Regional Basic Professional Training Course in Korea

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1. Nuclear Reactor Principles · 1 2. Radiation Protection · 55 3. Basic Principles of Nuclear Safety · 121 4. Design of Nuclear Reactors · 217 5. Siting Considerations · 305 6. Safety Classifications of Structures, Systems and Components · 357 7. Quality Assurance · 407 8-A. Deterministic Accident Analysis (Non‐LOCA) · 467 8-B. Deterministic Accident Analysis (LOCA) · 503 9. Probabilistic Safety Analysis · 555 10-A. Limiting Conditions for Operation · 623 10-B. Technical Specifications for Research Reactors & Non‐power Reactors · 667
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Regional Basic Professional Trainin
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2. Radiation Protection Regional Ba
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Table 2.1. Radiation Weighting Fact
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3. Basic Principles Of Nuclear Safe
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3.5. ROLE OF SUCCESSIVE BARRIERS IN
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❙ 127 ❙ 3. Basic Principles Of
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Safety Requirements; and, Safety Gu
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NUSSC Nuclear Safety Standards Comm
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A detailed analysis of the objectiv
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3.2.4. Technical aspects of safety
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are of very low probability. ❙ 15
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3.2.5. Verification of safety ❙ 1
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Efficient control of the chain reac
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First level: prevention of abnormal
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Quality control Fig. 5 Defense in d
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Fission product decay ❙ 175 ❙ 3
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Neutron activation of other materia
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Cladding failure ❙ 181 ❙ 3. Bas
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Evacuation ❙ 189 ❙ 3. Basic Pri
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criteria, regulations and guides;
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carried out; (11) Define liabilitie
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authorization and periodically duri
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(2) Public and occupational health;
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activity; ❙ 203 ❙ 3. Basic Prin
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egulatory framework is established;
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4. Design Of Nuclear Reactors Regio
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Fig.4.1. Concept of Defence‐in‐
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C O N T E N T S | Table of Contents
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5. Siting Considerations ❙ 309
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❙ 311 ❙ 5. SITING CONSIDERATION
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evaluated. ❙ 315 ❙ 5. SITING CO
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5.1.4. Population and emergency pla
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determine their liquefaction potent
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5.3.3.1. Marine floods ❙ 335 ❙
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and its time of arrival at the site
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Dry deposit The rate of dry deposit
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etention of radioelements by sedime
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5.6.1. General 5.6. DEMOGRAPHY AND
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6. Safety Classification Of Structu
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6.5. ELECTRICAL EQUIPMENT CLASSIFIC
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C O N T E N T S 7.1. NUCLEAR QUALIT
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7.1.1. Definition 7. Quality Assura
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independence of inspection. ❙ 413
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❙ 415 ❙ 7. Quality Assurance 7.
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7.2.3. Statute Related to Review an
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6. Document control 7. Control of p
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1. ‥‥‥‥‥‥‥ : : 17. In
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Operator Production Specializatio n
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￭ CSA N286.3: Construction and In
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Table 1. Comparison of nuclear qual
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❙ 429 ❙ 7. Quality Assurance (2
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systems and components. ❙ 431 ❙
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❱ Article 78 (Test Control) ❙ 4
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❙ 439 ❙ 7. Quality Assurance (h
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❙ 441 ❙ 7. Quality Assurance co
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❙ 443 ❙ 7. Quality Assurance ot
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❙ 447 ❙ 7. Quality Assurance in
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7.4.1. Introduction 7.4. QUALITY AS
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7.4.3. Type of Audit ❙ 451 ❙ 7.
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❙ 453 ❙ 7. Quality Assurance Qu
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❙ 457 ❙ 7. Quality Assurance ap
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7.5.1.2 Inspection Methods and Cont
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KINS/PI‐QM‐20 Welder qualificat
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8-A. Deterministic Accident Analysi
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| List of Tables | Table 8.1 Event
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Figure 8.8‐11 Core Level of 0.5 f
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C O N T E N T S 9.1. BASIC CONCEPT
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9.1.1. Background 9. Probabilistic
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❙ 561 ❙ 9. Probabilistic Safety
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that are important for safety and d
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Some typical uses of level 2 PSA ar
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Release of fission products during
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e indicated according to their spec
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several pumps due to an inappropria
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Parts common to a number of systems
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9.4.3. Level 1 - level 2 interface
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In-vessel processes during the late
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y data, analyses and consideration
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examples of useful insights of PSAs
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Assessment -vs- demonstration. PSA
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✼✼✼ REFERENCES ✼✼✼ ❙
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10-A. Limiting Conditions for Opera
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Table 10.2 Operational Modes of Ulj
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C O N T E N T S 11.1. THE HUMAN FAC
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11. Human Performance: A Perspectiv
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Methods Questions/Evaluations propo
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documented by pencil goes through.
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B. Model of Mistake 11. Human Perfo
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C. Model of Slips 11. Human Perform
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They can belong to one of these fam
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12. Surveillance Programmes 12.1. C
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12.2.2. Surveillance of integrity o
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Containment spray systems; Chemical
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High energy piping and associated p
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failure of which might put in jeopa
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12.3.6. Equipment ❙ 773 ❙ 12. S
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The grading criteria for detection
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12.4.1. General 12.4. IMPLEMENTATIO
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monitors are part of the safety sys
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inspection. ❙ 789 ❙ 12. Surveil
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12.5.4. Example of Regulatory Inspe
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maximum flow in addition to rated f
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C O N T E N T S 1. The Overview of
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15. Operational Safety Regional Bas
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15.3. OPERATING ORGANIZATION AT KOR
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16. In‐Plant Accident Management
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16.5.3. Reference source terms Tabl
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17. Radiological Emergency Planning
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2. Emergency Classification and Res
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19. Decommissioning 19.1. IAEA SAFE
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from regulatory control. ❙ 999
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material (of the order of 300 μSv
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methods of decommissioning the nucl
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✼✼✼ REFERENCES ✼✼✼ ❙
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20. Waste Management Regional Basic
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20. Waste Management 20.1. INTRODUC
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shall be appropriately taken into a
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20.5.3. Solidification of waste The
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Nuclide Half‐life Decay character
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For disposal of LILW from NPPs, the
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C O N T E N T S 21.1. DEFINITION AN
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Licensing Process of Nuclear Facili
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C O N T E N T S 1. Introduction to
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Introduction Of e‐FAST and Exerci
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❙ 1145 ❙ Introduction Of e‐FA
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[Fig. 1.6] Schematic of RCS(Reactor
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[Fig. 1.9] Schematic diagram of BOP
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2.1.3. e‐FAST Function [Fig. 2.3]
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2.2 USER MANUAL 2.2.1. General Guid
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[Fig. 2.4] e‐FAST for KSNP 2.2.2.
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14.1~2 Main Steam Line Break Inside
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Summary [Fig. 2.6] Trend graph of v
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[Table 3.1] Simulation result for p
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[Fig. 3.1] Trend of major system pa
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[Fig. 3.3]Trend of major system par
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Nuclear Safety Information Center (
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| List of Tables | Table 1. Informa
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Operational Performance Information
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2.5. References Operational Perform
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