KEPCO RESEARCH INSTITUTE NUCLEAR POWER LABORATORY 1 ISOE ALARA Workshop(2010.08.30; Kyung Joo) A Draft Suggestion on the Dose Constraints for Korean NPPs.

Slides:



Advertisements
Similar presentations
4/2003 Rev 2 I.1.1 – slide 1 of 13 Session I.1.1 Part I Review of Fundamentals Module 1Introduction Session 1Learning Objectives, Course Table of Contents.
Advertisements

PUBLIC DOSES ESTIMATION BASED ON EFFLUENTS DATA AND DIRECT MEASUREMENTS OF TRITIUM IN ENVIRONMENTAL SAMPLES AT CERNAVODA E. Bobric, I. Popescu, V. Simionov.
1 Radiological protection, dosimetry & environmental monitoring National Training Course on Radiopharmacy, Radiochemistry and Radioisotope Production Site.
14th Annual RETS/REMP Workshop June 28-30, 2004 U.S. Nuclear Power Sister Plant Radiological Effluent Release Comparisons J.T. Harris 1,3, D.W. Miller.
IRPA 13: Refresher Course RC 19
Exemption, Clearance, Discharges
 Progress with the revision and consolidation of the European Basic Safety Standards Directive Stefan Mundigl European Commission DG Energy and Transport.
RADIOACTIVE DISCHARGES CONTROL JE Jan Horyna State Office for Nuclear Safety Czech Republic September 2009 Vienna.
Perspectives on USNRC Study Request Nuclear & Radiation Studies Board April 26, 2010 Ralph Andersen, CHP Senior Director – Radiation Safety & Environmental.
The UK Approach - the Initial Radiological Assessment Methodology Laura Newsome Scientist – Environment Agency September 2009.
MODULE “PROJECT MANAGEMENT AND CONTROL” EMERGENCY PLANNING SAFE DECOMMISSIONING OF NUCLEAR POWER PLANTS Project BG/04/B/F/PP , Programme “Leonardo.
School for drafting regulations Nuclear Safety Decommissioning Vienna, 2-7 December 2012 Tea Bilic Zabric.
Fusion Power Plant Licensing and Waste Management by Antonio Natalizio for Presentation at the 9 th Course on Technology of Fusion Reactors at Erice (Monastero.
IAEA International Atomic Energy Agency Emergency Response Protective Actions Day 10 – Lecture 3.
Alexander Brandl ERHS 630 Effective and Committed Effective Dose Environmental and Radiological Health Sciences.
IAEA plans with respect to environmental protection EC PROTECT Workshop Oslo, Norway, 28–30 January 2008.
SÄTEILYTURVAKESKUS STRÅLSÄKERHETSCENTRALEN RADIATION AND NUCLEAR SAFETY AUTHORITY Protection of the environment from ionising radiation - views of a regulator.
PART IX: EMERGENCY EXPOSURE SITUATIONS Module IX.1: Generic requirements for emergency exposure situations Lesson IX.1-2: General Requirements Lecture.
IAEA International Atomic Energy Agency International Workshop on the Safe Disposal of Low Level Radioactive Waste WG3 debriefing.
Maximum Permissible Dose (MPD)
ALARA Programs & Occupational Dose Trend in Wolsong NPP Korea Hydro & Nuclear Power Co., Ltd Wolsong Nuclear Power Plant Unit 3&4.
Regulatory Approach to the Lifetime Management of the Nuclear Power Plants in Korea June 30, 2004 Choi, Kyung Woo Korea Institute of Nuclear Safety International.
International Atomic Energy Agency IX.4.5. Control of effluents Approach to regulatory control, establishing authorized discharge levels.
KINS Analysis on Occupational Exposure of Radiation Workers in Korea by KISOE 2013 ISOE International ALARA Symposium Tokyo, Japan, August, 2013.
The System of Radiation Protection
MODULE “PROJECT MANAGEMENT AND CONTROL” RADIATION PROTECTION SAFE DECOMMISSIONING OF NUCLEAR POWER PLANTS Project BG/04/B/F/PP , Programme “Leonardo.
INTERNATIONAL COMMISSION ON RADIOLOGICAL PROTECTION —————————————————————————————————————— ICRP’s 2005 Recommendations on Radiological Protection From.
Development of Cyber ALARA Program 2012 ISOE Asian ALARA Symposium Choi, Hoon Radiation Health Research Institute Korea Hydro-Nuclear Power Company.
Current and Planned Reports and Conferences of the National Council on Radiation Protection and Measurements Thomas S. Tenforde President Presentation.
ISO training courses Developed by DOE and IBRAE RAN and conducted at the Training Center “Emergency Response” of the Institute for Advanced Training.
Intervention for Chronic and Emergency Exposure Situations Assessment and Response during Radiological Emergency Dose Assessment Overview Lecture IAEA.
INTERNATIONAL COMMISSION ON RADIOLOGICAL PROTECTION —————————————————————————————————— Optimisation of Radiological Protection in ICRP’s New Recommendations.
Cepn ALARA and Occupational Exposures: Experience and Challenges J. Lochard ISOE International ALARA Symposium Tsugura, Japan, November 2008.
MODULE “PREPARING AND MANAGEMENT OF DOCUMENTATION” SAFE DECOMMISSIONING OF NUCLEAR POWER PLANTS Project BG/04/B/F/PP , Programme “Leonardo da Vinci”
Intervention for Chronic and Emergency Exposure Situations General Principles and Types of Events Prolonged (Chronic) Radiation Exposure Lecture IAEA Post.
56th Regular Session of the IAEA General Conference
Technical Meeting on Milestones for nuclear power infrastructure development Radiation Protection Khammar Mrabit Head, Regulatory Infrastructure and Transport.
IAEA International Atomic Energy Agency Regulations Part III: Radiation Protection Performance Requirements Day 8 – Lecture 5(3)
International Atomic Energy Agency Roles and responsibilities for development of disposal facilities Phil Metcalf Workshop on Strategy and Methodologies.
IAEA International Atomic Energy Agency IAEA Safety Standards for Research Reactors W. Kennedy Research Reactor Safety Section Division of Nuclear Installation.
-1- UNRESTRICTED / ILLIMITÉ Demonstrating the Safety of Long-Term Waste Management Facilities Dave Garrick 2015 September.
Korea Institute of Nuclear Safety – 5. IAEA/RCA Asian Region ALARA Network Meeting Korea Information System on Occupational Exposure (KISOE)
1 Course : بسم الله الرّحمن الرّحيم Chapter 7: BSS & International Regulations Omrane KADRI, Ph.D. Office 2021 Health Safety & Radiation.
International Atomic Energy Agency IX.4.2. Principles of radioactive waste management Basic technical management solutions: concentrate and contain, storage.
RER/9/111: Establishing a Sustainable National Regulatory Infrastructure for Nuclear and Radiation Safety TCEU School of Drafting Regulations November.
Tsuruga November 2008 ISOE International ALARA Symposium 1 OCCUPATIONAL EXPOSURE DYNAMICS IN DIFFERENT TYPES OF RUSSIAN NUCLEAR POWER PLANTS Dr.
DEVELOPMENT OF THE NATIONAL INFRASTRUCTURE FOR NUCLEAR POWER IN VIETNAM DEVELOPMENT OF THE NATIONAL INFRASTRUCTURE FOR NUCLEAR POWER IN VIETNAM Vuong Huu.
THE RADIATION SAFETY IN A “DAILY LIFE” Introduction Volodymyr Berkovskyy.
OPTIMISATION OF RADIATION PROTECTION (ALARA): A PRACTICAL GUIDEBOOK Sotirios ECONOMIDES (GAEC, Greece), Cristina NUCCETELLI (ISS, Italy), Serena RISICA.
1 International Iran nanosafety congress INSC2014”, Tehran, 19, 20 February 2014 Demin V.F., Demin V.A., Kashkarov P.K. NRC “Kurchatov institute”, Moscow,
ALARA IMPLEMENTATION AT UKRAINIAN NPPs T. Lisova, Nuclear Energy Department, Ministry of Fuel and Energy of Ukraine Y. Roshchyn, National Nuclear Energy.
Meet your Regulator Workshop with FANR licensees October 2011 Dr. John Loy Director, Radiation Safety Federal Authority for Nuclear Regulation.
Use and Conduct of Safety Analysis IAEA Training Course on Safety Assessment of NPPs to Assist Decission Making Workshop Information IAEA Workshop Lecturer.
Technical Services. Objectives To identify the technical services needed within the infrastructure for an effective implementation of regulatory programme.
Radiological impacts from nuclear industrial facilities on the public and the environment : Their magnitude and the next 50 years forecast Sylvain Saint-Pierre.
2013 ISOE International ALARA Symposium
Nuclear decommissioning: Turning waste into Wealth
 Progress with the revision and consolidation of the European Basic Safety Standards Directive Stefan Mundigl, Vesa Tanner European Commission DG Energy.
Transposition of Requirements set out in the Basic Safety Standards for Nuclear Facilities in Lithuania Gintautas KLEVINSKAS Albinas MASTAUSKAS Radiation.
ALARA Programs & Occupational Dose Trend in Wolsong NPP
Vesa Tanner European Commission Directorate-General Energy
Optimization in ICRP Recommendations
Update on New Federal Guidance for Dose and Risk Assessment
The pathological effects of ionising radiation
Principles of Radiation Protection
4th ISOE European Workshop on Occupational Exposure Management at NPPs Lyon, France, March 2004 Kirsi Alm-Lytz Radiation and Nuclear Safety Authority.
Occupational Radiation Protection during High Exposure Operations
Comparison of Performance Indicators of Different Types of Reactors Based on the ISOE Data H. Janžekovič, M. Križman.
Current Radiation Protection Legislation in Slovakia
Optimisation in Operational Radiological Protection
Presentation transcript:

KEPCO RESEARCH INSTITUTE NUCLEAR POWER LABORATORY 1 ISOE ALARA Workshop( ; Kyung Joo) A Draft Suggestion on the Dose Constraints for Korean NPPs Based on ICRP103 Recommendations ISOE ALARA Workshop( ; Kyung Joo) A Draft Suggestion on the Dose Constraints for Korean NPPs Based on ICRP103 Recommendations Hee Geun KIM Nuclear Power Laboratory KEPCO Research Institute Hee Geun KIM Nuclear Power Laboratory KEPCO Research Institute

KEPCO RESEARCH INSTITUTE NUCLEAR POWER LABORATORY 2 Topics for Presentation 1. Introduction 2. ICRP-60 Experiences 3. Brief Summary of ICRP ICRP-103 Implementation Plan 5. Concepts of Dose Constraints(DCs) 6. Korean RP Regulations for DCs 7. Draft Suggestion of Dose Constraints

KEPCO RESEARCH INSTITUTE NUCLEAR POWER LABORATORY 3 1. Introduction, 2. Aims and Scope, 3. Biological Aspects, 4. Quantities in Radiological Protection, 5. System of Radiological Protection of Humans, 6. Implementation, 7. Medical Exposure, 8. Protection of the Environment, Glossary & Reference Annex A. Health Risks, Annex B. Basis for Dosimetric Quantities. ICRP-103 Recommendations (2007)

KEPCO RESEARCH INSTITUTE NUCLEAR POWER LABORATORY 4 Current Status of Korean Nuclear Industry Power reactors: 24 units in op. & 4 units under con. Research reactors: 1unit in operation Fuel fabrication facilities: 1unit in operation RGs & RIs are used at over 4,000 facilities Radwaste facility will be constructed by Dec The impact of the ICRP 103 will be significant. (Main Items: Optimization and dose constraints) Impact analysis on the ICRP-103 and draft suggestion of constraints are essential

KEPCO RESEARCH INSTITUTE NUCLEAR POWER LABORATORY 5 Nationwide ICRP-60 Experiences ICRP 60 Publication (1990) Mid-term research (1992~1997) to incorporate recommendations into the relevant national atomic energy laws and regulations by MOST/KINS Ministerial Notice on Radiation Dose (practical ICRP 60 implementation through step by step approach; 1998~2003) Draft of RP regulations (1997) ICRP-60 Implementation to Korean Nuclear Industry (Dose limits, Effective dose, Internal Dosimetry, Effluent Control Limits)

KEPCO RESEARCH INSTITUTE NUCLEAR POWER LABORATORY 6 ICRP-60 Experiences for NPPs ICRP 60 Publication (1990) 1 st phase Longterm Dose Reduction Plan(LDRP) (1991 ∼ 2000) to meet the ICRP-60 reduced dose limits (20mSv/y, 1mSv/y) 2 nd phase LDRP Implementation (2001 ∼ 2007) & 3 rd phase LDRP Implementation(2008 ∼ 2017) Project to set up the ICRP-60 implementation & countermeasure plan/Feedback to 2 nd phase LDRP to reduce the occupational dose (1999 ∼ 2000) ICRP-60 Implementation for Korean NPPs (LDRP, Two-TLD Algorithm, Internal Dose Assessment, Effluents Control & C-14, Free Access Conditions, RMS Setpoint, Derived Release Limits)

KEPCO RESEARCH INSTITUTE NUCLEAR POWER LABORATORY 7 Longterm Dose Reduction Plans(1 st and 2 nd Phase) o Reduction techniques - Plant operation upgrading: High pH, Fine filters, etc - System upgrading : RTD, New nozzle dam, Low or free Co. - New Facility : Tritium Removal Facility(Wolsong NPPs) - Procedure upgrading: Internal dose, ALARA, Peer reviews o The doses(man-Sv) have been continuously decreasing

KEPCO RESEARCH INSTITUTE NUCLEAR POWER LABORATORY 8 Consolidated updates since 1990 (ICRP-60) Updated science, but no fundamental change New radiation and tissue weighting factors Overall detriment still 5% per Sv Process based  Situation based Demonstrate protection of the environment Stability Fundamental principles unchanged (with more emphasis on optimization in all situations) ⇒ Main Issues: Dose Constraints and Reference Levels Dose limits unchanged

KEPCO RESEARCH INSTITUTE NUCLEAR POWER LABORATORY 9 National Legislations IAEA Basic Safety Standards (2010) ICRP-103 Recommendations (2007) UNSCEAR, BEIR etc

KEPCO RESEARCH INSTITUTE NUCLEAR POWER LABORATORY 10 Implementation Takes Time… ICRP 1977 Recommendations (Publication 26) International standards : 1984 National standards : 1989 ICRP 1990 Recommendations (Publication 60) International standards : 1996 National standards : 2000 ~2002 ICRP 2007 Recommendations (Publication 103) International standards : 2010? National standards : 2013 ~?

KEPCO RESEARCH INSTITUTE NUCLEAR POWER LABORATORY 11 Research Plan for ICRP 2007 Implementation by KINS (Reference: K.W.Cho’s Presentation of KINS) Year Detailed Research Plan Analysis of the ICRP 2007 recommendations - Identification of requirements Comparative analysis of existing laws and ICRP Identification of troublesome on implementation Research on the solution of the troublesome - Issuance of the first draft of national laws Opinion hearing and analysis on the first draft - Feasibility study on the requirements Issuance of the final draft new laws and regulations Formal legislation process

KEPCO RESEARCH INSTITUTE NUCLEAR POWER LABORATORY 12 Dose Limits and Dose Constraints Dose Constraints/ Reference Levels Dose Limits From a single source in all exposure situations From all regulated sources in planned exposure situations Dose constraints : A prospective and source-related restriction on the individual dose from a source, which provides a basic level of protection for the most highly exposed individuals from a source, and serves as an upper bound on the dose in optimization of protection for that source. For occupational exposures, the dose constraint is a value of individual dose used to limit the range of options considered in the process of optimization. For the public exposure, the dose constraint is an upper bound on the annual doses that members of the public should receive from the planned operation of any controlled source.

KEPCO RESEARCH INSTITUTE NUCLEAR POWER LABORATORY 13 Dose Limits, Constraints, and Reference Levels Exposure Situations PlannedExistingEmergency Exposure Types Occupational Dose Limits Dose Constraints n/aReference Levels Public Dose Limits Dose Constraints Reference Levels Medical Diagnostic Reference Levels (Dose Constraints) n/a

KEPCO RESEARCH INSTITUTE NUCLEAR POWER LABORATORY 14 Dose to the public cannot be measured directly. It is necessary to characterize an individual, either hypothetical or specific, whose can be used for determining compliance with the relevant dose constraint. This individual is defined as the “representative person”. The goal of protection of the public is achieved if the relevant dose constraint for this individual for a single source is met and radiological protection is optimized. The representative person should be borne in mind: reasonableness, sustainability, and homogeneity Three age categories for estimating annual dose 0-5years(1-year-old infant), 6-15years(10-year-old child), 16-70years(adult)

KEPCO RESEARCH INSTITUTE NUCLEAR POWER LABORATORY 15 Representative person is: For the purpose of protection of the public, it is necessary to characterize an individual receiving a dose that is representative of the more highly exposed individuals in the population. A number of factors should be taken into account Must account for all relevant pathways of exposure Must consider spatial distribution of radionuclides to ensure that the group receiving the highest dose is included Habit data should be based on the group or population exposed and must be reasonable, sustainable, and homogeneous DCF have to be applied according to specific age categories Dose to the representative person may be calculated using deterministic or probabilistic methods Using the 95 th percentile of behavior in deterministic calculations is a cautious assumption for defining an intake rate.

KEPCO RESEARCH INSTITUTE NUCLEAR POWER LABORATORY 16

KEPCO RESEARCH INSTITUTE NUCLEAR POWER LABORATORY 17 Minister’s Notice No Article 16 (Detriment protection for the environment) 1. Regulations to be applied to the design of the nuclear power plant a. annual dose at the exclusion area boundary by the gaseous effluents 1) air absorbed dose by gamma rays: 0.1 mGy 2) air absorbed dose by beta rays: 0.2 mGy 3) effective dose by external exposure: 0.05 mSv 4) skin equivalent dose by external exposure: 0.15 mSv 5) organ equivalent dose by particulate, H-3, C-14 and iodines: 0.15 mSv b. annual dose at the exclusion area boundary by the liquid effluents 1) effective dose: 0.03 mSv, 2) thyroid equivalent dose: 0.75 mSv 2. Regulation to be applied to the operation of many nuclear power plants within the same site boundary 1) effective dose at the exclusion area boundary : 0.25 mSv 2) thyroid equivalent dose at the exclusion area boundary : 0.75 mSv

KEPCO RESEARCH INSTITUTE NUCLEAR POWER LABORATORY 18 The example of collective dose for Korean NPPs design Target of collective dose : 1.0 person∙Sv/unit∙yr - Trend of advanced reactor : 1.0 person∙Sv/unit∙yr - EPRI URD : 0.7 person∙Sv/GWe∙yr Expected dose at NPP design : 0.76 person∙Sv/unit∙yr KINS KNGR’s Safety Requirement(Dose constraints) Maximum individual dose : 5.0mSv/yr, Average dose : 2.0mSv/yr The example of dose constraints for Korean NPPs design Maximum individual dose : 10mSv/yr, Average dose : 2.0mSv/yr Expected occupational dose Maximum individual dose : 7.0mSv/yr, Average dose : 0.84mSv/yr No meet for dose constraints. But the minimum workers involved and increase worker capability at operation/maintenance period

KEPCO RESEARCH INSTITUTE NUCLEAR POWER LABORATORY 19

KEPCO RESEARCH INSTITUTE NUCLEAR POWER LABORATORY 20

KEPCO RESEARCH INSTITUTE NUCLEAR POWER LABORATORY 21 The dose limits: 100mSv/5years(averaging 20mSv/yr) Occupational dose trend of Korean NPPs A total of 135,889 workers were monitored from 1990 to 2007 with the number continuously increasing over time The average annual doses have been continuously decreasing The number of workers receiving high doses has been decreasing since 1990 and no workers received a 20mSv/yr after 2000 Workers who received >15 and 10mSv/yr also decreased However, the fraction of >10mSv/yr is about 4% of total workers and the fraction of 15mSv/yr is about 1.3% of total workers Most exposure occurred during refueling period(23:77) The external dose accounted for 95% and 5% internal Dose Constraint for O/M : > 80% of limit(16mSv/yr)

KEPCO RESEARCH INSTITUTE NUCLEAR POWER LABORATORY 22 Exposure Pathways and Public Dose Calculations

KEPCO RESEARCH INSTITUTE NUCLEAR POWER LABORATORY 23

KEPCO RESEARCH INSTITUTE NUCLEAR POWER LABORATORY 24 DCs for public: Notice No Article 16(Detriment protection for the environment) Exposure pathway for public near Korean NPPs Contaminated food intake caused by tritium(about 90% or more) Multi reactor units in a site: Minimum 6 units and more 10 units (Maximum 3 units in USA) More conservative X/Q(smaller margin for public dose) Should be monitored for Carbon-14 (no margin for public dose) Koir SiteYonggwang SiteUlchin Site Atmospheric Dispersion Factor(sec/m 3 ) 2.973E E E-05 C 14 Public Dose (mSv/yr) H 3 Public Dose (mSv/yr) Total Percent for Notice No

KEPCO RESEARCH INSTITUTE NUCLEAR POWER LABORATORY 25 Should consider the main exposure pathways Gaseous exposure(>95%): Inhalation& food intake/consumption Liquid exposure(Minor): Seafood consumption More than 90% of total dose caused by tritium Cautious decision: Maximum individual, Representative person Draft dose constraint for the member of public No classification for gaseous and liquid effluents Dose constraint for single reactor init: 0.1 ∼ 0.2mSv/yr Dose constraint for a site : 0.6mSv/yr Delete the dose constraint for a site, if necessary Many comments and feedback from stakeholders Consider the difficulty of operation and maintenance for nuclear power plants

KEPCO RESEARCH INSTITUTE NUCLEAR POWER LABORATORY 26