Regional Basic Professional Training Course in Korea

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Regional Basic Professional Training Course (BPTC) on Nuclear Safety The NSSS main components inspection schedule, Appendix 1‐1 also indicates the frequency of inspections on reactor licensee activities, and if one manufacturer or supplier produces many types of components, inspection criteria and frequency of the component having longest manufacturing term applies. NSSS Main Component Manufacture QA Inspection Schedule Inspection Procedure Schedule (months after initial QA program review) Procedure No. Inspection area 0 3 6 9 12 15 18 21 24 27 30 33 36 (Phase 1) Quality Assurance Program Review KINS/PI‐QM‐01 Quality assurance program ○ ● KINS/PI‐QM‐02 Authorized inspection ○ ○ ○ KINS/PI‐QM‐03 Nonconformance and corrective actions (Phase 2) Quality Assurance Program Implementation ❙ 460 ❙ ○● ○ ○● ○ ○● ○ ○● ○ ○● ○ ○● ○ KINS/PI‐QM‐05 Design process and design document control ○ ○ KINS/PI‐QM‐06 Quality audit ○ ○ KINS/PI‐QM‐07 Personnel indoctrination and training ● ○ ● ○● KINS/PI‐QM‐08 Control of procedures, instructions, and drawings ● ○ ● ● ○ KINS/PI‐QM‐09 Process control ○ ○ ○ KINS/PI‐QM‐10 Material identification and control of materials ○ ○ KINS/PI‐QM‐11 Handling and storage of items ○ ○ ○ KINS/PI‐QM‐12 Control of measuring and test equipment ○ ○ KINS/PI‐QM‐14 Welding procedure and procedure qualification ○ KINS/PI‐QM‐15 Welding material control ○ ○ KINS/PI‐QM‐16 Weld joint preparation and welding ○ ○ ○ KINS/PI‐QM‐17 Post‐weld heat treatment ○ ○ KINS/PI‐QM‐19 Application of special welding process ○
KINS/PI‐QM‐20 Welder qualification ○ ○ ○ ❙ 461 ❙ 7. Quality Assurance Review of Surface inspection (MT, PT) ○ KINS/PI‐QM‐21 Review of SG tube ECT ○ Review of Volumetric inspection (UT, RT) ○ KINS/PI‐QM‐22 Casting and forging ○ ○ KINS/PI‐QM‐23 Material forming ○ ○ KINS/PI‐QM‐24 Product testing ○ KINS/PI‐QM‐18 Quality inspection ● ● ● (Phase 3) Quality Assurance Program Validity KINS/PI‐QM‐01 Quality assurance program ○ ○ ○ KINS/PI‐QM‐04 Subcontractor control ○ ● ○ ● ○● KINS/PI‐QM‐13 Quality assurance records ● ● ○● ○ (*) Columns marked with ∙ are inspection schedule for reactor licensee 7.5.1.4 Inspection Details per Each Inspection Objects Reactor Licensee Inspection: Reactor licensee inspections are performed as scheduled inspections. The inspection should determine whether the reactor licensee established an appropriate inspection program based upon safety importance, and implements the program adequately, and verifies and approves contractors' disposition for noncompliance and/or deficiencies in design, fabrication, testing. If necessary for this purpose, reactive inspections may be performed in addition to scheduled inspections. The followings shall be determined in reactor licensee inspections: Whether quality assurance standards (Article 68 or Article 85 of Regulations on Technical Standards for Nuclear Reactor Facilities, and Article NCA‐4000 of ASME Sec.Ⅲ or KEPIC MNA) are satisfied. Whether the quality assurance program and technical specifications submitted as construction permit application documents are complied.
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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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❙ 511 ❙ 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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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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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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