Regional Basic Professional Training Course in Korea

More documents

Recommendations

Info

Regional Basic Professional Training Course (BPTC) on Nuclear Safety 9.1.7. Uncertainties We can distinguish three major categories of sources of uncertainties in the PRA models. 9.1.7.1. Completeness There is never a guarantee that all the initiating events leading to significant consequences have been taken into account. This lack of completeness introduces an uncertainty in the results and conclusions of the analysis that is difficult to assess and quantify. 9.1.7.2. Modeling adequacy There are uncertainties introduced by the relative inadequacy of the conceptual models and the mathematical models. Sensitivity studies are usually performed to assess their relative importance. In the PSA level 2, the uncertainties of the progression of the accident are so important that it is necessary to use expert judgment to show the results of the physical progression in terms of probability distribution. 9.1.7.3. Input parameter uncertainties This category is related to the uncertainties of the parameters of the models used in the PSA. This type of uncertainty is more easily quantified. 9.1.7.4. Propagation of uncertainties The quantification of the third category of uncertainties is usually done by using a Monte-Carlo simulation that consists of generating a random sample of inputs of the model determining the PSA output from each set of inputs in the sample. ❙ 568 ❙
❙ 569 ❙ 9. Probabilistic Safety Analysis 9.2. GENERAL METHODOLOGY - SEQUENCES AND SYSTEMS MODELING 9.2.1. Introduction The general objective of a Probabilistic Safety Assessment (PSA) is to evaluate the probability that an installation will be the origin of serious consequences. Since the first application of this approach [9.1], it appeared that the interest in PSA is not only to give an overall result of risk, but also (and mainly) to provide insights into plant design, performance and environmental impacts, including the identification of dominant risk contributors and the comparison of options for reducing risk. PSA provides a consistent and integrated framework for safety related decision-making. In international practice, in the case of nuclear plants safety, three levels of PSA are defined: - Level 1: The assessment of core damage frequency. - Level 2: The assessment of containment release frequency. - Level 3: The assessment of off-site consequences (public and environmental risk) This aim of this report is to present an overview of the methods used for conducting a level 1 PSA. This paper does not constitute a PSA guide, and the details concerning the application of the methods can be found in relevant literature [9.4]and [9.10]. A first part, mainly qualitative, describes the general approach. A second part gives the main elements concerning quantification.
Page 5 and 6:
1. Nuclear Reactor Principles · 1
Page 7:
1. Nuclear Reactor Principles Regio
Page 10 and 11:
Table 1.2. Average cross sections f
Page 13 and 14:
1. Nuclear Reactor Principles ❙ 7
Page 15 and 16:
energy of the fuel nuclei. ❙ 9
Page 17 and 18:
❙ 11 ❙ 1. Nuclear Reactor Princ
Page 19 and 20:
Page 21 and 22:
Page 23 and 24:
1 Bq = 2.7x10 -5 µCi = 2.7x10 -8 m
Page 25 and 26:
1.1.5. Natural radioactive series
Page 27 and 28:
238 U 92+ 1 n0 -----> 135 Te 52 + 9
Page 29 and 30:
Page 31 and 32:
σ t = σ s + σ a = σ elastic +
Page 33 and 34:
FIG. 1.10. And here in the 1keV to
Page 35 and 36:
Page 37 and 38:
Page 39 and 40:
1.2.3.2. Neutron emission in fissio
Page 41 and 42:
Page 43 and 44:
Three possible states could then be
Page 45 and 46:
TABLE 1.3. Slowing down efficiency
Page 47 and 48:
1 UNGG/AGR CANDU PWR/BWR TABLE 1.5.
Page 49 and 50:
Page 51 and 52:
Page 53 and 54:
Page 55 and 56:
Page 57 and 58:
Page 59:
✼✼✼ REFERENCES ✼✼✼ ❙
Page 63 and 64:
2.1. Introduction C O N T E N T S 2
Page 65 and 66:
2. Radiation Protection 2.1. Introd
Page 67 and 68:
2.2.1. Exposure ❙ 61 ❙ 2. Radia
Page 69 and 70:
❙ 63 ❙ 2. Radiation Protection
Page 71 and 72:
Page 73 and 74:
2.2.4. Effective dose ❙ 67 ❙ 2.
Page 75 and 76:
Page 77 and 78:
Page 79 and 80:
Page 81 and 82:
Page 83 and 84:
schematically in Fig. (2.7). ❙ 77
Page 85 and 86:
Page 87 and 88:
The great utility of the G‐M tube
Page 89 and 90:
Page 91 and 92:
Page 93 and 94:
Page 95 and 96:
Page 97 and 98:
Page 99 and 100:
protection conditions. These factor
Page 101 and 102:
2.6.2. Effects of dose, dose‐rate
Page 103 and 104:
Page 105 and 106:
2.7. Principles of Radiological Pro
Page 107 and 108:
Page 109 and 110:
Page 111 and 112:
Page 113 and 114:
Page 115 and 116:
Page 117 and 118:
Page 119 and 120:
Page 121 and 122:
❙ 115 ❙ N 0 = N 2 1 t / t 1/ 2
Page 123 and 124:
ln 10 = μ t1/10 ≈ 3 · ln 2 = 3
Page 125:
Page 129 and 130:
C O N T E N T S | Table of Contents
Page 131:
Fig. 1 Committees for IAEA Safety S
Page 134 and 135:
Regional Basic Professional Trainin
Page 136 and 137:
Page 138 and 139:
Page 140 and 141:
Page 142 and 143:
Page 144 and 145:
Page 146 and 147:
Page 148 and 149:
Page 150 and 151:
Page 152 and 153:
Page 154 and 155:
Page 156 and 157:
Page 158 and 159:
Page 160 and 161:
Page 162 and 163:
Page 164 and 165:
Page 166 and 167:
Page 168 and 169:
Page 170 and 171:
Page 172 and 173:
Page 174 and 175:
Page 176 and 177:
Page 178 and 179:
Page 180 and 181:
Page 182 and 183:
Page 184 and 185:
Page 186 and 187:
Page 188 and 189:
Page 190 and 191:
Page 192 and 193:
Page 194 and 195:
Page 196 and 197:
Page 198 and 199:
Page 200 and 201:
Page 202 and 203:
Page 204 and 205:
Page 206 and 207:
Page 208 and 209:
Page 210 and 211:
Page 212 and 213:
Page 214 and 215:
Page 216 and 217:
Page 218 and 219:
Page 220 and 221:
Page 222 and 223:
Page 225 and 226:
Page 227 and 228:
❙ 221 ❙ 4. DESIGN OF NUCLEAR RE
Page 229 and 230:
4.1.1.2. The concept of defence in
Page 231 and 232:
4.1.2. Requirements for management
Page 233 and 234:
Page 235 and 236:
Page 237 and 238:
administrative control. ❙ 231 ❙
Page 239 and 240:
Page 241 and 242:
Page 243 and 244:
Design basis accidents ❙ 237 ❙
Page 245 and 246:
Single failure criterion ❙ 239
Page 247 and 248:
Page 249 and 250:
Page 251 and 252:
Deterministic approach The determin
Page 253 and 254:
accidents, with account taken of th
Page 255 and 256:
Fuel elements and assemblies Fig. 4
Page 257 and 258:
Reactor shutdown ❙ 251 ❙ 4. DES
Page 259 and 260:
Page 261 and 262:
Page 263 and 264:
Page 265 and 266:
functional in the event of a severe
Page 267 and 268:
4.1.5.4. Instrumentation and contro
Page 269 and 270:
Page 271 and 272:
Page 273 and 274:
Page 275 and 276:
4.1.5.9. Radiation protection Gener
Page 277 and 278:
Page 279 and 280:
Page 281 and 282:
Page 283 and 284:
Operation at a power level < 1 MW.
Page 285 and 286:
Page 287 and 288:
of these exchangers, the water is c
Page 289 and 290:
Page 291 and 292:
Page 293 and 294:
Page 295 and 296:
Page 297 and 298:
Page 299 and 300:
Fig. 4.11. HANARO Core Pool Fig. 4.
Page 301 and 302:
4.2.6.2.3 Reactor Systems ❙ 295
Page 303 and 304:
Page 305 and 306:
4.2.6.5. Neutron Activity Analysis
Page 307 and 308:
Page 309 and 310:
❏ physical separation. ❙ 303
Page 311:
5. Siting Considerations Regional B
Page 314 and 315:
5.4.2. Sources of risk 5.4.3. Evalu
Page 316 and 317:
Page 318 and 319:
Page 320 and 321:
Page 322 and 323:
Page 324 and 325:
Page 326 and 327:
Page 328 and 329:
Page 330 and 331:
Page 332 and 333:
Page 334 and 335:
Page 336 and 337:
Page 338 and 339:
Page 340 and 341:
Page 342 and 343:
Page 344 and 345:
Page 346 and 347:
Page 348 and 349:
Page 350 and 351:
Page 352 and 353:
Page 354 and 355:
Page 356 and 357:
Page 358 and 359:
Page 360 and 361:
Page 362 and 363:
Page 365 and 366:
Page 367 and 368:
6. Safety Classification Of Structu
Page 369 and 370:
Page 371 and 372:
Safety functions necessary to preve
Page 373 and 374:
Page 375 and 376:
6.1.3. Principal Safety Classes 6.
Page 377 and 378:
Page 379 and 380:
Page 381 and 382:
Page 383 and 384:
function; 6. Safety Classification
Page 385 and 386:
Page 387 and 388:
Page 389 and 390:
the safety function would be requir
Page 391 and 392:
Page 393 and 394:
Page 395 and 396:
6.3.2. Description of Quality Group
Page 397 and 398:
Page 399 and 400:
Page 401 and 402:
Page 403 and 404:
Page 405 and 406:
6.4.3. Seismic category 1: 6.4.3.1.
Page 407 and 408:
Page 409 and 410:
Page 411 and 412:
Page 413:
7. Quality Assurance Regional Basic
Page 416 and 417:
7.5.1. Manufacture Quality Assuranc
Page 418 and 419:
Page 420 and 421:
Page 422 and 423:
Page 424 and 425:
Page 426 and 427:
Page 428 and 429:
Page 430 and 431:
Page 432 and 433:
Page 434 and 435:
Page 436 and 437:
Page 438 and 439:
Page 440 and 441:
Page 442 and 443:
Page 444 and 445:
Page 446 and 447:
Page 448 and 449:
Page 450 and 451:
Page 452 and 453:
Page 454 and 455:
Page 456 and 457:
Page 458 and 459:
Page 460 and 461:
Page 462 and 463:
Page 464 and 465:
Page 466 and 467:
Page 468 and 469:
Page 470 and 471:
Page 472 and 473:
Page 475 and 476:
C O N T E N T S 8.1. INTRODUCTION |
Page 477 and 478:
❙ 471 ❙ 8-A. Deterministic Acci
Page 479 and 480:
Page 481 and 482:
Page 483 and 484:
guidelines for this categorization.
Page 485 and 486:
Page 487 and 488:
Page 489 and 490:
Table 8‐3 Typical Initial Conditi
Page 491 and 492:
Page 493 and 494:
Page 495 and 496:
Page 497 and 498:
8.5.3. Decrease in Reactor Coolant
Page 499 and 500:
Page 501 and 502:
or by operator error, often during
Page 503 and 504:
Page 505 and 506:
Page 507 and 508:
Page 509:
8-B. Deterministic Accident Analysi
Page 512 and 513:
| List of Tables | Table 8.7‐1 Ru
Page 515 and 516:
❙ 509 ❙ 8-B. Deterministic Acci
Page 517 and 518:
Page 519 and 520:
Page 521 and 522:
SG Containment RCP RCP RCP SIT SIT
Page 523 and 524: ❙ 517 ❙ 8-B. Deterministic Acci
Page 527 and 528: 8.2.5. Evaluation Model ❙ 521 ❙
Page 533 and 534: Figure 8.7‐7 Flow chart of KREM
Page 535 and 536: Cladding Temperature (K 1300 1200 1
Page 541 and 542: 8.8.1.6. Loop Seal Formation and Cl
Page 545 and 546: to ECCS injection time using CEFLAS
Page 549 and 550: Table 8.8‐2 SBLOCA Break Spectrum
Page 551 and 552: F TEMPERATURE, o 0 100 200 300 400
Page 555 and 556: 8.8.2.2.3 RELAP5‐sEM Methodology
Page 561: 9. Probabilistic Safety Analysis Re
Page 564 and 565: 9.4. LEVEL 2 PSA 9.4.1. Objectives
Page 566 and 567: Regional Basic Professional Trainin
Page 624 and 625:
Page 626 and 627:
Page 628 and 629:
Page 631 and 632:
Page 633 and 634:
❙ 627 ❙ 10-A. Limiting Conditio
Page 635 and 636:
performance, correct set points, an
Page 637 and 638:
Page 639 and 640:
injecting borated water into the pr
Page 641 and 642:
Page 643 and 644:
Page 645 and 646:
Page 647 and 648:
Positive reactivity insertion rates
Page 649 and 650:
Page 651 and 652:
Page 653 and 654:
Page 655 and 656:
Page 657 and 658:
Page 659 and 660:
Page 661 and 662:
10.4.3.3. Canadian type NPP ❙ 655
Page 663 and 664:
Page 665 and 666:
Page 667 and 668:
2) Safety Limits and Safety System
Page 669 and 670:
the technical specifications is not
Page 671 and 672:
Page 673:
10-B. Technical Specifications for
Page 677 and 678:
Page 679 and 680:
Page 681 and 682:
Page 683 and 684:
Page 685 and 686:
Page 687 and 688:
10.7.7.1. Monitoring Systems 10-B.
Page 689 and 690:
Page 691 and 692:
10.8.1. Reactor Core Parameters 10-
Page 693 and 694:
10.8.6. Emergency Power 10-B. Techn
Page 695 and 696:
Page 697 and 698:
Page 699 and 700:
authorized by responsible authority
Page 701 and 702:
Page 703:
11. Human Performance: A Perspectiv
Page 706 and 707:
Figure 11.1 Model of violation Figu
Page 708 and 709:
Page 710 and 711:
Page 712 and 713:
Page 714 and 715:
Page 716 and 717:
Page 718 and 719:
Page 720 and 721:
Page 722 and 723:
Page 724 and 725:
Page 726 and 727:
Page 728 and 729:
Page 730 and 731:
Page 732 and 733:
Page 734 and 735:
Page 736 and 737:
Page 738 and 739:
Page 740 and 741:
Page 742 and 743:
Page 744 and 745:
Page 746 and 747:
Page 749:
12. Surveillance Programmes Regiona
Page 752 and 753:
12.4. IMPLEMENTATION 12.4.1. Genera
Page 754 and 755:
Page 756 and 757:
Page 758 and 759:
Page 760 and 761:
Page 762 and 763:
Page 764 and 765:
Page 766 and 767:
Page 768 and 769:
Page 770 and 771:
Page 772 and 773:
Page 774 and 775:
Page 776 and 777:
Page 778 and 779:
Page 780 and 781:
Page 782 and 783:
Page 784 and 785:
Page 786 and 787:
Page 788 and 789:
Page 790 and 791:
Page 792 and 793:
Page 794 and 795:
Page 796 and 797:
Page 798 and 799:
Page 801:
13.Maintenance Management in KHNP R
Page 805 and 806:
❙ 799 ❙ 13.Maintenance Manageme
Page 807 and 808:
Page 809 and 810:
Page 811 and 812:
Page 813 and 814:
Page 815 and 816:
Page 817 and 818:
Page 819 and 820:
Page 821 and 822:
Page 823 and 824:
Page 825 and 826:
Page 827 and 828:
Page 829:
Page 833 and 834:
Page 835 and 836:
15. Operational Safety 15.1. IAEA S
Page 837 and 838:
❙ 831 ❙ 15. Operational Safety
Page 839 and 840:
Page 841 and 842:
Page 843 and 844:
and modified if required. ❙ 837
Page 845 and 846:
Page 847 and 848:
Page 849 and 850:
Page 851 and 852:
Page 853 and 854:
15.2.2. Organization and functions
Page 855 and 856:
− Temporary and permanent plant m
Page 857 and 858:
Page 859 and 860:
Operating procedures and instructio
Page 861 and 862:
Page 863 and 864:
Off‐normal conditions are easily
Page 865 and 866:
15.2.6. Work authorizations ❙ 859
Page 867 and 868:
conventional hazards at the point o
Page 869 and 870:
15.2.7. Accident management ❙ 863
Page 871 and 872:
Page 873 and 874:
Page 875 and 876:
commissioning process. ❙ 869 ❙
Page 877 and 878:
Event reports and root cause analyz
Page 879 and 880:
Material regarding evaluation of ex
Page 881 and 882:
Page 883 and 884:
Page 885 and 886:
Page 887 and 888:
Page 889 and 890:
Monitoring of initiatives in progre
Page 891 and 892:
Page 893:
Page 897 and 898:
Page 899 and 900:
16. In‐Plant Accident Management
Page 901 and 902:
❙ 895 ❙ 16. In‐Plant Accident
Page 903 and 904:
Page 905 and 906:
16.2.2. Safety Functions ❙ 899
Page 907 and 908:
is to place the plant in a safe, st
Page 909 and 910:
each a final stable and controlled
Page 911 and 912:
Page 913 and 914:
Page 915 and 916:
Page 917 and 918:
Page 919 and 920:
16.3.5. Review of Korean SAMG by KI
Page 921 and 922:
Page 923 and 924:
Page 925 and 926:
Page 927 and 928:
Page 929 and 930:
this stage. Control rod degradation
Page 931 and 932:
Page 933 and 934:
Page 935 and 936:
Page 937 and 938:
Pressurization of the containment
Page 939 and 940:
Page 941 and 942:
Page 943 and 944:
Page 945 and 946:
Page 947 and 948:
Page 949 and 950:
Page 951 and 952:
Fractional Relase Fractional Relase
Page 953:
Page 957:
Page 960 and 961:
Page 962 and 963:
Page 964 and 965:
Page 966 and 967:
Page 968 and 969:
Page 970 and 971:
Page 973:
19. Decommissioning Regional Basic
Page 976 and 977:
| List of Tables | Table 1. Stages
Page 978 and 979:
Page 980 and 981:
Page 982 and 983:
Page 984 and 985:
Page 986 and 987:
Page 988 and 989:
Page 990 and 991:
Page 992 and 993:
Page 994 and 995:
Page 996 and 997:
Page 998 and 999:
Page 1000 and 1001:
Page 1002 and 1003:
Page 1004 and 1005:
Page 1006 and 1007:
Page 1008 and 1009:
Page 1010 and 1011:
Page 1012 and 1013:
Page 1014 and 1015:
Page 1016 and 1017:
Page 1019:
20.1. Introduction C O N T E N T S
Page 1022 and 1023:
Page 1024 and 1025:
Page 1026 and 1027:
Page 1028 and 1029:
Page 1030 and 1031:
Page 1032 and 1033:
Page 1034 and 1035:
Page 1036 and 1037:
Page 1038 and 1039:
Page 1040 and 1041:
Page 1042 and 1043:
Page 1044 and 1045:
Page 1046 and 1047:
Page 1048 and 1049:
Page 1050 and 1051:
Page 1052 and 1053:
Page 1054 and 1055:
Page 1057:
21. Safety Culture Regional Basic P
Page 1061 and 1062:
21. Safety Culture 21.1. DEFINITION
Page 1063 and 1064:
FIG. 21.1. Basic elements of safety
Page 1065 and 1066:
❙ 1059 ❙ 21. Safety Culture Ult
Page 1067 and 1068:
Obtaining useful information from o
Page 1069 and 1070:
terms of what they do. There is an
Page 1071 and 1072:
Consequently, people also understan
Page 1073 and 1074:
❙ 1067 ❙ 21. Safety Culture 21.
Page 1075 and 1076:
❙ 1069 ❙ 21. Safety Culture 21.
Page 1077 and 1078:
organization e.g. contractors. ❙
Page 1079 and 1080:
❙ 1073 ❙ 21. Safety Culture opp
Page 1081 and 1082:
❙ 1075 ❙ 21. Safety Culture Pri
Page 1083 and 1084:
❙ 1077 ❙ 21. Safety Culture cou
Page 1085 and 1086:
❙ 1079 ❙ 21. Safety Culture All
Page 1087 and 1088:
21.4. MANAGEMENT OF SAFETY 21.4.1.
Page 1089 and 1090:
subdivided in 4 sub‐objectives, w
Page 1091 and 1092:
❙ 1085 ❙ 21. Safety Culture pro
Page 1093 and 1094:
21.4.4. Specific safety management
Page 1095 and 1096:
21.4.4.5. Self assessment ❙ 1089
Page 1097:
❙ 1091 ❙ 21. Safety Culture as
Page 1101:
Page 1104 and 1105:
Page 1106 and 1107:
Page 1108 and 1109:
Page 1110 and 1111:
Page 1112 and 1113:
Page 1114 and 1115:
Page 1116 and 1117:
Page 1118 and 1119:
Page 1121:
AtomCARE Regional Basic Professiona
Page 1125 and 1126:
AtomCARE 1. OVERVIEW OF NATIONAL RA
Page 1127 and 1128:
❙ 1121 ❙ AtomCARE The RETAC of
Page 1129 and 1130:
❙ 1123 ❙ AtomCARE secondary rad
Page 1131 and 1132:
❙ 1125 ❙ AtomCARE actions by pr
Page 1133 and 1134:
2.1.4. Component Modules (Configura
Page 1135 and 1136:
Classification Major Functions Tech
Page 1137 and 1138:
❙ 1131 ❙ AtomCARE containment b
Page 1139 and 1140:
❙ 1133 ❙ AtomCARE b) Monitors a
Page 1141 and 1142:
a) Calculates the distribution of t
Page 1143 and 1144:
❙ 1137 ❙ AtomCARE telephone or
Page 1145:
Introduction Of e‐FAST and Exerci
Page 1148 and 1149:
| List of Figures | Fig. 1.1 Schema
Page 1150 and 1151:
Page 1152 and 1153:
Page 1154 and 1155:
Page 1156 and 1157:
Page 1158 and 1159:
Page 1160 and 1161:
Page 1162 and 1163:
Page 1164 and 1165:
Page 1166 and 1167:
Page 1168 and 1169:
Page 1170 and 1171:
Page 1172 and 1173:
Page 1174 and 1175:
Page 1176 and 1177:
Page 1178 and 1179:
Page 1180 and 1181:
Page 1182 and 1183:
Page 1185 and 1186:
C O N T E N T S 1.1. OVERVIEW OF TH
Page 1187 and 1188:
❙ 1181 ❙ Nuclear Safety Informa
Page 1189 and 1190:
Page 1191 and 1192:
Page 1193 and 1194:
Page 1195 and 1196:
Page 1197 and 1198:
Page 1199:
Page 1203:
1. Overview of OPiS C O N T E N T S
Page 1206 and 1207:
Page 1208 and 1209:
Page 1210 and 1211:
Page 1212 and 1213:
Page 1214 and 1215:
Page 1216 and 1217:
Page 1220:
show all

Regional Basic Professional Training Course in Korea

Create successful ePaper yourself

Delete template?

Save as template?