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1 2001 ICRP60 Radiological Consequences from KNGR Design Basis Accidents Based on the Framework of Alternative Source Term and ICRP60,, 3609 NRC DBA TID14844 Regulatory Guide 14, 125, 177 NUREG1465 Regulatory Guide , NUREG ICRP ICRP60 DBA ICRP60 ICRP60 DBA Abstract In 1995 and 2000, NRC issued the accident source term of NUREG1465[ and Regulatory Guide 1183[2], as an alternative source term (AST) to TID14844[3] and Regulatory Guide 14[4], 125[5], and 177[6], to assess radiation dose from design basis accidents (DBA) The alternative source term of NUREG1465 was developed as a representative source term to reflect the insight of a few ten years research on severe accidents ICRP did an important role to develop and to change the standards on radiation protection In 1990, ICRP published ICRP60[7] as a baseline to assess radiological effects on human body and published succeeding ICRP recommendations The methodology to assess the radiation exposure to human body has been changed with improvement of knowledge on interactions between radiation exposure and human body In Korean Next Generation Reactor (KNGR) Project, the framework of AST and ICRP60 is being applied to assess radiation doses from DBAs In this paper, the radiation doses from DBAs were estimated based on the different frameworks of accident source term and dose assessment The results were compared each other and the design margin of KNGR was evaluated 1

2 1 NRC DBA SLB) TID14844 Regulatory Guides 14, (Feedwater Line Break, FWLB) NUREG1465 Regulatory Guide 1183 (RCP Locked Rotor, RCP LR) , (Control Rod Ejection NUREG1465 Accident, CEA) LOCA (Letdown Line Break, LDLB) (S/G Tube Rupture, SGTR) (LOCA) (Fuel Handling ICRP 1990 ICRP Accident, FHA) ICRP60 DBA ICRP60 ICRP60, DBA, ICRP60 2 DBA,,,,,,, (Exclusion Area Boundary, EAB),, LOCA, (DBA), DBA (Steam Line Break, 21 DBA LOCA 2

3 & Q in = f rel, Q in f rel A core A core : : : 3 NUREG, ,,, 2 1 LOCA 22 NonLOCA NonLOCA NonLOCA C rcs A = Fpp( f fm + f ff f gap) M C rcs = F pis C rcs TS core rcs + C rcs TS, F pp, F pis Power Peaking Factor Iodine Peaking Factor C rcs, C rcsts Tech Spec M rcs NonLOCA Reg Guide 125 Reg Guide 177 (TID14844 Reg Guide 14) NRC NRC NUREG1465, NUREG ,, LOCA22,, 21 LOCA TID14844 Reg Guide 14 SRP 15 NUREG1465 Reg Guide 1183 SRP 1501

4 22 LOCA PWR BWR PWR, BWR 100% 100% ( ) 100% 50% % 4 % 5 % 100% 40% 30% (Cs, Rb) 485 % 015 % 95 % 4 ANSI/ANS 565 SRP652 NUREG/CR 5966 NUREG/CR NonLOCA Kr85 10 (30) % NG 10 % I % ( 10 % ) ( / ) D 2] off, in = ( x / Q) off BR ( Fi, in Qi ) i RG 125 RG 1183 RG 177 D off, ex = ( x / Q) off ( Fi, ex Qi ) i 91 % 4 % 5 % 9975 % 025 % ( / ) 10 % 5 (10) % 8 (10) % 5 (10) % 12 (0) % 485 % 015 % 95 % 97 % 3 % FHA 2] CEA TID14844 NUREG1465 NRC NUREG/CR5966[8] NUREG/CR6189[9] (18hr) NonLOCA23 (Cs, Rb) 22 DBA ( (EAB), (LPZ)) D off,in, D off,ex : D on,in, D on,ex : F i,in, F i,ex x/q off Q i BR : i ( ) ( ) : : i : DBA,,

5 DBA 25,,, I 132E (ICRP) ICRP ICRP 24, DBA TID14844 RG 14 RG 1109 ICRP30 EPA FGR No11 EPA FGR No12 ICRP68 ICRP71 ICRP72 ICRP74 = Cs136 Cs137 I 131E I 133E I 134E I 135E I 131O I 132O I 133O I 134O I 135O I 131P I 132P I 133P I 134P I 135P Rb 86 Cs134 Cs136 Cs137 TID14844 RG 1109 [12] FGR No11 [13] ( : rem/ci) ICRP68 [14] ICRP71 [15] 148E E E E E E E E E E E E E E E E E E E E E E E+04 E : elemental, O : organic, P : particulate 740E E E E E E E E E E E E E E E E E E E ( : remm 3 /Cisec) RG 14 FGR ICRP72 RG 1109 No12 [16] [17] ICRP9[10] ICRP26[1 ICRP60 (1959) (1977) (1990) KR85M KR85 KR87 KR88 XE131M XE133M XE133 ALARA XE135M XE135 XE138 I 131E I 132E I 133E I 134E I 135E I 131O I 132O I 133O I 134O I 135O I 131P I 132P I 133P I 134P I 135P Rb 86 Cs E02 425E02 308E01 751E02 151E02 315E02 970E03 225E02 590E02 131E01 249E02 558E04 196E01 484E01 502E03 104E02 113E02 108E01 616E02 274E01 951E02 565E01 151E01 651E01 389E01 178E02 389E01 542E01 584E01 277E02 440E04 152E01 377E01 144E03 507E03 577E03 755E02 440E02 213E01 673E02 414E01 109E01 481E01 295E01 178E02 280E01 392E01 448E01 M : meta stable, E : elemental, O : organic, P : particulate 253E02 942E04 146E01 360E01 137E03 471E03 514E03 685E02 411E02 201E01 5

6 3 DBA 4 DBA DBA DBA ICRP [18] 41 TID14844 Reg Guide 14 DBA DBA 41 3 [19] 41 Case A 9812 [20] [2 ICRP60 (Whole Body Dose), ) ICRP60 ( ) (Total 31 DBA Effective Dose Equivalent) 10CFR NUREG1465 (LOCA) RG 1183 Case C (Total Effective SRG 15 RG 1183 Dose) (NonLOCA) SRP 1501 SRG 15 RG 1183 (, SRP 1501 ) ( ) 2000 Reg (EAB) Guide SRP 15 DBA ICRP60 [22], DBA 2 (Thyroid Dose) Case B (1997 Case C 6 EAB (0

7 2hr) : 892x10 4 sec/m 3 : 015 vol%/day NonLOCA, Case B C Iodine Spiking, Tech Spec LOCA Case (Spray Removal Case A RG 14 ICRP9 Case B RG 1183 ICRP26 Containment Mixing)22 Case A SRP652 Case C RG 1183 ICRP60 Case B Case C NUREG/CR5966[8] STAR NAUA 42 NonLOCA RCS>SG> SG Dried Undried Tube 1 Flashed : 1 Unflashed : NonLOCA 2 RCS> 43 [23,24] LOCA STARDOSE [25] Flashed : 1 RCS> Unflashed : 100 Case A 2, SFP> 500 Case B Case C 1 2, NonLOCA 2 Case C FGR No12 42 CEA DBA 540 LDLB , SGTR 44 EAB 42 Case A NonLOCA, DBA ( 2 ) RCS (%) (lbm) SLB(FP) RCS>SG SLB(ZP) 2] RCS>SG FWLB RCS>SG RCP LR RCS>SG RCS>CTMT RCS>SG RCS>Env RCS>SG SGTR(LOOP) RCS>SG RCS>SG (LOOP+SF) FHA 3] E+05 SFP>FHA FP : SLB during Full Power Operation 2] ZP : SLB during Zero Power Operation 45 3] FHA

8 44 DBA Case DBA (Ci) 2] LOCA SLB(FP) FWLB CEA SGTR(LOOP) Case A Case B Case C Xe E E E E E+04 I131E 109E E E E E+01 I131O 184E E E01 580E E+00 I131P 629E+01 Cs137 Xe E E E E E+04 I131E 320E E E E E+01 I131O 555E E E E E+01 I131P 623E+02 Cs E E E01 200E03 676E01 E : Elemental, O : Organic, P : Particulate 2] 2 (LOCA 2 ) 41 DBA 8

9 45 DBA / (rem) (rem) (rem) DBA Case A Case A Case B Case C LOCA SLB Full Power Zero Power FWLB RCP LR CEA LDLB SGTR LOOP LOOP+SF FHA Case A (Thyroid Dose) % of Criteria Case A (Whole Body Dose) Case B (TEDE) Case C (TED) DBA 42 DBA 9

10 445 LOCA NonLOCA, Case A LOCA ( ), SLB SGTR(LOOP+SF) Case B Case C DBA Case A RCP LR, CEA, FHA DBA (, ) Case B Case C Case B 25 ICRP26 NUREG1465,, Case C LOCA NUREG1465 Case B LOCA LOCA ICRP60 ICRP26 LOCA RCP LR CEA Case A case B ICRP60 ICRP 60 DBA TID14844 ICRP9 ICRP60 ICRP60 NUREG1465 Non LOCA, LOCA TID14844 LOCA NUREG1465, NRC 10

11 6 1) NUREG1465, Accident Source Terms for Light Water Nuclear Power Plants, US NRC, ) Regulatory Guide 1183, Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors, US NRC, ) TID14844, Calculation of Distance Factors for Power and Test Reactor Sites, US AEC, ) Regulatory Guide 14, Assumptions Used for Evaluating the Potential Radiological Consequences of a Loss of Coolant Accident for Pressurized Water Reactors, Rev2, US NRC, ) Regulatory Guide 125, Assumptions Used for Evaluating the Potential Radiological Consequences of a Fuel Handling Accident in the Fuel Handling and Storage Facility for Boiling and Pressurized Water Reactors, US NRC, ) Regulatory Guide 177, Assumptions Used for Evaluating a Control Rod Ejection Accident for Pressurized Water Reactors, US NRC, ) ICRP Publication 60, 1990 Recommendations of the International Commission on Radiological Protection, ICRP, ) NUREG/CR5966, A Simplified Model of Aerosol Removal by Containment Sprays, US NRC, ) NUREG/CR6189, A Simplified Model of Aerosol Removal by Natural Processes in Reactor Containment, US NRC, ) ICRP Publication 9, Recommendations of the International Commission on Radiological Protection, ICRP, ) ICRP Publication 26, Recommendations of the International Commission on Radiological Protection, ICRP, ) Regulatory Guide 1109, Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I, US NRC, ) Federal Guidance Report No11, EPA , "Limiting Values of Radionuclide Intake and Air Concentration and Dose Conversion Factors for Inhalation, Submersion, and Ingestion", US EPA, ) ICRP Publication 68, Dose Coefficients for Intakes of Radionuclides by Workers, ICRP, ) ICRP Publication 71, Agedependent Doses to Members of the Public from Intake of Radionuclides : Part 4 Inhalation Dose Coefficients, ICRP, ) Federal Guidance Report No12, EPA402R 93081, "External Exposure to Radionuclides in Air, Water, and Soil, US EPA, ) ICRP Publication 72, Agedependent Doses to Members of the Public from Intake of Radionuclides : Part 5 Compilation of Ingestion and Inhalation Dose Coefficients, ICRP, ) ,,,, ) (III),, ) 9812,,, ) ,,, ) KNGR(III), N001END461001, Technical Report : New Source Term Study Report, RevA, KOPEC, 10/30/ ) KNGR(III), Memo from KOPEC/NSSS to KOPEC/AE, NND/ES00064M, 3 Offsite, 11/07/ ) KNGR(III), Memo from KNFC to KOPEC/AE, NFD/ES00087M, 3 Dose Analysis, 11/02/ ) STARDOSE User Manual, Rev0, Polestar Applied Technology, Inc,

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