Regional Basic Professional Training Course in Korea

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Regional Basic Professional Training Course (BPTC) on Nuclear Safety 8.5.5. Increase in Reactor Coolant Inventory For a PWR, the initiating events that can result in increase in reactor coolant inventory are as follows: • Inadvertent operation of the ECCS; • CVCS malfunction – pressurizer level control system malfunction with loss of offsite power. The above two events are all AOOs. HOT AND AVERAGE CHANNEL FUEL AND CLAD TEMPERATURES, ℉ 50 00 40 00 30 00 20 00 10 00 FUEL CENTERLINE MAXIMUM AVERAGE CHANNEL MAXIMUM HOT CHANNEL FUEL RADIAL AVERAGE CLAD SURFACE 0 0 0 1 2 3 4 TIME, se conds Fig. 8‐5 Changes in Fuel and Clad Temperatures for a Control Element Assembly Ejection Inadvertent operation of the ECCS can be initiated either by control system malfunction ❙ 494 ❙ 2500 2000 1500 1000 500 HOT AND AVERAGE CHANNEL FUEL AND CLAD TEMPERATURES, ℃
or by operator error, often during testing of the ECCS. The safety aspects of the event are as follows: ❙ 495 ❙ 8-A. Deterministic Accident Analysis (Non‐LOCA) (a) RCS pressurization due to an increase of the coolant inventory. (b) Emergency injection of cold coolant, leading to non‐symmetric reduction of the coolant temperature at the RV inlet, potentially affecting vessel integrity. (c) Pressurizer overfilling that could lead to the pressurizer safety valve becoming stuck in the open position. (d) Containment pressurization in the case of loss of integrity of the pressurizer relief tank. CVCS malfunction may be initiated by a failure in the CVCS control system, which leads to an increase of the RCS coolant inventory. Safety aspects are the same as for the ECCS startup. Moreover, there is a potential for injecting non‐borated water, which would cause an RIA. Figure 8‐6 shows one example of predicted RCS and SG Pressures trends versus time for a CVCS Malfunction. PRESSURI ZER PRESSURE, psi a 2 6 0 0 2 5 0 0 2 4 0 0 2 3 0 0 2 2 0 0 2 1 0 0 2 0 0 0 1 9 0 0 1 8 0 0 1 2 7 0 3 0 0 6 0 0 9 0 0 1 2 0 0 1 5 0 0 1 8 0 0 TI ME, S E C O N DS 1 8 3 1 7 6 1 6 9 1 6 2 1 5 5 1 4 8 1 4 1 1 3 4 PRESSURI ZER PRESSURE, kg/c m 2 A STEAM GENERATOR PRESSURE, psi a 1 4 0 0 1 3 0 0 1 2 0 0 1 1 0 0 1 0 0 0 9 0 0 8 0 0 5 6 0 3 0 0 6 0 0 9 0 0 1 2 0 0 1 5 0 0 1 8 0 0 TI ME, S E C O N DS (a) RCS Pressure (b) SG Pressure Fig. 8‐6 Changes in RCS and SG Pressures for a CVCS Malfunction 9 8 9 1 8 4 7 7 7 0 6 3 STEAM GENERATOR PRESSURE, kg/c m 2 A
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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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F TEMPERATURE, o 0 100 200 300 400
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❙ 547 ❙ 8-B. Deterministic Acci
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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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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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