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1 유럽요건충족방사선방호설계고려사항 2013 KINS 안전기술정보회의 이승기

2 Contents I. 개요 II. 유럽원전방사선방호설계요건 III. 설계개발현황 2

3 I. 개요 3

4 I. 개요 개발목표 유럽사업자요건 (EUR) 을충족하기위한 개발 EUR 협회설계인증 (DC) 취득 유럽권원전수출을위한노형개발 주요방사선방호설계개발항목 정상운전 (DBC 1) 방사능방출기준충족설계 예상운전과도 (DBC 2), 설계기준사고 (DBC 3,4), 설계기준초과사고 (DEC) 및중대사고 (SA) 방출허용기준충족설계 중대사고표준방사선원항개발 출력운전중원자로건물접근설계 유럽기준차폐및환기계통설계 해체고려설계등 4

5 II. 유럽원전방사선방호설계요건 5

6 II.1 DBC 1 허용기준 EUR (EUR ) Release Limits (DBC1) Liquid (other than H-3) : 10 GBq Gaseous -Noble Gases : 50 TBq -Halogen & Aerosols : 1 GBq YVL (YVL ) Release limits Limits for each nuclide should be defined bas ed on dose limit i of msv/y Korea (MEST Notice No ) Release limits There are nuclide-specific concentration lim its applied at the EAB Dose Limits (due to direct radiation) Individual < 0.01 msv/y 1/30 occupancy at 100m 1 occupancy at 300m Dose Limits (due to external and internal) Individual < 0.1 msv/y (per site) < 0.01 msv/y (per unit) Collective : should be evaluated for 500 yea rs for long-livedlived nuclides (YVL 7.2) Collective doses should include all operations including waste handling and disposal as well as storage and transportation of spent fuel in Finland. Dose Limits for Single Unit Gaseous effluents - Gamma air absorbed dose < 0.1 mgy/y - Beta air absorbed dose < 0.2 mgy/y - External whole body dose < msv/y - External skin equivalent dose < 0.15 m Sv/yr - Equivalent dose < 0.15 msv/y Liquid effluents - Whole body dose < 0.03 msv/y - Equivalent dose < 0.1 msv/y Dose Limits for Multi-unit site Whole body dose < 0.25 msv/y Thyroid equivalent dose < 0.75 msv/y 6

7 II.2 DBC 2 허용기준 EUR (EUR ) YVL (YVL ) Korea Release Limits (DBC2) Dose Limits (due to external and Release limits internal) None Liquid (other than H-3) : 10 GBq Gaseous Individual dose < 0.1 msv/event - Noble Gases : 50 TBq Global Collective dose < 5 man Sv/GWe - Halogen & Aerosols : 1 GBq for 500 years (YVL ) Combination of DBC 1 and DBC 2 shall meet the above criteria (EUR Rev.D, 2012) Dose Limits (due to direct radiation) Individual < 0.01 msv/event 1/30 occupancy at 100m 1 occupancy at 300m 7

8 II.3 DBC 3&4 허용기준 EUR YVL Korea DBC 3 (Frequency 10-4 <f<10-2 ) Postulated Accident (Level 1) Postulated Accident (Frequency 10-3 < f <10-2 ) (Dose at EAB and LPZ) No action beyond 800m (Xe-133, I-131, Cs-137) : 1 msv Individual dose < 1mSv LOCA : 250 msv Collective dose shall be analyzed SGTR - Fuel damage orpis : 250 msv Limited economic impact (I-131, Cs-137) - GIS : 25 msv I-131 < 10 TBq for ground release MSLB < 150 TBq for elevated - Fuel damage or PIS : 250 msv Cs-137 < 1.5 TBq for ground release - GIS : 25 msv < 20 TBq for elevated RCP Locked Rotor : 25 msv Rod Ejection : 63 msv DBC 4 (Frequency 10-6 < f <10-4 ) Postulated Accident (Level 2) Fuel Handling Accident : 63 msv No action beyond 800m (Xe-133, I-131, Cs-137) : 5 msv I-131 < 10 TBq for ground release < 150 TBq for elevated Cs-137 < 1.5 TBq for ground release < 20 TBq for elevated (Frequency f <10-3 ) Individual dose < 5mSv Collective dose shall be analyzed 8

9 II.4 DEC & SA 허용기준 EUR (2.1B.2) YVL (VNA 733/2008) Korea Design Extension Conditions (DEC) Design Extension Coditions Severe Accident (Complex Sequences & Severe Accidents) 20 msv No criteria Complex sequence should aim at DBC4 targets Severe Accident ( B) No acute harmful effect in the vicinity of NPP No emergency protection action beyond 800m - 50 msv (9 nuclides) : 50 msv (24 hr) No long-term restriction on use of extensive land and water - Cs-137 < 100 TBq No delayed action beyond 3km - Hazard from other nuclides after 3 (9 nuclides) : 30 msv (4 days) months should be less than the effect from Cs-137 of 100 TBq No long term action beyond 800m (9 nuclides) : 100 msv (Whole duration) Probability that the above requirement is not met shall be extremely low. (= 5x10-7 /RY) Limited economic impact (Whole duration, Ground + Elelvated release) I-131 < 4,000 TBq Cs-137 < 30 TBq Sr-90 < 400 TBq 9

10 II.5 RST 개발요건 (EUR 2.5.1) Offsite Release Targets for Severe Accidents 중대사고시방사능방출허용기준은 2.1.B.1 임 방사선원항정량적분석방법은부록 A 적용 현실적가정과최적평가기법을적용 과학적불확실도를반영 (EUR451)G 4.5.1) General approach hto the In-Containment t Source Term 노심용융사고에만적용하며, 기타 DEC에일부내용적용 설계자는노심용융시나리오에대한단일설계표준방사선원항 (RST) 를결정해야함 RST 는냉각재와갭방출평가내용을포함해야함 RST는 PSA에서분석되는모든중대사고를대표하여야함 방사선원항은 RCS로부터의방출과노외용융노심으로부터의방출로정의됨 핵분열생성물의일차원자로건물로의방출시간, 방출율, 형태, 양및물리화학적형태등을특성화하여야함 RST 정량화방법은부록 A 지침및요건을적용 부록 A와불일치하는사항에대해서는국제적으로인정되는코드와실험자료를근거로입증해야함 RST를유도하는설계자가사용하는가정, 변수및전산코드는국제적으로인정되는실험자료에근거하고입증되어야함 중대사고에적용되는 RST는비현실적이므로 Complex sequence에는사용할수없음 Complex sequence 방사선원항은냉각재, 요오드스파이크및갭방출에만해당됨 10

11 II.6 Environmental Zone 적용요건 EUR 아래사항을고려하여환경구역 (Environmental zone) 설정 온도 / 습도 / 공기정화 / 접근빈도 방사선준위 잠재적오염 Radiation Zone 과 Contamination Zone 을설정 YVL 다음세가지 Environmental zone 을설정하여설계 External radiation level Airborne contamination Surface contamination 11

12 II.6 Radiation Zone 적용요건 12

13 II.7 출력운전중원자로건물접근설계요건 EUR 일차원자로건물은정상운전중설비의큰변경없이 Occasional Access 가능해야함 Occasional Access 는계획되지는않으나예상치못한필요에의해접근해야하는상황임 이차원자로건물은 Permanently Access 가가능해야함 Finland 요건 원자로건물접근지역에서 msv/hr 가유지되도록설계 출력운전중수행될수있는유지 보수작업 계획예방정지를위한사전작업 계측장비유지 보수작업 핵연료이송장치유지 보수작업 크레인유지 보수작업 일차계통상의 Relief Valve 등과같이오작동될수있는기기의유지 보수작업 13

14 II.8 해체고려설계적용요건 (EUR ) Decommissioning Feasibility Study 배치, 유지 / 보수관점에서해체가용이함을입증 해체가안전하게수행될수있음을입증 해체관점에서불리한사항발견시검토및설계수정필요 (YVL 2.6) Decommissioning of the plant 설계단계에서해체를고려한방사선방호설계이행 방사화최소화설계 부식생성물확산방지설계 표면오염제염용이설계 대형기기교체및해체를고려한용이성확보설계 대형기기철거용이 방사화기기취급용이 계통제염용이 14

15 III. 설계개발현황 15

16 III.1 DBC 1 기준충족설계 Vent stack 설치및통합배기설계 지상 100m 높이 Vent stack 설치 원자로건물, 보조건물, 복합건물관리구역정상배기를통합배출 고공방출모드적용으로부지주변선량감소 Aux. Bldg. Charcoal adsorber 설치 Iodine 방출저감을위하여활성탄흡착제설치 Tech. Spec. LCO 조정 RCS 비방사능운전제한치하향조정 SG 설계누설율운전제한치하향조정 RCPB 미확인누설율하향조정 설계기준유출물평가방법변경 국내원전운전경험을반영한 PWR-GALE 코드 Default data 변경 전산코드개정및검증 16

area HVAC system 설치 재장전운전중기기반입구가개방된상태에서원자로건물내핵연료취급사고시방출방사능을수집하여처리 Secondary system safety valve

17 III.2 DBC 2, 3, 4 요건충족설계 Double containment 설치 일차원자로건물외부에이차원자로건물설치하여사고누설수집 Annulus area HVAC system 설치 안전급환형공간누설방사성물질수집하여여과후배출 정상및사고시부압유지설계 부압상실시작동하여 DBC 및 DEC/SA 공유운전 Equipment hatch hall area HVAC system 설치 재장전운전중기기반입구가개방된상태에서원자로건물내핵연료취급사고시방출방사능을수집하여처리 Secondary system safety valve 설계변경 DBC 2시이차측안전밸브개방방지설계요건 충족을위해기존대기방출밸브 (ADV) 를 Relief valve 형태의 MSADV 로설계변경 주증기안전밸브 (MSSV) 개방전에개방토록설계 17

18 III.3 DEC & SA 요건충족설계 Double containment & Vent Stack 설치 DEC 와 SA 시방사능누설수집및여과후배기 Stack 방출을통해고공방출모드적용하여 DEC 및 SA 방출기준충족 SA dedicated containment spray system (SACSS) 설치 SA 전용 AAC 전원을공급받은중대사고전용살수계통설치 SA 시 CET 신호로작동하여핵분열생성물제거하여 SA 방출기준충족 SG Blowdown system 설계변경 Multiple SGTR 시유로변경을위한비상취출계통자동작동설계 유로를 IRWST로배기하여 DEC 선량및방출기준충족 Containment filtered vent system (CFVS) 설치 재장전중최종열제거원 (UHS) 상실시재장전수 Boiling에의한원자로건물압력감소를위해설치 운전원조치로작동하여 DEC시원자로건물손상방지및핵분열생성물환경방출감소 Passive external cooling system (Core catcher) 설치 노심용융중대사고시 Corium 냉각및퍼짐성능요건충족을위해설치 노외방출핵분열생성물의 Scrubbing 효과로 SA 시 Long-term 선원항감소 18

19 III.4 RST 요건충족설계 전용 RST 개발 Level 1 PSA 결과에근거한중대사고 Sequence 분석 노심손상빈도 (CDF) 에영향을주는대표적시나리오선정 Containment Bypass 시나리오제외 MAAP 코드를사용한대상시나리오에대한중대사고방사선원항분석 방출시간, 방출량, 화학형태등에대한대표값선정 RST 설정 관련설계영향분석 19

20 III.5 Environmental Zone 요건충족설계 방사선구역조정 Zone 0 ( 외부 ) : 신설 Zone 1 (Yard, Clean area) : 감시구역설정 Zone 2 : 핀란드기준적용 공기중오염구역신설 Zone 2 : DAC 유지하여내부피폭을 Zone 2 상한치의 1% 이내로제어 Zone 3 : 1% 이내유지 Zone 4-5 : 0.5~0.1% 유지 ICRP Classification Nonsupervised Supervised Area Zone 6-8 : 0.1~0.0002% 유지 Controlled Area 표면오염구역신설 운전경험에근거하여설정 Zone ID N/A APR1400 Zone ID Number Total Dose Rate Design Target (msv/hr) Green Orange 구역간분리배치및 Shoe boundary 설치 8 > 5000 Red Airborne Surface Concentration Contamination Design Target (Bq/cm 2 ) N/A DAC (Green) 0.05 DAC (Green) 0.1 DAC (Green) 1 DAC (Orange) N/A : 0.4, : 4 : 4, : 40 : > 4, : > 40 20

21 III.6 원자로건물접근가능요건충족설계 (1/2) Reactor cavity 차폐구조변경 Rx cavity를통한neutron/gamma streaming 을방지하기위해 Permanent pool seal 상부에 Removable 콘크리트차폐블럭설치 재장전시운전층에 Laydown Secondary shield 설계변경 NSSS 기기가설치된 Secondary shield wall 내부로부터운전원접근이요구되는외부로의선량률감소를위해차폐두께 0.5 ft 증가 SG 격실설계변경 SG 상부로의 Skyshine 차폐를위해 SG 격실상부를차폐 21

22 III.6 원자로건물접근가능요건충족설계 (2/2) Primary shield 설계변경 Reactor와 Primary shield wall 사이로의공기흐름확보를위해 Primary shield wall에서 SG 격실로의 Opening 추가 Primary i coolant piping i 배치설계변경 CVCS Letdown 배관 Secondary shield wall 내부로이동배치 RDT drain line 배관이동배치 Containment purge system 설계변경 출입결정후수시간이내에접근성확보를위해원자로건물공기중오염제거가능설계 22

23 III.7 해체고려설계요건충족설계 Primary shield Activation 최소화설계 Reactor와 Primary shield wall 사이에중성자흡수체설치 Biological shield 의 deep penetration 방지 해체용이성설계 대형기기일괄철거가능토록 SG 격실 Removable wall 설치 해체작업공간확보설계 해체방사성폐기물최소화및환경오염방지설계 해체고려설계 Checklist 개발및설계적용 잠재적누설조기감지설계구현 환경오염방지를위한이중방호벽설계구현 이차계통오염을설계기준으로반영 23

24 감사합니다 24

歯154배영직.PDF

歯154배영직.PDF 2002 (DBADOSE) Development of Doe alculation Program(DBADOSE) Incorporating Alternative Source Term Due to Deign Bai Accident * *, **, **, ** **, * ( ) 167 ** ( ) 360-9 (PWR) TID- 14844[1] Reg Guide 14[2],