Overview of Environmental Impact Assessment in Korea

Transcription

1 Overview of Environmental Impact Assessment in Korea Jong Yi MOON Korea Institute of Nuclear Safety

2 Table of Content 1. Current Status of NPP in Korea 2. Overview of EIA System in Korea o EIA System for Nuclear Facilities o Requirements & Tech. Standards o Off-Site Dose Calculation 3. Participation Plan

3 1. Current Status of NPP in Korea Korea has achieved a remarkable growth in nuclear power since the commercial operation of Kori unit 1 in operating NPPs : 16 PWRs & 4 PHWRs Total licensed output of 20 units is 17,716MWe Generation capacity : 24.8% (As of Dec. 2008) Actual production : 35.7 % 6 PWRs are now under construction. 2 additional units are planned. Total units in operation by 2015 : 28 units

4 Current Status of NPP in Korea Location of NPPs In operation : 20 Under construction : 6 Planned : 2 PWR Suspended KEDO Ulchin 1,2,3,4,5,6 Shin-Ulchin 1&2 PWR Yonggwang 1,2,3,4,5,6 PWR KINS PHWR & PWR PWR Wolsong 1,2,3,4 Shin-Wolsong 1,2 Kori 1,2,3,4 Shin-Kori 1,2,3,4

5 2. Overview of EIA System Historical Progress Since introduction of US NEPA of 1969, the EIA system has been adopted and implemented by about 110 countries. Korea adopted EIA system in 1977 with enactment of Environmental Conservation Act. It was then introduced in full scale in 1981 when the Regulations on Preparing the EIA Report was issued.

6 EIA System for Nuclear Facilities No. FAEP AEA EIAA Radiological EIA Non-Radiological EIA FAEP : Framework Act on Environmental Policy AEA : Atomic Energy Act EIAA : Environmental Impact Assessment Act

7 EIA System for Nuclear Facilities Framework Act on Environmental Policy Establishment of Environmental Standards In Article 10, "the government should establish environmental standards to protect the health of its citizens and maintain the quality of environment in comfortable state" Prevention of Environmental Contamination from Radioactive Materials In Article 21-2, "The government should take appropriate measures of environmental contamination and its prevention from radioactive materials, and the measures shall be controlled by the relevant regulations of the Atomic Energy Act" Basis Article the AEA requires the submission of radiological environmental report

8 EIA System for Nuclear Facilities The construction of NPP is the activity subject to EIA by Atomic Energy Act and Environmental Impact Assessment Act by the regulation of Framework Act on Environmental Policy. The EIA is divided into two parts, radiological and non-radiological, by the jurisdiction of the two Acts. - Atomic Energy Act - Environmental Impact Assessment Act The applicant prepares two types of EIA Report and submit it to each authority. - radiological part to the MEST - non-radiological part to the MKE for consulting with MOE

9 EIA System for Nuclear Facilities No. Draft ER Applicant - Non-Radiological Part - Radiological Part Local Gov. Public Hearing Radiological Prep. ER Applicant Submit ER Non-Radiological Review KINS MEST MKE Consult MOE License MEST License MKE Review KEI Construction Permit of Rx and Related Facility Installation Permit of Electrical Facility

10 Requirements & Tech. Standards MEST Notice No Title Regulations on Preparing a Radiological Environmental Report for the Nuclear Facilities Revised and announced with the minor change of previous Notice in June 2005(first issued in 1984) Standard format and contents of a Radiological Environmental Report - Outline of Construction Plan - Current Environmental Status - Description of Facilities - Environment Effects of Construction - Environmental Effects of Operation - Environmental Effects of Accidents - Environmental Monitoring Program - Gathering of Residents' Opinions - General Conclusion

11 Requirements & Tech. Standards MEST Notice No Title Standards for Radiation Protection Revised and announced with a minor change of preview Notice in January 2003, originally established in 1984 To prescribe design objectives per unit of the nuclear power plant and the environmental radiation protection standards per site for multi-facilities site in Article 16(prevention of environmental hazards)

12 Discharge Limits-Dose Constraints Items for one unit for Multiple Units at a Site Gaseous Effluent Air Absorption Dose by Gamma Rays Air Absorption Dose by Beta Rays Effective Dose by External Exposure 0.1 mgy/y mgy/y msv/y - Skin Equivalent Dose 0.15 msv/y - Organ Equivalent Dose by Particles, H-3, C-14, and Iodine 0.15 msv/y - Liquid Effluent All Pathways Effective Dose 0.03 msv/y - Organ Equivalent Dose 0.1 msv/y - Effective Dose msv/y Thyroid Equivalent Dose msv/y

13 Requirements & Tech. Standards The detail guidelines and procedures are described in the "Environmental Standard Review Plan for the Nuclear Power Plant" (KINS/GE-N004,1999). Calculation methodology for off-site dose was developed by modifying the methodology from USNRC Reg. Guide 1.109, 1.111, Incorporating ICRP-60 recommendation and BSS-115 from IAEA.

14 Off-Site Dose Calculation General Requirement & Methodology The radioactive materials are released from operating of the nuclear facilities to the environment, even though very small Necessary to evaluate off-site doses to make sure the compliance with design criteria. Consideration of unique food chain of Korean - Kimchi, Seaweeds (laver, brown seaweed, kelp), etc

15 Off-Site Dose Calculation Computer Codes Dose calculation INDAC, TEDII-60, KDOSE-60 Calculation of atmospheric dispersion parameter XOQDOQ, AZAP, WINDIFF, XOQDW Mixing ratio in ocean POM (Princeton Ocean Model)

16 Off-Site Dose Calculation INDAC INDAC (Integrated Dose Assessment Code Package for KINS) Developed by KINS Incorporating ICRP-60 concept into GASDOS/LIQDOS ㅁ GASDOS/LIQDOS developed by modifying food chain from GASPAR-II/ LADTAP-II. For agricultural and marine products, the rice, green vegetables used to make kimchi, and the seaweeds are added to represent the typical food chain in Korea.

17 Off-Site Dose Calculation

18 Off-Site Dose Calculation TEDII-60 developed by KOPEC as a replacement for the AZAP code, incorporates the characteristics of the Korean environment, the Reg. Guide 1.109, and calculation models of the USNRC, and the dose coefficient (ICRP-67, 69, 71, 72) recently recommended by the ICRP

19 Off-Site Dose Calculation KDOSE-60 This code was developed by KEPRI to calculate the off-site dose of nuclear power plants in Korea during their normal operation, on the basis of the ICRP-60 dose evaluation concept and the methodology of Reg. Guide of the USNRC

20 3. Participation Plan Multi-institute Joint Research Coordination Institute -KINS Collaboration Institute - KAERI -KIRAMS - KEPRI KAERI : Korea Atomic Energy Research Institute KIRAMS : Korea Institute of Radiological & Medical Science KEPRI : Korea Electric Power Research Institute

21 3. Participation Plan Terms of Reference Normal operation Release to the atmosphere Radiotoxic impact to human

22 Thank you for your attention

23 Reference Slides

24 Off-Site Dose Calculation- General Requirement The maximally exposed individual(mei) concept applies to the calculation of the individual exposure dose MEI has the characteristics of ingestion, activities, physiology and metabolism, which surpass those of the common individual. MEI is taken as the object of exposure in the dose calculation to obtain a conservative evaluation For gaseous radioactive effluents, the evaluation is made based on the local population, agricultural products distributed by distance (2, 4, 6, 8, 10, 20, 35, 50, 65, and 80 km), and orientation (divided into 22.5 ). For liquid radioactive effluents, the evaluation is made based on the information on the local population, major fishing ports, and public beaches within 80km of the nuclear power plant.

25 Off-Site Dose Calculation- General Requirement It is recommended that the parameters (agricultural products, characteristics of ingestion, dwelling, shielding, environmental transfer factor, etc.) used in the calculation of the exposure dose should reflect the characteristics of the specific site. The radiation doses of 4 or 6 exposure groups based on MEI concept are compared with the standard of off-site dose specified in Article 16, MEST Notice No

26 Off-Site Dose Calculation-General Requirement 4 age group Babies: neonates ~ aged 1 year or under, DCF: 3 months Children: aged 1 ~ 11 years or under, DCF: 5 years Teens: aged 11 ~ 17 years or under, DCF: 15 years Adults: population aged 17 years or older, DCF: adults 6 age group Babies ~ population aged 1 year or under, DCF: 3 months Aged 1 ~ 2 years or under, DCF: 1 year Aged 2 ~ 7 years or under, DCF: 5 years Aged 7 ~ 12 years or under, DCF: 10 years Aged 12 ~ 17 years or under, DCF: 15 years Aged 17 years or older, DCF: adults

27 Off-Site Dose Calculation- Usage Factor For MEI individual Infant Child Teen Adults Grain(kg/yr) Fruit(kg/yr) Kimchi(kg/yr) Leafy vegetable (kg/yr) Beef(kg/yr) Pork(kg/yr) Poultry(kg/yr) Mlik(l/yr) Inhalation rate (m 3 /yr)

28 Off-Site Dose Calculation- Usage Factor For average individual Child Teen Adults Agricultural product(kg/yr) Meat(kg/yr) Milk(l/yr) Inhalation rate (m 3 /yr)

29 Off-Site Dose Calculation - Dose on Exposure Pathway Exposed dose for pathways (gaseous, 1year child) Thyroid dose Effective dose Plume Ground deposition Inhalation Food consumption Exposed dose for pathways (liquid, 10 year child) Effective dose Seashore activity Swimming Boating Food consumption

30 Off-Site Dose Calculation- Dose Conversion Factor The conversion factor from radioactivity to dose for a hypothetical individual who represent the pertinent age group, by appropriate units. The dose conversion factor(dcf) of the inhalation and ingestion pathways are presented in ICRP-67, 69, 71, and 72. The DCF for external exposures, including submersion in noble gases, radioactive deposits on ground surfaces, and sea-shore activities (swimming, on-the-seashore activities, etc.) are applied with the values of the DFEXT Code developed by Eckerman et al. of the ORNL (Oak Ridge National Lab.) of the US. This Code provides the external exposure DCF calculated with the model presented in Federal Guidance Report No. 12 of the EPA of the United States.

31 Off-Site Dose Calculation-Exposure Pathway External Exposure Pathways The external exposure pathways to radiation sources can be classified into five channels of transmission: radiation source vicinity residents radiation source water vicinity residents radiation source water deposit vicinity residents radiation source air vicinity residents radiation source air soil vicinity residents

32 Off-Site Dose Calculation-Exposure Pathway Internal Exposure Pathways The major internal exposure pathways include the following: radiation source water vicinity residents, radiation source water seaweed vicinity residents, radiation source water shellfish vicinity residents, radiation source water fish vicinity residents, radiation source water soil plant vicinity residents, radiation source air vicinity residents, radiation source air soil plant vicinity residents radiation source air soil plant livestock vicinity residents

33 Off-Site Dose Calculation- Exposure Pathway

34 Off-Site Dose Calculation - Dose at Site Boundary for multiple facilities Site boundary EAB

35 IERNet Integrated Environmental Radiation Monitoring Network set up as a part of the national emergency response plan. to provide timely, scientifically sound data and information to decision makers and the public. KINS plays a comprehensive role in the technical information structure of the Korean Emergency Planning and Response to nuclear accidents.

36 IERNet Fig. The Environmental Radiation Monitoring Network in Korea

37 CLEAN System Computerized Local & Overall Country s Environmental Radioactivity Data Analysis Network System To manage comprehensively all data regarding environmental radiation / radioactivity in Korea To establish systematically baseline data for the evaluation of environmental contamination level when nuclear accident occur To offer promptly the accurate environmental monitoring data to the government and the publics

38 Structure of Clean System Sampling Pre-treatment Analysis and result Data of Central Lab. in KINS Data of NPP operator Data of RMS CLEAN SYSTEM Data analysis system Data Open system GIS system

39 AtomCARE System Atomic Computerized technical Advisory System for a Radiological Emergency To assess - a status of safety functions of the nuclear power reactors on a real-time basis and - the off-site radiological consequences. To provide - the technical support and assistance and - the recommendations for the resident public protective actions to the central and local government.

40 Component Modules of the AtomCARE System OACS/CFMS SIDS Monitoring Posts IERNet Automatic Weather Systems REMDAS Safety Parameters Radiological Data Meteorological Data STES FADAS AtomCARE AINS GIS ERIX GTS IAEA IEC Local Gov. LEMC Central Gov. NEMC/MOST Utility ERFs