Regional Basic Professional Training Course in Korea

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Regional Basic Professional Training Course (BPTC) on Nuclear Safety because they know what is right, not because it is required. 21.4.4.3. Sustainability Humans tend to choose the easiest way, to forget things, to stop thinking, and to transfer carefully considered procedures into automatically followed routines. Therefore, safety culture is an inherently declining feature. If we do not continually strive to enhance it, it gradually degrades. We constantly have to move forwards, even standing still means stepping backwards. The management of safety has to establish an ongoing learning process as part of the safety culture; otherwise an established standard cannot be maintained. 21.4.4.4. Performance indicators Monitoring the safety performance is a management responsibility. The use of quantitative performance indicators has a lot of advantages (e.g. enabling trending, goal setting and benchmarking with other plants), but care should be taken not to give them too high a value in order to avoid misleading effects. For example, if reaching a low number of “unplanned automatic scrams” is valued very highly; pressure could rise to adjust the set points for triggering the scram “appropriately”. Or, with regard to the “collective dose”, people could find themselves seduced to reduce equipment tests, or they could welcome a reason for not performing inspections of the workplace and work practices (this problem is independent of the more general dispute on the appropriateness of this indicator due to substantial doubts regarding the validity of the linear‐no‐threshold hypothesis, which is the base of the “collective dose”). As a last example, the number of “significant events” as a performance indicator could increase tendencies to cover up or to play down the importance of the event. Very probably, every indicator can exert negative influences, if it is valued too highly. So, performance indicators are useful and probably even necessary, but they should be used with care and the management should clearly explain their limited importance. ❙ 1088 ❙
21.4.4.5. Self assessment ❙ 1089 ❙ 21. Safety Culture As already stated, safety culture tends to degrade with time. This problem is amplified by the very nature of humans, which impedes early recognition of declining performance. First signs and precursors are often denied or just regarded as isolated cases. This psychological defence mechanism is principally stronger when the information about negative signals comes from outside institutions. The other way around, it is generally easier to accept unpleasant news, if they are detected by ones self. Therefore, it is preferable for an organization to have an internal or self‐evaluation program. This self‐ assessment generally can identify signs of degradation earlier than an external audit or review. If detection is left to the latter (or even to actually occurring events), the required corrective actions are often far more extensive and expensive to implement. Of course, the critical self‐assessment has to be complemented by clearly prioritized action plans, which address the root causes, and which are pursued rigorously. The self‐assessment reinforces the responsibility of the operator. But to avoid complacency and professional blinkers, the self‐evaluation program should be supported by periodic external peer reviews. The frequency of these external reviews can be much less than that of the internal assessments, but from time to time an external check seems to be a sound corrective. 21.4.4.6. Indivisibility Safety is indivisible. Low standards in industrial safety or in housekeeping, a large backlog in maintenance work, a poor archiving system, and all similar conditions give clear evidence of threats to nuclear safety. 21.4.4.7. Top is top, but only the number makes it work The strong commitment of senior management is a prerequisite to establish and maintain a high safety culture. But the strongest commitment from senior managers cannot
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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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❙ 627 ❙ 10-A. Limiting Conditio
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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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❙ 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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Page 1139 and 1140: ❙ 1133 ❙ AtomCARE b) Monitors a
Page 1141 and 1142: a) Calculates the distribution of t
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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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