Regional Basic Professional Training Course in Korea

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Regional Basic Professional Training Course (BPTC) on Nuclear Safety 10.4.4. Improvement Status of Operational Technical Specifications The operational safety of an NPP should always be considered and approached systematically from the siting process and even for a substantial period after the decommissioning of the NPP. Especially, the operational safety is maintained by tests, maintenance, and periodic inspections to make sure that the appropriate actions of safety related systems are activated to mitigate accidents or transients along with insuring that safety related system and components actuate appropriately during design basis accidents or severe accidents and confirming the prevention of accidents. The operational technical specifications make all of these actions legally binding to insure operational safety and prescribe Safety Limits, Limiting Safety System Settings, Limiting Conditions for Operation (Conditions, Applicability, Action, Surveillance Requirement), and Administrative Control to prevent accidents and to confirm the safety in cases of accidents. In other words if an NPP is operated according to the operational technical specifications, the NPP can be controlled at a level that is permissible to the public during normal operations, transients, and design basis accidents. Korea has imported NPPs from the US, France, and Canada and has constructed the NPPs according to the technical standards and systems of each country of import. Korean utility has also used the respective unedited operational technical specifications of each country of import which is believed to have been written according to the inherent characteristics and design philosophies of each country's NPP. However, since the foreign vendor develops the operational technical specifications, the content of the operational technical specifications could not be understood sufficiently enough, thus causing difficulties when the regulatory body tried to incorporate its intentions. Moreover, although the regulatory requirements of the operational technical ❙ 656 ❙
❙ 657 ❙ 10-A. Limiting Conditions for Operation specifications should only include essential NPP safety related items that have been derived from analyses/assessments of safety analysis reports, up to this point, requirements related to the operation of nuclear reactors tended to also be included in the operational technical specifications. The reason behind such broad usage of the operational technical specifications is due to the lack of well defined criteria. Furthermore due to this matter, frequent demands were made to modify the technical specifications, which resulted in the increased volume of the technical specifications. The absence of consistency made it difficult for both the regulatory body as well as the industry. Therefore, according to each type of domestically operating reactor, regulatory philosophies and methods, inherent design concepts, and technical background interpretations of each country of import were researched to develop an appropriate standard operational technical specification while considering the domestic regulatory system and levels of technology1), 2),. 10.4.5. Operational Technical Specification Writing Format 10.4.5.1. Initial Operational Technical Specifications The initial operational technical specifications were developed in an operator oriented fashion according to the necessary items and individual characteristics of each NPP from a radiological viewpoint. Table 10.4 shows a typical example of an initial operational technical specification that discusses the limiting conditions for operation of the reactor 1) Korea Electric Power Corporation (KEPCO) Yonggwang Unit 2, “Pressurized Water Reactor (CE type) Standard Operational Technical Specifications", Topical Report, KEPCO Tech‐0005, 1999.9 2) Korea Electric Power Corporation (KEPCO) Kori Unit 2, “Pressurized Water Reactor (WH type) Standard Operational Technical Specifications", Topical Report, KEPCO Tech‐0005, 2000.3
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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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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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