Regional Basic Professional Training Course in Korea

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Regional Basic Professional Training Course (BPTC) on Nuclear Safety sensitive seismographs for a minimum period of several years. Wherever possible, regional strong motion recordings shall be collected and used for deriving appropriate seismic wave attenuation functions and in developing the design response spectra. Geological data should be collected on the four scales investigation. Regional studies to provide the geological and tectonic framework, and to identify those geological features that may influence or relate to the seismic hazard at the site shall be performed. Near region investigations to amplify the existing information: geological mapping associated with geophysical field survey and neotectonic studies to determine the latest movements of faults also shall be carried out. To define in greater detail the neotectonic history of faults and to identify sources of potential instability, investigations of the site vicinity shall be conducted. These investigations should examine geological maps with cross‐ sections, trenching and age dating, characterization of the seismic stability of slopes, and potential for induced seismicity (large dams or reservoirs). Geological, geotechnical, hydrogeological and site effects investigations should be performed in the site area to determine the physical properties of the foundation materials, and their stability and response under dynamic earthquake loading. 5.3.2.3. Construction of a regional seismotectonic model The regional seismotectonic model should be based on a coherent merging of the total regional database. Such a model consists of identifying seismogenic structures and zones of diffuse seismicity for which the maximum earthquake potential has to be evaluated. The identification of the seismogenic structures is made on the basis of geological and geophysical features, in correlation with historical and instrumental earthquakes to determine the associated potential maximum earthquake. The dimensions of the structure, amount and direction of displacement, maximum historical earthquake, paleoseismological data, and earthquake frequency should be used in this determination and, if possible, maximum magnitude potential associated with these structures should be ❙ 330 ❙
❙ 331 ❙ 5. SITING CONSIDERATIONS evaluated. The zones of diffuse seismicity or seismotectonic province (concept of active crustal volumes) for which is assumed an area of equal seismic potential is used when seismogenic structures cannot be identified. The boundaries of those zones may be delimited by different tectonic conditions as significant differences in rates of seismicity or in hypocentral depth. The maximum earthquake potential should be evaluated on the basis of historical data and the seismotectonic characteristics of the zone, including rate of strain release. 5.3.2.4. Determination of design basis ground motions At least two levels (SL‐1 and SL‐2) of design basis ground motion are evaluated for each plant, based on the seismotectonic model. The SL‐2 level corresponds to a ground motion of very low probability of being exceeded during the lifetime of the plant and represents the maximum level to be used for design purposes. The SL‐1 level corresponds to a less severe, more likely earthquake load condition which has different safety implications than SL‐2. The factors that may influence decisions on the level of ground motion chosen are: seismotectonic setting, design considerations, post‐earthquake situation or plant inspection considerations. The design basis ground motions (SL‐1 and SL‐2) are usually characterized by time histories and response spectra for several damping values. When sufficient data are available, a site‐specific response spectrum is calculated directly for both levels. However, current practice is to choose a standard spectrum shape that is scaled to a prescribed level of free field acceleration (or velocity or displacement). Intensity and magnitude data are relevant for estimating the characteristics of the design‐ basis ground motions: attenuation, response spectra and duration. Intensity based calculations may be appropriate when the database is rich in historical and macroseismic information and attenuation relationships can be derived from isoseismal maps of past earthquakes in the region. After the design‐basis intensity at the site has been established, the corresponding maximum ground acceleration or velocity should be obtained using relevant empirical relationships. Magnitude based calculations may be appropriate when
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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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Operation at a power level < 1 MW.
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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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15.2.7. Accident management ❙ 863
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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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21.4.4.5. Self assessment ❙ 1089
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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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