생물다양성협약 당사국총회 결의에 따르면, 환경영향평가란 제안된 계획 또 는 개발이 환경에 미칠 것 같은 영향을 이익적 측면과 불리한 측면에서 사회경 제적, 문화적 및 인간의 건강에 미치는 영향과 연계하여 평가하는 과정을 의미한다. 해양에서의 환경영향평가 제도는 다수의 국가에 의해 국내법적으로 수용 하여 수행되어왔으며, 국제적으로도 많은 환경협약과 하위 지침들로부터 의무 화하여 수행되고 있다. 국제법상 국가관할권 이원지역에 대한 환경영향평가의 수행의무는 분명히 존재한다. 최근 채택된 BBNJ협정은 국가관할권 이원지역에 대한 종합적인 환경 및 해양생물다양성 보호를 목적으로 하는데, 그중 제4부는 환경영향평가의 발동요건, 절차, 평가의 내용, 협의과정, 의사결정 등 환경영향 평가 수행 전반에 대한 요건을 서술하고 있다. 본 연구에서는 다수의 환경영향 평가와 관련된 기존제도들 중 국가관할권 이원지역만을 협약의 적용지역으로 하고, 명확히 환경영향평가의 의무를 부과하고 있는 남극조약체제 및 국제해저 기구 주관하의 심해저 광업규칙상 환경영향평가제도와 BBNJ협정상 환경영향 평가제도의 비교를 통해 환경보호의 대응기조가 어떻게 유사하게 반영되었는 지 또는 차이점이 있는지 살펴보고 그 실효성에 대하여 논한다. 결론적으로 1) 기존제도와 달리 BBNJ협정은 call-in mechanism의 적용을 통 해 환경영향평가서에 대한 최종 의사결정권을 당사국에게 부여하고 있다. 2) 국가관할권 내측 지역으로부터의 월경 오염에 대한 환경영향평가 절차를 포함 함으로써 월경오염에 대한 준수의 효과성을 보장하고자 하였다. 3) 대중통고 및 협의, 활동의 영향에 대한 검토 조항을 통해 환경영향평가의 절차에서 넓은 범위의 이해관계자를 포함하고, 기존제도와 달리 국가관할권 이원지역에서의 활동으로부터 야기된 월경오염으로 영향을 받을 수 있는 연안국을 명시하여 환 경영향평가 절차에서 역할을 부여하고 있다. 4) 기존제도상 환경영향평가시 고 려되던 누적영향 및 잔존영향에 더하여 전략환경평가라는 현대적 보전기법을 규정하고 있다. 남극조약체제 및 국제해저기구 주관하의 심해저 광업규칙상 환 경영향평가제도 역시 과거 작성되었던 규칙에 대비하여 비교적 최근의 규칙 및 현재 작성중인 문서에서 대중통고 절차 신설, 확장된 이해관계자의 참여 근거 규정 마련 등에 따라 환경보호를 위한 국제사회의 강화된 기조에 대응하고 있 음을 살펴볼 수 있었다. 향후 당사국 총회를 통해 환경영향평가의 세부 지침이 보완될 것임에 따라, 기존의 관련 제도상 환경영향평가 절차 및 내용에 대한 정확한 숙지를 기반으로 하여 대응해 나가야 할 것이다. 또한 관련 전문기관을 지정하고 과학 전문가 양성에 집중해야 할 것이다.

PURPOSES : In this study, the resources and energy consumed to produce hot mix asphalt mixtures and hot mix reclaimed asphalt mixtures in asphalt concrete plants were estimated and the emissions from the detailed processes of the production process were evaluated based on TRACI(the tool for the reduction and assessment of chemical and other environmental impacts). METHODS : To estimate the energy consumption of the aggregate drying process, which consumes a significant amount of energy in the production process, an energy consumption calculation model based on the thermal equilibrium equation was used, and the energy consumed for material transportation, storage, and operation of other facilities was cited from the literature. RESULTS : For the system boundary conditions established and the inventory considered, the emissions to produce one ton of hot mix reclaimed asphalt mix are greater than the emissions to produce one ton of hot mix asphalt mix for a number of key impact categories. The process of producing hot mix reclaimed asphalt mixtures was evaluated to consume more resources and energy in the production of recycled aggregates and heating for drying than in the production of hot mix asphalt mixtures, but less resources and energy in the production of binders and natural virgin aggregates and the heating to heat these materials. CONCLUSIONS : The results of the emissions assessment using the life cycle inventory for the production of hot mix asphalt mixtures were generally similar to the results understood in the field and in much of the literatures, confirming the reliability of the methodology. However, in order to evaluate the dominance of specific processes or mixtures, it is believed that the construction of a wide range of inventory databases after inventory redesign is necessary for a specific and rigorous assessment.

본 연구는 전원주택단지를 대상으로 한 경관영향평가에서 진행하고 있는 각 단계별 계획항목과 내용 등에 대한 분석을 바탕으로 체계적인 경관영향평가 수립을 위한 기초자료를 제시하는데 주안점을 두 었다. 각 평가항목 별 중요도는 전문가 설문을 바탕으로 수행하였으며, 구체적인 분석방법으로는 기술 통계분석, 요인분석, MCB분석 등의 통계분석방법이 사용되었다. 분석결과 평가항목의 중요도 평균은 5.73(7)으로 높게 나타났으나 ‘이용자 안전을 고려한 가로시설물 시설계획’의 중요도가 6.38(7)로 가장 높게 나타난 것에 비해 문헌분석 출현빈도는 8%로 나타나 그 중요도에 비해 기존 경관영향평가에 활용 된 평가항목은 미흡했던 것으로 분석되었다. 평가항목은 33개의 평가항목이 7개의 평가항목 군과 3개 의 경관영역에 유형화되어 평가항목 리스트로 구성되었다. 평가항목 군별 중요도 분석결과 모두 5점 이상으로 높게 나타났으며, 그 중 색채 군에서 6.04로 가장 높게 나타났다. 본 연구는 문헌분석으로 도출 된 평가항목이 전문가 설문 분석결과 대부분 중요도가 5점대 이상으로 높게 나타나 경관영향평가 평가 항목 리스트에 적용함에 무리가 없을 것으로 판단된다.

Domestic nuclear power plants conduct radiological environmental impact assessments every year in accordance with the Nuclear Safety and Security Commission (NSSC) notice. Among them, gaseous effluents are evaluated for their effects due to inhalation, external exposure in the air, exposure from ground surface deposits, food intake. In order to evaluate the impact of this exposure pathway, an evaluation point for each pathway must be selected. In the case of evaluation points, each country has different evaluation points. In the case of Korea, the evaluation point is calculated on the assumption that one lives 365 days a year at the EAB and consumes food from the nearest production area. In the case of the United States, external exposure and inhalation are evaluated at the site boundary or the nearest residential area, and food intake is evaluated by assuming that food produced in the nearest residential area or the nearest production area is consumed. Currently, the dose evaluation is optimized and selected so that EAB evaluation point for each site includes 16 direction evaluation points for each unit. In the E-DOSE60 program currently under development, the evaluation point was selected by calculating 16 direction x number of units without optimization. The food intake evaluation point was selected as the point that satisfies the minimum farmland area of the U.S. NRC NUREG-1301 and is the shortest distance from the site. The location of the production point from multiple units in included all 16 directions for each unit and quantity of evaluation points was optimized to satisfy the shortest distance. It can contribute to improving the reliability of the E-DOSE60 program currently under development by selecting new evaluation points for evaluating inhalation and external exposure evaluation and selecting optimized dose evaluation points for each site for evaluation by ingestion.

우리나라 해양환경에 유출되는 위험·유해물질(Hazardous Noxious Substances, HNS)의 해양환경 및 사회환경 영향평가 결과 와 HNS 확산 영역, 해양환경 정보, HNS 실태조사 결과 등 관련 연구 결과 및 자료를 정책결정자와 연구자들에게 공유할 수 있는 HNS 국내 용 플랫폼을 구축하고자 한다. 국내의 HNS 관리 및 배출 체계 마련을 위한 의사결정 지원이 가능하고 국내 실정에 적합한 플랫폼의 설계 를 위하여 유해물질의 데이터 관리 및 유출 시 대응 도구, 기초적인 정보 등 플랫폼에 관련된 기술동향을 분석하는 등 국내·외의 플랫폼 개발 사례를 고찰하였다. 유속 벡터의 전처리 기능 개발, 전처리 결과에 따른 동적 시각화 구현, 해양산업시설 배출 HNS의 유출량과 유출 범위의 전처리 모듈, HNS 해양환경 영향평가 연산 모듈 프로토타입을 개발하였다. HNS 해양환경 영향평가를 위한 국내용 HNS 플랫폼은 초기 위해성을 평가하고 대응 및 관련 법제화 시 과학적인 기초 도구로써 활용될 수 있을 것으로 기대된다.

The US NRC developed a program called NRCDose3 to evaluates the environmental impact of radiation around nuclear facilities. The NRCDose3 code is a software suite that integrates the functionality of three individual LADTAP II, GASPAR II, and XOQDOQ Fortran codes that were developed by the NRC in the 1980’s and have been in use by the nuclear industry and the NRC staff for assessments of liquid effluent and gaseous effluent, and meteorological transport and dispersion, respectively. Through the integrated program, it is possible to conduct safety assessment and environmental impact assessment from liquid and gaseous effluent when operating permits are granted. In addition to a more user-friendly graphic user interface (GUI) for inputting data, significant changes have been made to the data management and operation to support expanded capabilities. The basic calculation methods of the LADTAP II, GASPAR II, and XOQDOQ have not been changed with this update to the NRCDose3 code. Several features have been added. The previous program used only ICRP-2 dose conversion factor, but the new program can additionally use dose conversion factor of ICRP-30 and ICRP-72. In the previous program, 4 age groups (infant, child, teen, and adult) were evaluated during dose evaluation, but when ICRP-72 was selected, 6 age groups (infant, 1-year, 5-year, 10-year, 15-year, and adult) could be evaluated. In addition, when selecting ICRP-72, many user-modifiable parameters such as food intake and exposure time were added. It will be referred to E-DOSE60, a program currently under development.

After the Fukushima nuclear power plant accident in 2011, interest in technology for evaluating residents’ exposure to effluents generated from nuclear power plants at the time of the accident has increased. KHNP has developed the S-REDAP program and is using it to evaluate radiation dose and recommend resident protection measures in the event of a nuclear power plant emergency. Its main functions are source term evaluation, atmospheric diffusion evaluation, radiation dose evaluation, etc. Based on these evaluations, resident protection measures are evaluated. In Japan, evaluation is conducted through a program called SPEEDI-MP (System for Prediction of Environmental Emergency Dose Information Multi-model Package) created by JAEA (Japan Atomic Energy Agency). Similar to S-REDAP, the program also evaluates effluents emitted from nuclear facilities through source term evaluation and atmospheric diffusion factor evaluation. In JAEA, through a program using SPEEDI-MP, the source term evaluation was performed in collaboration with NSC (Nuclear Safety Commission) in the event of the Fukushima nuclear plant accident, and dose evaluation in Japan was performed 2 months as an atmospheric diffusion factor using meteorological data for 2 days. Through comparative analysis of evaluation data from Japan, improvements to the current program be derived.

K-DOSE60, a off-site dose calculation program currently used by khnp, is performing evaluation based on the gaseous effluent evaluation methodology of NRC Reg. Guide 1.109. In particular, H-3 and C-14, which are the major nuclides of gaseous effluent, are evaluated using a ratio activity model. Among them, H-3 is additionally evaluating the dose to OBT (Organically Bound Tritium) and HT as well as HTO (Triated water). However, NRC Reg. Guide 1.109 is a methodology developed in the 1970s, and verification was performed by applying the evaluation methodology of H-3 and C-13 presented by IAEA TRS-472 in 2010 to the current K-DOSE60. The IAEA TRS-472 methodology also includes OBT and HT for H-3. In order to apply the ratio radioactivity model presented in IAEA TRS-472, the absolute and relative humidity were calculated using the weather tower of the nuclear site and used for H-3 evaluation. For the dose evaluation of HT, the previously used Canada Chalk River Lab. (CNL) conversion factor was used. For atmospheric carbon concentration, the carbon concentration presented in IAEA TRS-472 was used, not the carbon concentration in the 1970s of NRC Reg. Guide 1.109. It was confirmed that the K-DOSE60, which applied the changed input data and methodology, was satisfied by performing comparative verification with the numerical calculation value.

In 2022 and 2023, the Korea Institute of Nuclear Safety (KINS), a regulatory body, revised the regulatory guidelines for off-site dose evaluation to residents, marine characteristics surveys around nuclear facilities, and environmental radiation surveys and evaluation around nuclear facilities. In addition, the NRC, a US regulatory body, has revised regulatory guide 1.21 (MEASURING, EVALUATING, AND REPORTING RADIOACTIVE MATERIAL IN LIQUID AND GASEOUS EFFLUENTS AND SOLID WASTE) to change environmental programs for nuclear facilities. The domestic regulatory guidelines were revised and added to reflect the experience of site dose evaluation for multiple units during the operation license review of nuclear facilities, the resident exposure dose age group was modified to conform to ICRP-72, and the environmental monitoring plan was clarified. In the case of the US, the recommended guidelines for updating the long-term average atmospheric diffusion factor and deposition factor, the clarification of the I-131 environmental monitoring guidelines for drinking water, and the clarification of the procedures described in the technical guidelines when changing environmental programs have been revised and added. Through such regulatory trend review, it is necessary to preemptively respond to changes in the regulatory environment in the future.

Currently, there are 25 nuclear power plants (NPPs) in operation in Korea, including 22 pressurized water reactors (PWRs) and three pressurized heavy water reactors (PHWRs). Two NPPs, including Kori Unit 1 and Wolsong Unit 1, are permanently shut down and awaiting decommissioning. If Kori Unit 2, which is expected to be permanently shut down soon, is included, the number of decommissioning NPPs will be increased to three. Spent fuels (SFs) are continuously generated during the NPP operation, which are stored in an SF storage pool in NPPs to cool down the decay heat emitted from SFs. For safe NPP operation, SFs must be regarded as waste, and a disposal site must be selected to isolate SFs. However, an appropriate site has yet to be selected in Korea. SFs contain long-lived nuclides with a high specific activity. For disposal, it is important to characterize the nuclides in the fuels and delay the migration of the nuclides to the environment when SFs are placed in a future disposal facility. If the disposal container is broken, the nuclides in the fuels escape from the filling material, such as bentonite. These escaped nuclides are dissolved in groundwater and migrate to the surface of the earth. Thus, it is possible to assess the radiological impact, such as the exposure dose during and after the disposal, if the types and characteristics of nuclides in SFs are known. This study investigated the nuclides in SFs and identified exposure scenarios that may occur in the disposal process of SFs and migration characteristics when the nuclides leak into groundwater to propose a dose assessment methodology for workers and the public.

해양산업시설의 위험유해물질 배출이 미치는 사회영향을 평가하고, 기술근거배출허용기준 설정과정에서 요구되는 사회영향평 가 항목 및 방법적용에 대한 시사점을 도출하였다. 연구범위는 인천광역시에 있는 해양산업시설을 대상으로 하였다. 분석결과는 다음과 같다. 첫째, 기업 및 산업에 대한 영향은 ‘큰’ 것으로 평가되었지만, 대기업은 영업이익손실과 도산가능성, 그리고 고용손실의 영향이 적 었고, 소기업과 중기업은 영향이 큰 것으로 나타났다. 둘째, 지역사회 및 경제에 대한 영향은 ‘적은’ 것으로 평가되었으나, 직접적으로 인 과관계를 지니는 어업생산자나 지역관광종사자, 그리고 해당 지역은 그 영향이 집중되어 크게 나타날 수 있기 때문에 이에 대한 세심한 정책적 개입이 필요한 것으로 판단된다. 셋째, 기술근거배출허용기준의 설정방법에서 사회적 손실비용 및 사회적 편익산정 항목과 방법 이 유용하게 적용될 수 있는 것으로 판단된다.

We deduced the proper estimation methodology for the amount of carbon sequestration by damaged trees for Environmental Impact Assessment (EIA). The nine development projects related to renewable energy, damaged trees occur, assessment status and used method of evaluating the carbon storage of damaged trees were summarized. And after re-calculating the carbon storage of damaged trees through allometric equations, the difference between the two groups, re-calculated the damaged trees carbon storage and the damaged trees carbon storage in the report, was validated. As a result, damaged trees carbon storage in words was more than the re-calculated damaged trees carbon storage, and it was statistically significant (p<0.005). This result means that the existing method for calculating damaged tree carbon storage is overcalculated. It was judged that it was necessary to improve the calculation method. Therefore, allometric equations suitable for each dominated-tree species should be used when calculating the damaged tree carbon storage. Furthermore, we propose to establish a carbon storage calculation system based on actual data from the ecosystem so that researchers can efficiently and accurately the damaged trees carbon storage. Key words: damaged vegetation, carbon sequestration, allometric equation, environmental impact

Recently, the construction of tall buildings utilized by high strength-concrete in the whole world is tending to be on the rise. The application of high-rise structural system in buildings results in the excellent cut-down effect in construction materials due to section reduction. Therefore, in order to investigate the CO2 and resource reduction effect for the high-rise structural system, comparisons of GWP and ADP in embodied energy of structural materlais between 4 type of high-rise structural system have been performed. As a result, GWP emission increased in the order of steel structure outrigger system, RC shear wall system, and RC outrigger system. On the other hand, ADP emissions increased in the order of RC shear wall system, RC outrigger system, and steel structure outrigger system.