Format and Content of the Safety Analysis Report for Nuclear Power Plants - Application Set -

Transcription

1 Format and Content of the Safety Analysis Report for Nuclear Power Plants - Application Set

2 Contents 1. Overview 2. Chapters and Content of a SAR Chapter 1 General Information Chapter 2, 3, 4, Chapter 17 Chapter 18 Human Factors Engineering 3. Summary

3 1. Overview Comparison with IAEA Standards Initial (preliminary) or, pre-construction SAR (PCSAR) Updated (intermediate) or, pre-operation SAR (POSAR) Finalized (final) or, station SAR (SSAR) - Detailed design information & supporting calculations - Safety features incorporated into the design - Possible challenges to the plant - More specific information on the topics in initial SAR - Finalized detailed plant design & demonstration of its safety - Revision of plant in as-built Preliminary SAR (PSAR) Final SAR (FSAR)

4 1. Overview Comparison with IAEA Standards Chapter & Content of SAR (GS-G-4.1) Chapter I: Introduction Chapter II: General plant description Chapter III: Management of safety Chapter IV: Site evaluation Chapter V: General design aspects Chapter VI: Description & conformance to the design of plant systems Chapter VII: Safety analyses Chapter VIII: Commissioning Chapter IX: Operational aspects Chapter X: Operational limits & conditions Chapter XI: Radiation protection Chapter XII: Emergency preparedness Chapter XIII: Environmental aspects Chapter XIV: Radioactive waste management Chapter XV: Decommissioning & end of life aspects Chapter & Content of SAR (Korea) Chapter 1: General information Chapter 2: Site characteristics Chapter 3: Installation of SSC Chapter 4: Reactor Chapter 5: Reactor coolant system Chapter 6: Engineered safety features Chapter 7: Instrumentation and control Chapter 8: Electric power Chapter 9: Auxiliary system Chapter 10: Steam& power convers. system Chapter 11: Rad-waste management Chapter 12: Radiation protection Chapter 13: Organization Chapter 14: Initial test (PSAR), COO (FSAR) Chapter 15: Accident analysis Chapter 16: Technical specification Chapter 17: Quality assurance Chapter 18: Human factors engineering

5 1. Overview Comparison with IAEA Standards Chapter & Content of SAR (GS-G-4.1) Ch. I: Introduction Ch. II: General plant description Ch. III: Management of safety Ch. IV: Site evaluation Ch. V: General design aspects Ch. VI: Description & conformance to the design of plant systems Chapter & Content of SAR (Korea) Ch. 1: General information Ch. 3: Installation of SSC Ch. 17: Quality assurance (without Safety Culture) Ch. 2: Site characteristics Ch. 4: Reactor Ch. 5: Reactor coolant system Ch. 6: Engineered safety features Ch. 7: Instrumentation and control Ch. 8: Electric power Ch. 9: Auxiliary system Ch. 10: Steam& power convers. Sys.

6 1. Overview Comparison with IAEA Standards Chapter & Content of SAR (GS-G-4.1) Ch. VII: Safety analyses Ch. VIII: Commissioning Ch. IX: Operational aspects Ch. X: Operational limits & conditions Ch. XI: Radiation protection Ch. XII: Emergency preparedness Ch. XIII: Environmental aspects Ch. XIV: Radioactive waste management Ch. XV: Decommissioning & end of life aspects Chapter & Content of SAR (Korea) Ch. 15: Accident analysis Ch. 14: Initial test Ch. 13: Organization Ch. 18: Human factors engineering Ch. 16: Technical specification Ch. 12: Radiation protection * Extra Document * Extra Environmental Report (ER) Ch. 11: Rad-waste management * Different Process

7 1. Overview

8 Chapter 1: General Information a. Overview of the application for a permit b. Major characteristics of reactor facilities and the site - Principal site characteristics, site location, population distribution, plant arrangement, etc. - NSSS, Reactor core, RCS, ESF, SIS, HVAC, MCR, Electrical sys., BOP, Fuel handling and storage. EDG, etc. c. Details of comparison with other similar reactor facilities

9 c. Details of comparison with other similar reactor facilities (Example)

10 Chapter 1: General Information d. Parties to the contract for construction of reactor facilities and the scope of their responsibilities - KHNP, KEPCO E&C, DOOSAN, KEPCO NF, Constructor e. Additional technical data to be submitted - Drawings and diagrams - Regulatory compliance, industry codes and standards (ASME, KEPIC, IEEE, etc.)

11 2. Chapters and Contents of SAR - Regulatory compliance, industry codes and standards (Example)

12 Chapter 2: Site Characteristics a. Geographic characteristics and status of population distribution b. Nearby industrial, transportation and military facilities c. Meteorology d. Hydrologic engineering e. Geology, seismology and geotechnical engineering

13 Chapter 2: Site Characteristics (Example)

14 Chapter 3: Installation of SSC a. Compliance with design criteria b. Classification of structures, components, equipment and systems c. Protective measures against natural hazards including, but not limited to, hurricanes, floods and tsunamis, missiles or falling objects, or a postulated pipe rupture and so forth

15 b. Classification of structures, components, equipment and systems

16 Chapter 3: Installation of SSC d. Seismic design e. Design of structure of containment and other facilities pertaining to the safety of nuclear reactors f. Design of mechanical structures, facilities and components thereof g. Seismic and environmental qualification design of safety-related equipment

17 g. Seismic and environmental qualification design of safety-related equipment

18 g. Seismic and environmental qualification design of safety-related equipment

19 Chapter 4: Reactor a. Design of nuclear fuel systems b. Design of reactor cores c. Thermohydraulic design d. Materials of nuclear reactors - CEDM and reactor internals e. Design of reactivity control systems

20 a. Design of nuclear fuel systems

21 a. Design of nuclear fuel systems

22 b. Design of reactor cores

23 Chapter 5: Reactor Coolant System a. Overview of the nuclear reactor cooling system and components b. Pressure boundary of the nuclear reactor cooling system c. Reactor vessel d. Component design e. Subsystem design

24 a. Overview of the nuclear reactor cooling system and components

25 a. Overview of the nuclear reactor cooling system and components

26 b. Pressure boundary of the nuclear reactor cooling system IRWST M M Vent Sample IRWST POSRV(4) Aux. Spray Spray RCP 1B RCP 2A Main Steam Loop 1B Pressurizer Loop 2A Main Steam Steam Generator No. 1 Surge Line Steam Generator No. 2 Vent Sample RDT SIS SCS SIS SCS Letdown (CVCS) MFW Sample Loop 1 Reactor Vessel Loop 2 RDT MFW RDT RDT RCP 1A Loop 1A SCS SIS SCS Charging(CVCS) SIS SCS Refuel Level SCS Spray Loop 2B RCP 2B RDT

27 b. Pressure boundary of the nuclear reactor cooling system

28 Chapter 6: Engineered Safety Features a.engineered safety systems - Containment isolation system, Safety injection system, Safety depressurization system, Containment spray system. b. Containment systems - Containment function design, Combustible gas control, Containment leakage testing c. Safety injection systems

29 Chapter 6: Engineered Safety Features d. Control room habitability systems e. Fission product elimination and control system - ESF filter system, Containment spray system. f. Safety depressurization and vent system g. In-containment refueling water storage system (IRWST) h. In-service inspection of the above items

30 g. IRWST and Cavity Flooding System

31 Chapter 7: Instrumentation & Control a. Reactor protection system b. Actuation system of engineered safety features c. Safe shutdown systems d. Safety related display instrumentation e. Diverse instrumentation and control system f. Automatic seismic trip system g. Data communication systems

32 a. Reactor protection system

33 Chapter 8: Electric Power a. Overview b. Off-site electrical power systems c. On-site power systems - AC and DC power system, Fire protection for cable system d. Station blackout - SBO coping analysis

34 Chapter 9: Auxiliary Systems a. Nuclear fuel storage and handling systems b. Water systems c. Process auxiliary system d. Heating, ventilating and air conditioning systems e. Fire protection systems f. Emergency diesel engine system

35 Chapter 10: Steam & Power Conversion Systems a. Overview b. Turbine generator - System description, Inspection and testing requirements c. Main steam supply systems - System description, Inspection and testing requirements, Secondary water chemistry, Steam and feed-water system material

36 Chapter 11: Rad-Waste Management a. Sources of radioactive wastes b. Solid waste control systems c. Liquid waste control systems d. Gaseous waste control systems e. Monitoring and sampling systems

37 Chapter 12: Radiation Protection a. Protection program for radiation workers b. Radiation source c. Radiation protection design d. Radiation dose evaluation method e. Health physics programs

38 Chapter 13: Organization a. Management system b. Job education and training c. Management procedures

39 Chapter 14: Initial Test a. Scope of the initial test program b. Matters pertaining to the initial test organization c. Overview of the initial test program regarding inherent characteristics or special design features of the power plant d. Regulations related to the formulation and execution of a test program and plan to utilize industry codes

40 Chapter 14: Initial Test e. Measures to take advantage of the operational and testing experiences of other similar power plants f. Schedule of a test program g. Overview of the pilot application of power plant operation procedures and emergency operating specifications h. Plan to supplement staff in the course of the execution of a test program

41 Chapter 15: Accident Analysis a. Safety Objective and Acceptance Criteria b. Identification and Classification of PIEs c. Deterministic Analysis d. Results of the Safety Analysis Chapter 16: Technical Specification - The form of controls, limits, conditions, rules and required actions for the safe operation

42 Chapter 17: QA 1. Organization of a quality assurance system 2. Quality assurance program 3. Design control 4. Procurement document control 5. Instructions, procedures and drawings 6. Document control 7. Control of purchased items and services 8. Identification and control of items 9. Control of special process

43 Chapter 17: QA 10. Inspection 11. Test control 12. Control of measuring and test equipment 13. Handling, storage and shipping 14. Inspection, test and operating status 15. Control of nonconforming items 16. Corrective action 17. Quality assurance records 18. Audits.

44 Chapter 18: Human Factors Engineering a.application method and analysis mechanism of a human factors engineering design b.main control room c.remote control room

45 3. Summary 1. Comparison Korean SAR and IAEA Contents 2. Chapters and Contents of SAR Chapter 1 General Information Chapter 2, 3, 4, Chapter 17 Chapter 18 Human Factors Engineering