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日本原子力学会標準原子力発電所の出力運転状態を対象とした確率論

1. PRA Probabilistic Risk Assessment E E 2008 12 PRA 1960 1975 2 WASH 1400 19950 NUREG 1150
2. P008 201X A B 1 B B 7 oleg 24 A B 200208 4 eo UH gu A A B 7 eo 4 D 4 ono 0070 Bu I LI A BOD y A B I OD B L A B AD A B A B AQ B
3. ER tarn df VAY lid UN RY ONIS HE 2 3 4 SA PY FECCSZK DF DL OIE ES UE AERE 1
4. IPRA 200x 199 22 Standards Committee of AESJ 110 H Ht BU HH 0E DH 00850 u 0 201X P008 201X 00000000000000
5. OMOEA 0000008085 00000000000000001000000000 0000000008903 00000900000000000000000 000000000000900 0 0 0 00 0 0 0 0 0 0 000 HHHHHHHHH IlHHHHHHHHH LOCAHHHHHHHHHHHHHHHHHHHHH 10800000000 0008908 0000000000000000000000000000 000000808 0 0000000 9 0 HIHHHHHHHIMHL O OOOO 9 P008 201X HHHHHHH 0000000000000000000000000000000000 HHHHHHH 5 0000000000000000000000000000808 00000 HHHHHHHHHHHHHH 00000000000000000000000090000000000080 0 0000000000000000000000909000000000000 0 00000000000000000000000009600000000000 00000000000000000000000000000980 000 a0 b 00 900000000000000000000000000000900000 HHHHHHHHHHHHHHHHH e 0000000000000000098000000000000000000 000000000000000098900080 0000000000000 0 000000000000000909000006098000000000000 0 000000000000009890000000008098 0 00000000 000000000000009600 0 000000000000968000000000000100 013 3 0 0000000000000000
6. 95 P008 201X 0 CCCGHHHHHHHHHHHHHH 0 0 00000 0000000060000 YUU 0000 0000000000000 uut HHHHHHH HHHHHHHH D uuu D auus HHHHHHHH HHHHHHIHHHIHHHHHLH HHHHHHHHHHHHHHHHHHH UUUUUUUUUUUU 0000 1 USNRC Guidelines on Modeling Common Cause Failures in Probabilistic Risk Assessment NUREG CR 5485 INEEL EXL 97 01327 USNRC 1998 96 P008 201X HUD 0000 00000000000000000000900000 HH HHHHHHH9 0000000000000000090000000000090 HHHHHHHHHHHHHHHHH AE 1 HHHHHHHHHHHHHHHHHHHHHHHH 0 00000000000000000000000000000808000 USNRC Common Cause Failure Parameter Estimations NUREG CR 5497 INEEL EXL 97 01328 USNRC 1998 USNRC Common Cause Failure Database and Analysis System Vols 1 4 NUREG CR 6268 INEEL EXL 97 00696 USNRC 1998 USNRC Common Cause Failure Database and Analysis System Event Data Collection Classification and Coding NUREG CR 6268 Rev 1 INL EXT 07 12969 USNRC 2007 000 AF 1 000 000 000 AF 2 0 E ESL EZ EJ ET EX de E EI Ee GE ae EI L UU DT 000 AF 3 97 P008 201X HHHHH10 000000000000000000000000000090 HHHHHHHHHHHHHHHHHH HHHHHHHHHHHHHHHH 0 000000
7. HHHHHHHHHHHHHHHHH HHHHHHHHHHHHHHHHHHHHH HHHHHHHHHHHHHH 0 000000000000000000000000 90800000000 0 000000000000000000000000200090000000 0 000000000000000000000009000000080900 0000000000 HHHHHHHHHHHHHHH 0 00000000000000000000000900000000000 0 000000000000000000000000009600000000 0 000000000000000000000000000000960000 HHHHHHHHHHHHHHHHHHHHHHH 00000 0 00000000000000000 00000000000000 0 00000000000000000000090000000000 e 000000 0 0000000000000900000000000000960000000 0 0000000000000009680000000000000000000 00000000000000000096800000000090000 RPSHHHH 0000000 amp 8 8000000000000000096940000000000 0 000000080000000000000000000000000000 0000000908051 e HHHHHH 0000000 000000000080000000000000000000 0 0 00000000000008080000000 o 0000000 DH 0 0000000960000000010040000000000000000 0000000000 09 09 0000 0000000000000000000 0 0000000010000090800000000000000000000 0 000000000000000000000000000000000000 080000000000000000000000000000000000 009080000000000000000000000000000 0 000089090800000000000000000000000000000 000000006008000000 b LOCA PFHEBDUDUUDUUDUBOUDUUDUDOUDUBUDUUOUOUUDUOU UU 48 P008 201X 1 2 3 4 5 6 HHHHHHHHHHHHHHHHHHHHHHHHHLOCAHHHHHHHHHHHH HHHHHHHHHHHHHADSHHHHHHHHHHHHHHHHHHHHHHHHH HHHHHLOCAHHHHHHHHHHHHHHHHHHHHH MLHHHHHHHH HHHHHHHHHHHHH HHHHH LOCAHH
8. OO 10 000000 0000 00 00 0 0 00 HHHHHH 105HHHHHHHHHHHHHHHHHHHH 0 0 0 0 0 0 0 f g 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Ld Ga ea ea eet EE EIE ES E E 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 p SES E E E OBERE BEEF P E ETE UIE VE E Bete Ey IE ET ERES E CES EI UE E EX EJ E TEE 6 50000000000 AG 6 0000000000 IIHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHH 00980000000000900000000000000000000000000 103 P008 201X HHHHHHHHHHUHHHHHHHHHHHHHHHH HHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHH 0000000000000 4000000000000000089000000000 000 00000 0 00000000000000000000000090000000000090 0 00000000000000000000004980000000000000 00000000000000000000000060980000000000 0000000000000000000000000006809080000000 0 0000000000000000
9. P s RO DHEA U RS 2 ROAR BERT JESUS Ea URN bY U COUR TIBET TE Neg Z 0o ii Bit 0 2 00000000000 kas
10. 0000 Latin Hypercube Sampling 5 5 00000000000 00000 000 000 000 0000000000000000010000000000000000 00800000000 000000000000000000000000 000 0980 0000000000000000000000000000 E amp oo 140 P008 201X wooo Y KX4 Xo Nw X Xi A 00000 X2 X n AW 0000 1 IAEA Development and Application of Level 1 Probabilistic Safety Assessment for Nuclear Power Plants Specific Safety Guide Series No SSG 3 IAEA April 2010 2 USNRC A Review of NRC Staff Uses of Probabilistic Risk Assessment NUREG 1489 USNRC March 1994 141 POO8 201X 000 0000 000000013 DDDUDBUDBDUBHBHDUHBHDUHDUDUDUDUHHDUDUDUUDUGuDDUDUUuHDU AX 1 000000 HHHHHHHPRAH 0000 0 0000000000000000000000000000000000009 000000600 0 000000000
11. 0000000000 00000000 00000000 20110 40 1000000000 000000 0 000089080000000000000000 0000000000000000000 0 00000008080000000000000000000000000 00000000 0000000000808000000000000000000000000000000 00000000 xii POO8 201X 000 1 ZAIN SR E AEDEM 1 1 4 DUHH 1PRAD DDD eh NN 2 41 000 1PRAQDO00000000 llo e eda 2 42 2PRA O O ausser aaa 2 43 JUD 1PRADO000000000000 etre tortor o 2 DOOOOOOD eI 5 51 0000 DTI erento SS aaa eae 5 52 DO00000000 A oet eer et te 5 6 0000000000000000 4 5 61 Q 5 62 DO000000000 vee rre 6 63 D0000000000 A 7 fsla naa saq 9 7 1 OO O C NDS 9 72 UUDDUDDHUDDUHUUDDHBD eoe ete e 9 T3 TAT ET ERE RE TD 10 7 4 OO 1 8 11 B EPOR tite E 11 82 EE CIE onte et ors eet beoe tetas dates 11 E ER 12 84 000 2PRADD DOLO Meses 12 9 lt 13 Aa RAPER MRa k an A uuu u uama uku
12. HU 9 e 1 1000000000010000 1 Loss of RCS flow 1 loop 2 00000000000000000 2 Uncontrolled rod withdrawal 0 3 00000000000000000 3 CRDM problems and or rod drop 000000000 4 000000000 4 Leakage from control rods 5 1000000000 5 Leakagemmmprimary system 6 O00000 6 Low pressurizer pressure 7 000000000 7 Pressurizer leakage 8 HHHHHH 8 High pressurizer pressure 9 000000000000000 9 Inadvertent safety injection signal 10 000000000 10 Containment pressure problems 1 000000000000000 11 CVCS malfunction boron dilution 1000000000000 12 0000000000000 12 Pressure temperature power imbalance position error 13 10000000000000 13 Startup of inactive coolant pump 14 1000000000000000 14 Total loss of RCS flow 15 0000000000 15 os or reduction in feedwater flow 1 loop 16 HHHHHHHHHHHHHH 16 Total loss of feedwater flow all loops 17 000000000010000 17 Full or partial closure of MSIV 1 loop 18 000000000000000 18 Closure of all MSIV 19 00000000010000 19 Increase in feedwater flow 1 loop 30 HHHHHHHHHHHHHH 20 Increase in feedwater flow all loops 21 00000000 000 21 Feedwater flow instability operator error 22 00000000 0400 22 Feedwater flow instability miscellaneous mechanical causes 23 HHHHHHHH 10000 23 Loss of condensate pumps 1 loop 24 0000000000000 24 Loss of condensate pumps all 1oops 25 0000000410 25 Loss of condenser va
13. 9 HPCI HPCS 10 1 11 12 13 3 4 5 7 82K sa SRE 1 1 1 2 3 1 2 RPS 3 5 TENT 1 00000 oo HHHHHHH 0000 Uu 00000000000 55 P008 201X B D U D U D U U D LU 0 0 0 0 0 HHHHHH 0 0 0
14. p Eas Ee E 0000 9 HHHHHHHHHHHHHHHHHH HHHHHHHHHHHHHHHHH 0000000090090 mut 140 2 0000000400000008000000000000000000000 umi 158 3 000009000000000000009650000000000000000 00000 00000 00000 18 4 000000 009000000000000 250 40 30000000000 0 2500020800000 000 5000 20 b USNRC Safety Goals for the Operations of Nuclear Power Plants Policy Statement 51FR28044 USNRC 1986 e OOO U OD HHH 20 0 008 0 DASMEANS PRAQ 0 000000000000000 0000000000009 00000000000000000 1PRAHHHHHHH 0000000000000 07000000000000000000000000 00980 00000000079000000000000000000 12 8 0000 152 P008 201X HHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHH NRCH WASH 14002HHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHH HHHHHHH WASH 1400 00000000000000000000900080500000 0 00000000000000000000000000900000 20680800 000 000000000 0000000000000000000000009000000000000 0000000000000 00000000 0000000000000 000 b 0000000000000 00060 HHHHHHHHHHH 000 0000000000000980000068098000000000000 00000000000000000989000000000680
15. 000000 2600 2000 2600 20 700000000000000000 00009000000000000000000000000 JEAC4111 2009T 0 0000000 U 00 210 090 14000 1000 D 210 100 32 P008H 201X OOO 0000 000 00000000000000 00 000000004 OOO 1 1 0 00 00000 0 000000000000000000000000000904000000000 HHHHHHHHHHHHHHHHHHHH ci HHHHHHHH a HHHHHHHHHHHH 100 40008 00000000000000 0000000000000 000 00000000000 00000000805000000000000 0 0000000000000 2 000000000 0480 0000000000000 1PRA HHHHHHHHH 3 00000000000000000000 0 0 MA 0 0 HHHHHMHHHHHHHHHHHHHHHHHHHHHHHHHHH 0000090 000 00 00 0 0 0 00000 2ugagagguadgopDgmpaguggaguggagpamugud 00980000000068080000000000000000000 00980000000000008980000000000 b 000 000000000000900000000000 200 HHHHHH 0000000 2 00000000000 3 0000000 MAMBO 00000000000000000 100 90000 1 105000000000000000000000000000000 2 0 090 000000000000000000000000000 000000808 00000000000000 3 000000089000000000000000 1PRAHHHHHH 0000000 17 00000000000 0 0 0 0 33 P008 201X c2 HHHHHHHHH HHHHHHHHHHHHHHHHH 900 900000009 00000 a 00000000000000000
16. 0A000000 00000 HHHHHHHHHEHHHUHHHHHHHHHH HHHHHHHH 000000000000000000000000000000 00000000000 0900000000000 000000000 0 00 0000000000000000000 e HHHHHHH 1 HH b 00000 1 OOD ES SERI EE E ESSI ERI ERI ESSE EF SEI ELE 6 Py Es Ea UE Jem ET EE ES Ee E J TL GEO E ES E rA myo oO 145 POO8 201X 00 0000 00000 L HHHHHHHHH LU HHHHHHH E ELTE ESL ESL SEE Ea EZ LJ EX ls EI EP EJ El D 0 D UEBLD U uu HHHH HHHHHHHH LU ET ud OE Ea ES e T DO U COU OO EDS U d D B8 d BOLD UD O 7 DI 0 OU 000000000000000 D uuu HHHHHHHHHHH HHHHHHHHHHHHHHHHH HHHHHH 146 P008 201X 0000000000 00000000000 1 HHHHHHHHHHHHHHHHHHHHHHH 00000000000000000000800000000000098 0000000000000000000 u DH 000000000000000000000059 2 HHHHHHHH 000000000000000
17. HHHHHHHHHH 1 HHHHH 2 0000000000 3 HHHHH 4 HHHHH L3 PWRHHHHHHHHHHHH a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e HHHHHHHHHHHHHHHHHHHHHHHH LOCAHHHHHHLOCAH 050000 7 00000000000000000000000 2090008085 00000 00000000000000000000000090900000080800 000000000 0000 PWRO0D0000000000000000000 0 041 20 0000000000000 0000006000000 o 00000 0000000000000000000000000000000900000 OO 1000000000000000000000000100000099070 0 000000000000000098000000000000000000 00000000000000009090808 0 0000000
18. HH 00009000000000000000 asa Uewsuyey 0000 000 00000000 0000 00000 Dawsusrew Ora Ud Uv d34H 9071 Ty xi ZFA xepug UU UTI Z OB UO Osuney 3u8reA O D C B0 HD D D U INT IA 00090900000000000000 00 503 Surdeug Misa 1 U L 0 HH 00000000 0000009000000000000090000000 0000000000001 0000000000000000000 00 001715860 00000000039 0000000000000000000000000 UPON asd UU U U poodrlerT sseoonS WITS A 0 O Sree HO DWHON 000000000005000000 09000 DAN HHHHHHHHHHHHVaa 00000000650 ueoq uonenpean 0000000000001 00000000000000000000000 000 uenbeg HHHHHHHHHHHHIHHHHHHHHHagsVHHHHHHHHHHHHHHHHHH ddSV 0 00000000001 0000 0000000000000000000000 J 0 001 00000000000000000000000000 1 HHHHHHH 9000 ON P008 201X 116 1 0 117 P008 201X V MO I OOT 6 Age I 0 G AG T 01 uuu HHHHH 0000000 ILDN uro L 03Br9dO LVO UO DUO 00 0 p sg 0 d 0 uu 0 d 0 U 00000000000000000 O O eeu HHHHHHHHHHHasmHr 00
19. 2 AC 6 GkV 440V AC 6 6kV BUTI FR 440V TEES NE 40 P008 201X BWRIHHHHHHHHHHH HH 00 T 00000 Jis Electric load rejection 2 0000000000000000000 2 Electric load rejection with turbine bypass valve failure 3 HHHHHHHH 3 Turbine trip 4 0000000000000000000 4 Turbine trip with turbine bypass 000 valve failure 5 00000000 00600 5 Main Steam isolation valve closure 6 00000000 10 6 Inadvertent closure of one MSIV 7 0000000000 7 Partial MSIV closure 8 00000000 8 Loss of normal condenser vacuum 9 0000000 00 9 Pressure regulator fails open 10 10 Pressure regulator fails closed 11 000000000000000 1l Inadvertent opening of a safety relief valve stuck 12 000000000000 12 Turbine bypass fails open 13 00000000000000000 13 Turbine bypass or control valves cause increased pressure closed 14 0000000000 0000 14 Recirculation cont
20. uuu HHHHHHHH HHHHHHH 00000000000000000080900000000 0000000 0 000000000000000000000900000 00000000 0 000000000000000000000000805 000000000 000000000 00000000000000000000000000000 000000000990980 000000 b 0000000049000 9 2 5 0 00000080000000000000000000 0 00000000000000000000980000000000000000 0000008980 0000000000007 o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
21. 96 000 TE 97 000 460000 0 0 0 mL 99 OOO 0 009000000000800000000000000000000 NR a 110 000 AE E epist tiet edit inn 112 000 0000006909000000000900000000000 113 000 00000000 0955 0 0007000000000000 114 000 ALO OOD THERPO 0000000000000 un 115 000 AMDO0O00000000000000000000 121 00000 00000 0 00 000 0 00000 123 AOD THRO 000000000000000000000000 124 000 0000800000000000000000000000000 125 000 460000000 95 0000000000000 C Ame 126 ttum 127 DODO OOOO 00 00000 eunt 131 3 P008 201X FL EL atii FOTO T Saa aa DE ttp d tacos mu 133 000 Av0000000000000000 eoo Eu P dedi 136 000 137 000 138 000 AXNOOODOOO OO 141 000 400000000000 A o 142 Haa ese EI M UM tuens 147 c SAA 147 2 PRAD DD 147 3 DODO0000000 See tette ameta iste tec 149 4 OOO 150 5 DER Nb usual 150 6 i Ql 151 7 OD
22. 48 9 0 000 0000000000 02012000000 00000004 000000000 0000000000000 096000 0 0 00000000 0 HHHHHHHHR HHHHHHHHHHHHMHHHHHHHHHHHUHHHHHHH 0 000000 04 000000000000 0 0 0000 FRAHHHHHHHHHHHHHHH UE BaD HHHHHHHHHHHH 00 00000000000000000000 0000 0000000096850 000000000000000000000 PRAHHHHHHHHHHH HH HH 00000000000000000000000000000000 1PRAHHHH 1 00 0 0 0000 0000 00000 00 0 0 00 0000 2PRAHHHHHHHHHHHHHHHHHHHHHH 0 000000000000 0 000 HHHH HHHHHHHHUUHHHHHHHHHPRAHHHHHHHHHHHHHHHHH EI E EJ Eg I 0 0 0 0 0 0 0 0 0 0 0 ET 0 0 0 0 0 ES E eT GE P008 201X PRAHHHHHHHHHHHHHHHHHHHHHHHHHHHH HHHHHIHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHH 1PSA 2008 0000 5000000000000000000000000000000000 00000 PRAHHHHHHHHHHHHHHHHHHHHHHHHL llHHUHHHHHHHH HHHHHHHHHHHHHH HHHH FRAHHHHHHHHHHHHHHHHHHHHHHL HHHHHHHHHHHHHHHHHHHHHHHHHHHH PR 0 0000000000000000000000000000 FF HHHHHHHHHHHHHHHHHHHHHH ii
23. U 1 0000000000000000000 78 P008 201X HHHHHHHHHHHHHH gn HHHO CSB SLM OS UBPBESO GCOZIK 0 X lw asta ee aE E 79 P008 201X 000000000000000000090000 00000009 0000000000000000090000000000090 HHHHHHHHHHHHHHHHH vi HHHHHHHHHHHHHHHHHHHHHHH HHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHTRHH Va HHHH Vl 00000000 000080000000000 0000 OU GO D 0GO FLOW 0000000000000009800000000 0000000 0008000000000 000000000 HHHH 0000 0000 000 Lr V2 GOQ 0 0 GO FLOW a GOOG 0900 000000000000000960000000000000000 069080 0000000000000 600000000000000 HHHHHH HHHHHHHHHUHHUHHHUHHHHHHHHHHHHH 00080000 041 00000 0000000000 eon 10 20000000000 0 00000000000000000000 1300 6700 0000000 HHHHHHHHHHHHHHHHH 1000000000000000000000000000000 000969 000000000000000000000000 00000 UU G OU OU WH GO OU OU 0 H 0 0 GOHHHHHH 00000 U 00000 00000 0000 HHHHHHHHHUHHHHHH HHHHHHH HHHHHHHHHHHHHHHHHHHGOHHH 0000000000 80 P008 201X 00000000000000000000000000000000000000 00000000000000000000000000000000000000 0006000000000000000000000000005 00000
24. 45 P008 201X 0000000000000000000000000000000000000000 0 000000000000000000000000000000000000000 0 0000000000000000000000000000090800000000 HHHHHHHHHH 0000 1 ASME ANS Addenda to ASME ANS RA S 2008 Early Release Frequency Probabilistic Risk Assessmen Applications ASME ANS RA Sa 2009 ASME ANS 2009 andard for Level 1 Large uclear Power Plant 46 P008 201X I 0 L3 L3 r3 0000000060000 HHHHHHH6 0000000000000000909000000000080 HHHHHHHHHHHHHH 110000 000000000 IU O 0 0 ULOCAUSGTR PWRILU O 00000008086 LOCAT Daupuupnupgupupgaupguggupgpagaupuggupuubnubm EB HHHHHHHHHHHHHHHHHHHHU HHHH ATWSHHHHHUHHHHHH HHHHHHHHHHHHHHHHHHHU HH CAHHHHHHHHHHHHHH OQUO0000000000000 0909 1 000 0 000000000000000989000000000098000000000 0 0000000000000009000000000000006098000000 00000000000000000 dB L2 BWRIHHHHHHHHHHHH a OOOO 0000000008 000000000000000000000000000 0000000099090 000000000000000000000000 0 0000009090000090650 000000000 0 000000099000000000990000000000000000000 000 1100 000 1 0000009850 0000000 00000000809080000000000000000000000000 0 00000000008080000000 2 0000000 0000000000000000000000000000000000000 1 600000000000000000000 3 DOURDEOOOO 00000 0000000000000000000000000000 0000000009850 00 0000000000000 000000000000000000000000 0 019850 000000 11000000000000000000000000 47 P008 201X
25. 0 000000000000000 000 0000 80 0000000000000006 600 1222 TH g DU D DB D BOE BLB 7BLBL D OI 9 0090000000000000000 0 0000000000000680800000000000000000000000 00000000000000000808071000000000000000000 0000000000000000000000000000000000000000 DI 12 3 3 HHHHHHHH HHHHHHHHHHHHHHHHHHHHHHHHHHHHH 000000000000600 0000000000000000000000000 L I UB LU 123 0000000 23 P008 201X HHHHHHHHHHHHHHHHHPRAHHHHHHHHHHHHHHHHHHH HHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHH HHHHHHHHHHHHHHHHHHHH 0 000000000090008 0800000 Fussell Vesely 00000000000 DOU U UO DO U ll ll Fussell Vesely 0 00000000000000 88 00000000090000000000080 HHHHHHHHHHHHHHHHHHHHHHHHI HHHHHHHHHHHHH 0 00000000000000000000000000080000000 ATI 0000000 000 124 HHHHHHHHHH 0000000 90000000000008000 000 125 HHHHHHHH 0 00000000000000004909000000080000000000 AV 0 0000000000000000900000000008 BD 13 000000000000 13 1 0000 0000000000000 00010000 132 HHHHHHHHHHHHHHHH 12 HHHHHHHHMHHHHHHHHHHHHHHHHHHHHHHHHHHHH 0 00000000009096000000000000000000000006 D 0000000000
26. ALD 000 THERPHHHHHHHHHHHHHH 0000095 0000 100000000 000 10 42 HHHHHHHHHHHHHHHHHH 0 000000000090980 00000 00 000 0 0 0 00000 000000000090000098 0000000000000000000000 HHHHHH 10 43 D D DAD U D UUIDDUDDUDBDUDUDUDUDHBHRBDUDUDDUDUDUDUBUDUDDDUDUDUDUDUUuDUL 00000 00 0 0 0 0 0 0 0 000 000 0 000000000000000068080700000000000000 00000000000000000060000000000000000 LI 10 4 4 IIHBULD HD UO D UL D UL D U D 7 DI 0000000000009 0000000000 6 60000000000 000 0 00000000000009000000000000000000000000 0006000000000 000000000000000000000 000 19 P008 201X HHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHH HHHHHH a HHHHHHHHHHHHHHHHHHHHHHHHH HHHHHHHHHHHHHHHHHHHHHHHH 0000000000000000000000000090 HHHHHHHHHHHHHHHHHH 000000000000000000000000 908 0000000000000 000000000000000000 000000000000000000006000 0000000000 1045 HHHHHHHHHHHHHHHHHHHHHHHHHH 0 00000000000000000098000000000000000000 00000000000000000094990008000 1022 00000000 00000000000000000090900000609800000000000 0000000000000000099000000000 98000000000 00000000 000 6 500000000 000 1046 HHHH
27. 00000009480000000008098000000000 000000900000000000000898000000 00010000809 000000000000010000 0000000000 0 000000000000009 000 2607 00000000 000000000 00000000 40 0000000000000000000000000 0 0 0 0 00000090000 HHHHHHHHHHH 0904010000000 e 0000 000000000006080000000000000000000000 00 0000000000080807000000000000000 b LOCA 1gagupsugusbngupupgupguggupgaupugdguud ubbu lulu 1 00000000080800000000000000000000000060 0000000000090 00000000000000000000000 DO 0 0 LOCAHHHHHMUHHHH LOCAHH LOCAHH LOCAHHHHHHHH E 51 P008 201X LOCAHHHH LOCAHHHH LOCAHHHHHHHHHH 1 LOCA 10000000000000000000000000 40800000000 000000000000000000000000 000009 2 LOCA 0 0 000000000010000090000000000080 0 000000000000000000000498000 3 LOCA 0 LocAgpngugugganagaununagunaagagugdtmgmga 000000 000000000000000000000000000000009680 000 OOOO 1000000000000000000000000000 2ZHB 00000000000 4 LOCA 000000000000000900000000800000 LOCAHH 00 0000000000000090000000000680800000 5 LOCAHHHHHHH 00000000000000090890000000000004000000 HHHHHHHHHHHHHHHHHH HHHHHHHH
28. 27 28 29 30 31 32 33 34 35 36 72 P008 201X 0000 00 HHHHHHH8 HHHHHHHHHHHHHHHH MLHHHHHHHHHHHHH HHHHHHHHHH R1 HHHHHHHHHHHHHH 000000000000000000000000000000000008070 0 0000000000000000040000000000000000000 0 000000000000000000 0190 000000000000000 0 0000000000000000009000008098000000000000 0 00000000000000000900000000060980000000000 0 00000000000000090900000000 R 1000 00000000000000000680980000000000000900000 0 0000000000000000000090000 80009000000 0 00000000000000000000000808000090000000 0 00000000000000000000000000 8989700000000 0 00000000000000000000000000000000000006000 0000000000 0960980 000000 000000000000000 000000000 0900000968000000000000000000000 0 00000000900000000898000000000000 73 P008 201X A B CHHHHHHHTH ET D 80 B y Aa Om Oo pr Om prp 1 2 3 4 5 6 7 8 A B No 1 A R1 000000000000000000000 74 P008 201X HUDS 000000000000000 00 00000008 0000000000000000900000000000008 0000000000 si 000000000000000 000000000
29. HHHHHHHHHHHH 52 000000000 e 00000000000 0000000090650 00000000000 000000000000000009800000000098000000000 00000000000000009 HHHHHHHHHHH 0000000000000000000808000 6 HHHHHHHHHHHHHHHH 61 0000000 eii 00000004000 0 00000000900000980 00000000000 8000000000 0000000000000 000068400000000000 00000000 0000000090000000000 0 589 000000000000000 00000000 0090800000 000 00900000000000000 L LU HHHHHHHHHHHH HHHHH b 000000000 o HHHHHHHHHHHHHHHHHHEHH YUE DHOO TFPRAHHHHHHHHHHHHHHHHHHHHHHHHHHHHH 9000 0895 0000000000000000000000000000000 0000000009053 0000000000 0000000000090 0000000000000000000000000 6 P008 201X 00060 000000000000000000000 e HHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHH 00000000000000000000000000 09800000000 0 00000000000000000000000009090080800000 0009 00 OOO 0000000000000000090000000000080 0 0000000000000000000 0 00000000000000000000000000908000000000 000000000000000000000000000000 6 12 HHHHHHHHHHHHHH 00000000000000000000000000000000000900 000000000000000000098000000000000000000 HHHHHHHHHHHHH 960000009008
30. 081 0 8 0 00000 0 000 0 0 0 0 0 0 000 0 0 0000000000 TOE BLU UU Dnugnuuapnunuannungunn HpBuHDpuduDunnung 6 20000000 0000000000000000000000000000000000000000 0098 00000000000000000000000000000000000 00000904 000000000000 000000000000000000 00000000808 00000000000000000000000000000 00000000000080000000000000000000000002000 010000000000000700000000000000000000 100 P008 201X AG 3 HHHHHHHHHHHHH HHHHHHHHH HHHHHHHHHHHHHHHHHHHHHHHHHHHHH HHHHHHHHHH HHHHHHHHHH Human Error Probability HEPOO U O HHHHHHHHHH 0 000000000000000 90008080000 00000000 HHHHHHHHH 0 0000000000000000000000090000000000098 00000000000 Time Reliability Curve TR LH H E UU WU D U TRC HHHHHHHH AG1HHHH 0000009 000000000 b 00000000000 0000000000000000000000000000 00009800000 00000000000000000000000000000000080 0 HEPHHHHHHHHHHHHHHHH HHHHHHHHHHHHHHHHHHH LU 0 HHHHHHHHH 00000000000000900000000060980000000000 00000000000 ODO 2 HHHHHHHH 6 200900000000 HEPHHHHHHHH U I DU H BO 3 00000000 HHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHH 00000000803 00000000000000 6 3000
31. 1 0 119 P008 201X HH o 095000000040600000000000000000 0 0 HH HBINo H HHHHHHHpoomv HHHHHH 0 00 0 serdmoo 000 naam HHHT HHHHHHHHHH HHHHHHasd A HHHHHHHHHHeey 0000000000000 0 mature jour 00000000 0000 asa 0 HHHHHHHHo HHHHHg 00000090000000000 D HHHHHHHHHHHHHe OO 0 O O O O O 0 000e 000 HHHHHHHHHe HHHHHHHHHHHHHHHHHHHH Bey 0000 000e 000000000000009 ON O O O O D HHHHHHHHHe 3urdeqs socemuxoneaSHHHHHHHHHg8 0000 00000 HHHHHHHHHHHHHHHHHHHHHHHHHHHHHH sa 008 HHHHHHHH svasey 00 06661 HHHHHHHHHHHHHHHoON HHHSvds HH 0000000 0000 ON HHHHHHHHHHHHHHHHHHHasmHL tTy 0 120 P008 201X 0000 1 D W Whitehead Evaluation of Potential Severe Accidents during Low Power and Shutdown Operations at Grand Gulf Unit 1 NUREG CR 6143 USNRC June 1994 2 D M Ericson et al Analysis of Core Damage Frequency Internal Events Methodology NUREG CR 4550 SAND86 2084 Rey 1 Vol 1 USNRC 1990 3 Swain Accident Sequence Evaluation Program Human Reliability Analysis Procedure NUREG CR 4772 USNRC 1987 4 D E Embrey P Humphreys et al SLIM MAUD An Approach on Assessing Human Error Probabilities Using Structured Expert Judgment NUREG CR 3518 USNRC 1984
32. 1470 y gt r3 E Et oN ero r3 ml c oo og os oo r3 i oo oo C oy oo 4 EJ oo r3 oo o r3 r3 o io m ed oo ca oo ip r3 r3 Oo E33 ip r3 r3 r3 m r3 io E a mim E Ej oo ow oot in Ay mi pan oo E io N os y oo an og in r3 aot 1 oe in r3 r3 r3 r3 EZ 5000000000 s 00000000000 HH 0000 E gt HH 70000000 80000000000 9000000000 100000000 00000000 gt 91218 00000000 18 000000000 13 0000000000 N 000 1PRA D D D 14000 oO oO oO r3 I 21 5 P008 201X 5 000000000 5 1 000000 0O00 1 0000000000000000000080 2000000 00000000000000000000000000 0000000000000000000000000090800 b 0000000000000000000000009000000000008 0 9000 000000000000000000000000000009600000000000 HHHHHHHHHHHHHHHHHHHHHHH E 08000000 HHHHHHHHHHHHHHHHHHH 2 000000000808000 HHHHHHHHHHHHHHHHHHHHHHH
33. Technique for Human Event Analysis 1 0000000000 000000 00000000000000808000000 PRAHHHHHH HHHHHHHHHHHHHHH 0 0 00 00 00 00 0 0000000000000009000000000 0000000000000000 28 9 00000000000 011000000 000000000 000000000060080000000 0 00 00000000000000000808 0000 00000000 000 HHHHHHHHLUHHHUHHHHHHHHHHHHHHHHHHHHHHHHHH 00000000000 0000 State of knowledge correlation SOKC OOO OOD NHHHHHHHHHHHHHHHHHHHHHH 000 HHHHHHS KCIHHHHHHHHHHHHHMIHHHHHHHHHHHHHHH HIHHHHHHHH HHHHHHHHH HHHHHHHHHHPRAHHHHH HHHHHHHHHHH HHHHH HHHHHHHHHHHHHHHHH a PRAHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHH Ey ara CEA UE E E E ERI we WEE p E EST Eb pd DHBASUgBDBOUDBUUHDBODOUSUSOSOSUDBUSUOOUDOUUBUDUDUOUDU 0000000000000000000000000000000 00000009053 000000000000000000000000 b 0000000000900 0000000000000000000000000 HHHHHHHHHHHHH HHHHHHHHHHHHHHHHHHHHHH
34. 3000 0 ASME ANS PCO OOO 59 00 0 000 06 1 00000 00 HHHHHHHHH HHHHHHHHHHHHHHHHHWSAHHHHHHHHH 1HHH 9HHHHHH HHHHHHHHHHHHHHH 0010 0000000000 0000000000000 8 3000000000000000 1 00 0280 0 O U 0 0000000090000009 000000000 000 D PRAD 0 D 0 000000099000000000900 0000 200 30000000000 000000009000000000 0 011 0000000000 10000 0000000000980 0 011000000000000000000000000 0000000000 0000000070000000000 400000 00000 0 0011 000000808 00000900 132 P008 201X AS 1 HHHHHHHHHHHH NEI 00 02 0 OOO 1000000 LEREHHHHHH 00001 D 0 01x0 00 CDF 0020 0 LERF 0000 2 0 0001x 0 0 DF 0 0 0001x 000000000000000 HHnnnnnnnnnnnnnn U 900010 0 MAg 0 0 a CDF LERE 9 core damage frequency b large early release frequency 0000000 0000 1 USNRC PRA PROCEDURES GUIDE A Guide to the Performance of 2 3 4 5 Probabilistic Risk Assessments for Nuclear Power Plants Final Report NUREG CR 2300 USNRC Jan 1983
35. 0000006800000000070000000000000 AG 3 HHHHHHHHHH HEPHOBDHOBOUDAHOUDODUDUDU b HHHHHHHHHHHHHH HHHHHHHHHHHHHHHHHHHHHHHUHHHHHHHHHHHHHHH 0000000000000000000000000000000000 00009800000000000000000000000 000000808 000000000000000 HEPHHHHHHHHHHH 000000000 009850 000000 0 00000000000 HEPHHHH 0000000000000000000000000 HEPHHHHHH 102 P008 201X AG 5 00000000 HHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHH 0 00000000000000000000000000000409800000000 000 NO 0 000000000000000000000090000000000098 0 00000000000000000000 008 0000000000000 0 0 0000008080000 000000000000000000000680980000000 HHHH 500000000 000 0 0 L3 EJ 000 00 00 oo 0 0 0 L1 L1 L1 OOOO gn dgamauuiutubpulullulbdudlu 0 0000000090000000000808000000000 UUDDUDUDBDUDUDUDUDUUHBUBUDUDUDUDUDUDUUUUUDUGUDDUUDU 0 00000000000000008080000 000000 0 0000000000000000000906840000000000 000040000000000000000000000 000900080 000000000000000000000000 0099000009080 000000000000000000000 UU
36. J D 5 5 000060068000000000 0000 1 2 3 4 5 USNRC PRA PROCEDURES GUIDE A Guide to Performance of Probabilistic Risk Assessments for Nuclear Power Plants Final Report NUREG CR 2300 USNRO Jan 1983 PLG TVA Watts Bar Nuclear Plant Unit 1 Probabilistic Risk Assessment Indivisual Plant Examination vol 1 PLG TVA 1992 EPRI ATWS A Reappraisal part3 Frequency of Anticipated Transients EPRI NP 2230 EPRI 1982 USNRC Reactor Safety Study An Assessment of Accident Risks in U S Commercial Nuclear Power Plants Appendix V WASH 1400 NUREG 75 014 USNRC 1975 100000 000000000 0 0000 PSRAHHHHHH 0000 Oe BUOOOUO 0 0 070 0 0 00400 0 0 190 40 43 P008 201X 000 G 0000 0000000 00 00000006 00000000000000009900000000008680 00000000000 ci 0000000 0 000000000000000000000000000000009009000 HHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHT HHHHHHHHHHHHHHHH8 00049000000009 00000000 HHHHHHHHHHHHHH 000000000000000909000008095 00000000000 0 10000008 08 0000 LOCA 0000000000000000900000000000000698000000 0 0000000000000000099800000000000 00000000 000000000000000000008080000000010000000 0 00000000000002000000000808000000000000 0 00000000000000000000000
37. o cO oO c Oo LITE 1 3 J 13 000 0 2 RHR OO a O ogoni LT BB 1 8 0000000183 0 lt PORVHHHHHHHH 66 P008 201X 000 N 0000 OO 00 00000007 0000000000000000099000000000080 0 00000000000000000000000 1 00000000000000000000000000 00000000000000000000000000000000 SWR HHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHH 10000000000000000000980000000000000000 0 0000000000000000009900980000000000000 0 000000000000000009090000000980 000000000 0000000000000 9000000000 9 80000000 0000000000000009607 000000000009 800 ugmmagmgmumnagnmnagagmiagmuubiee I 0000 1 l 67 P008 201X O HHHHHHH7 0000000000000000099000000000080 oi 24HHHHHHHHHHHHHHHHHH 00000 7 3 3 00080000 0 00000000000000000240 00000 CO HH
38. soexdogna pnpna augugpnDgHODDHOUNHU UH HHHHHHHer 00000008 0 00 061 00000000000000000000000 9 Ur Lo 00000900000000000 mee HHHHHHHHHr 9 Dr uo tr AO eAnru80p PT usu 0000008900000 r gG AD ZAL 9 dxe HHHHHHHHHHHHHaoOH 0000000 000 ON QOOUODUUUOUOUOUUUU0UUdaaHE 0 000 00000000896 00000 ep 0000007000 HH 0000000007 00 084a 00 00 0 0 Do HH TTTL 00000000 000000000 0 7 000000 ED 0 THII OO00 at UASD 00000 Ooo D HHHHHHH 6 Dvn 00004000 0000000 0100000000 0 0000 0000 0000000000000 0 SpA en HHHHHHHHHHHHHHH 0000000000 0000000 0000000000000 00090000 0 aer d VNV EV 000000000000 OOO O O O HKrrqeq0morxg D 000 00000000000 Damog 8 0 0 0000000000000000 HHHHHHHHHHHHHHHHHvn 0000900 Duny 000000000000000 ersun va 0000000000 OO vNvanivo 000 000000000000004 0000000000000000000000000 103284 Surdeug 00000000000000000000 00 0 HH 0000000 0000 P008 201X 118
39. ADS 1 3MUWC ADS 1 2 0000 ARI SDV RPT HPCS RCIC ADS LPCS l ADS 1 3LPCI ADSB D U U 0 ADSI 1 3MUWC ADS 1 2FP 0000 1 2RHR LPCS 1 3LPCI 000 1 3MUWC 1 2FP 0 0 0 120 200000 1000 6 00 0000000000000 08 00900000 00000000000 LPCI HHHHHH S R D SLC HHHHHHHH ADS HHHHHH RBS 000000 HPCS HHHHHHHHHH FP HHHH SDV 000000000 RCIC HHHHHHHHHH PCS HHHHHH ARI 00000000600 LPCS HHHHHHHHHH RHR HHHHHHH MUWC HHHHHHH PCV 0100000 65 P008 201X M2 0000000000000 D rnt 0000 22 1 2 000000 ZJ I Set ia 0 en 7 ms i x 00 0001 3 1 3 o o B E LESE E3 E3 ir ESL E EJ EJ EJ E3 EJ EJ EYE EI C3 ij B E 1 3 1 e oo ID 1 3 0 i
40. SN2 V4B V1 NC p gt V10 V8 C1 TS1 O P5 V4A F2 PMP1 Containment V10 P4 SN2 PMP2 TS2 C2 V4 9000000000000000 00000 1270000 00 84 P008 201X 000 W Uu 000000000000000 00 00000009 00000000000000000000000000000 00000000 wi HHHHHHHHHHHHHHHH 0000 1 USNRC Fault Tree Handbook NUR 2 85 P008 201X HHHHHHHHHHHHHHHHHHHHHH 000000000000000000 00000000000000000 OO INHIBIT I 0000000 AND FH B E INHIBIT TH 0900 11259 21 HU 1 00000 0000 00000000001 HHHHHHHHHH HHHHHHHHHHHHH HHHHHHHHHHHHHH HHHMWHHH L3 OW1 00000000000 HH GO p TV3H
41. ET 2 ES DESI ESP ESD ES a E ERO EO E E Ed SS E SS er ee LIE E E Ei EJ BERE Emp EX SSeS Sa Ed EE zit ES eS UE ES SEES SEI Ej E Eae Ez EY EE OE EE dE ET E E E E gm E ERN E ESI SEE Ex ERE Ed GER ES E EX EE EM CENE 0000000000000 OO 0000 000000000 0000000000 000 00000000000 OO 0000000000 00000 OO 0000000 MME 72 ELT ES GER GET ERI EER 2 ER ET EZ P008 201X 0000000 000000000 201xQ XI I D OO 000 0000 OOO HH HH HHHHHHHHHHHH OO 00 HH 0000 0 OO 0000000 DD 00400 0000000 0 OO OO 00000000 OO 00 50 00000000000000 0 OO OO HHHHHHHHHHHH OO 00 80500 0 OO HH HHHH DD DU 0008909000 0 OO OO HHHHHHHHHHHH OO 00 HH 0 OO OO 0000000 00 DD x FO 0 OO OO 00000000000 Bg OO OO HHHHHHHHHHHH 0 00 0 0000000 HH 000 R AY GE 0 DD OO 000000 0000000 OO 0000000 0 00 00 00 OO 00 HBHDBUDUU 0 OO HH HHHH OO 00 HH 000908900000000 0 OO OO 000000000 Steve
42. 0 0 0000000000000 0 0 HHHHHHHHHHHH o L1 L1 0000000000000 1 Oyo L3 L3 Cojo O 000000000 80 20000000000 20000 90 HHHHHHHHHHH 1000000000 L uU uu 10000000 HHHHHHHHHH HHHHHHHHHH 00000000 00000000000 0000090000000 3L UUUUUG HHHHHH LOCA 50 HHHHHHHHHH 60 B LI LU D U D U 000905 00 ae ooo ooo ooo ooo ooo ooo O12 PWRIHBUDOUDUDUDOUDSBUDUDEUULU 56 P008 201X 00009 0000 HHHHHHHHHHHHHHM 00 00000006 0 000000000000000090000000000060 HHHHHHHHHHHHHH J 1 0000 0 00000000000000000000000000000000905000 00000000000000000000000000060 000000 U ASME HHHHHHHHHHHHHHHHHHHHMMUHHHHHHHHHH PRAHHHHH HHHHHHHHHHHHHHHHHLOCA HHHHHHHHHHHHHHH HHHHHHHHHHHHHHHHHHL J 2 HHHHHHHHHHHHHH 0000000000000000000980 0000000000000 200 b HHHHHHH 00000000000000000000 0000000 b 00000000000000000000000 00 000000000 000000000 49000000000000000000000000 0000000090909 0000000 9000000000000000000 HHHHHH 0 00000090000 00004 10000 9 50 000008
43. 0000000 1982000 200700 2600 5500000 2013 http www nucia jp jfiles reliability REPORT201306 pdf USNRC Analysis of Core Damage Frequency Internal Events Methodology NUREG CR 4550 SAND86 2084 USNRC 1990 USNRC Nuclear Computerized Library for Assessing Reactor Reliability NUCLARR Vols 1 5 NUREG CR 4639 EGG 2458 USNRC 1994 JSNRC Component Performance Study 1987 1998 Vols 1 4 NUREG 1715 JSNRC 2000 at U S Commercial Nuclear Power Plants NUREG CR 6928 INL EXT 06 11119 USNRC 2007 b HHHHHHHH 0000000000000009 8 000 00 HHHHHHHHHHHHHHHHHHHHHHHHHH 1993 USNRG Modeling Time to Recovery and Initiating Event Frequency for Loss of Offsite Power Incidents at Nuclear Power Plants NUREG CR 5032 SAND87 2428 USNRO 1988 USNRC Evaluation of Loss of Offsite Power Events at Nuclear Power Plants 1980 1986 NUREG CR 5496 INEEL EXT 97 00887 USNRC 1998 127 POO8 201X Dnm 000 0000000000000 HHHHHHH12 DDUDUDBDUHUHBHDUUDUDDUDUDUHHUHDDUDUDUDUDUUuHBL HHHHHHHHHHHH AR 1 HHHH 0 00000000000000000000000000000008080000 00000000000000000000058000000000000000000 0000000000000000000 0000 AR2 00000000000 0 000000000000000800000000000890800000000 0 0000000000000008 0 000000000000000080980000000000070000000 HHH
44. 0000000000000 0 HHHHHHHHHHHHHH 3 4 0000 0 0000000000000000000000 3 5 00000 0 000000000000000000000000000009050000000 D Uu 3 6 00000 0 000000000000000009090680800000000000 01 00 00 DE U NPSH Net Positive Suction Head 0041000 THERP Technique for Human Error Rate Prediction THERPT OOO 4 000 1PRAHHHHH 41 000 1PRAHHHHHHHH 000 1PRAHH5 40801000000 14 00000000 10000000 0 000 9 100001980 000000000000000000000 000000000900 10000009680000000000000000000 0 00000000 00 0000000 12 8 000000000000 000 42 000 2 000 1 0000060 gt 2 00000 1PRAQ 0 000 0000000000000 2 00 00 0 0 0 0 0 0 0 0 00000 0000000000000000000000000000000000000000 19790 000000000000000000000000 1PRAHHHHHHH OU 2 110000000 2 10000000 0000 000 1 00600000000000 000 43 000 1 080000000 DOU 1 0000000000000000000000000000000 00000000000000 1PRAHHHHHHHHHHHHHHH 3 P008 201X HB l1gHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHH 000000000 80000 8 2000 300000000 1PRAHHHHHHHH 00 0 0000000 1 00000000000 0000000 1PRAHHHHHHHHHHHHHHHHHHI P008 201X 4 I 1 1 1 1 l 1 1 1 1 i FEY A ict ia 1 1 1 1 1 1 iG EFE ODi ae IE3R om Soe B C Po a E E B D
45. 0000000000000 PRA Q 00000000800 0000 L1 0 0 0 0 32 HHHHHHHHH HHHHHHHHHHHHH 000000000000000000000000000000000000 LU OU OU 0000000000000000000000000000000 96 Ca aani O DD rr LU LU LU 0000000000909 0000000000000000000000000 00980 000000000900000000000000000000000000 150 P008 201X HHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHH HHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHH 4 00000000000 00000000000000000000000009000000080800 HHHHHHHHHHHHHHHHHHHHHHHHH 0000000000080 0000000000000000000000000 0 0000000000060 0 00000000000000000000000000096040000000000 0 0000000000000000000000000000009090000000 HHHHHHHHHHHHHH 200000 10000000000000000000000000000000000090 0 0 0000000000000000000980000000000 NuCIAHHHH 00000000000000000009090008000000000000000 0 0000000000000000098900000080980000 00000 000000000 NPO 0 0 TH 00000000 HHHHHH 18 00000000900000000000000608000000 0 000000000000000008089000000000000000000 0 0000000000000000000080800000000 0000000 0 000000000000000000000008050000400000000 HHHHHHHHHHHHHHH 2000000000 40000000000000000000000000000 00000000000909 0000
46. 0001 2 2 COOL 4 001 7 0006 3 3 0001 001 002 s f 001 4 4 0001 001 002 004 e 002 5 5 0001 001 002 004 008 003 6 6 0001 001 002 004 008 0L0 005 7 7 0001 001 002 004 008 016 0 009 8 8 0001 001 002 004 008 016 032 064 02 9 9 0001 001 002 004 008 016 032 064 18 03 10 10 0001 001 002 004 008 016 032 064 13 25 05 11 11 15 10 12 16 20 l 20 0 O O PriFil 25 15 18 21 40 20 14 gt 40 25 101000000009800000900000 02 0000000008007 0000000000 0000 122 P008 201X AM2 1HHHHHHHHHHHHHHHHHHHHHHHHHHH NUREG CR 1278 0000 Dn 000000000 x 0400008 1 2 3 4 5 6 7 8 HHHHHHH 1 000000000 05 31 50 74 90 2 000000000 15 67 80M 87 92 95 097 0000000000000 3 10 40 61 74 83 89 92 95 4 80 58 75 85 91 94 s97 98 5 9 95 95 95 95 95 95 95 6 98 98 98 98 98 98 98 98 7 99 99 99
47. 4 4 3E 3 IE 3 4E 4 3E 3 1E 3 1E 3 1E 2 2E 3 1E 3 LE 2 2E 3 r T Medium pipe break LOCA PWR This analysis 1E 6 3E 5 1E 4 WASH 1400 3E 5 8E 4 3E 3 NUREG 1150 3E 4 1E 3 2E 3 BWR This analysis 9E 7 3E 5 9E 5 WASH 1400 3E 8E 4 3E 3 NUREG 1150 8 5 3E 4 7 4 Large pipe break LOCA PWR This analysis 1E 7 4E 6 5 WASH 1400 1E 5 3E 4 1E 3 NUREG 1150 1E 4 SE 4 1E 3 BWR This analysis 9E 7 2E 5 9E 5 WASH 1400 1E 5 3E 4 1E 3 NUREG 1150 3E 5 1E 4 2E 4 The LOCA frequencies estimated in this analysis are based on calendar years of operation i e reactor calendar years rather than reactor critical years in order to facilitate comparisons to WASH 1400 and NUREG 1150 In the main body of this report frequencies given in reactor critical years To convert the frequencies in this appendix to reactor critical years divide the frequency by industry average criticality factor of 75 USNRC Pipe Frequency BNL NUREG 52141 USNRC 1989 USNRC 1975 b LOCA frequency estimates calculated in this appendix Estimation for Nuclear Power Plants NUREG CR 4407 EGG 2421 USNRC 1987 USNRC Interfacing System LOCA Boiling Water Reactor NUREG CR 5124 Elicitation Process NUREG 1829 USNRC 2008 USNRC Reactor Safety Study Assessment of Accident Risks in U S Commercial Nuclear Power Plants Appendix V WASH 1400 NUREG 75 014 USNR
48. 99 99 99 99 99 0000 1 D Swain H E Guttmann Handbook of Human Reliability Analysis with Emphasis on Nuclear Power Plant Applications NUREG CR 1278 Final Report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wain H E Guttmann Handbook of Human Reliability Analysis with Emphasis on
49. ASME ANS Addenda to ASME ANS RA S 2008 Standard for Level 1 Large Early Release Frequency Probabilistic Risk Assessment for Nuclear Power Plant Applications ASME ANS RA Sa 2009 ASME ANS 2009 00000000000000000000000980 09000000000 0 180 40 8 U 0000 5 lt WOG Westinghouse Electric Company B amp WOG and Framatome Technologies Inc Probabilistic Risk Assessment PRA Peer Review Process Guidance NEI 00 02 Rev A3 March 2000 133 POO8 201X 000 AT 0000 00000 HHHHHHH12 0000000000000000490000000000080 HHHH ATi 00000 HHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHH HH 0 0000000000000000000000000000000000060090 00000000000000000000 98000000000000000 RCD H HHHHHHHHHHHHHHHH 0 Risk Reduction Worth RRW 2 0000000000000004900000000000000 908000000 00000000000000000808000000000 F CD 0000000 Wy oe F CD 0 0000 F cD AOD 00000 OHHHHHHHHHH F CDgyBDUUBDH 0000000000000000090000000000000000 9000 HOO 0000000 0 00 00 00 0 00 0471 000 0 0 0 0 0 00 0 0 000 HHHHHH U Risk Achievement Worth RAW 902 HIHHHHHHHHHHHHHHHHHHHEHHHHHHHHHHHHHHHHHHHH OU D
50. ECCSHHH HHHHHHHHHHHHHHHH HHHHHHHHHHHHHH LOCAHHHHHH HHHHHHHHH HHHHHHHHHHHHHHHHHH 00000000000 5615 SGTRO 000000000 100B00000000 d 000000080000 LOCA 0000000900000000000000980000000000000000 00000000098000000000000070000000 LOCAHHHHH 000000000008080000000000000000000000000 0000 00000000000000000090800000000000000000000 00000000000000000000000000000000000000000 000 0000 0 000 0 0 0 0 0 00 0 0 000 D 0008 00000009680000000000000000000000000000 0 0 090 0000000000000000000000000 00000 2 ho O00 52 P008 201X HHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHH 900000000000 HHHHHHHHHH 1 00000 2 0000000000 3 00000 4 00000 P008 201X 36 38 BEER 49 Beil Hae 4 1 E BEE J 4 1000000000000 BWRIH 54 P008 201X uri BWRHHHHHHHHHHHHHHHHHHHHHHH 1 2 3 4 5 6 m TAKARO pk EE 8
51. Jan 1983 00000000000 118 P008 201X J oOo gt 000 000 000000000080000 000000019 000000000000000040000000000080 HHHHHHHHHHHHHHHHHHHH 0000000000000000000000000 HHHHHHHHHHHHHHHHHH 0 00000 000000000000000000000000 0900 00000000000000098000000000000000000 00000 00000000000000090900000 0980 0000000 0 0000000000009090000 0000809000000000 96 0 0 0000000000000808000 114 P008 201X 0000 00000000000000000000 HHHHHHH10 HHHHHHHHHHHHHUHHHHHHHH AK1 HHHHHHHHHHHHHHHHHHHHHHHHH 0 00000000000000000000000000000000690 0 0000000000000000000000 HHHHHHHHHHHHHH HHHHHHHHHHHHHHH 000000060 000 AL 1 000 0 D 000 115 POO8 201X AL 0000 HHHHH10 000000000000000 THERPHLOUDOUUODUDRHB HHHHHHHHHHHH 00000000000 00000000000 0000000000000008900000 THERPHHHHHHHHHHHHHHHHHHHHHHHHHH THERE WO 000000000000000000 4 0 00000000000 9 HCR MN ATHEANAO G0 GU SPAR H G0 G1 HHHHHHHH AL1HHHH HHHHHHHHHHHHHTHgRPHHHHHH 00000000 0000006000000 D U DL UO D RO 000000000
52. a 0 00000009000800000000000000000000 2010 0000000090000 000000000000000000000 0 000000900000000009850 000000000000000000 0 00000900000000000000980000000000000000 000000 898000000000000000000 b 0000000080800000000040000000000000 6 3 1 0 00000000000608000009000000000000000000 Ag X 0000000000000000 6 8 1 HHHH U 000000000 000000000 Top 0000 0000000000900 000000 000000000000 10 200 300 HHHHHH 0000010000 0 50 000000 00000000000000000 0000000000000 06 00000000000000 D 0 8 P008 201X c 2 3 1 2 3 4 HHHHzHHHHHHHH 2z 10 5 727HHHHHHH z77HHHHH 0000000000 1000000 50 000000000 66320 000 HHHHHHHHHHHHHHH 01 0 5 2T 0 455 27 000000000000000 6 3 2 00000 100000000000000000000 95 0 00 0 0 mm0 6 3 420 000000000000000000980000000000000 OOO004 0000 ts 17 000000000000000000 0500000 63 9 Ay t 2 0 0000000000000 0 986 34 HHHH 95 D D 0 00000400000 s ln EF 71 645 0 0000000000009000000000000006808000000 0 000000000000008080000 9 HHHHHHHHHHH10 0000080000000 0000000 000000000000000000008090001000000000 0 0000000000000000000009870000000000 LU
53. 0000000 00 000000000000000000000000000 0000000090980 0 00 e gdgnangguopadmgmaggguggapagagddgpgoauu 7 0000 0900000000 RAHHHHHHHHHHHHHHHHH o 00000009080 200 5000000 D pagagagggadmagoudaoguu 2 00000000000 3 HHHHHHHHHHHHHHHHHH 4 000000000 00000000000000000000 5 DDBiPRAGHHBOUUUDDOUOUHU 000000000 IIHHHH HH 12 8 000000000000000000000000 000800000 1PRAHH HHHHHHHHHHHHHHHHHHHHHHHHHH 31 P008 201X 0000000000000 9220 000 0 000000000000000 000000000000 200 9000000000000 a 000 1 000000000000000000 0800000000 HHHHHHHHHHHHHHHHHHHHHHHHHH b 00000000000000000000000000000 o 000 1PRAHHHHHHHHHHHHHHHHHH HHHHHHHHHH D 1 e 00000 1PRAHHHHHHHHHHHHHHHHH 000000 HHHHHHHHHHHHHHHH A 0000000000000 1PRAHHHHHHHHHHHHHHHHHH 0 0000000000000000008000000000000000000 00 00 00 FEAT 00 00 0 0 0 0 0 0 0000 0000000000000000090000000980 00000000000 0 00000000000000009000000000 00000000 0 0000000000000049000000000000000 0000 JEACA111 2009 00 210 90 2 HHHHHHHHH HHHHHHHHHHHHHHHHHHHHHH 700 30 700 30
54. HBgu unmnaupnaupnapnauguduudndndu 000008080000002 0000000000 AESJ SC RK001 2010 DupnupnupnuDgmpapgpnupnupngupgpngapnupnagnpnu 201 000000 0 050 00000000070000000000 00000000000000 156 P008 201X HHHHHHHHHHHHHHHHHHHHHHHHPRAHHHHHHHHTPRAHH HHHHHHHHPRAHHHHHHHHHHHHHHHHHHHHHHHHHHHHHH 0000000000000000000000000000090800000000 0000000000000000000000 000009800080500000 00000 00000000 gt A GE EBs BER 6 HHHHHHHHHHHHHHHHHH 00000000 0000D 00000000000000000000000000000000009090 0 0000000000000000000 090 000000000000 0000 0 00000000000000000009090008000000000000000 0 000000000000000009900000698000000000000 000000000000000009890000000006809800000 0000 0 HHHHHHHH 000000000 2009 http www nucia jp jfiles reliability REPORT200905 pdf 2 HHHHHH 00049 0000000 0000000000000000000 0000000 19820 020070 0 260 0 5500000 2013 http www nucia jp jfiles reliability R EPORT201306 pdf
55. HHHH 0 000000000000000390000000000805000000000 0000000000 0000090000000000000068080000000 HHHHHHHHHHHHHHHH 128 5000000000000 20 8 00000 0 000000000000000000080800000000000000 0000D 000000000000000000000 0985700000 000000000 00000 00000908080000000000000000000000000 0000000008980 0000000000000 EJ NEL 99 P008 201X AG 0000 0000000000 HHHHHHH10 000000000000000 THERP 00000000096 HHHHHHHHHHHHHH AG 1 0000000000 AG 1HHHHHHHHHHHHHHHHHHUHHHHHHHHHHH SE 0 0 HHHHHHHHHHHHHHHHHHHU HHHHHHHHHHHHHHHHHHH HHHHHHHHHHHHHHHHHH HHHHHHHHHHHHHHHH 490000000000000009021000000 THERP 90 Technique for Human Error Rate Prediction DA U O O 0 0 THER 00000000000 00 0000000000009 000000000000000000000000000 9 0 0000000000 UU U 0000 0 THERP 00000000000 1278
56. P008 201X 00000000 00000000000000000 HHHHHHHHHHHH HHHHHHHHHHHH 000 b 0000000000000000 0000000000 00000000000000 00000000000000000000000008098000 000000000000000000000000000 000 o HHHHHHHHHHH HHHH11 0000000000400 090000000000000000 0 000000000000000000000 HHHHHHHHHH 20000090000000000060000 000 e 0000000000000 00000000 0 00000000000060 1000008080000 000900000000 0 000000000000000000000006908000000 8 000000 0000000 000 HHHHHHHaHHHHHH 0000000808 000000000000000000000000 0000000000080800000000000000 0090000000000000808 00000000000000 0000000000000 925 0000000000000 HHHHHHHHHHHHH HHHHHMHHHHHHHHHHHHHHHHHH 0 0000000000000000808 00 000000000000000000 0000000000000000000000 000 0000000000000000000000000000000000 0000000000000000000 000000080 b 00 e 00000 9 26 HD OD UO D BL BL 100000 16 P008 201X HHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHH HHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHH HHHHHHHHHHHHHHHHHHHHHHHHHHHHMABMHHHHHHHH HHHHHHHHHHH 000 93 HHHHHHHHHHHHHHHHHHHHH 9 81 HHHHHHHH 0 00000000000000000000000 908 000000000000 0 00000000000000000000 AHHHHH HHHHHHHHHH 00000 000 a HHHHHHHHHHHHHHH 0 00000000000000000000000000000000090 0 00000000000000000985000000000000000000
57. P008 201X FOREWORD This document is intended to provide requirements and methodologies for conducting level 1 probabilistic risk assessment PRA which is carried out to evaluate the risk of nuclear power plants by evaluating the core damage frequencies due to internal initiating events during power operation This standard was approved and published by the Atomic Energy Society of Japan on the deliberations at the Subcommittee on Level 1 PRA under the Risk Technical Committee of the AESJ Standards Committee AESJ formulated and issued this document after deliberation by the Risk Technical Committee and the Standards Committee PRA of a nuclear power plant is a probabilistic approach for comprehensively and quantitatively assessing plant risk This involves quantitative analysis of accident scenarios up to core damage and of the further evolution of events after core damage with careful attention to events that are related to core or fuel damage finally to arrive at an estimation of event frequencies and consequences The PRA enables the following logical and comprehensive assessment of nuclear power plant risk on the basis of realistic assumptions quantitative analysis of various factors that may impact safety and explicit acknowledgement of uncertainty in assessment results arising from uncertainty in knowledge or data on characteristics and phenomena that conc m nuclear power plants and their components Since the Nuclear Regulatory Commissio
58. ia r3 r3 noo o 8 Ooo deb Ee A s doood o_o lt soog Er 2 5 se Ed oP a 5 meee C3 C3 C3 C3 CALLES C3 C3 C3 C3 C3 c3 DJ gi 02 c c3 E3 E3 E3 E3 E3 C3 C3 C3 CJ E E31 E3 DDD rd CN co YOO 00 O5j N HO HAN oO x CN co io L3 i E r3 E53 a Ao EI O g oO c3 ES Ed EJ EI 1 3 is Oo 4 r3 r3 oo Oo d goo gana Ee o Oooo E ed OOO Boo L3 E3 E3 L3 0 p 5 Sea ao r3 mmm ja taies s r3 pogga m lt a a Been o E e o 35 P008 201X HHHHHHHHHHHHHHHHHH FRAHHHHHHHHHHHHHHHHHHH HHHHHHHHHHHH D 2 HHHHHHHHHHHHHHHHHHHHH 0 2 100000000000000000000000
59. limitations and uncertainties that arise from imperfections in methodology or data and that decision making should also be supported appropriately by non PRA information sources such as deterministic analyses and expert judgments Therefore we placed emphasis on the need to clarify assumptions made in PRA processes and to make explicit statements about uncertainties so that others may be able to make relevant judgments 000 201 0 x HHHHHHHHHHHHUHHHHHHHUHHHHHUHHHHH 2 3 7 TEL 03 3508 1263 0 0 0 000 O O 105 0004 0000 P008 201X 0000 HHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHH 0000000000000000000000000000000000000000000000 0 00000000000000000000000000000000 48 000000000000 0000000000000000000000600000 0 00000000000000000000000000000090000680980000000 0000000000000000000000000000009000000009080000 00000000000000000000000000000900000000000096800 0 00000000000000000000000000004980000000 0 000000000000000000000000000008080 00000000000 0 000000000000000000000000000000 Disclaimer This Standard was developed and approved by the Standards Committee of AESJ in accordance with the Standards Committee Rules which assure fairness impartiality and transparency in the process of deliberating on a standard The Committe 1s composed of individuals who are competen
60. 0 000000000000007000000000000000000000000 0 00000000070000000000000000000000000 139 POO8 201X HHHHHHHHHHH AW HHHHHHHHHHHHHHHHHH 0 0000000000000000000000000000600800 00000 0 000000000000000000000000000090000009680000 HHHHHHHHHHHHHHHHHHH 000 0 0800 00000 XH LLL 000000000000000000000 10000000000 U YOU SO XM 0 0E 000 0 00 000 0000000000000000000000000 YEDI UL HHHHHHHHHHHHHHHHHHHHHHHHHHHH 000000000000000000060000000000000000000 000000000000000000000000900 0000000000000 000000000000000000000000 00000000 lt 9800000000000000059000000 000000000000000000 6 10 State of knowledge correlation SOKC 00 0000000000000060080000000000000000 0 0000000000000000000000095 00070000000 AB 00000000000000000000000000890000000000 0450 0000000000000000000000 00 HHHHHHM LJ EYES EI SEIPGES UE Fey ed E E de ERE IE
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68. 00000 0000 0900000090 0000 0000000 4 000008000000 UUIDAGUDUUDGUDUDUDUDUUHIBDDUDUGUDUDDUGDUGDUUDUUUUDU DUUDDUHDBDDUDIIDDUDDBDDDUDDDUDDUUUUDUUDUDDHDUDUU 0000000900 00000000900000000000000000 HHHH AG 4 000000000 00000000000000000000000000000000000 19000 095 0000000000000000000000000000000 00000000090 000000 000000000000000000000 00008 8 0000000000000000000000 0000 0000000000000000 a 101 P008 201X HHHHHHHHHHHHHHHHHHHHHHHHHHHHUHHHHHHHHH HHHHHHHHHHHHHUHHHHHHHHHHHHHHHHHHHHHHHHH 0 0000000000000000000000000 049850 00000000 0 0000000000000000000000000000 0980 000 1 0000000000 0 0000000000000000069000 40000000098 00000000 LU 0 00000000000000000000009090 0 0 0 0 HHHHHHHHHH HHHHHHHHHH MHHHHHHHHHHHHHHH 00000000 1 ODDO UUDDUUBBLUIDDDUDUUDUGUDUGUDUUUDUUDUDUDUDULU 00000000805 0000 0 0000000000805000040000000 0 0 000 000 000 000 HHHHHHUMHHHUHHHHHHHHHHHHH 3 00000008000 0m00000000 UUDDUDUDBUDDDBDHBHBDDUDBDUDUUDDUDBDUDUGUDUDUDUDUuDBDUUUD 0009000000008080000000000000000000 0009000000000000096 000000980 MED 40 0000
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72. 000000 000008 0000 1 D Swain E Guttmann of Human Reliability Analysis with Emphasis on Nuclear Power Plant Applications NUREG CR 1278 Final Report USNRC 1983 112 P008 201X 000 AI 0000 0000000000000 HHHHHHH10 0000000000000000090000000008098 HHHHHHHH 11 0000000000000 0 000000000000000000000000000000809800000 6 0 000000000000000000000000000000000000090 HHHHHHHHHHHHH 00000000000000008000 080 00000000 2800 1 0 000000000000009080000000000000809000000 HHHHHHHHHHHH 1D 1 50000 00000 U 00 0000 0 00000000000000000000000000990000000000 0000000000850 000 0 00000000090 0980 000000000 0 000000090000000098000000000000000000000 00000000910 0000000008980000000000000000 b 00000 08 0000000000000 ODODE OU D 0000000000000 D D 00000000000000000980 9000000 THERPHHHHHHHH HHHHHHHHHHHHHHHHH 4800000000000000000000000000000000000 00008080000000000000 0000 2 USNRC PROCEDURES GUIDE A Guide to the Performance of Probabilistic Risk Assessments for Nuclear Power Plants Final Report NUREG CR 2300 USNRC
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81. 0000000000000000 D uuu b 4 LOCA WASH MOO 000000000000 LOCAHHHHH 100000 LOCA WASH 14000 0 0 60 000 000 0 LOCAHHHHHH 1380000 1 x 10 1 58 P008 201X 414 1 HHHHHHHHHHHHHHHHHHHHHHH a LOCA L1 OO 1 HHHHHHHHHBWRHH 16 6 0000000000000968000000 LOCA JUUU rwx Prw x ZGSCC 000000808 J 20 0000 Frw UUUUUUUUUUUD Prw 0000000000000008 IGSCCswna IGSCCO 0000 BWRO D D b LOCAHHHHHH WASH 140000 000000000000000B0000 OU HHHHHHHHHHHHHHHH 0 000000000000000008000000000000000000 0 0000000000 8000 NRC 009090008000000000000000 00000 J5 0000000000000040 OU 0 0000000000000000000080800000000 0000000 0 00000000000000000000000808000000000000 HHHH 0000 1 2 3 4 5 J 1 LOCAQG OO00000 NUREG CR 57509 59 P008 201X Lower Bound per reactor Frequency mean per reactor Upper Bound per reactor calendar year calendar year calendar year Small pipe break LOCA PWR This analysis 1 4 WASH 1400 1E 4 NUREG 1150 3E 4 BWR This analysis 1E 4 WASH 1400 1E 4 NUREG 1150 3E 4
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101. 3 Z000 UT BAO O O NUREG CR 44079 0000000005 0000 5000 0000000000 3 0000000000004 0 000000000000608 100000000000000000 000000000 950 00000000000000000000000000 108000000000000000000000000 19000000000 0000000900000 000000000000000000000000 000000000 20100000 9 2 0000000000000000000 0000000000007 00000 57 P008 201X 43 HHHHHHHHHHHHHHHHHHHH a HHHHHHHHHHHHHHHHHHHHHHHHHHH 0 0000000000000000000000000090800000000 0 0000000000000000000000090900808900000 0 00000000000000000000009000000080800 0 000000000000000000000909000000000080 000 b 000000000000 Locagg 0 00000000000000000000000000900 000 00000000000000000000000000000009055 LOCAHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHH HHHHHHHHHHHHHH LOCAH HHHHHHHHHHHUHHHH U 0 00089 000000000000 0000000000009600000060098000000000 0000000000000 09000 LOCAD 099000000 0 00000000009000000000000 Fs H 00088000000000000000000 au O oO OO fs HHHHHHHHHHHH D DL F 00000000000000000000960 B HHHHHHHHHHHHHHH H DUDED WB J 4 LOCA 0000000409000 1 0000000080890000000000009000000000000000 0 0000060800000000000000 0000000000000 098000
102. 5 USNRC Evaluation of Potential Sewere Accidents during Low Power and Shutdown Operations at Surry NUREG CR 6144 USNRC 1995 6 USNRC Improved Reliability of Residual Heat Removal Capability in PWRs as Resol ution of Generic Issue 99 NUREG CR 5015 USNRC 1988 7 T L Chu W J Luckas R G Fitzpatrick W H Yoon A Time dependent Human Reliability Analysis for a PWR PSA 89 8 R E Hall et al Post Event Human Decision Errors Operator Action Tree Time Reliability Correlation NUREG CR 3010 5 1982 9 HHHHHH 0000000000 000000009097000000000 http 990010 00090 0 0 220 40 www jnes go4p content 000015844 pdf GOHHHHHH 00 2100 PSAHHHHHHHHHHHHH 7 000 19080 00030 00 230 10 http www jues go jp content 000117644 pdf 112000009 22 000 000000006 11000 00040 0 0 240 80 http www jnes go jp content 000123426 pdf 121 POO8 201X AM 0000 000000000000000008 HHHHHHH10 000000000000000090000000000080 HHHHHHHHHHHH AM HHHHHHHHHHHHHHHHHH 000000000000000000000000000000009009000 HHHHH HEPHHHHHH 100000000000000000000900 HHHHHHHHHHHH HEPHHHHHAM 2HHHH 0 AM1 0000000000000000000000000 NUREG CR 1278 0 0000 0000090000000000000 Pelei HH HMSHHHHHHHHHHH 1 2 3 4 5 6 9 10 L 1 00
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108. C Rates of Initiating Events at U S Nuclear Power Plants 1987 1995 NUREG CR 5750 INEEL EXT 98 00401 USNRC 1999 USNRC Estimating Loss of Coolant Accident LOCA Frequencies Through the 60 P008 201X 000 K 0000 00000000000000000000 080000 HHHHHHH7 0000000000000000099000000000080 HHHHHHHHHHHHH Ki HHHHHHHHHHHHHHHHHHHHHHHHHH ASME ANS 000000000000000000000808000 HHHHHHHHHHHHH Capability Category CCHI OOO DD UI U HHHHHHHHH 458020 0 0000000 ONUREG CR 45500 B B 0 00 U 0 60 0000 000 000 a 0000000 2800 0 6mHHHHHHHHHHHHHHHHHHH 0000000 0008085000000 b PWRHHHHH uud 0000080 C C 0 00000000000090000000000000 a BWRHHHHH 113000000000009800000000000000000000000 gt 2 500 1371 b EWRHHHHHHHHHHHHHH 00000 0 TAFHHHHHHHHHHHHH DHBDDUDDUDUDUDDUDUDDUGUUDUDUUUDUUDUDUDUUUD gt 2 200 0 1204 G pniuagggumganugagguguguamggugagmmuagug 2180 F mu 61 P008 201X 982 C 000000000000000000 3900000000000 gt 1 200 FT 649 C ASME ANS PRAQ 00 C C IUIII HHC C TH HB DA 0 000000000000000000000000
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112. HH 0000000004 0000000000000000000000000 155 POO8 201X HHHUHHHHHHHHHHHH HHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHH HHHHH18 000000000000000 0 00PRA0 40800000000 HHHHHHHHHHHHHHHH 9 lt 0000000009000808900000 0 000000000000000000000000009090000006808600 HHHHHHH 11 ASME ANS 0000000000000 0888 0 HHHHHHHHHHH ASMEANS 0000000080800 supporting requirements 0 PRADO000000000000 00 00 HHHHHHHHHHHHHHHHHHHHH capability category U 0000000000 000000000000 0000000 100 MOD 000000000000000 09000000000 ASMEANS PRAQ OOO 0 000000000000009600000000000000 0 000000000000000068080000000000004000000 0 000000000000000000068080000000 00000000 0000000000000 1000000908000 0400000000 0 HHHHHHHHHHMHHHHHHHHHHHHHHHHHHHHHHHHHHHH 0 0000000000909680000000000000000000000000 0000000 90000000000 000 L J BE E E J um ESI 0000 1 ASME ANS Addenda to ASME ANS RA S 2008 Standard for Level 1 Large Early Release Frequency Probabilistic Risk Assessment for Nuclear Power Plant Applications ASME ANS 5 2009 ASME ANS 2009 12
113. HHHH 00000 0 00 86 P008 201X 000 X Dg 0000000000 00 00000009 00000000000000000000000000000 00 X1 0000000000 HHHHHHHHHHHHHHHHBWRHHHHHHHHHHHH CSE HHHHHHHHH PWRHHHHHHHHHHHHHHHHHHHHHHHH XA X 2 87 P008 201X CS ALBO digi Cs L1 O X1 0000000000004 00000000000 R gt EARRA D 8B BEATA BHE x2 HHHHHHHHHHHHHHHHHHH PWRH 88 P008 201X OOO Y 0000 0000000006000 00000009 00000000000000000 HHHHHHH HOODOO Yi HHHHHHHHHHHH HHHHHHHHHHHHHHHHHHHHHHHHHHH 00000000 Q Q DU D D DAD U U 0 1 lexp 47 1 41 12 D AT lt lt 1H 1 00 0000002000000 U uuu 0000 89 P008 201X HHHHHHHHHHHHHHHHH To 0000 000000 1 000000000 7000000000 000000000000000000000000000000090 00000 e HHHHHHHHHHHHHHHHH um T rs 4 x T D uu 000001 T 000000008 HHHHHHH 0 0000000000000000000000001 0
114. HHHHHHH LOCADA LOCA UO 08 08 00 D LOCAHHHH LOCAHHHH LocADODanpanL upt LOCA HOODOO 00000 000 Dh LOCA 000 00000000000000000000000000000000 0000000000000000008901000000000000000 LOCA 0 000000900000000000908000000000 000000000000800000000000000808000000 000000000 000 LOCA 0 0000000000000000000090000070 LocAn U 000000000000000000000006908 00000 00000 Loca 000000900080000000000000000000000000 LOCA d H LU D D UD 000900000000000000980000000000000000 00009080000000000000000000000000 ECCS 00000008080000000 0000000000068 00 0 00 0 00 0 00 0 00 0 0 HHHHHHHHHHHHHH A HHHHHHHHHHHH Loca ASE 0000000000000000000000000000000000 190000804 00000000000000000000000 LOCAHHHHH 00000000903 0000000000000000000000000000 0000 000000000000000000000000000000000000 00980 0000000000000000000000000000000000 49 P008 201X HHHHHHHHHHHHHHHHHHHHHHHHHHHHHH 1 HHHH 0 0000000000000000000000009080000000 000 50000000000000000000900080500000 0000000000000000000000 9600000000000000 0000000060000 00000000000
115. HHHHHHHHH 0 00000000000000000009090000000010000000 0 0000000000000000000 0002 80000000000000 000 000 105 00000000 000000 10 5 1 0000000190809 U D B D B D B DI 5 0 000000400000808000000000000000000000 00000 106 10 61 0000000000 HOODOO 000000000000000000 000000000000000000006000 800000000000000000000000000000000000 0098000000000 0000680980 0000000000 0000000 1062 HHHHHHHHHHH HHHHHHHHHH 01980 000000000700000000000000000000000000 20 P008 201X 0 000000000000000000000000000000000000 HHHHHHHHHHHHHHHHHHHHHHHHH 000 107 HIHHHHHHHHHHHHHHHHH 10 7 1 00000000000 00000000000000000000000009000000080800 HHHHHHHHHHHHHHH 0000000000000000000000000 78 0000000000 600000000000000 000006 ALD O U U THERP HHHHHHHHHHHHHH HHHHH9 00000000008000 000 10 72 HHHHHHHHHHHHHHHHHH 000000000000000000000000000000000009090 000000000000000000098000000000000000000 000000000 10 7 3 000000000 0 0000000000000009900000000068098000000000 0000000 00 90 09000000000000000068000000 000 000 0 000000000000000000068080000000 00000000 D THERP 0 000 0000000000000000000000989
116. HHHHHHHHHHHHHHHHH 198000000000000000 200 0 0 2400000000 24000000 0 000000000000000900000000000000009800000 HHHHHHHHHHHHHUHHHHH HL 0 2 HHHHH 4000000000000 PWRHHHHHHLOCAHHHHHHHHHHHHHH 3087000000000 HHHHHHHHHHHMWHHHHHHHHHHHHH24HHHHHUHHHHHHHH p 00 23809 0000000000000 68 P008 201X L3 r3 r3 r3 0000 00000 00000007 0000900000 0000000000600 HHHHHHHHHHHHH 000000000000000000000000000000080 HHHHHHHHH HHHHHHHHHHHHHH DU Uu HHHHHUHHH 69 P008 201X 0000 0000 00000000000 00 00000008 0000000000000000098000000000080 000000000 9 1 00000000000 000000000000000000000000000000009009000 000 HHHHHHHHHHHHHUHHHHHHHM 0 000000000000000900098000000000000000 000000000000000909000000098000000000000 0 000000000000009000000000000968000000000 0 00000000000096000000
117. HHHHHHHHHHHHHHHHH AND 00 000000000000000 0 000000000000000000000 70008500 Ag 20 20 00000 0 00000000000000 40 748c 0 00000000000 A400 00 110000000 F TABO T OFgO FG oo o v vo v v AR 1 0000 0000 00 0 000000000000000009600000000000000000000 0090000000000000000000000000000000 1 000800000000000000000000000000000000 000000080800000000000000000000000000 HHHHHHHHHHHH MkHHHHHHHHHHHHHHHHHHHHHHH HHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHH L LET E D Fale E c EI 128 P008 201X 000 0 00000000000000000000000000000000000 HHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHLH NAND 00000000000000000000000000009000000000 HHHHHHHHHHHHUHHHHHHHHHH AR3 HHHHHHHHHHHHHHH 0 00000000000000000000000000000000000000 00000000000000000000 00000000000000000000000000080800000000 000000000000000000000000000000080800000 00000
118. HHHHHHHHHUHHHHHHHH 0 00000000000000000000000000000000000 0 00000000000000000000000009080000000 0 0 LEES UUIDDUDDUDBDUDUDUDUDUDUDDUDUUDDUDUDBDBDUBHBUDUDUUDBHHL 00000000000000000000000900000 0000000000000000000000 955 9000000000000 0 0000000000000000000000009600000000000 0000000000000 00000000000 0000000 0000000 00000000000 0000000 00 0000000009950 HHHHHH CRHHHHHHHH 0 000000000000000900000000980 000000000 0 00000000000000989000000000 898 0 000000 0 0 0 E E EE EE m Ei E E I EEE EE EE EE EIE E E ELAR ENE EJ EX E 00000000000000080800000000000000000 HHHHHHHHHHHHHH CROCUS 05000000004100000 0 000000000000000000008080000000000 PRAHHHHHHHHHHHH 9 CRHHHHHHHHH 000000 000000000000000000000000 0000000 U 2 2 ECCSHHHHHHHHHHHTHH WECS 0000000000000 000000 2 20980 0000000000009000000000 Eg EST EA Fey Ey EC L HHHH ECCSHHHHHH ECCSHHHHHH 000
119. HUN 000 000 AESJ SC P008 201X 000000000 0 0 00000008 00000000 0690000000 201X 201X X 0 00 0000000 P008 201X 0000 HHHHHHHHHHHHHHHHHHHHHHHHHHHHHHHH HHHHHH 1PRA 0 M HHHHHHHHHHHHHHHHHHHHHHHHHHHH RRA 0808000000000 000000000000000000000000000000910000068098000000 0 0000000000000000000000000000990000000000909000 RAHHH HHHHHHHHHHHHHHHHHH 10 00000000000008 HHHHHHHHHHHHHHHHHHHH HHHH 0000000000000000000000904900000000 E L1 LT ES TRIES 00000000000000000000000080800000000000000 0000 00000 970000000000 000000 WASH 1400 0000000000 UUDUDUDUDUDDDDUUDUDDDUDUUDUUUUDBUBDBDUDUDDDDUDUDDDUHUUUUuUUUDU 2010 0 00000 DUUDUDUDUDUDDDDUDDDUDUUDUDUDBUDUDUDDUDUDHDBBDDBUUUDUDDUDDDUDUUD 0 000000000000000000000000000900 8 0000000000 Endy E ES ES E p E p L3 Ez 3 EE ET ET E E eae ESL EIE TESI em EST ET E ESI ES ET Tl end 0000
120. Nuclear Power Plant Applications NUREG CR 1278 Final Report USNRC 1983 124 P008 201X Ao 0000 0000000000000000000009000 HHHHHHH10 000000000000000040000000000080 HHHHHHHHHHHHHHHHHHHH 1 HHHHHHHHHHHHHHHHHHHHHHHHH 0 0000000000000000000000000000000090 HHHHHHHHHHHHHHHHHHHHH b 0000000000 o 000000000000000000 0000000000 e 00000000000000 1000000000000 g 0000000000000 h 000000000000000000080 HHHHHHHHHHHHHHH j 0000000000000000000000000805 0000000000 000000000000000000000000000 000000000009890901000000000000000000000000 0 000000000900000900000000000000000000000 0 000000099000000000900000000000000000000 000000006 125 POO8 201X AP 0000 IlHHHHHHHHHHHHHHHHHHHHL HHHHHHH10 HHHHHHHHHHHHHHHHHHUHHHHHH HHHHHHHHHHHHHHHHHHHHHHHHHHH 0 00000000000000000000000000000000690 0 00000000000000000000000000000000000090 HHHHHHHHHHHHHHHHHHHH HHHHHHHHHHHHHHHHH HHHHHHHHHHHHHHHHH 126 POO8 201X 0000 000000000000000008 00 00000001 000000000000000090000000000080 HHHHHHHHHH AQ1 HHHHHHHHHHHHHHHHHH 0000000000000000000000000000000090900 a 00000000000 00000000 0000000004850 00000000000000000 000000000 2009 http www nucia jp jfiles rehability REPORT200905 pdf 000000 000000000000000000 0980 00000000
121. O DSSS SSS 153 8 D0D0D0000000000 oe 153 9 NN 154 10 0000000000000000 9251 0 0 0 0 154 11 ASME ANSPRAHHHHHHHHHHHHMHHHHHH 4 155 12 0000000000000000000000 gt M 155 4 1 P008 201X EE EE HHHHHHHHHHHHHHHUMHL IIHHHHHHHHHHHHH HE 3PRA T 201X A Standard for Procedures of Probabilistic Risk Assessment of Nuclear Power Plants during Power Operation Level 1 PRA 201X 1 0000 0 0000000000000000 0453 0000000000000000 Probabilistic Risk Assessment PRAD MO 0 HHHHHHHHHHHHHHHHHHU HH 00000000000 OOMOO 2 0000000000900 0000053 00000 00000 000 2 0000 HHHHHHHHHHHMLHUHHHHHHHHHHHHHHHHHHHHHHHH AESJ SC RK0032001 MHHHHHHHHHHHHHHHHHHHHHHHH U US DELU 2011 AESJ SC RK001 2010 00000 000000 2010 3 000000 000000000000809802 000000000000000000000 0000000002 00000009060 9000000 10000 3 1 OOOO DH 8 2 0000 HHHHHHHH 1 0190000000 20000000 3 3 2 P008 201X 0000
122. PRA 4 De 00 050 1970 PRA 1990 0 0 1 2000 0 UB uH DU 2002 HH A ho IPRA O00 PRAE TR DE 201030 11 UH 098 0 3 Tb TS DH 1 RU PRA Ooo H PRA 900000 0 TH Woo 0960 PRA AL 001 1 o O ma mn HH u LL 201X X 1X P008 201X HHHHHHHHHHHHHH 0000 00000 000000000 D 20X0 xp XII U x r3 T E Cm 1 L3 oO o g oo oo oo i EE E yu E E g J E EJ E Pot OGY Ye Base acces W N om o Moods Q FA 2 6 H ooo cc ood El CES CA oo rrr ue E twEBSN o no rA Es Se Se eS o o o EX Epor ES t GF 0 rz ESI SES ES nm ES oo ee EE tI t Ea oo oo HE ea Se EE ee 12 eh Er TE r er E CEDE ee
123. SC of the AESJ is preparing a procedures guide for nuclear facilities Differences in the coverage of indices used in assessing the consequences of events translate into the differences among PRA levels Level 1 PRA covers estimation of core damage frequency Level 2 PRA goes further to the estimation of containment failure frequency and estimates th amount and timing of radioactive releases to the environment source term estimation and Level 3 PRA addresses the frequency and scale of impacts on the public and the environment In view of the broad areas of PRA the AESJ took a stepwise approach for developing PRA standards commensurate with the needs and maturity of PRA methodology in Japan As set forth herein this standard replaces the 2008 issue A Standard for Procedures of Probabilistic Safety Assessment of Nuclear Power Plants during Power Operation Level 1 PSA 2008 of the same standard We decided to make this amendment because five years have passed since the 2008 issue was published For the present amendment we updated various requirements in view of advancements in PRA techniques and to improve the quality and transparency of PRA We worked on amending the Implementation Standard for Probabilistic Risk Assessment of Nuclear Power Plants during Power Operation in recognition of the fact that whenever one uses the results of PRA in decision making it is iii P008 201X very important to do so while fully recognizing the
124. US 08000000004 0000000 0 00000000000000000000000808000040000 7 0000000 7 1 0000 00000000090000 0980 000000000000000000000 000000000900000000 0980 000000 00000 007000 00000 b HHHHHHHHHH 0 000000000000080807000000000 72 HHHHHHHHHHHHHHHH 724 10000000000 Dupnumgmgapnnugnagapnupnunupnuong 000000000000000 00000000000000000 2011 00000000000 0000000000 0900 0000000000000000000000000 00000000000 1200 1 00000 00000000 0000000000 UUHDBLDDDDUDUDDUUDUDBUUDUDUUDDUUUDUDBUUUIDDUU HHHHHH 10 P008 201X HHHHHHHHHHHHHHHHHHHHHHH 000 722 HHHHHHH HHHHHHHHHHHHHHHHHHHHHHHH8 0000D C0 0 TDW HHHHHHHHHHUHHHHHHHHHHHHHHH 0 00000000000000000000000098000000000080 0000000000000000006000 HHHHHHH 000000 0000000000007 0000000000000 000 72 3 HHHHHHHHHHHHHHHHHHHHHHH 0 000000000000000000098000000000000000000 0 000000000000000000090900080000 0 00000000000000009800000809800000000000 0 0000000000000000989000000000 9800000000 0 0000800000 0 00000000000000000808900000000000000000 000000 000 000000000680800000000410000000 000 73 0000000 7 3 1 0000000080000 0 0000000000909680 000000000000000000000000 0000000000090000 0980 000000000000
125. cuum 26 26 Steam generator leakage 27 0000000 27 Condenser leakage 38 20000080 28 Miscellaneous leakage in secondary system 29 000000009 29 Sudden opening of steam relief valves 30 HHHHHH 30 Loss of circulating water 31 00000000 31 Loss of component cooling 32 000000000 32 Loss of service water system 33 0 0000000000000000 33 Turbine trip throttle valve closure EHC problems 34 0 00000 34 Generator trip or generator caused faults 35 Loss of all offsite power 36 000000000 36 Pressurizer spray failure 37 000000800 37 Loss of power to necessary plant systems 38 0000000 hE U 38 Spurious trips cause unknown 39 0000000 39 Automatictrip no transient condition 40 40 Manual trip no transient condition 4 0000 41 Fire within plant 42 P008 201X 1 ER Lo 2 HEAD x 3 LES H Jap FRAMED bus sis uite ba RNA aa SHE ic
126. may be reproduced in any form witho AESJ en permission of Copyright O 201X Atomic Energy Society of Japan All Rights Reserved P008 201X HHHHHHHHHHHHHHHHHHHHHHL ma 00900 DD PG 04 Oho Dn 0106 0 na 1106 0 g 106 00 JB rim U HH 2011 3 11 DELL Da n 1000 DO 000 HH DOO theo 201X X P008 201X 00000000000000
127. n Wody Epstein 0 OO HH 0000000 Scandpover 1 rc HHHHHHHHHHHHH 0 00000000 2400090000000 0000000000000 0 0000000080000 09000000 0000000000 00000 00000009000 LI xi P008 201X 000 1PRAQ OU 000000000 201X X D 0000 000 HH HH 0000000000 0 02000000008 00 000000 0000000 00 0 00 00 HH 0000000000 HH 0 HH 00000 HH 0000000000 00 000000 HH 0900 D 00 HH 00 GE 0 HHHHHHHHHH HH 000000000 HH 000000000 0000000000000 000000000 0000000000 00000 HH HHHHHH 008000000 HHHHHH 000000000 HH 000000 0100 00 HH 000000000 HH 00000 00 00000 00 00 00000 00 00000 HH 0 POO8 201X 0000000000 UU 0 0000000000000000000000000092000000805 0 00000000000000000000000000900000000000 0 0000000000000000000000009090000000000 LU 0 000000000000000000000000000009050000000 00000000000000000000000000000000009060 000 0 00000000000000000000000000000000000090900 0 0000000000000000000980000 00000000000000000900008000000000000000 0 0000000000000000099000006980 mur L3 Co
128. n of the United States introduced the concept of PRA in its publication The Reactor Safety Study WASH 1400 in 1975 many efforts were made worldwide to develop PRA techniques apply the PRA methodology to actual cases and conduct application studies As a result PRA today is well recognized as an efficient methodology to assist decision making in safety regulation as well as in the related fields of safety engineering operation management etc In addition Fukushima Daiichi nuclear power plant accident that occurred in March 2011 was caused by loss of multiple important safety functions due to common cause failures induced by tsunami inundation into the reactor building The PRA is also a very valid method for analyzing the impact of common cause failures of functions important for safety that could severely affect the integrity of the reactor core and the containment In Japan PRA has been implemented to evaluate the validity of Accident Management Strategies and the quantitative safety of NPPs in the Periodic Safety Review Furthermore in the regulatory area the Nuclear Regulation Authority which is the new regulatory authority founded in 2012 intends to utilize PRA in their new safety regulation positively As the validity of PRA lias come to be accepted preservation of the quality and transparency of PRA has become important issues Recognizing that preparation of a standard for PR A procedure is effective in addressing these issues the
129. rol failure increasing flow 15 HHHHHHHHHH 15 Recirculation control failure decreasing flow 16 0000000000 10 16 Trip of one recirculation pump 1 0000000000 00 17 Trip of all recirculation pumps 18 000000000 18 Abnormal startup of idle recirculation pump 19 000000000 19 Recirculation pump seizure 20 000000 00000 20 Feedwater increasing flow at power 21 000000 21 Loss of feedwater heater 22 22 Loss of all feedwater flow 28 DDD DD 23 Trip of one feedwater pump or condensate pump 24 000000 24 Feedwater low flow 25 QOO00CGODO O00000 25 Low feedwater flow during startup or shutdown 26 00000 000000 26 High feedwater flow during startup or shutdown 27 0 27 Rod withdrawal at power 38 U U 28 High flux due to rod withdrawal at startup 29 29 Inadvertent insertion of rod or rods 30 00000000 30 Detected fault in reactor protection system 831 430 00000 81 Loss of offsite power 32 D 32 Loss of auxiliary power loss of auxiliary transformer 332 000090900000000000 33 Inadvertent startup of HPCI HPCS 34 DBHEUSGEHHES ULDEUtlULlL 34 Scram due to plant occurrences 35 0000000000000 35 Spurious trip via instrumentation RPS fault 36 000000 36 Manual scram no out of tolerance condition 37 6000 37 Cause unknown 41 P008 201X 0 F4 FEWRHHHHHHHHHHH
130. s with Emphasis on Nuclear Power Plant Applications NUREG CR 1278 Final Report USNRC 1983 110 P008 201X HHHHHHH10 000000000000000905000000000000 0 000000000000000000000000000890 000000000000000000000000000000060 0000000000000000000000000000000000008 HHHHHHHHHHHH 0 00000000009000098000000000000000 000000000 0980 00000000000 0000000000000000 DED HHHHHHHUHHHHHHHHHHH 000 01 000000000000000000000000 111 POO8 201X O 1 00000000000000000000000000000000 NUREG CR 1278 9 000 BH UH UB UU 000000000 0000000000600 LU DU D D 090 HHHHHH HHHHHHHHHH Dependence 1 or 10 RO 2 10 RO SROU SS seem RO TH HD 3 50 RO SRO RO HD eeu abated a ROO D SROHH LDH MD 1000000 40 4 150 RO SRO AF 8 RO L HD ss M ROG M SROO H LDO J MD STA AM o 0 SR HH LDHH MD 00000000000 ROO O 800 D HDHH CD 1000000 0 010000000 0 O ROH O Reactor Operator SRO U Ul Senior Reactor Operator SSI 0 Shift Supervisor STAD 0 0 E O D Shift Technical Advisor AOH 0000 O Auxiliary Operator HDO 0 O High Dependence CDH 0 0 Complete Dependence MDH 0 0 0 Moderate Dependenc LDH 0 O Low Dependence 00400 5000000000000008000000000000
131. t or interested in the subject and elected keeping the balance of organizations they belong in the subject with their professional affiliations well balanced as specified in the Rules Furthermore the standard proposed by the Committee was made available for public review and Comment providing an opportunity for additional input from industry academia regulatory agencies and the public at large AESJ accepts the responsibility for interpreting this standard but no responsibility is assumed for any detriment caused by the actions based on this standard during onstruction operation or decommissioning of facilities AESJ does not endorse or approve any item construction device or activity based on this standard AESJ does not take any position with respect to the validity of any patent rights or copyrights claimed in relation to any items mentioned in this document nor assume any liability for the infringement of patent rights or copyrights as a result of using this standard The risk of infringement of such rights shall be assumed entirely by the users The Committee acknowledges with appreciation the participation by regulatory agency representatives and industry affiliated representatives whose contribution is not to be interpreted that the government or industry has endorsed this standard P008 201X 000 HHHHHHHHHUHHHHHHHHHHUHHHHHHHHHHUHHHHHHHHHHHUHHHHH HHHHHHHHHHHHHHHHHHHHHHHHHH Copyright No part of this publication

日本原子力学会標準原子力発電所の出力運転状態を対象とした確率論

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日本原子力学会標準 原子力発電所の出力運転状態を対象とした 確率論

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日本原子力学会標準原子力発電所の出力運転状態を対象とした確率論