Regional Basic Professional Training Course in Korea

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Regional Basic Professional Training Course (BPTC) on Nuclear Safety ⑦ Tables and Figures and shows many differences in format compared to US type operational technical specifications. Also, its operation modes are classified into 9 modes, which are shown in Table 10.2; however, the operation modes consist of mostly the same items included in the US standard technical specifications. Mode Number 1 2 3 4 5 6 7 8 9 Designation of standard operating mode Refueling Cold Shutdown Maintenance Cold Shutdown (RCS open) Normal Cold Shutdown Monophasic Inter Shutdown with RRA Biphasic Inter Shutdown conditional RRA Normal Inter Shutdown without RRA Hot shutdown P = 0 Hot standby P ≤ 2% RP Power operation 2%RP≤P≤RP Table 10.2 Operational Modes of Uljin No.1and No.2 NPP Core criticality deviation Neutron characteristics Shutdown and Control rod bank position ≥ 5000pcm All bank inserted ≥ 5000pcm All bank inserted ≥ 1000pcm ≥ 1000pcm ≥ 1000pcm ≥ 1000pcm ≥ 1000pcm and... 0 0 SA, SB and B banks at least are withdrawn except LCO 16.4.3.1 SA, SB and B banks at least are withdrawn SA, SB and B banks at least are withdrawn SA, SB and B banks at least are withdrawn SA and SB are withdrawn SA and SB are withdrawn and CBs are above insertion limit SA and SB are withdrawn and CBs are above insertion limit ❙ 654 ❙ Reactor coolant system pressure/temperature 10℃≤ T ≤60℃ atmospheric pressure 10℃≤ T ≤70℃ atmospheric pressure 10℃≤ T ≤90℃ 1 ≤ P ≤ 28 bars RCV pressure control (if applicable) 90℃≤ T ≤177℃ 24 ≤ P ≤ 28 bars RCV pressure control 120℃≤ T ≤177℃ 24 ≤ P ≤ 28 bars PZR pressure control P/T parameter is in area 6 in Fig F‐16‐1. PZR pressure control Tavg = 286℃(+3,‐2) P=155 bars PZR pressure control Same as Mode 7 286℃≤Tavg≤304.6℃ P=155 bars PZR pressure control
10.4.3.3. Canadian type NPP ❙ 655 ❙ 10-A. Limiting Conditions for Operation In the case of the CANDU type Wolsong unit 1, the Operating Policy and Principle (OP&P) that stated the LCOs was used as the technical specifications, when the NPP first initiated commercial operations in 1983. However the OP&P was considered to make up for its contents in more detail. In the meantime, licensees should submit the operational technical specifications that describe the plant operation and security by the Atomic Energy Act amendment. Operational technical specifications by the Atomic Energy Act is used in Wolsong unit 2,3 and 4 instead of the OP&P. However, the contents of LCOs in the Wolsong unit 2,3, and 4 are week in substance compared to the content of the operational technical specifications of Kori and Yonggwang NPPs. Operation modes have been initially classified into 4 modes considering the characteristics of the CANDU type nuclear reactors. However, the operation modes have been classified into five modes as has been shown in Table 10.3 in order to remove any ambiguities between operating conditions and operation modes. Operation Mode Table 10.3 Operational Mode of Wolsong NPP Reactor Output (% FP) Reactor Outlet Header Temp. (℃) 1. Power Operation > 2% > 260 2. Low‐power standby ≤ 2% > 100 3. Hot Shutdown 0 > 100 4. Cold Shutdown 0 ≤ 100 5. Secure shutdown 0 ≤ 60 Reactivity Conditions
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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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of these exchangers, the water is c
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Fig. 4.11. HANARO Core Pool Fig. 4.
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4.2.6.2.3 Reactor Systems ❙ 295
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4.2.6.5. Neutron Activity Analysis
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❏ physical separation. ❙ 303
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5. Siting Considerations Regional B
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5.4.2. Sources of risk 5.4.3. Evalu
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6. Safety Classification Of Structu
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Safety functions necessary to preve
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6.1.3. Principal Safety Classes 6.
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function; 6. Safety Classification
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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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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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❙ 799 ❙ 13.Maintenance Manageme
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15. Operational Safety 15.1. IAEA S
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❙ 831 ❙ 15. Operational Safety
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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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❙ 1079 ❙ 21. Safety Culture All
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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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