Regional Basic Professional Training Course in Korea

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Regional Basic Professional Training Course (BPTC) on Nuclear Safety nuclear site in the immediate vicinity of an active volcano is still out of the question, a location roughly ten kilometers away can often be considered after a serious analysis. Note moreover, that unlike many natural phenomena, the development of a volcanic crisis extends over a rather long period of time, from a few days to a few months. 5.3.2. Evaluation of the seismic risk Earthquakes have been a continuing concern for the nuclear energy sector worldwide. In the early years of nuclear power, seismic knowledge was very limited. But understanding of earthquake behaviour, along with instruments and methodologies to measure many seismic phenomena more accurately, has increased vastly over the past 30 years. New knowledge has triggered strengthening of the safety barriers of many nuclear plants. For example, the Diablo Canyon plant in quake‐prone California was upgraded to withstand a prodigious shock of 0.76g ("g" value is acceleration of gravity in seismic speak) as a result of a major US assessment programme. The main purpose of the present course is to provide guidance on the determination of the design‐basis ground motions for a nuclear power plant at a selected site. This text is based on the IAEA safety guide related to earthquakes (Safety Guide No. 50‐SGS1 [5.3]). The type of information required, and the investigations to be performed are described in the context of their dependence on the geological, seismological and geotechnical aspects of the region. 5.3.2.1. General requirements Ground motion, faulting, seismically generated water waves and permanent ground deformations associated with earthquakes and geological phenomena shall be investigated for every nuclear power plant site. The geological, geophysical and seismological characteristics of the region which surrounds the site shall be investigated, together with the geotechnical characteristics of the site area. However, the size of the ❙ 328 ❙
❙ 329 ❙ 5. SITING CONSIDERATIONS region to be investigated, the type of information to be collected and the scope and detail of the investigations shall be determined by the nature and complexity of the seismotectonic of the environment. Regardless of any lower apparent exposure to seismic hazard, it is recommended a minimum value of 0.1g peak ground acceleration corresponding to the safety level SL‐2 earthquake. A quality assurance programme shall be established and implemented to cover all the data collection, data processing, field and laboratory investigations and evaluations. 5.3.2.2. Required information and investigations (database) The elements of the database should be collected at four scales of investigation: regional, near regional, site vicinity and site area‐‐most intensively close to the site. The geographical area for regional (radius≥150 km) and near regional (radius = 25 km) investigation should be adjusted to the seismotectonical pattern and local conditions In most cases, the data can be obtained from either published or unpublished sources, supplemented by specific studies. Site vicinity investigations should provide a more detailed database, up to 5 km in radius, in order to understand the potential for permanent ground deformation, including surface faulting. Boreholes, trenching and geological mapping are likely to be required. Site area shall include investigation of the area covered by the plants (1 km2 or more) in order to add detailed knowledge on the potential for permanent displacement, and to provide information on the geotechnical properties of the foundation materials. All available information on historical and instrumental earthquakes that have occurred in the region shall be collected with their characteristics: date, time, epicentre and focal location, macroseismic intensities, magnitude, seismic moment, dimension and geometry of the after shock zone, focal mechanism, intensity at the site accompanied with any available details on soil effects, as well as estimates of uncertainty for each parameters. To supplement the available data, it may be useful to operate a site‐specific network of
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1. Nuclear Reactor Principles · 1
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1. Nuclear Reactor Principles Regio
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Table 1.2. Average cross sections f
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1. Nuclear Reactor Principles ❙ 7
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energy of the fuel nuclei. ❙ 9
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❙ 11 ❙ 1. Nuclear Reactor Princ
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1 Bq = 2.7x10 -5 µCi = 2.7x10 -8 m
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1.1.5. Natural radioactive series
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238 U 92+ 1 n0 -----> 135 Te 52 + 9
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σ t = σ s + σ a = σ elastic +
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FIG. 1.10. And here in the 1keV to
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1.2.3.2. Neutron emission in fissio
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Three possible states could then be
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TABLE 1.3. Slowing down efficiency
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1 UNGG/AGR CANDU PWR/BWR TABLE 1.5.
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✼✼✼ REFERENCES ✼✼✼ ❙
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2.1. Introduction C O N T E N T S 2
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2. Radiation Protection 2.1. Introd
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2.2.1. Exposure ❙ 61 ❙ 2. Radia
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❙ 63 ❙ 2. Radiation Protection
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2.2.4. Effective dose ❙ 67 ❙ 2.
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schematically in Fig. (2.7). ❙ 77
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The great utility of the G‐M tube
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protection conditions. These factor
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2.6.2. Effects of dose, dose‐rate
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2.7. Principles of Radiological Pro
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❙ 115 ❙ N 0 = N 2 1 t / t 1/ 2
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ln 10 = μ t1/10 ≈ 3 · ln 2 = 3
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C O N T E N T S | Table of Contents
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Fig. 1 Committees for IAEA Safety S
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Regional Basic Professional Trainin
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❙ 221 ❙ 4. DESIGN OF NUCLEAR RE
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4.1.1.2. The concept of defence in
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4.1.2. Requirements for management
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administrative control. ❙ 231 ❙
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Design basis accidents ❙ 237 ❙
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Single failure criterion ❙ 239
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Deterministic approach The determin
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accidents, with account taken of th
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Fuel elements and assemblies Fig. 4
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Reactor shutdown ❙ 251 ❙ 4. DES
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functional in the event of a severe
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4.1.5.4. Instrumentation and contro
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4.1.5.9. Radiation protection Gener
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6. Safety Classification Of Structu
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the safety function would be requir
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6.3.2. Description of Quality Group
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6.4.3. Seismic category 1: 6.4.3.1.
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7. Quality Assurance Regional Basic
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7.5.1. Manufacture Quality Assuranc
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C O N T E N T S 8.1. INTRODUCTION |
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❙ 471 ❙ 8-A. Deterministic Acci
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guidelines for this categorization.
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Table 8‐3 Typical Initial Conditi
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8.5.3. Decrease in Reactor Coolant
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or by operator error, often during
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8-B. Deterministic Accident Analysi
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| List of Tables | Table 8.7‐1 Ru
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❙ 509 ❙ 8-B. Deterministic Acci
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SG Containment RCP RCP RCP SIT SIT
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8.2.5. Evaluation Model ❙ 521 ❙
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Figure 8.7‐7 Flow chart of KREM
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Cladding Temperature (K 1300 1200 1
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8.8.1.6. Loop Seal Formation and Cl
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to ECCS injection time using CEFLAS
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Table 8.8‐2 SBLOCA Break Spectrum
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F TEMPERATURE, o 0 100 200 300 400
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8.8.2.2.3 RELAP5‐sEM Methodology
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9. Probabilistic Safety Analysis Re
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9.4. LEVEL 2 PSA 9.4.1. Objectives
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performance, correct set points, an
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injecting borated water into the pr
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Positive reactivity insertion rates
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10.4.3.3. Canadian type NPP ❙ 655
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2) Safety Limits and Safety System
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the technical specifications is not
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10-B. Technical Specifications for
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10.7.7.1. Monitoring Systems 10-B.
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10.8.1. Reactor Core Parameters 10-
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10.8.6. Emergency Power 10-B. Techn
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authorized by responsible authority
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11. Human Performance: A Perspectiv
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Figure 11.1 Model of violation Figu
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12. Surveillance Programmes Regiona
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12.4. IMPLEMENTATION 12.4.1. Genera
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13.Maintenance Management in KHNP R
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15. Operational Safety 15.1. IAEA S
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and modified if required. ❙ 837
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15.2.2. Organization and functions
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− Temporary and permanent plant m
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Operating procedures and instructio
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Off‐normal conditions are easily
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15.2.6. Work authorizations ❙ 859
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conventional hazards at the point o
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commissioning process. ❙ 869 ❙
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Event reports and root cause analyz
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Material regarding evaluation of ex
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Monitoring of initiatives in progre
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16. In‐Plant Accident Management
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❙ 895 ❙ 16. In‐Plant Accident
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16.2.2. Safety Functions ❙ 899
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is to place the plant in a safe, st
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each a final stable and controlled
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16.3.5. Review of Korean SAMG by KI
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this stage. Control rod degradation
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Pressurization of the containment
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Fractional Relase Fractional Relase
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19. Decommissioning Regional Basic
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| List of Tables | Table 1. Stages
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20.1. Introduction C O N T E N T S
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21. Safety Culture Regional Basic P
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21. Safety Culture 21.1. DEFINITION
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FIG. 21.1. Basic elements of safety
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❙ 1059 ❙ 21. Safety Culture Ult
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Obtaining useful information from o
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terms of what they do. There is an
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Consequently, people also understan
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❙ 1067 ❙ 21. Safety Culture 21.
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organization e.g. contractors. ❙
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21.4. MANAGEMENT OF SAFETY 21.4.1.
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subdivided in 4 sub‐objectives, w
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21.4.4. Specific safety management
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AtomCARE Regional Basic Professiona
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AtomCARE 1. OVERVIEW OF NATIONAL RA
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❙ 1121 ❙ AtomCARE The RETAC of
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❙ 1123 ❙ AtomCARE secondary rad
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❙ 1125 ❙ AtomCARE actions by pr
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2.1.4. Component Modules (Configura
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Classification Major Functions Tech
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❙ 1131 ❙ AtomCARE containment b
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❙ 1133 ❙ AtomCARE b) Monitors a
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a) Calculates the distribution of t
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❙ 1137 ❙ AtomCARE telephone or
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Introduction Of e‐FAST and Exerci
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| List of Figures | Fig. 1.1 Schema
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C O N T E N T S 1.1. OVERVIEW OF TH
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❙ 1181 ❙ Nuclear Safety Informa
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1. Overview of OPiS C O N T E N T S
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Regional Basic Professional Training Course in Korea

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