaneous release of all reactor coolant mass into the containment, assuming that reactor coolant activity equals 300pCi/gm dose equivalent 1-131.Reactor coolant activity above this level is greater than that expected for iodine spikes and corresponds to an approximate range of 2% to 5% fuel clad damage. Since this condition indicates that a significant amount of fuel clad damage has occurred, it represents a loss of the Fuel Clad Barrier. " The monitor reading is calculated assuming the instantaneous release and dispersal of the reactor coolant noble gas inventory associated with a concentration of 300pCi/gm of dose equivalent 1131 into the containment atmosphere.

Concentration of this magnitude is several times larger than the maximum technical specification RCS concentration and is therefore indicative of fuel clad damage. Halogens and particulates are assumed to be largely retained by the water and/or removed via other physical processes (e.g. plateout and settling) and not dispersed throughout the containment.

This yields a slightly lower (conservative) radiation monitor reading.

The Reactor Coolant System fission products concentrations are taken from WCAP14722 Table 7.6-6, while all these isotopes are scaled to match DEl of 3001pCi/gm.

NUREG/CR-5106 pg E-1 9 ICRP Publication 30 (Ref 7) provides the inhalation dose conversion factor (REM/Ci)for 1-129 and 1-132. The isotope 1-127 is considered a stable isotope per Chart of Nuclides and will not be part of this analysis.

The rest of inhalation dose conversion factors for ICRP Publication 30 are listed in Faw Shultis "Radiological Assessment" Table G.6 in units of (Sv/Bq).The converstion factor of Sv/Bq to Rem/Ci is as follows: Ci :=3.7. 010 *Bq jpCi :=10- *.Ci Sv REM:=-100 page 5 of Faw, Shultis "Radiological Assesment" page 14 of Faw, Shultis "Radiological Assesment" note 5.Sv 102REM 1---=3.7x 1 Bq Ci MathCAD internal conversion The following excell worksheet was developed as follows:

= Activity. " k-) " Factor" (1i Factor. = Factor.

• LD3.7. *0 2(j Activity~'

'C m Activity'*

i/'.m 106"C-i 1 Relative Dose Conversion Weighted_____

Activity Factor Factor Activity Factor Activity (R/gm)(uCi/gm) (R/Ci) (Sv/Bq) (Ci/gm) (R/Ci)WCAP14722 NUREG- Faw,Shultis Table 7.6-6 5106 1-131 1.400E+i-00_____

2.90E-07 1.400E-06 1.073E+06 1.502E+00 1-132 2.300E+O0 6.30E+03 2.300E-06 6.300E+03 1.449E-02 1-133 2.700E+00 4.90E-08 2.700E-06 1.813E+05 4.895E-01 1-134 6.300E-01

______ 2.90E-10 6.300E-07 1.073E+03 6.760E-04 1-135 1.900E+00 8.50E-09 1.900E-06 3.145E+04 5.976E-02 SUM 2.07E+i00 And Ci :=3.7. 010 *Bq Ci p.Ci :=DOSeDEI :=2.07. 100.R-gm gm Do s CDEI RatioDEy to_1.131 .-=- 1.38_ Dose 1.131 MaSSRCS : 417219. lb = 1.892 x 108gm lib =453.592gm This statement defines the unit of Curies, since Becquerels are defined in MathCAD, while Curies are not. Reference is page 102 of Shultis Fundamentals of Nuclear Science and Engineering.

The sum in table above generated this number.The dose was generated in the table above.The RCS mass was obtained from WCAPI15097 page 4.1-3 MathCAD internal conversion and rounding to six sig. fig.The iodine gas activity as compaired to WCAP14722 is calculated below ActivityLl 3 1 := 1.4- 10-6. C-~gm.. .300. C.*Ratioiodine

.g = 155.28 RatioDEt to_1. 131 "Activityl.

1 3 1 The isotopes activity WCAP14722 table 7.6-6 was multiplied by 155.28, which was calculated above. The activity related to Xe and Kr was assumed to have 100% release as indicated in the NEI99-01 problem statement.

The activities related to Xe and Kr were obtained from WCAP14722 table 7.6-6.

18 gm The RCS mass was obtained from MaSSRCS := 417219- lb = 1.892 x 1gm WCAP 15097 page 4.1-3 lib =453.592gm MathCAD internal cornversion and rounding to two sig fig.The isotopes activities in next excell spreadsheet are calculated as follows: Isotope _________FC-EAL5 Activity (uCi/gm) Containment

______ WCAP14722 Activity (Ci)1-129 2.70E-08 7.93E-04 1-130 2.20E-02 6.46E+02 1-131 1.400E+00 4.11E+04 1-132 2.300E+00 6.76E+04 1-133 2.700E+00 7.93E+04 1-134 6.300E-01 1.85E+04 1-135 1.900E+00 5.58E+04 Kr-83m 4.500E-01 1.32E+04 Kr-85 7.700E+00 2.26E+05 Kr-85m 1.800E+00 5.29E+04 Kr-87 1.200E+00 3.53E+04 Kr-88 3.500E+00 1.03E+05 Kr-89 1.100E-01 3.23E+03 Xe-131m 2.900E+00 8.52E+04 Xe-133 2.400E+02 7.05E+06 Xe-133m 4.600E+00 1.35E+05 Xe-135 7.900E+00 2.32E+05 Xe-135m 4.500E-01 1.32E+i04 Xe- 137 2. O00E-01 5.88E+03 Xe-138 7.200E-01 2.12E+04 This activity was multiplied by 155.28, and multiplied by 10^-6 to convert from uCi to Ci, and mul ti Plied by gram ms RCS mass 1._892E8 .1-129 isotope is a Stable isotope. It will be dropPed f~rom -the m odel................................I The activities in the above table were entered into the GRODEC computer program (F-86-03 Ref.9) to convert the activity to specific energy groups which are used to estimate the detector response.

The volume of 5.66E1 0cc was used in GRODEC. Note: GRODEC was installed on a computer DELL SN#CYC7LS1 that was running Windows XP. To verify the program proper operation nine test cases were executed and output results were matched to the verification files listed on pages G1-G26 CALC F-86-03. The GRODEC input and output files can be found in GRODEC section of this calculation.

Containment volume: lff3 = 2.832 x 104 mL MathCAD internal converstion CC : lmL Volumnecontainment

= 2. 106.* if 3 Containment volume obtained from SM-97-1638-002 page A-8.Volumecontainment

= 5.66 x 101 cc The GRODEC results were entered into the EXCEL spread sheet below. The Dose Conversion Factors were obtained from SM-94-0466-001 page 32. A copy of these conversion factors is also attached to this calculation (reference Table 3 Etherington "Nuclear Engineering Handbook").

The geometric correction factor 768 was obtained from SM-94-0466-001 page 30.Dose Rate (/hr) = Source (MeV/cc-sec) x Geometric Factor + Dose Conversion Factor (MeV/cc-sec per I Rad/hr)Group Dose Cony GRDODEC FC EAL5 Energy Factor Source Dose Rate (MeV) (R/H per (MeV/cc- (R/h)Me V/cc- sec)sec)0.1 5.900E+05 1.358E+05 1.767E+02 0.3 5.540E+05 4.394E+04 6.091E+01 0.5 5.430E+05 1.621E+04 2.292E+01 0.7 5.490E+05 6.403E+04 8.957E+01 1 S.770E+05 5.842E+04 7.776E+01 1.5 6.270E+05 5.418E+04 6.637E+01 2 6.810E+05 5.294E+04 5.970E+01 2.5 7.350E+05 6.760E+04 7.063E+O1 3 7.890E+05 1.591E+i04 1.549E+01 Total Dose Rate (Rad/h) 640.06 Containment Barrier Potential Loss 3.A Containment radiation monitor RE-0027A&B (QI D21 RE0027A&B, Q2D21 RE0027A&B) can be read to one significant digit (page 15 of U264698), thus the value of 7,969R/hr is rounded off to 8,000R/hr (The revision 1 of this calculation had 3,000R/hr).

This rounding is acceptable because per RG1 .97 the instrument accuracy is expected to be within a factor of 2 or +/-50%.The range of this monitor is 1Ito R/hr (page 3-16 of Al181 015).NEI 99-01 Rev 6 pg 116 "The radiation monitor reading corresponds to an instantaneous release of all reactor coolant mass into the containment, assuming that 20% of the fuel cladding has failed. This level of fuel clad failure is well above that used to determine the analogous Fuel Clad Barrier Loss and RCS Barrier Loss thresholds.

NUREG-1228, Source Estimations During Incident Response to Severe Nuclear Power Plant Accidents, indicates the fuel clad failure must be greater than approximately 20%in order for there to be a major release of radioactivity requiring offsite protective actions. For this condition to exist, there must already have been a loss of the RCS Barrier and the Fuel Clad Barrier. It is therefore prudent to treat this condition as a potential loss of containment which would then escalate the emergency classification level to a General Emergency." A major release of radioactivity requiring offsite protective actions from core damage is not possible unless a major failure of fuel cladding allows radioactive material to be released from the core into the reactor coolant. Regardless of whether containment is challenged, this amount of activity in containment, if released could have such severe consequences that it is prudent to treat this as a potential loss of containment.

NUREG-1 228, "Source Estimations During Incident Response to Severe Nuclear Power Plant Accidents," indicates that such conditions do not exist when the amount of clad damage is less than 20%, which is the value used for this analysis.

The activity for isotopes can be found as follows: ActivitYisotope

= CoreInventoryisotope*

PowerDBAcorecton Release_Fraction

• MeltedFuel%

PowerDBAeoreto

= 102% =1.02 WCAP 14722 Table 7.6-1 Releaseaae 0 ion131 := 0.08 These release fractions come from RG1.195 Table 2.Reeseto Kr85 :=0.10 ReleasehactionOtherNobleGases

= 0.05 Releasefration_Othrlodines

= 0.05 MeltedFuel%

= 20% = 0.2 This value comes from NEI99-01 page 5-F15.The Core Inventory is listed in WCAP14722 Table 7.6-5. Per RG1 .195 Table 3 we only consider Xe, Kr, and Idoine isotopes.

Per RG1.195 page 12 and 13 section 3.2 and table 2: The core inventory release fractions for non-LOCA events where only cladding is breached, the release fractions in table 2 should be considered:

1-131 is 0.08, Kr-85 is 0.10, Other Noble Gases 0.05, Other Iodines 0.05. The power DBA correction factor is 1.02 (102%) per WCAP14722 Table 7.6-1 page 7.6-10. Per NUREG1301 DEl definition on page 6 the DEl is based on I-I131,1I-132,1I-133,1I-134, and I-135, so only these five Iodine isotopes were considered.

The following Excel Sheet is developed with the criteria listed above.

Isotope WCAP14722 PowerDBA T Release % failed CTMTEAL6 Table 7.6-5 Fraction fuel_______ ____________

RGi. 195 ____ _ _ _ _ ______ (ci) ______I_____

_____(ci)i..................

i..............

I I + I I 1-131 7.50E+07 1.02 0.08 0.2 1. 224E+06 1-132 1.10E+08 1.02 0.05 0.2 1.122E+06

....1-133 1.60E+08 1.02 0.05 0.2 1.632E+06__

1-134 1.70E+08 1.02 0.05 0.2 1.734E+I06 1-135 1.50E+08 1.02 0.05 0.2 1.530E+06 Kr-83m 9.70E+06 1.02 0.05 0.2 9.894E+04

_Kr-85 7.20E+05 1.02 0.10 0.2 1.469E+04 Kr-85m 2.10E+07 1.02 0.05 0.2 2.142E+05 Kr-87 4.00E+07 1.02 0.05 0.2 4.080E+05 Kr-88 5.70E+07 1.02 0.05 0.2 5.814E+05 Xe-131m 8.40E+05 1.02 0.05 0.2 8.568E+03

_Xe-133 1.50E+08 1.02 0.05 0.2 1.530E+06__

Xe-133m 4.80E+06 1.02 0.05 0.2 4.896E+04 Xe-135 3.50E+07 1.02 0.05 0.2 3.570E+05__

Xe-135m 3.00E+07 1.02 0.05 0.2 3.060E+05__

Xe-137 1.40E+08 1.02 0.05 0.2 1.428E+06__

Xe-138 1.300E+08 1.02 0.05 0.2 1.326E+i06 J i J f 1 i t!..........

.............

1. The activities in the above table were entered into the GRODEC computer program (F-86-03 Ref.9) to convert the activity to specific energy groups which are used to estimate the detector response.

The volume of 5.66E1 0cc was used in GRODEC. Note: GRODEC was installed on a computer DELL SN#CYC7LS1 that was running Windows XP. To verify the program proper operation nine test cases were executed and output results were matched to the verification files listed on pages G1-G26 CALC F-86-03. The GRODEC input and output files can be found in GRODEC section of this calculation.

Containment volume: ift3 2.832 x 104 mL MathCAD internal converstion cc :=lmL Volumecontaimet

=2. 106. ft 3 Containment volume obtained from SM-97-1638-002 page A-8.Volumecontainment

=5.66 x 101 cc The GRODEC results were entered into the EXCEL spread sheet below. The Dose Conversion Factors were obtained from SM-94-0466-001 page 32. A copy of these conversion factors is also attached to this calculation (reference Table 3 Etherington "Nuclear Engineering Handbook").The geometric correction factor of 768 was obtained from SM-94-0466-001 page 30.Dose Rate (R/hr) = Source (MeV/cc-sec) x (MeV/cc-sec per I Rad/hr).Group Dose Cony GRDODEC FC EAL5 Energy Factor Source Dose Rate (MeV) (R/hr per (MeV/cc- (R/hr)Me V/cc- sec)se C)0.1 5.900E+05 3.131E+04 4.076E+01 0.3 5.540E+05 1.424E+05 1.974E+02 0.5 5.430E+05 3.740E+i05 5.290E+02 0.7 5.490E+05 1.205E+06 1.685E+03 1 5.770E+05 1.417E+06 1.886E+03 1.5 6.270E+05 1.555E+'06 1.905E+03 2 6.810E+05 8.608E+05 9.707E+02 2.5 7.350E+05 5.353E+05 5.594E+02 3 7.890E+05 2.012E+05 1.959E+02 Total Dose Rate (Rad/h) 7.969E+03 Geometric Factor -Dose Conversion Factor RCS Barrier Potential Loss 3.A The containment radiation monitor RE-0002 (NI D21 RE0002, N2D21 RE0002) was calculated as 1.07 R/hr and can be conservatively down rounded to 1 R/hr (The revision 1 value for this monitor was 0.1 R/hr). Per A181015 page 3-5 the instrument range is 1E-4 to 1IE1 rads per hour.Or The containment radiation monitor RE-0007 (Ni D21 RE0007, N2D21 RE0007) was calculated as 0.54 R/hr and can be conservatively down rounded to 0.5 R/hr (The revision 1 value for this monitor was 0.2 R/hr). Per A181015 page 3-12 the instrument range is 1E-4 to 1E1 rads per hour.NEI 99-01 Rev 6 pg 111 "The reading should be determined assuming the instantaneous release and dispersal of the reactor coolant noble gas and iodine inventory, with RCS activity at Technical Specification allowable limits, into the containment atmosphere.

Using RCS activity at Technical Specification allowable limits aligns this threshold with IC SU3. Also, RCS activity at this level will typically result in containment radiation levels that can be more readily detected bycontainment radiation monitors, and more readily differentiated from those caused by piping or component "shine" sources. If desired, a, plant may use a lesser value of RCS activity for determining this value." This reading is calculated assuming the instantaneous release and dispersal of the reactor: coolant noble gas and iodine inventory associated with normal operating concentrations (i.e., within technical specification limits) into the containment atmosphere.

It is indicative of an RCS leak only without significant clad damage.Technical Specification 3.4.16 limits the RCS activity to 0.5 pCi/gm dose equivalent 1131.NUREG/CR-5106 pg E-19 ICRP Publication 30 (Ref 7) provides the inhalation dose conversion factor (REM/Ci) for 1-132. The rest of inhalation dose conversion factors for ICRP Publication 30 are listed in Faw Shultis "Radiological Assessment" Table G.6 in units of (Sv/Bq). The RCS design basis activity is listed on page 7.6-52 of WCAP14722 Table 7.6-6.Per NUREG1301 DEl definition on page 6 the DEl is based on 1-131, 1-132, 1-133, 1-134, and I-135, so only these five Iodine isotopes were considered.

The converstion factor of Sv/Bq to Rem/Ci is as follows: Ci :=3.7.1010

• Bq lLCi :=10- *.Ci_Sv REM:=-100 page 5 of Faw, Shultis "Radiological Assesment" page 14 of Faw, Shultis "Radiological Assesment" note 5.1*-Sv = .x112 REM Bq Ci MathCAD intemnal conversion The following excell worksheet was developed as follows: Activity Activity Factor" 'R---i Factor. = Factor- 3.7. 02

= Activity

• g* '0°(Relative Dose Conversion Weighted _____Activity Factor Factor Activity Factor Activity (R/gin)(uCi/gm) (R/Ci) (Sv/Bq) (Ci/gm) (R/Ci)WCAP14722 NUREG- Faw, Shultis Table 7.6-6 5106 Table G.6 1-131 1.400E+00 2.900E-07 1.400E-06 1.073E+06 1.502E+00 1-132 2.300E+00 6.300E+03

______2.300E-06 6.300E+03 1.449E-02 1-133 2.700E+00

_____ 4.900E-08 2.700E-06 1.813E+05 4.895E-01 1-134 6.300E-01

_____ 2.900E-10 6.300E-07 1.073E+03 6.760E-04 1-135 1.900E+00

_____ 8.500E-09 1.900E-06 3.145E+04 5.976E-02 SUM 2.07E+00 Ci :=3.7- 101 *Bq Ci 1 iCi := --6 DOSeDET := 2.07. 100 -gm Dose 1 1 3 1 :=1.50. 100.R gm Do s eDEL RatioDET to_1.131 :=. .1.38_ DOSel.1 3 1 MassRCS : 417219. lb =1.892 x 108 gm lib = 453.592 gm This statement defines the unit of Curies, since Becquerels are defined in MathCAD, while Cunes are not. Reference is page 102 of Shultis Fundamentals of Nuclear Science and Engineering.

The sum in table above generated this number.The dose was generated in the table above.The RCS mass was obtained from WCAP 15097 page 4.1-3 MathCAD internal conversion.

The iodine gas activity as compaired to WCAP 14722 is calculated below:-6 Ci Activityi.

1 3 1 :=1.4. 10 gm 0.5. ptCi RatlOiodines

.- g = 0.259 RatioDEl to 1.131 "ActivitYI.

1 3 1 The activity from WCAP14722 Table 7.6-6 was multiplied by 0.259, which was calculated above. The activity was also multiplied by 1 0^-6 for Ci/gm vs uCi/gm unit conversion and multiplied by 1 .892E8gm to account for RCS mass. The table was calculated for Iodines and Noble Gases.

Isotope IRCSEAL4 Activity (uCi/gm)WCAP14722 Conainen I + -. _______________________________

This activity was multiplied by 0.259, and multiplied by 10^-6 to convert from uCi to Ci, and multiplied by g~ramms of RCS mass 1.892E8 1 11-129 isotope is a stable isotope. It will be 1-129 2.70E-08j 1.32E-06f dropped from the model.1-130 2. 20E-02 1.08 E+00 1-131 1.400E+O0 6. 86E+01 1-132 2. 300E+00 1. 13E+02 1-133 2.700E+00 1.32E+02 1-134 6.300E-01 3.09E+01 1-135 1.900E+00 9.31E+01 Kr-83m 4.500E-01!

2.21E+01 Kr-85 7.700E+00' 3.77E+02 Kr-85m 1.800E+00 8.82E+01 Kr-87 1.200E+O0 5.88E+01 Kr-88 3.500E+00 1.72E+02 Kr-89 1.100E-O1 5.39E+00 Xe-131m 2.900E+00 1.42E+02 Xe-133 2.400E+02 1.18E+04 Xe- 133 m 4.600E+i00 2.25 E+02 Xe-135 7.900E+00 3.87E+02 Xe-135m 4.500E-01 2.21E+401 Xe-137 2.000E-01 9.80E+003 Xe-138 7.200E-01 3.53E+01.4 The activities in the above table were entered into the GRODEC computer program (F-86-03 Ref.9) to convert the activity to specific energy groups which are used to estimate the detector response.

The volume of 5.66E1 0cc was used in GRODEC. Note: GRODEC was installed on a computer DELL SN#CYC7LS1 that was running Windows XP. To verify the program proper operation nine test cases were executed and output results were matched to the verification files listed on pages G1-G26 CALC F-86-03. The GRODEC input and output files can be found in GRODEC'section of this calculation.

Containment volume: lff3 = 2.832 x 104mL, MathCAD internal converstion cc :=lmL Volumecontainment

=2. 106. -ft 3 Containment volume obtained from SM-97-1638-002 page A-8.Volumecontainment

=5.66 x 101 cc The GRODEC results were entered into the EXCEL spread sheet below. The GRODEC input and output file "RCSEAL4" are listed below. The Dose Conversion Factors were obtained from SM-94-0466-001 page 32. A copy of these conversion factors is also attached to this calculation (reference Table 3 Etherington "Nuclear Engineering Handbook").The geometric correction factor of 768 was obtained from SM-94-0466-001 page 30. The use of this geometric factor for R-2 radiation sensor is a good approximation because RE-0027 and RE-0002 are at the same height in the containment of 160'0" (D205148).

Dose Rate (R/hr) = Source (MeV/cc-sec) x Geometric Factor -Dose Conversion Factor (MeV/cc-sec per 1 Rad/hr).Group Dose GRDODE RCS EAL4 Energy Conv C Source Dose (MeV) Factor (MeV/cc- Rate (R/hr per sec) (R/hr)Me V/cc-se c) ____0.1 5.90E+05 2.27E+02 2.96E-O1 0.3 5.54E+05 7.33E+01 1.02E-01 0.5 5.43E+05 2.70E+01 3.82E-02 0.7 5.49E+05 1.07E+02 1.49E-01 1 5.77E+05 9.76E+01 1.30E-01 1.5i 6.27E+05 9.04E+01 1.11E-01 2 6.81E+05 8.84E+01 9.97E-O2 2.5 7.35E+05 1.13E+02 1.18E-0l 3 7.89E+05 2.65E+01 2.58E-02 Total Dose Rate (Rad/h) 1.07 RE-0007 is located near the seal table at elevation 133'-6" (Reference (D 175149 Zone C11).The containment volume visible to the monitor is shown on the following three sheets. This is modeled as a cylinder approximately 33' high with a radius of 31'. Using the methodology as described in Reference (SM-94-0466-001 page 26 -30) and is developed below.EL_RE00O7

=133.5

• ft ELplattnlnn=

137- ft The approximate elevation for RE-0007 is listed at 0175149 Zone B12.The platform elevation is listed in D205068 zone F5.hI = Lplffrm- ELRE0007 = 106.68 cm Height niodel "= 33

• ft The approximation assumption is 33feet. This approximation is shown on the folowing three sheets of this calculation.

h =Height model --h = 899.16ecm Rcontainment

"=6 5 *ft ..1 2 4 V 1 := -- Reontainment

• Height_model

=7.3.x 104 ft3 6 V 2:= 2.88"104 ft3 diameter is 65feet per 0176200., As shown on one of the three provided below markups, the pie section represents approximately six's of the presented volume.This volume was developed on the third marked up page. This page is provided below.R2 Volumecylinde

7E -R height Radius Heihtmoel

31.336ft S*Higt moe Calulating the cylinder equivalent radius that will be used for this model.-0.112 Radius--= 0.941 Radius Per table 6.4-3 page 382 of"Engineering Compendium on Radiation Shielding Vol. 1" the function (I) can be found. Liniar interpolation was also used.Linear Interpolation (X,-- x 1)(Y 3-- Yi)-0.112 Radius-___ 0.941 Radius 4)I (0.112 -0.1) -(1.34-- 1.68) +16 (0.2 -0.1)4)AI =1.64 (0.941 -0.4) -(0.628 4) A2 : 1.03)___+ 1.03 (1.0 -0.4)4 A2 =0.668 Equation 6.4-20 page 381 of"Engineering Cmpendium on Radiation Shielding:

h:=106.68cm h:=899.16cm Radius := 31.336ft 955.121 cm SV 4) .X -(h. 4 A1 + h. -)A2),)aaoo2 := --(h. ")A1 + h 2-4)A So 387.543 cm The viariable Sv was dropped out in this equiation line to calculate the ratio, and the Sv variable reinserted in the boxed equation.RE0007 = Sv .387.4 387.5 R R 4)RE0002 '= -- .1.07--- = 0.54-768 hr hr Thus the monitor R-7 response to the release is 387.5/768 times the R-2 monitor response, 0.54R/hr.

1.o~ ~.~ta*

W 1(.4*cOt.s1 fA ~A.Y7T~$ ~3

V~&N Ar ;. rVATION 129'-&'

a I* .I* i ----:* ... , E~:r:% 2'Y(ING '~5~

GRODEC FC_EAL_5 Input File 1 19 60,1 .32e+04,0 61 ,2.26e+05,0 62,5.29e+04,0 63,3.53e+I04,0 64,1 .03e+05,0 65,3.23e+03,0 1 40,6.46e+02,0 141,4.1 le+04,0 1 42,6.76e+04,0 1 43,7.93e+04,0 144,1 .85e+04,0 145,5.58e+04,0 1 46,8.52e+04,0 I147,7.05e+06,0 148,1 .35e+05,0 1 49,2.32e+05,0 150,1 .32e+04,0 151 ,5.88e+03,0 152,2.1 2e+04,0 FC_EAL_5.G_0 Output file OUTPUT OF GRODEC CALCULATION OPERATING IN MODE 1 DATA FILE NAME:FCEAL_5 INPUT DATA LISTING ISOTOPE INITIAL ADDITION ACTIVITY(CI)

RATE(CI/HR)-

KR-83M I1.320E+04 0.000E+00 KR-85 2.260E+05 0.000E+00 KR-85M 5.290E+04 0.000E+00 KR-87 3.530E+04 0.000E+00 KR-88 I1.030E+i05 0.000E+00 KR-89 3.230E+03 0.000E+00 I-130 6.460E+02 0.000E+00 1-131 1-132 1-133 1-134 1-135 XE-I131M XE-I133 XE-I133M XE-i135 XE-I135M XE-I137 XE-1 38 4.110OE+04 6.760E+'04 7.930E+04 1 .850E+04 5.580E+04 8.520E+04 7.050E+06 I1.350E+'05 2 .320E+05 I1.320E+04 5.880E+03 2.1 20E+04 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 WHAT ARE THE START, STOP, AND INTERVAL TIMES 1.00 1.00 1.00 TIME THIS INCREMENT

=1.000000 HOURS TOTAL ACTIVITY = 8144320.000000 CURIES ISOTOPE ISOTOPE NUMBER NAME INITIAL ACT(C I)ADDITION RATE(CI/HR)

ACTIVITY (CI)60 61 62 63 64 65 75 76 77 84 140 141 142 143 144 145 146 KR-83M KR-85 KR-85M KR-87 KR-88 KR-89 RB-87 RB-88 RB-89 SR-89 1-130 1-131 I-132 1-133 1-134 1-135 XE-131M 1 .320E+04 0.000E+00 9.094E+03 2.260E+05 0.000E+00 2.260E+05 5.290E+04 0.000E+00 4.519E+'04 3.530E+04 0.000E+00 2.043E+04 I1.030E+05 0.000E+00 8.042E+04 3.230E+03 0.000E+00 6.770E-03 0.000E+'00 0.000E+00 4.478E-11I 0.000E+00 0.000E+00 7.880E+'04 0.000E+00 0.000E+00 5.650E+-01 0.000E+00 0.000E+00 1 .238E-01 6.460E+02 0.000E+00 6.106E+02 4.110E+04 0.000E+00 4.095E+04 6.760E+04 0.000E+00 4.975E+04 7.930E+04 0.000E+00 7.664E+04 1.850E+04 0.000E+00 8.316E+03 5.580E+04 0.000E+00 5.030E+04 8.520E+04 0.000E+00 8.509E+04 147 XE-133 7.050E+06 0.000E+00 7.013E+06 148 XE-133M 1.350E+05 0.000E+00 1.333E+05 149 XE-135 2.320E+05 0.000E+00 2.193E+05 150 XE-135M 1.320E+04 0.000E+00 9.184E+02 151 XE-137 5.880E+03 0.000E+00 1.378E-01 152 XE-138 2.120E+04 0.000E+00 1.970E+03 161 CS-I135 0.000E+00 0.000E+00 5.946E-06 163 CS-137 0.000E+00 0.000E+'00 1.453E-03 164 CS-138 0.000E+00 0.000E+00 4.594E+03 171 BA-137M 0.000E+00 0.000E+00 1.453E-03 START OF MESS RUN ISOTOPES NOT INCLUDED IN MESS RUN NAME ACTIVITY (CI)RB-87 4.477765E-11I I-130 610.609700 CS-I135 5.945921 E-06 WHAT IS THE SOURCE VOLUME (CC)5.660000E+1 0 WHAT IS THE SOURCE DENSITY (GM/CC)1 .000000E-03 START EXECUTION OF THE MESS SUBROUTINE, ID NUMBERS ARE MESS ID NUMBERS,NOT MAIN PROGRAM IDS.THE NUMBER OF ENERGY GROUPS INPUT: 10 THE MAXIMUM ENERGY OF EACH GROUP: ENERGY MAXIMUM GROUP ENERGY 1 1 .000000E-01 2 3.000000E-01 3 5.000000E-01 4 7.000000E-01 5 1 .000000E+-00 6 1 .500000E+00 7 2.000000E+00 8 2.500000E+00 9 3.000000E+00 10 I.000000E+01 MESS INPUT DATA: SOURCE DENSITY (GM/CC) = 1.000000E-03 SOURCE VOLUME (CC) = 5.660000E+10 ISOTOPE ID NO.UC/GM SOURCE STRENGTH UC/CC CI KR 83M 45 KR 85 47 KR 85M 46 KR 87 48 KR 88 49 KR 89 50 KR 89 51 RB 88 67 RB 89 68 SR 89 21 1131 4 I132 5 I133 6 I134 7 I135 8 XEI131M 53 XE 133 54 XEI133M 55 XE 135 56 XEI137M 57 XE 137 58 XE 138 59 CS 137 35 CS 138 36 BAI137M 78 1 .606748E+0; 3.9929 10E+03 7.98431 8E+0;3.609242E+02 1 .420800E+03 1.196137 E-04 1 .196137 E-04 1 .392279E+03 9.981931 E-01 2.1 87626 E-03 7.235484E+02 8.789404E+02 1 .354038E+03 1 .469265E+02 8.8871 59E+02 1 .503393E+0 1 .238983E+05 2.354879E+0 3.873833E+03 1.622541 E+0 2.433959E-03 3.481 397E+01 2.567481 E-05 8.11 5789E+01 2.567368 2 1.606748E-01 3.992910OE+00 2 7.984319E-01 3.609242E-01 1 .420800E+00 1 .196137 E-07 1 .196137 E-07 1 .392279E+00 9.981 932E-04 2.187626 E-06 7.235484E-01 4 8.789405E-01 4 1.354038E+00 7 1 .469265E-01 8 8:887159E-01 5)3 1.503393E+00 1 .238983E+02

)3 2.354879E+00 3.873833E+00

)1 1.622541E-02 2.433959E-06 3.481397 E-02 2.567481 E-08 8.1 15789 E-02 5 2.567368E-08 9.0941 94E+03 2 .259987E+05 4.5191 24E+04 2.042831 E+04 8.04 1727E+04 6.770 134E-03 6.7701 34E-03 7.880300E+04 5.649773E+01 1.2381 97E-01.095284E+04

.974803E+04 T.663855E+04

.316039 E+03.0301 32E+04 8.509204E+04 7.01 2643E+06 1.332861 E+05 2.1 92590 E+05 9.1 83580E+02 1.377621 E-01 1.970471 E+03 1 .453194E-03 4.593537E+03 1.4531 30E-03 MESS OUTPUT DATA: ENERGY MAXIMUM SOURCE STRENGTH GROUP ENERGY (MEV/CC-SEC)(GAMMAS PER SEC)1 2 3 4 5 6 7 8 1 .000000E-01 3.000000E-01 5.000000E-01 7.000000E-01 1 .000000E+00 1 .500000E+00 2.000000E+00 2.500000E+00 1 .357539E+05 4.394020E+04 1 .620586E+04 6.402692E+04 5.842256E+04 5.41 8294E+04 5.2941 09E+04 6.759647E+04 7.683671 E+1 6 8.290051 E+15 1 .834504E+

15 5.1 77034 E+ 15 3.30671 7E+1 5 2.044503E+1 5 1 .498233E+

15 1 .530384E+

15 9 3.000000E+O0 1.591065E+04 3.001810E+14 10 1.000000E+O01 O.O00000E+O0 O.O00000E+O0 CTMTEAL6 Input File 1 17 60,9.894e+04,0 61,1 .469e+04,0 62,2.142e+05,0 63,4.080e+05,0 64,5.81 4e+05,0 141,1 .224e+I06,0 142,1 .122e+06,0 143,1 .632e+06,0 144,1 .734e+06,0 145,1 .530e+06,0 146,8.568E+03,0 147,1 .530e+06,0 148,4.896e+04,0 1 49,3.570e+05,0 I150,3.060e+i05,0 151,1 .428e+06,0 152,1 .326e+'06,0 CTMTEAL6 Output File OUTPUT OF GRODEC CALCULATION OPERATING IN MODE 1 DATA FILE NAME:CTMTEAL6 IN PUT DATA LISTING ISOTOPE INITIAL ADDITION ACTIVITY(Cl)

RATE(CI/HR)

KR-83M 9.894E+04 O.OOOE+OO KR-85 1 .469E+04 O.000E+OO KR-85M 2.142 E+05 0.000OE+OO KR-87 4.080E+05 O.OOOE+00 KR-88 5.814E+05 O.OOOE+OO I-131 1.224E+06 O.OO0E+OO I-132 1.122E+06 0.O00E+00 I-!133 1.632E+06 O.O00E+0O I-134 1 .734E+06 O.O00E+OO I-135 1 .530E+06 0.00OE+00O XE-131M 8.568 E+03 0.O00E+00 XE-133 1.530E+06 0.000E+00 XE-I133M 4.896E+04 0.000E+00 XE-I135 3.570E+05 0.000E+00 XE-I135M 3.060E+05 0.000E+00 XE-I137 1 .428E+06 0.000E+00 XE-138 1.326E+06 0.000E+00 WHAT ARE THE START, STOP, AND INTERVAL TIMES 1.00 1.00 1.00 TIME THIS INCREMENT

=1.000000 HOURS TOTAL ACTIVITY = 9649019.000000 CURIES ISOTOPE ISOTOPE NUMBER NAME INITIAL ADDITION ACT(CI) RATE(CI/HR)

ACTIVITY (Cl)60 61 62 63 64 75 76 141 142 143 144 145 146 147 148 149 150 151 152 161 163 164 171 KR-83M KR-85 KR-85M KR-87 KR-88 RB-87 RB-88 1-131 I-132 1-133 I-134 I-135 XE-131M XE-I133 XE-I133M XE-I135 XE-I135M XE-i137 XE-i138 CS-I135 CS-137 CS-I138 BA-I137M 9.894E+04 0.000E+00 6.817E+04 I1.469E+-04 0.000E+00 I1.469E+04 2.142E+05 0.000E+00 1.830E+05 4.080E+05 5.814E+05 0.000E+00 0.000E+00 1 .224E+06 1 .122E+06 I1.632E+06 1 .734E+06 I1.530E+06 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.361E+05 4.539E+05 5.175E-1 0 4.448E+05 I1.220E+06 8.257E+05 I1.577E+06 7.795E+05 I1.379E+06 8.568E+03 0.000E+00 1.153E+04 I1.530E+06 0.000E+00 1.531 E+06 4.896E+04 0.000E+00 4.834E+04 3.570E+05 0.000E+00 4.447E+05 3.060E+05 0.000E+00 2.129E+04 I1.428E+06 0.000E+00 3.346E+01 I1.326E+06 0.000E+00 I1.232E+05 0.000E+00 0.000E+00 I1.064E-05 0.000E+00 0.000E+00 3.529E-01 0.000E+00 0.000E+00 2.873E+05 0.000E+00 0.000E+00 3.529E-01 Southern Nuclear 0peratinl Cornpany SOUTHERNAAjL Plant: FNP SM-SNC524602-001I COMPANYt Unit: 1 &2 Title: NEI 99-01 EAL Calculations Attachment G START OF MESS RUN ISOTOPES NOT INCLUDED IN MESS RUN NAME RB-87 CS-I135 ACTIVITY (Cl)5.175433 E-10 1 .064398E-05 WHAT IS THE SOURCE VOLUME (CC)5.660000E+1-I0 WHAT IS THE SOURCE DENSITY (GM/CC)I1.000000E-03 START EXECUTION OF THE MESS SUBROUTINE, ID NUMBERS ARE MESS ID NUMBERS,NOT MAIN PROGRAM IDS.THE NUMBER OF ENERGY GROUPS INPUT: 10 THE MAXIMUM ENERGY OF EACH GROUP: ENERGY MAXIMUM GROUP ENERGY I 2 3 4 5 6 7 8 9 10 1 .000000E-01 3.000000E-01 5.000000E-01 7.000000E-01 I1.000000E+'00 I1.500000E+00 2.000000E+00 2.500000E+00 3.000000E+00 1 .000000E+01 MESS INPUT DATA: SOURCE DENSITY (GM/CC) = 1.000000E-03 SOURCE VOLUME (CC) = 5.660000E+-10 ISOTOPE ID NO.UC/GM KR 83M 45 1.20 KR 85 47 2.595 SOURCE STRENGTH UC/CC CI'4331 E+03 1.204331 E+00 6.816512E+04

$645E+02 2.595645E-01 1.4691 35E+04 KR 85M 46 KR 87 48 KR 88 49 RB 88 67 1131 4 I132 5 I133 6 I134 7 I135 8 XE 131M 53 XE 133 54 XEI133M 55 XE 135 56 XEI137M 57 XE 137 58 XE 138 59 CS 137 35 CS 138 36 BA 137M 78 3.232970E+03 3.232970E+00 1.829861 E+05 4.171 588 E+03 8.01 9932E+03 7.858942E+03 2.154801 E+04 1 .458833E+04 2.786620E+04 1.377138 E+04 2.436802E+04 2.037676E+O 2.704368E+04 8.540360E+O 7.856226E+03 3.761 344E+O 5.911 043E-01 2.177516E+03 6.235311 E-03 5.0761 96E+03 6.235037E-0:

4.171588 E+00 8.01 9933E+00 7.858943E+00 2.154801 E+01 1 .458833E+01 2.786621E+01 1.3771 38E+01 2.436802E+01

)2 2.037676E-01 I.2.704368E+01

'2 8.540360E-01

'2 3.761345E-01 5.91 1044 E-04 2.177516E+00 6.2353 12E-06 S5.076197E+00 3 6.235037E-06 2.36111 9E+05 4.539282E+05 4.4481 62E+05 1.219617E+06 8.256995E+05 1 .577227E+06 7.79460 1E+05 1 .379230E+06 1.1 53325E+04 I1.530672E+06 4.833844E+04 4.446624E+05 2.128921 E+04 3.345651 E+01 1 .232474E+05 3.5291 86E-01 2.8731 27E+05 3.529031 E-01 MESS OUTPUT DATA: ENERGY MAXIMUM GROUP ENERGY 1 1.000000E-01 2 3.000000E-01 1 3 5.000000E-01 ,C 4 7.000000E-01 I 5 1.000000E+00 6 1.500000E+00 7 2.000000E+00 8 2.500000E+00 9 3.000000E+00 10 1.000000E+01 SOURCE STRENC (MEV/CC-SEC)(GAMMAS PER SEC)3.131267E+04

!.424045E+05 3.740096E+05 1.204571 E+06 I1.41 691 6E+06 1 .555426E+06 8.607784E+05 5.353415E+05 2.0121 73E+05 0.000000E+00 1 .772297E+16 2.686697E+16 4.233789E+1 6 9.73981 8E+16 8.01 9742E+16 5.869141 E+16 2.436003E+1 6 1.21 201 3E+'16 3.796299E+1 5 0.000000E+00 RCSEAL4 Input File 1 19 60,2.21 e+01 ,0 61 ,3.77e+02,0 62,8.82e+01

,0 63,5.88e+01

,0 64,1 .72e+02,0 65,5.39e+00,0 140,1 .O8e+00,0 141 ,6.86e+01

,0 142,1 .13e+02,0 143,1 .32e+02,0 144,3.09e+01

,0 145,9.31e+01

,0 146, 1.42e+02,0 147, 1.18e+04,0 1 48,2.25e+02,0 1 49,3.87e+02,0 150,2.21 e+01 ,0 151 ,9.80e+00,0 1 52,3.53e+01

,0 RCSEAL4 Output File OUTPUT OF GRODEC CALCULATION OPERATING IN MODE DATA FILE NAME:RCSEAL4 1 INPUT DATA LISTING ISOTOPE INITIAL ADDITION ACTIVITY(CI)

RATE(CI/HR)

KR-83M 2.210E+01 0.000E+00 KR-85 3.770E+02 0.000E+00 KR-85M 8.820E+01 0.000E+00 KR-87 5.880E+01 0.000E+00 KR-88 1 .720E+02 0.000E+00 KR-89 5.390E+00 0.O00E+00 I-130 1.080E+00 0.000E+00 I-131 6.860E+01 0.OOE+00 1-132 1.130E+02 0.000E+00 I-133 1 .320E+02 0.000E+00 I-134 I-135 XE-i131M XE-I133 XE-i133M XE-1 35 XE-i135M XE-I137 XE-I138 3.090E+01 9.310OE+01 1 .420E+02 1.1 80E+04 2.250E+02 3.870E+02 2.210OE+01 9.800E+00 3.530E+01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 WHAT ARE THE START, STOP, AND INTERVAL TIMES 1.00 1.00 1.00 TIME THIS INCREMENT

=1.000000 HOURS TOTAL ACTIVITY = 13625.140000 CURIES ISOTOPE ISOTOPE NUMBER NAME INITIAL ACT(C I)ADDITION RATE(CI/HR)

ACTIVITY (CI)60 61 62 63 64 65 75 76 77 84 140 141 142 143 144 145 146 147 148 149 KR-83M KR-85 KR-85M KR-87 KR-88 KR-89 RB-87 RB-88 RB-89 SR-89 1-130 1-131 1-132 1-133 1-134 I-135 XE-131M XE-1 33 XE-I133M XE-I135 2.210OE+01 3.770E+02 8.820E+01 5.880E+01 1 .720E+02 5.390E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1 .080E+00 6.860E+01 1 .130E+02 1 .320E+02 3.090E+01 9.310OE+01 O.O00E+OC O.O00E+O0 O.O00E+OC O.O00E+O0 O.O00E+O0 0.O00E+O0 0.O00E+O0 0.OO0E+O0 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00]1.523E+01 3.770E+02]7.535E+01 3.403E+01 1 .343E+02 1 .1 30E-05 7.459E-1 4 1 .316E+02 9.428E-02 2.066E-04 1.021 E+00 6.835E+01 8.31 6E+01 1 .276E+02 1 .389E+01 8.393E+01 1 .420E+02 0.000E+00 1.41 8E+02 1.180E+04 0.000E+00 1.174E+04 2.250E+02 0.000E+00 2.221E+02 3.870E+02 0.000E+00 3.658E+02 150 XE-135M 2.210E+01 0.000E+00 1.538E+00 151 XE-I137 9.800E+00 0.000E+00 2.296E-04 152 XE-138 3.530E+01 0.000E+00 3.281E+00 161 CS-135 0.000E+00 0.000E+00 9.918E-09 163 CS-137 0.000E+00 0.000E+00 2.422E-06 164 CS-I138 0.000E+00 0.000E+00 7.649E+00 171 BA-I137M 0.000E+00 0.000E+00 2.422E-06 START OF MESS RUN ISOTOPES NOT INCLUDED IN MESS RUN NAME ACTIVITY (CI)RB-8"7 7.458713E-14 I-130 1.020834 CS-135 9.918468 E-09 WHAT IS THE SOURCE VOLUME (CC)5.660000E+1 0 WHAT IS THE SOURCE DENSITY (GM/CC)I1.000000E-03 START EXECUTION OF THE MESS SUBROUTINE, ID NUMBERS ARE MESS ID NUMBERS,NOT MAIN PROGRAM IDS.THE NUMBER OF ENERGY GROUPS INPUT: 10 THE MAXIMUM ENERGY OF EACH GROUP: ENERGY MAXIMUM GROUP ENERGY 1 1.000000E-01 2 3.000000E-01 3 5.000000E-01 4 "7.000000E-01 5 1.000000E+00 6 1.500000E+00 7 2.000000E+00 8 2.500000E+00 9 3.000000E+00 10 1.000000E+01 MESS INPUT DATA:

SOURCE DENSITY (GM/CC) = 1.000000E-03 SOURCE VOLUME (CC) = 5.660000E+10 ISOTOPE ID NO.UC/GM SOURCE STRENGTH UC/CC ,Cl KR 83M 45 KR 85 47 KR 85M 46 KR 87 48 KR 88 49 KR 89 50 KR 89 51 RB 88 67 RB 89 68 SR 89 21 1131 4 I132 5 1133 6 1134 7 I135 8 XE 131M 53 XE 133 54 XEI133M 55 XE 135 56 XE 137M 57 XE 137 58 XE 138 59 CS 137 35 CS 138 36 BAI137M 78 2.690086E-0' 6.660739E+0O 1 .331223E+O 6.01 1994E-01 2.372598E+00 1 .996030E-07 1 .996030E-07 2.32497 1 E+00 1 .665715E-03 3.650559E-06 1 .207675E+00 1 .469235E+00 2.253884E+00 2.454069E-01 1 .482786E+00 2.505659E+(2.073757E+0", 3.924798E+(6.46201 5E+0(2.71 6527E-0 4.056599E-06 5.796855E-02 4.2791 36E-08 1.351 355 E-01 4.278947E-0 1 2.690086E-04 p 6.660739E-03

'0 1.331223E-03 6.01 1995E-04 S2.372598E-03 1 .996030E-10 1 .996030E-10) 2.324971 E-03 1.66571 6E-06 3.650559E-09 1 .207675E-03 6 1 .469235E-03 8 2.253884E-03 1 2.454069E-04 1.1 .482786E-03 8 00 2.505659E-03 2 2.073757E-01

)0 3.924798E-03) 6.462015E-03

'2 2.716527E-05 4.056599E-09 S4.279136E-11 1.351 355E-04'8 4.278947E-11I 1 .522589E+01 3.769978E+02 7.534721 E+01 3.402789E+01 1 .342890E+02 I1.129753E-05 1 .129753E-05 1.31 5934E+02 9.427950E-02 2.0662 17E-04 1.835438E+01

.315868E+01

.275698E+02

.389003E+01

.392568E+'01 1 .418203E+02 1 .173746 E+04 2.221 436E+02 3.657500E+02 1 .537554E+00 2.296035E-04 3.281 020E+00 2.421991 E-06 7.648672E+00 2.421 884E-06 MESS OUTPUT DATA: ENERGY MAXIMUM SOURCE STRENGTH GROUP ENERGY (MEV/CC-SEC)(GAMMAS PER SEC)1 2 3 4 5 6 7 8 9 10 1 .000000E-01 3.000000E-01 5.000000E-01 7.000000E-01 I1.000000E+00 I1.500000E+00 2.000000E+00 2.500000E+00 3.000000E+00 1 .000000E+01 2.2721 89E+02 7.329755E+01 2.703011E+01 1 .068445E+02 9.759991 E+'01 9.042906E+01 8.837747E+01 I1.128665E+02 2.651 560E+I01 0.000000E+00 1 .286059E+14 1 .382880E+13 3.059809E+1 2 8.6391 37E+12 5.524155E+12 3.4121 90E+1 2 2.501 082E+1 2 2.555298E+1 2 5.002609E+11I 0.000000E+00

Southern Nuclear Operatin9 Cornpany,"

SOUTHE~RNA Plant: FNP TteNE990EACacliosAttachment G COMPANY' Unit: 1&2 TteNl901ELCcuain I SHEET G-42 , (... I/ NUCLEARl ENGINEERING HANDBOOK..

/J HAROLD ETHERtINGTON, Editor S!""Vice President Nuclear Producie--frc~o, Divis ion of ACfF Inusutries D)irector 2 Naval and Reactor Engineering Diviaione Argonnem National Laboratory

FIRST EDITION New York Toronto London McGRA.W-ItILL BOOK COMPANY, INO.1958 7-66 RADIATION RADIOLOGICAL PROTECTION

[SEC. 7 Table 3. Flux for Unit Tissue Dose*Eo. Photon flux ior Energy flux for photon energy, I rad/hr, I read/hr, Mev m-9 8ee-1 Mevf(re') (aeo)0.1 3O .90 X 10° 5.90 X 10'0.15 3.88 X t0' 3.82 X 10'0.20 2.91 X tO' 5.82 X 10'0.30 1.847 X 10' 3.54 X (0'0.40 1.357 X lO' 5.43 X (0'0.50 1.085 X 108 5.425 X 0.60 9.065 X 10' 5.44 X IC'0.90 6.98 X 10' 5.58 X 10'1,0 5.77 X I0' 5,77 X IC'1.25 4.77 X l10' 5.96 X JO'1.5 4.18 X I0' 5.27 X 10'2.0 3.4fi5 X tO' 6.6( X 10'3.0 2.63 X I1(1 7.89 X 10'4.0 2.10 >1 ID' 8.41 X 10'5.0 1.80 )( 1os 9.00 X 10'6.0 I.577 X I0' 9.46 X 108 8.0 1.2704X ID' 1.022X I0'10.0 1.067 X 1.067 X (0'* Ct'.ceitzt-.ot1 Croiii It'if, 4.where B,(pi) is the dose-rate build-uji f.ct~or chosen fromt Tab~les 4 and 5 for source energy B, per photon, material of shileldl, thniekeni:.

of shield 1,it, atcenuation coeitcient for source energy It, ond geometry isot~ropie or plane c~ollimated source--see below).For more conipli;ated source configurations it, is uneeessnry to integrate this expres-sion over the sources, sines doses from d iffercnt sources must, be radded to obtain total dose at a point.The build-up facotms in Tables 4 and 5 are ca~lculated on the. assumption that the dose is to be determined in air. They arc ade~quate for dose in t~issue, since the mass attenuat~ion cocfli<.ielt8 are very niearly tlhe s0m.fl~For convenience, Table 6 is given, which shows the number of curies of Go6° and Cs'" i'-ray sources whieh are adequately shielded in lead shields of different thicknesses.

1.33 Calculations of *{eating Due to y Rays. 'the rate of heatt deposition in the shield from scatte~red plus unscatltered y radlilt-io, at, a distance 1R from the source with t em or shield intervening is given by H(~t =1.02X I°(, ergs/(sec) (g)(5)where B 0 (t = energy ab~sorption build-up factor, elhosen for photon energy Bo, material, and umbe~cr of relaxation lengths in the shield pi (Table 7)// = energy ahsorption mass at, t, nuat~ion coefficient for the shield material, cm2/gni (from Table 2)1.4 Factors Affecting Calculational Method The use of the foregoing article and the accompanying tables is dependent upon the conditions of the problem. In most instances a judicious choice must be made with some compromise in accuracy.

The recommendations which follow are designed to give conservative estimates of dose rate with a minimum of complication.

More sophisticated approaches yielding more accurate results can be found in the references.

1.41 Choice of "Point Isotropic" (Table 4) or "Plane Collimated" (Table 5) Build-up Factors. If the source is embedded in or immediately adjacent to the shield, the"point isotropic" build-up factor is to be used (Fig. 3a). If a small (in linear extent)

SEc. 7-31 NUCLEAR RADIATION SHIELDING 7--115 Table 26. Physical Properties of Concretes Conm-at l..bn hik Expels- Specific Condoc-prieRupture" Ea.Ulhodhrn-son, heat, t~ivity, Diffu-, Conorete*

Lh/[t' Baga/ydi strengt~h, modulhs, modules--strength, age, %" in./(in.)

Bte/ Btu/(hr) ity jupsi psit (X l0-')t pst('I) (lb)('F) (I t){oF) fts/hr Cony. C15) 153 .-.5.0 4.960 630 4.6 ... 0.04! 5.5 0.23 1.50 0.042 Q (16) 154 9.0 8.870 1,005 5.9 900 0.012 P (16) 185 9.0 5,865 700 4.4 970 0.021 0 (17) 210 6.53 4,640 516 5.0 1,396 0.023 5.6 0.20 1.20 0.030 M (15) 226 5.!I 6,130 445 4.3 ... 0.029 10 0.157 0.884 0.025 L (15) 230 5.0 3.340 630 3.7 ... 0.029 10 0.146 0.867 0.026 K' (17) 224 7.0 5.780 684 4.3 1,423. 0.018 5.7 0.21 1.68 0.034 F (17) 273 6.55 3.180 406 5.4 1.266 0.013 5.9 0.18 2.75 0.056*Concrete composition is similar to that given in table of concrotes, except for K', which ha~s 46-lb limonite and 0.6-Lb fixed water per cubio loot. COny, is Grand Coulee concrete.

Placement method is given in Table 25. The liomonite used was from Michigan; the barite was from Nevada; specific gravity ofro agnetite was 4.4.t Strength ,values are for moist cured specimens, 28 dayo old.so~asce: H. 8. Davis, Ref. 33.Table 27. Concrete Shield Cost s Coat. dollars /yd5 ConceteType

_____________Total cost/lb.Concete ypecents Forms Conerete Ordiuiary struntural

.......................

45 25 1. 7 Ordinary .......................

Q 60 40 2.4 High density .................

Kor N 100 120 3.7 High density ..................

0 300 250 9.5 High deneity ..................

F 600 500 15.5 snvaca: H. S. Davia, _Nucieon~ce.

Ref. 33.REFERENCES

1. Faun, U.: Gamma-ray Attenuation, Nuc.Zeonic, 11(1): 8 (August, 1953); 11(2): 55 (September, 1953).2. Goldstein, H., and 3. E. Wilkins: "Calculations of the Penetration of Gamma Rays," NYO-8075, June 30, 1954 (available from the Office of Technical Services, Depart-ment of Commerce, Washington).

3. "Reactor Handbook," Vol. I., chap. 2.3, Technical Information Service, U.S. Atomic Energy Commission, 1955.4. Grodatein, Gladys White: "I Ray Attenuation Coefficients from 10 Key to 100 Mev," N~aU~. Bur. Ci'c. 583, April, 1957.5. Davisson, C. M., and R. D. Evans: Rena. Mod. Phyj., 24: 79 (1952).6. Nelms, A,: Graphs of the Compton Energy--Angle Relationship and the Kelei-Nishina Formula from 10 Key to 500 Mev, NaIL. Rur. ,Standards Cire. 542.7. Gamble. R. L,: "'Prompt Fission Gamma Rays from Uranium 235," Dissertation, University of Texas, Austin, Tex., June, 1955, 8a. Hollander, 3. M., I. Perlman, and G. T. Seaborg; Table of Isotopes, Revs. MPod. Phyao., 258: 469 (1953).b. Clark, F. H.: "Decay of Fission Product Gammas," NDA-27-39, Dec. 30, 1954.c. Moteff, John: "Fission Product Decay Gamma Energy Spectrum," APEX-134, June, 1953.d. Way, K4., et al. "Nuclear Data,"' NaIl. Hur. Stassdarda Circ. 499 and Supplements 1 and 2.e. Supplements and Nuclear Data Compilations in NSA.9, Rockwell, T. (ed.): "Reactor Shielding Design Manual," TID-7004, March, 1956.

SM-SNC524602-001 Attachment I ENERCON Calculation for E-HU1 SHEET I-2 CALC NO. SNC024-CALC-003

~jEN E R CON CALCULATION REV. 0 oy REVISION STATUS SHEET PAGE NO. 2 of 8 CALCULATION REVISION STATUS REVISION DATE DESCRIPTION 0 1010712015 Initial Submittal PAGE REVISION STATUS PAGE NO. REVISION PAGE NO. REVISION 1-8 0 APPENDIXIATTACHMENT REVISION STATUS APPENDIX NO. NO. OF REVISION ATTACHMENT NO. OF REVISION PAGES NO. NO. PAGES NO.

SM-SNC524602-001 Attachment I ENERCON Calculation for E-HU1 SHEET I-3 CALC NO. SNC024-CALC-003 IE NE R CON TABLE OF CONTENTS REV. 0 Excellence--Evey propecK Fv¢y PAGE NO. 3 of 8 Section 1.0 2.0 3.0 4.0 5.0 6.0 7.0 8.0 Purpose and Scope Summary of Results and Conclusions References Assumptions Design Inputs Methodology Calculations Computer Software Page No.4 4 5 5 6 7 8 8 SM-SN C524602-001 Attachment I SHEET I-4_________________

ENERCON Calculation for E-HU1 CALC NO. SNC024-CALC-003 FNP DETERMINATION OF -____________

EMERGENCY ACTION LEVEL REV. 0 SE N E R C 0 N FOR INITIATING CONDITION E-PAGE NO. Page 4of 8 1.0 Purpose and Scope The purpose of this calculation is to determine the emergency action level (EAL)thresholds for the initiating condition (IC) E-HU1, which is defined as damage to the confinement boundary of a storage cask containing spent fuel, as described in NEI 99-01 Rev. 6 [1]. The IC is defined as an "on-contact' radiation reading greater than two times the allowable dose readings as specified in the technical specifications listed in the cask's Certificate of Compliance (CoC). A dose rate reading greater than EAL threshold value indicates that there is degradation in the level of safety of the spent fuel cask.This calculation is performed under guidance from NEI 99-01 Rev. 6 [1], which describes development of a site-specific emergency classification scheme.2.0 Summary of Results and Conclusions The emergency action levels for initiating condition E-HU1 are calculated based on the HI-STORM 100 and HI-TRAC 125 cask system technical specification for spent fuel cask surface dose rates [2]. An elevated cask surface dose rate is indicative of degradation of the cask confinement barrier. The calculated elevated dose rates used as emergency action level thresholds are provided in Table 2-1.

SM-SNC524602-001 Attachment I IFNFRfln\I(3N iilIdtinn fnr F-HI-llI SHEET I-5 CALC NO. SNCO24-CALC-003 FNP DETERMINATION OF EMERGENCY ACTION LEVEL REV. 0~jE N E R C 0 N FOR INITIATING CONDITION E-..

ay. HU1I PAGE NO. Page 5 of 8 Table 2-1 Emergency Action Level Spent Fuel Cask Surface (Neutron + Gamma) Dose Rates for IC E-HU1 Location1 EA__________________________ (mrem/hr)HI-TRAC 125 _ ____Side -Mid -height 1 1360 Top J 260 HI-STORM 100 Side -60 inches below mid-height 340 Side -Mid -height 350 Side -60 inches above mid-height 170 Top -Center of lid 50 Top -Radially centered 60 Inlet duct 460 Outlet duct 160 3.0 References

1. NEI 99-01, Rev. 6, "Development of Emergency Action Levels for Non-Passive Reactors." Nuclear Energy Institute.

November 2012.2. FNP 10 CFR 72.212 Report. Docket Number 72-42, Version 12.4.0 Assumptions There are no assumptions made in this calculation.

SM-SNC0524602-001 Attachment I IFNI:PC'.fNI I.lrlIlllfinn far !:::_,I! II SHEET I-6 CALC NO. SNC024-CALC-003 FNP DETERMINATION OF EMERGENCY ACTION LEVEL REV. 0E N E R C 0 N FOR INITIATING CONDITION E-Eoy pwoJ.c,. £~ery,,o HUI1 PAGE N O. Page 6 of 8 5.0 Design Inputs 1. The contact dose rates from the HI-STORM 100 and HI-TRAC 125 cask system technical specification

[2, Table 6.2-3] are provided below in Table 5-1. These source values are scaled to develop the emergency action levels for initiating condition E-HU1.Table 5-1 Technical Specification Dose Rate Limits (Neutron + Gamma) for HI-STORM 100 and HI-TRAC 125 LoatonNumber of Technical Specification jMeasurements j Limit (mrem/hr)HI-TRAC 125 __________

Side -Mid -height 4 680.3 Top 4 ________129.4 HI-STORM 100 Side -60 inches below mid-height 4 171.8 Side -Mid -height 4 177.0 Side -60 inches above mid-height 4 84.7 Top -Center of lid 1 27.1 Top -Radially centered 4 30.0 Inlet duct 4 231.8 Outlet duct 4 82.2 SM-SNC524602-001 Attachment I

fnr II SHEET I-7 CALC NO. SNCO24-CALC-003 FNP DETERMINATION OF EMERGENCY ACTION LEVEL REV. 0 IIE N E R C 0 N FOR INITIATING CONDITION E-Ex e~ydj.0. HU1 PAGE NO. Page 7 of 8 6.0 Methodology The "on-contact" dose rates from the technical specification for the HI-STORM 100 and HI-TRAC 125 cask system are scaled by a factor of 2, as specified in NEI 99-01 Rev. 6[1], for use in initiating condition E-HU1.

SM-SNC524602-001 Attachment I ENERCON Calculation for E-HU1 SHEET I-8 CALC NO.SNC024-CALC-003 ENERCON FNP DETERMINATION OF EMERGENCY ACTION LEVEL FOR INITIATING CONDITION E-HU1 REV. 0 PAGE NO.Page 8 of 8 7.0 Calculations The dose rates in Table 5-1 are multiplied by 2 in order to calculate the EAL dose rate limits. These calculations are presented below in Table 7-1.Table 7-1 Dose Rate Scaling Calculations for EAL Limits (Neutron + Gamma)TTechnical LoainSpecification Scaling Calculated Value EAL LoainLimit Factor (mrem/hr) (mrem/hr)__________________________ (mrem/hr)

__ ___ __________

_______________ ______ _______ ______HI-TRAC 125 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _Side -Mid -height T 680.3 2 1360.6 J 1360 Top j 129.4 ] 2 258.8 J 260 Side -60 inches below mid-height Side -Mid -height Side -60 inches above mid-height Top -Center of lid Top -Radially centered Inlet duct Outlet duct 343.6 340 354 350 169.4 170 54.2 50 60 60 463.6 460 164.4 160 8.0 Computer Software Microsoft WORD 2013 is used in this calculation for basic multiplication.

SM-SNC524602-001 Attachment I ENFR(]fON (Th].lnultinn fnr F-H!!1 I SHEET I-9 CALC NO. SNCO24-CALC-003 CALCULATION PREPARATION REV. 0 F -i E NE R CON CHECKLIST NO. PagelIof 8 CHECKLIST ITEMS 1 YES NO N/A GENERAL REQUIREMENTS

1. If the calculation is being performed to a client procedure, is the procedure being used the latest revision?Client procedure is not used in this calculation.

ENERCON QA procedures used throughout this El El [project.2. Are the proper forms being used and are they the latest revision?

[] [ ] El 3. Have the appropriate client review forms/checklists been completed?T Clen roeur s o uedi ti clulton EECO A rceuesusdthoghuEti

__[][Cletproedueicotsdi.sclulto.EECNQ rcdre sdtruhu hsE 4. Are all pages properly identified with a calculation number, calculation revision and page number consistent with the requirements of the client's procedure?

Client procedure is not used in this calculation.

ENERCON QA procedures used throughiout thifs [] El [project.5. Is all information legible and reproducible?

[] ElE 6. Is the calculation presented in a logical and orderly manner?. [] El El 7. Is there an existing calculation that should be revised or voided?This calculation does not replace any ENERCON produced calculation.

Information generated El[][by this calculation will be used by SNC to update their Farley Nuclear Power Plant EAL report. l l _8. Is it possible to alter an existing calculation instead of preparing a new calculation for this situation?

No current ENERCON calculations exist that are similar to this calculation for addressing the El [] El SNC Farley EAL update.9. If an existing calculation is being used for design inputs, are the key design inputs, T assumptions and engineering judgments used in that calculation valid and do they [ ][apply to the calculation revision being performed.

SM-SNC524602-001 Attachment I IlkIIJC'C'lMl IPi4I I SHEET 1-10k.Jai~l,~LAII{A;LILjI I I..JI L----I CALC NO. SNC024-CALC-003 CALCULATION PREPARATION REV. 0 SEN E R CON CHECKLIST NO. Page 2of 8 No ENERCON design inputs or outputs are affected by this calculation.

This calculation will affect the Farley EAL evaluation.

12. Can the calculation logic, methodology and presentation be properly understood

[ ][without referring back to the originator for clarification?

OBJECTIVE AND SCOPE 13. Does the calculation provide a clear concise statement of the problem and objective of Ell the calculation?

[ ][14. Does the calculation provide a clear statement of quality classification?

[] El El 15. Is the reason for performing and the end use of the calculation understood?

[] El Li 16. Does the calculation provide the basis for information found in the plant's license basis?~The plant's license basis is not applied in this evaluation.

{] El El 17. If so, is this documented in the calculation?T The plant's license basis is not applied in this evaluation.

{] El El 18. Does the calculation provide the basis for information found in the plant's design basis documentation?

The plant's license basis is not applied in this evaluation.

[ ][19. If so, is this documented in the calculation?T The plant's license basis is not applied in this evaluation.

{] El El SM-SNC524602-001 SM-SN0524602-OO IAttachment I SETIi SHEET I-11___ __ __ __ ___ __ __ __ _ 'AI' J LsUI I,..i::IU

-!!.UII IUI! r--F--U CALC NO. SNCO24-CALC.-003 CALCULATION PREPARATION REV. 0 E ; E NE R CON CHECKLIST

<oy PAGE NO. Page 3of 8 CHECKLIST ITEMS 1 YES NO NIA 20. Does the calculation otherwise support information found in the plant's design basis documentation?

Calculation is applied in the development of the Farley Nuclear Power Plant EAL evaluation, LI LII [not the plant license basis.21. If so, is this documented in the calculation?

Calculation is applied in the development of the Farley Nuclear Power Plant EAL evaluation, [ ][not the plant license basis.22. Has the appropriate design or license basis documentation been revised, or has the change notice or change request documents being prepared for submittal?

Calculation is applied in the development of the Farley Nuclear Power Plant EAL evaluation, LI []I [not the plant license basis.DESIGN INPUTS 23. Are design inputs clearly identified?

[] [24. Are design inputs retrievable or have they been added as attachments?

I]Iu 1 []25. If Attachments are used as design inputs or assumptions are the Attachments traceable and verifiable?

Attachments are not included in this calculation.

LII 0][26. Are design inputs clearly distinguished from assumptions?

I ] [1010 DESIGN INPUTS (Continued)

27. Does the calculation rely on Attachments for design inputs or assumptions?

If yes, are the attachments properly referenced in the calculation?

Attachments are not included in this calculation.

0] [] 0 28. Are input sources (including industry codes and standards) appropriately selected and 00 are they consistent with the quality classification and objective of the calculation?

[ ][

SM-SNC524602-001 Attachment I ENERCON Calculation for E-l-SHEET 1-12 U1 CALC NO. SNC024-CALC-003 CALCULATION PREPARATION REV. 0 F E N ER CON CHECKLISTy PAGE NO. Page 4of 8 CHECKLIST ITEMVS' YES NO N/A 29. Are input sources (including industry codes and standards) consistent with the plant's design and license basis? [ ][30. If applicable, do design inputs adequately address actual plant conditions?

[ ][31. Are input values reasonable and correctly applied? El[][32. Are design input sources approved?

[ ][33. Does the calculation reference the latest revision of the design input source? [ ][34. Were all applicable plant operating modes considered?

[] El El ASSUMPTIONS

35. Are assumptions reasonable/appropriate to the objective?

[] El El 36. Is adequate justification/basis for all assumptions provided?

[ ][37. Are any engineering judgments used? El [] LI 38. Are engineering judgments clearly identified as such?No engineering judgments were applied in this evaluation.

LI [][39. If engineering judgments are utilized as design inputs, are they reasonable and can they be quantified or substantiated by reference to site or industry standards, engineering principles, physical laws or other appropriate criteria?

[ ][No engineering judgments were applied in this evaluation.

_METHODOLOGY

40. Is the methodology used in the calculation described or implied in the plant's licensing basis? [ ][

SM-SNC524602-001 Attachment I SHEET 1-13_________________

ENERCON Calculation for E-HU!CALC NO. SNCO24-CALC-003 CALCULATION PREPARATION REV. 0~~E N E RC(0N CHECKLIST NO. Page 5of 8 CHECKLIST ITEM~S 1 YES NO N/A 41. If the methodology used differs from that described in the plant's licensing basis, has the appropriate license document change notice been initiated?

Plant licensing basis was not affected by thjis evaluation.

LI LI []42. Is the methodology used consistent with the stated objective?

0] I 43. Is the methodology used appropriate when considering the quality classification of the 0 calculation and intended use of the results? [ ][BODY OF CALCULATION

44. Are equations used in the calculation consistent with recognized engineering practice 0] L [and the plant's design and license basis? ___45. Is there reasonable justification provided for the use of equations not in common use? T Equations applied in this evaluation are in common use in the industry.

{] LIL 0 46. Are the mathematical operations performed properly and documented in a logical 0 L fashion? [ ][47. Is the math performed correctly?

LI III[48. Have adjustment factors, uncertainties and empirical correlations used in the analysis z been correctly applied? [ ][49. Has proper consideration been given to results that may be overly sensitive to very small changes in input?Results generated by calculations performed in this evaluation are not significantly affected by LI LI 0]minor perturbations of variables.

SOFTWARE/COMPUTER CODES I__ __50. Are computer codes or software languages used in the preparation of the calculation?

Only basic functions and operations in Microsoft Word 2013 were applied in this calculation.

{ L LI 0]

SM-SNC524602-001 SM-SNC52602AttacHEETnt-I ENERCON Calculation for El-SHEET 1-14 LU1 CALCULATION PREPARATION REV.0 0E NE R CON CHECKLIST

£v,ry doy.PG O ae6o CHECKLIST ITEMS 1 YES NO N/A 51. Have the requirements of CSP 3.09 for use of computer codes or software languages, including verification of accuracy and applicability been met?.Only basic functions and operations in Microsoft Word 2013 were applied in this calculation.

El E0 SOFTWAREICOMPUTER CODES (Continued)

52. Are the codes properly identified along with source vendor, organization, and revision 0][][level?53. Is the computer code applicable for the analysis being performed?

El El 0]54. If applicable, does the computer model adequately consider actual plant conditions'?

El El 0]55. Are the inputs to the computer code clearly identified and consistent with the inputs and El El 0]assumptions documented in the calculation?

56. Is the computer output clearly identified?

Only basic functions and operations in Microsoft Word 2013 were applied in this calculation.

El El 0]57. Does the computer output clearly identify the appropriate units?Only basic functions and operations in Microsoft Word 2013 were applied in this calculation.

El El 0]58. Are the computer outputs reasonable when compared to the inputs and what was expected?Only basic functions and operations in Microsoft Word 2013 were applied in this calculation.

El l 0 59. Was the computer output reviewed for ERROR or WARNING messages that could invalidate the results?Only basic functions and operations in Microsoft Word 2013 were applied in this calculation.

l ll E T RESULTS AND CONCLUSIONS

60. Is adequate acceptance criteria specified?

This calculation provides results for the SNC Farley Nuclear Power Plant EAL evaluation.

No acceptance criteria required for this evaluation.

SM-SNC524602-001 Attachment I ENERCON Calculation for E-HU1 SHEETI1-15 CALC NO. SNC024-CALC-003 CALCULATION PREPARATION REV. 0 FIEN E R CON CHECKLISTE NO. Page 7of 8 CHECKLIST ITEM~S 1 YES NO N!A 61. Are the stated acceptance criteria consistent with the purpose of the calculation, and intended use?This calculation provides results for the SNC Farley Nuclear Power Plant EAL evaluation.

No El [] [acceptance criteria required for this evaluation.

62. Are the stated acceptance criteria consistent with the plants design basis, applicable licensing commitments and industry codes, and standards?

This calculation provides results for the SNC Farley Nuclear Power Plant EAL evaluation.

No El E] [acceptance criteria required for this evaluation.

63. Do the calculation results and conclusions meet the stated acceptance criteria?This calculation provides results for the SNC Farley Nuclear Power Plant EAL evaluation.

No acceptance criteria required for this evaluation.

64. Are the results represented in the proper units with an appropriate tolerance, if applicable?

[ ][65. Are the calculation results and conclusions reasonable when considered against the stated inputs and objectives?

[ ][66. Is sufficient conservatism applied to the outputs and conclusions?

El[][67. Do the calculation results and conclusions affect any other calculations?

No ENERCON calculations are affected by this evaluation.

Results are provided to SNC Farley [ ][Nuclear Power Plant for input into the Farley EAL evaluation.F1

68. If so, have the affected calculations been revised?No ENERCON calculations are affected by this evaluation.

Results are provided to SNC Farley [ ][Nuclear Power Plant for input into the Farley EAL evaluation.I Tl SM-SNC524602-001I Attachment I ENERCON Calculation for E-HUI SHEETI1-16 CALC NO. SNCO24-CALC-003 CALCULATION PREPARATION REV. 0EN E R CON CHECKLIST....

NO. Page 8of 8 CHECKLIST ITEMS 1 YES NO N/A 69. Does the calculation contain any conceptual, unconfirmed or open assumptions requiring later confirmation?

Calculation is based on design input and assumption data provided and used by client in their 10 El [] El CFR 72.2 12 Report. Parameters maintained for consistency.

70. If so, are they properly identified?

No open assumptions applied in this evaluation.

Assumptions have basis based on information El l provided by the client.DESIGN REVIEW 71. Have alternate calculation methods been used to verify calculation results? El[][Note: 1. Where required, provide clarificationfjustification for answers to the questions in the space provided below each question.

An explanation is required for any questions answered as "No' or "N/A".Originator:

/ v and Sign r Date SM-SN C524602-001I Attachment H ENERCON Calculation for RAI SHEET H-I"CALC NO. SNC024-CALC-001 E N ER C ON CALCULATION COVER Excelence--E ,yp oape E eiy day S H EET REV. 0 PAGE NO. I of 10 Title: Farley EALs RA1 Threshold to Address NEI Item Cover Sheet Items Yes No t Does this calculation contain any open assumptions, including preliminary

[] [information, that require confirmation? (If YES, identify the assumptions.)_________

2 Does this calculation serve as an "Alternate Calculation"? (If YES, identify the ][design verified calculation.)

____Design Verified Calculation No.__________

3 Does this calculation supersede an existing Calculation? (If YES, identify the El [design verified calculation.)

____Superseded Calculation No.__________

Scope of Revision: Initial Issue Revision Impact on Results: Initial Issue Study Calculation El Final Calculation

[]Safety-Related El Non-Safety-Related

[](Print Name and Sign)Originator:

David Hartmangruber

.4Date: I 23zO/I5/Design Reviewer Dominic Napolitano, Ph. D L/ _" Date: ~ , Approver:

Jay Maisler, CHiP# Digitally signed I Ia. J. M'aisler, CHPn~l... I,, I PunIl~ t'I

• f ;7" --,-..)'" ,-ounail~jmaisler@enercon.com, c=US 4/

16:45:56 -04'00' SM-SNC524602-001 Attachment H ENERCON Calculation for RA1 SHEET H-2 CALC NO. SNC024-CALC

-001 IIE N ER CO N CALCULATION0 Fxco, .....-Every project. &'ery day REVISION STATUS SHEET RV PAGE NO. 2 of 10 CALCULATION REVISION STATUS REVISION DATE DESCRIPTION 0 10/23/2015 Initial Issue PAGE REVISION STATUS PAGE NO. REVISION PAGE NO. REVISION 1-10 0 APPENDIX/ATTACHMENT REVISION STATUS APPENDIX NO. NO. OF REVISION ATTACHMENT NO. OF REVISION PAGES NO. NO. PAGES NO.

SM-SNC524602-001 Attachment H ENERCON Calculation for RA1 SHEET H-3 CALC NO. SNC024-CALC-001EN E RC ON TABLE OF CONTENTS REV. 0 Excellenc'--Every project. Frety doy/PAGE NO. 3 of 10 Section 1.0 Purpose and Scope.......................................................

2.0 Summary of Results and Conclusions

.....................................

3.0 References................................................................

4.0 Assumptions..............................................................

5.0 Design Inputs..............................................................

6.0 Methodology..............................................................

7.0 Calculations

..............................................................

8.0 Computer Software........................................................

9.0 Results and Conclusion

...................................................

Page No.4 5 6 6 7 8 8 9 10 SM-SNC524602-001 Attachment H SHEET H-4 ENERCON Calculation for RA1 CALC NO. SNC024-CALC-001 Farley EAL RA1 Threshold SEN E R CON to Address NEI 99-01 REV. 0Revision 6 PAGE NO. 4 ofl10 1.0 Purpose and Scope The purpose of this calculation is to calculate the Emergency Action Level (EAL)thresholds for the update of the RAI calculation in the Southern Nuclear (SNC) Design Calculation SM-96-1076-002 (Reference

1) in response to the changes made to the Initiating Condition (IC) AAI in Revision 6 of NEI 99-01 (Reference 2). Calculation RA1 is meant to address the IC AA1 (Section 4.1 of NEI 99-01 Revision 6 states "R may be used in lieu of A" for this recognition category provided the change is carried through for all the associated IC identifiers).

Revision 6 of NEI 99-01 IC AAI identifies an EAL threshold for a release of gaseous or liquid radioactivity resulting in an offsite dose to a member of the public greater than 10 mrem Total Effective Dose Equivalent (TEDE) or 50 mrem thyroid Committed Dose Equivalent (CDE). IC AA1 is applicable to all operating modes and there are 4 EALs outlined in NEI 99-01 for IC AAI.1. Reading of site specific radiation monitors greater than threshold values that would generate a dose rate greater than the dose criterion established in IC AA1 in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. Reading must be shown for 15 minutes or longer.2. Dose assessment using actual meteorology indicates doses greater than 10 mrem Total Effective Dose Equivalent (TEDE) or 50 mrem thyroid Committed Dose Equivalent (CDE) at or beyond site boundary 3. Analysis of a liquid effluent sample indicates a concentration or release rate that would result in doses greater than 10 mrem TEDE or 50 mrem thyroid CDE at or beyond site boundary for one hour of exposure.4. Field survey results indicate either of the following at or beyond site boundary.

A closed window dose rate greater than 10 mR/hr expected to continue for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or longer an analyses of field survey samples indicates a thyroid CDE greater than 50 mrem for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> of inhalation.

SM-SNC524602-001 Attachment H ENERCON Calculation for RA1 SHEET H-5 CALC NO. SNC024-CALC-001 Farley EAL RA1 Threshold jE N ER C ON to Address NEI 99-01 REV. 0...

Revision 6 PAGE NO. 5 ofl10 The scope of this calculation is to determine site specific instrument readings for the RAl EAL 1 threshold.

The IC RA1 EAL 2, 3, and 4 are not evaluated in this calculation.

The quality rating of this calculation is non-safety related due to results only being used to generate a revised set of EALs for submission by the Farley nuclear power plant (FNP).2.0 Summary of Results and Conclusions The instrument readings that indicate an EAL threshold value has been reached for IC RAl are calculated in this calculation.

IC RAI is the release of gaseous or liquid radioactivity resulting in offsite dose to a member of the public greater than 10 mrem TEDE or 50 mrem thyroid ODE.The RA1 EAL 1 is the valid reading on one or more of the following radiation monitors that exceeds or is expected to exceed the reading shown in Table 2-1.Table 2-1 Radiation Monitor RA1 EAL Threshold Values

' '"Monitor Reading RE0015C Steam Jet Air Ejector (SJAE) 1.3 R/hr RE0029B Plant Vent Stack 0.008 pCi/cm 3 RE0060A/B/C S/G Atmospheric Relief Valves 0.005 R/hr (ARVs) & Safety Relief Valves (SRVs)RE0060D Turbine Driven Auxiliary 0.11 R/hr Feedwater Pump (TDAFW)Turbine Exhaust SM-SNC524602-001 Attachment H SHEET H-6___________________

ENERCON Calculation for RA1 ________CALC NO. SNC024-CALC-OO1 Farley EAL RAI Threshold 0 EN E R CON to Address NEI 99-01 REV. 0.... E e ro y Revision 6 PAGE NO. 6 ofl10 3.0 References

1. SM-96-1 076-002 Rev 5, NEI 99-01 EAL Calculations, Southern Company, September 25 2015.2. NEI 99-01 Rev 6, Development of Emergency Action Levels for Non-Passive Reactors, November 2012, Nuclear Energy Institute.

4.0 Assumptions

Based on the analysis of the methodology of Reference 1, the following assumption is consistent with the previously performed calculations, but were not included in the listed assumptions of Reference 1.4.1 Perfect Monitor Response This assumption is also applied to be consistent with the calculations performed in Attachment E of Reference

1. It is assumed in this calculation that the monitors at the end of each pathwaY are not energy dependent or that the monitor response accounts for the relative energy spectrum associated with the thresholds determined in this calculation based on the expected proportion of each isotope in the overall concentration.

This is a simplifying assumption applied due to the limited information provided about the monitoring equipment.

SM-SNC524602-001 Attachment H ENERCON Calculation for RA1 SHEET H-7 CALC NO. SNC024-CALC-001 Farley EAL RA1 Threshold~jE NE R CON to Address NEI 99-01 REV. 0 Fler-ce-Eer pr.

t eery day Revision 6 PAGE NO. 7 of 10 5.0 Design Inputs 5.1 FarleylIndication and RS1 EAL 1 Thresholds SM-96-1076-002 (Reference

1) addresses the IC RS1, which is based on the release of gaseous radioactivity resulting in offsite dose to a member of the public greater than 100 mrem TEDE or 500 mrem thyroid CDE. SM-96-1076-002 evaluates four release pathways and determines the monitor readings that would indicate an EAL threshold value has been reached for IC RS1. The monitor readings that would indicate an EAL threshold value for IC RS1 are provided in Table 5-1.The indicating ranges for the radiation monitors are also provided in Table 5-1 and the ranges are based on Design Input I on Sheet 27 of Reference

1. These values are used to calculate the IC RAI EAL threshold values.Table 5-1 Radiation Monitor RS1 EAL Threshold Values Monitor Vent Path ,,o..

Reading ,Indicating RE0015C Steam Jet Air Ejector (SJAE) 13 R/hr 10- o 102 R/hr RE0029B Plant Vent Stack 0.08 pCi/cm 3 10-7 to 10 5 pCi/cm 3 RE0060A/B/C SIG Atmospheric Relief 0.05 R/hr 10-5 to~ 10 hr Valves (AR\Is) & Safety Relief Valves (SR\Is)RE0060D Turbine Driven Auxiliary 1.1 R/hr 10-5 to R0Phr Feedwater Pump (TDAFWV)Turbine Exhaust SM-SNC524602-001 Attachment H SHEET H-8___________________

ENERCON Calculation for RA1 ________CALC NO. SNC024-CALC-001 Farley EAL RA1 Threshold SEN ER C ON to Address NEI 99-01 REV. 0 en e ono. Revision 6 PAGE NO. 8 oflO0 6.0 Methodology In the SM-96-1076-002 (Reference

1) RSI evaluation, EAL 1 thresholds were set based on readings of radiation monitoring equipment for several effluent pathways.

The thresholds are shown in Table 5-1 of this calculation.

The calculations for dose rate estimates is linear, therefore the RSI readings are scaled down by a factor of 10 (multiple of 0.1) for the RA1 evaluation performed in this calculation resulting in EAL I threshold values reflecting an offsite dose to a member of the public greater than 10 mrem Total Effective Dose Equivalent (TEDE) or 50 mrem thyroid Committed Dose Equivalent (ODE). The calculation of the RA1 EAL I threshold values is provided in Section 7.0.7.0 Calculations As discussed in Section 6.0, the values provided in Table 5-1 are multiplied by a scaling factor of 0.1 for the RA1 EAL I thresholds.

The resultant threshold values for RA1 EAL 1 are shown in Table 7-1. All threshold values are within the indicating range of the radiation monitors.

SM-SN C524602-001 Attachment H ENERCON Calculation for RA1 SHEET H-9 CALC NO. SNC024-CALC-001 Farley EAL RA1 Threshold IEN ER C ON to Address NEI 99-01 REV. 0 Exo,...

Revision 6 PAGE NO. 9 ofl10 Table 7-1 Radiation Monitor RA1 Threshold Values Radiation

i'"Vent Path ".. ,Scaled' Resuiltant Indicating...

Monitor" ,........ o ,Factor Monitor Range ,... .. , : ...... .. ..... " .. .R eading :,, .. .o .. .. , ,R eading .. ... '. .. " RE0O15C Steam Jet Air Ejector 13 R/hr 0.1 1.3 R/hr 10-5 to 10 2 R/hr (SJAE)RE0029B Plant Vent Stack 0.08 pCi/cm 3 0.1 0.008 pCi/cm 3 10 toi0 5 pCi/cm 3 RE0060AIB/C SIG Atmospheric 0.05 R/hr 0.1 0.005 Rfhr 10 to 10 R/hr Relief Valves (ARVs)& Safety Relief Valves (SRVs)RE00600 Turbine Driven 1.1 R/hr 0.1 0.11 Rfhr 10-5 to 103 R/hr Auxiliary Feedwater Pump (TDAFW)Turbine Exhaust 8.0 Computer Software No computer software was used in the creation of this calculation.

SM-SNC524602-001 Attachment H ENERCON Calculation for RA1 SHEET H-10 CALC NO. SNC024-CALC-001 Farley EAL RAI Threshold F,'I: EN E R CON to Address NEI 99-01 REV. 0

£E'ey doa Revision 6 PAGE NO. 10 ofl10 9.0 Results and Conclusion The purpose of this calculation is to calculate the EAL thresholds for the RAl calculation in the SNC Design Calculation SM-96-1076-002 (Reference

1) for the Farley nuclear power plant for use in development of an EAL submittal based on NEI 99-01 Revision 6.Table 2-1 contains the threshold values associated with the RAl EAL 1. These values will be applied to the FNP Emergency Action Level Scheme developed using the guidance of NEI 99-01 Revision 6.

SM-SNC524602-001 Attachment H ENERCON Calculation for RAl SHEET H-Il CALCULATION PREPARATION REV.0 CHECKLIST ITEMS 1 YES NO NIA GENERAL REQUIREMENTS

1. If the calculation is being performed to a client procedure, is the procedure being used the latest revision?Client procedure is not used in this calculation.

ENERCON QA procedures used thi'oughout LI El 0]3. Have the appropriate client review forms/checklists been completed?

Client procedure is not used in this calculation.

ENERCON QA procedures used throughout

[] iii [this project.4. Are all pages properly identified with a calculation number, calculation revision and page number consistent with the requirements of the client's procedure?

Client procedure is not used in this calculation.

ENERCON QA procedures used throughout EJ LI 0]this project.5. Is all information legible and reproducible?

0] []i 6. Is the calculation presented in a logical and orderly manner? 0] LI LI 7. Is there an existing calculation that should be revised or voided?This calculation does not replace any ENERCON produced calculation.

Information generated

[] 0][by this calculation will be used by SNC to update their Farley Nuclear Power Plant EAL report. _ _ _8. Is it possible to alter an existing calculation instead of preparing a new calculation for this situation?

No current ENERCON calculations exist that are similar to this calculation for addressing the LI 0] LI SNC Farley EAL update.9. If an existing calculation is being used for design inputs, are the key design inputs, 1 assumptions and engineering judgments used in that calculation valid and do they 101 ] [apply to the calculation revision being performed.____________

SM-SNC524602-001 Attachment H SHEET H-12___________________

ENERCON Calculation for RA1 CALC NO. SNCO24-CALC-OO1 CALCULATION PREPARATION REV. 0 SE NE R CON CHECKLIST...

E NO. Page 2 of 8 CHECKLIST

'TEIMS 1 YES NO I NIA 10. Is the format of the calculation consistent with applicabl e procedures and expectations 9 I[ -i} [11. Were design input/output documents properly updated to reference this calculation?

No ENERCON design inputs or outputs are affected by this calculation.

This calculation will affect the Farley EAL evaluation.

12. Can the calculation logic, methodology and presentation be properly understood without referring back to the originator for clarification?

______ _____OBJECTIVE AND SCOPE 13. Does the calculation provide a clear concise statement of the problem and objective of Lii the calculation?

[ ][14. Does the calculation provide a clear statement of quality classification?

[] Li Li 15. Is the reason for per-forrning and the end use of the calculation understood?

[] EJ Li 16. Does the calculation provide the basis for information found in the plant's license basis?The plant's license basis is not applied in this evaluation.

Li [] [17. If so, is this documented in the calculation?

The plant's license basis is not applied in this evaluation.

Li Li [18. Does the calculation provide the basis for information found in the plant's design basis documentation?

The plant's license basis is not applied in this evaluation.

[ ][19. If so, is this documented in the calculation?

The plant's license basis is not applied in this evaluation.

Li [] [

SM-SNC524602-001 Attachment H ENERCON Calculation for RA1 SHEET H-13 CALC NO. SNC024-CALC-001 CALCULATION PREPARATION REV. 0~:E N E RC ON CHECKLISTE NO. Page 3 of 8 CHECKLIST ITEMS 1 YES NO N/A 20. Does the calculation otherwise support information found in the plant's design basis documentation?

Calculation is applied in the development of the Farley nuclear power plant EAL evaluation, LI L] [not the plant license basis.21. If so, is this documented in the calculation?

Calculation is applied in the development of the Farley nuclear power plant EAL evaluation, [ ][not the plant license basis.22. Has the appropriate design or license basis documentation been revised, or has the change notice or change request documents being prepared for submittal?

Calculation is applied in the development of the Farley nuclear power plant EAL evaluation, [] [] [not the plant license basis.DESIGN INPUTS 23. Are design inputs clearly identified?

[ ][24. Are design inputs retrievable or have they been added as attachments?

t]L u I iii 25. If Attachments are used as design inputs or assumptions are the Attachments traceable and verifiable?

Attachments are not included in this calculation.

"] III [26. Are design inputs clearly distinguished from assumptions?

[ ][27. Does the calculation rely on Attachments for design inputs or assumptions?

If yes, are the attachments properly referenced in the calculation?

Attachments are not included in this calculation.

1] [ ]28. Are input sources (including industry codes and standards) appropriately selected and I L are they consistent with the quality classification and objective of the calculation?

[ ][29. Are input sources (including industry codes and standards) consistent with the plant's LI[][design and license basis?

SM-SNC524602-001 Attachment H ENERCON Calculation for RA1 SHEET H-14 CALC NO. SNC024-CALC-001 CALCULATION PREPARATION REV. 0~jE N ER CON CHECKLIST...

NO. Page 4 of 8 CHECKLIST ITEMVS 1 YES NO NIA 30. If applicable, do design inputs adequately address actual plant conditions?

] [31. Are input values reasonable and correctly applied? [] LI I [32. Are design input sources approved?

[] L] I 33. Does the calculation reference the latest revision of the design input source? 0] ii ii 34. Were all applicable plant operating modes considered?

] Li LI ASSUMPTIONS

35. Are assumptions reasonable/appropriate to the objective?

0] LI El 36. Is adequate justification/basis for all assumptions provided?

0] L]I izi 37. Are any engineering judgments used? [] 0 Ii 38. Are engineering judgments clearly identified as such?No engineering judgments were applied in this evaluation.

Li [][39. If engineering judgments are utilized as design inputs, are they reasonable and can they be quantified or substantiated by reference to site or industry standards, engineering principles, physical laws or other appropriate criteria?

[ ][No engineering judgments were applied in tris evaluation.

METHODOLOGY

40. Is the methodology used in the calculation described or implied in the plant's licensing 0 L 41. If the methodology used differs from that described in the plant's licensing basis, has the appropriate license document change notice been initiated?

Plant licensing basis was not affected by this evaluation.

LI [][

SM-SNC524602-001I Attachment H ENERCON Calculation for RA1 SHEET H-15 CALC NO. SNC024-CALC-001 CALCULATION PREPARATION REV. 0 jE N E R CON CHECKLIST....

NO. Page 5 of 8 CHECKLIST ITEMS 1 YES NO N/A 42. Is the methodology used consistent with the stated objective?

[ ][43. Is the methodology used appropriate when considering the quality classification of the I~I mm calculation and intended use of the results? j] J' J BODY OF CALCULATION

44. Are equations used in the calculation consistent with recognized engineering practice LI [] [and the plant's design and license basis? ___45. Is there reasonable justification provided for the use of equations not in common use?Equations applied mn this evaluation are in common use mn the industry.

LI LI [46. Are the mathematical operations performed properly and documented in a logical [] ] I [fashion?I 47. Is the math performed correctly?.

] I L-i I [48. Havebe corcladjustmentaplidfactors, uncertainties and empirical correlations used in the analysis [] ] I [49. Has proper consideration been given to results that may be overly sensitive to very small changes in input?Results generated by calculations performed in this evaluation are not significantly affected by LI LI [minor perturbations of variables.

SOFTWARE/COMPUTER CODES ___50. Are computer codes or software languages used in the preparation of the calculation?

-I___No software languages or codes were used in the development of this calculation.

LI [] LI including verification of accuracy and applicability been met?I No software languages or codes were used in the development of this calculation.I SM-.SNC524602-001 Attachment H ENERCON Calculation for RA1 SHEET H-16 CALC NO. SNC024-CALC-0O1 CALCULATION PREPARATION REV. 0 SE NE R CON CHECKLISTE NO. Page 6 of B CHECKLIST ITEMS 1 YES NO NIA SOF'IWAREICOMPUTER CODES (Continued)

52. Are the codes properly identified along with source vendor, organization, and revision level?No software languages or codes were used in the development of this calculation.

~L 53. Is the computer code applicable for the analysis being performed?T No software languages or codes were used in the development of this calculation.

El {] LI 54. If applicable, does the computer model adequately consider actual plant conditions?

No software languages or codes were used in the development of this calculation.

[] Li 0 55. Are the inputs to the computer code clearly identified and consistent with the inputs and assumptions documented in the calculation?

No software languages or codes were used in the development of this calculation.

{ ] [j []56. Is the computer output clearly identified?

No software languages or codes were used in the development of this calculation.

0][][57. Does the computer output clearly identify the appropriate units?No software languages or codes were used in the development of this calculation.

I] Li 0]58. Are the computer outputs reasonable when compared to the inputs and what was expected?Li}Li0[No software languages or codes were used in the development of this calculation.

59. Was the computer output reviewed for ERROR or WARNING messages that could invalidate the results?No software languages or codes were used in the development of this calculation.Li i 0 I .

SM-SNC524602-001 Attachment H ENERCON Calculation for RA1 SHEET H-17 CALC NO. SNC024-CALC-001 CALCULATION PREPARATION REV. 0 SEN E R CON CHECKLIST

£v'ey, da PAGE NO. Page 7 of 8 CHECKLIST ITEMS 1 YES NO N/A RESULTS AND CONCLUSIO NS 60. Is adequate acceptance criteria specified?

This calculation provides results for the SNC Farley nuclear power plant EAL evaluation.

No acceptance criteria required for this evaluation.

61. Are the stated acceptance criteria consistent with the purpose of the calculation, and intended use?This calculation provides results for the SNC Farley nuclear power plant EAL evaluation.

No El El 0]acceptance criteria required for thifs evaluation.

62. Are the stated acceptance criteria consistent with the plant's design basis, applicable licensing commitments and industry codes, and standards?

This calculation provides results for the SNC Farley nuclear power plant EAL evaluation.

No El El 0]acceptance criteria required for this evaluation.

63. Do the calculation results and conclusions meet the stated acceptance criteria?This calculation provides results for the SNC Farley nuclear power plant EAL evaluation.

No ~ E acceptance criteria required for this evaluation.

64. Are the results represented in the proper units with an appropriate tolerance, if 0 l E applicable?

[ ][65. Are the calculation results and conclusions reasonable when considered against the 0 Ell stated inputs and objectives?

[ ][66. Is sufficient conservatism applied to the outputs and conclusions?

] El El 67. Do the calculation results and conclusions affect any other calculations?

No ENERCON calculations are affected by this evaluation.

Results are provided to SNC El l 0 Parley nuclear power plant for input into the Parley EAL evaluation.

68. If so, have the affected calculations been revised?No ENERCON calculations are affected by this evaluation.

Results are provided to SNC El l 0 Parley nuclear power plant for input into the Farley EAL evaluation.

SM-SNC524602-001 Attachment H ENERCON Calculation for RA1 SHEET H-18 CALC NO. SNC024-CALC-001 CALCULATION PREPARATION REV. 0 SEN E R CON CHECKLIST&c0,0lc-n 0,e Eve0i eay. dyPAGE NO. Page 8of 8 69. Does the calculation contain any conceptual, unconfirmed or open assumptions requiring later confirmation.?

Calculation is based on design input and assumption data provided and used by client in their El [] El ODCM and current EAL evaluation.

Parameters maintained for consistency.

70. If so, are they properly identified?T No open assumptions applied in this evaluation.

Assumptions have basis based on information El El 10 provided by the client.DESIGN REVIEW 71. Have alternate calculation methods been used to verify calculation results? t] []T []Note: 1. Where required, provide clarificationljustification for answers to the questions in the space provided below each question.

An explanation is required for any questions answered as 'No' or "NIA°.Originator:

David Hartmangruber Print Name and Sign Date SM-SNC524602-001I Attachment I ENERCON Calculation for E-HU1 SHEET I-1 CALC NO.SNCO24-CALC-003 FJENERCON gxceI~ence--Every project, Eoerydoy.CALCULATION COVER SHEET REV. 0 PAGE NO.1 of 8 Til:Level for Initiating Condition E-HU1 rjc dntfe:5C2 Item Cover Sheet Items Yes No 1 Does this calculation contain any open assumptions, including preliminary D][information, that require confirmation? (If YES, identify the assumptions.)

2 Does this calculation serve as an "Alternate Calculation"? (If YES, identify the design [][verified calculation.)

Design Verified Calculation No. __________

3 Does this calculation supersede an existing Calculation? (If YES, identify the design []" [verified calculation.)

____Superseded Calculation No. __________

Scope of Revision: Initial Issue Revision Impact on Results: Initial Issue Study Calculation Final Calculation IX Safety-Related

[] Non-Safety-Related (Print Name and Sign)J Originator:

Andrew Blackwell Date: toU2LS Design Reviewer:

Curt Lindner Date: -i/is.Date: 10/9/2015 Approver:

Jay Maisler, CliP