Knowledge Management in Licensing & Design Bases. Thomas Koshy, Head Nuclear Power Technology Development Division of Nuclear Power
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1 Knowledge Management in Licensing & Design Bases Thomas Koshy, Head Nuclear Power Technology Development Division of Nuclear Power
2 Outline of Presentation 2 Purpose Global Nuclear Safety & Security Framework Overall Plans Licensing & System Engineers Organization Interactions & Information Storage Licensing Documents Concluding Thoughts
3 Purpose 3 To build repository of information in a retrievable manner to: Establish and maintain licensing/design bases of the plant Preserve Nuclear safety Prevent undoing the lessons learned for operational safety Expedite decision making with adequate technical bases & background information
4 Nuclear Safety Lessons 28 March 1979 Three Mile Island Accident Unit 2 26 April 1986 Chernobyl Accident Unit 4 11 March 2011 Fukushima Daiichi Accident Units 1-4
5 Global Nuclear Safety and Security Framework Safety is an essential condition for a sustainable and successful nuclear power programme Safety is an integral component in all infrastructure issues Safety cannot be outsourced A safety culture starting with strong and effective leadership is essential Weak links need to be identified and strengthened
6 EXISTING SAFETY STANDARDS HIERARCHY 6 Safety Fundamentals Safety Requirements Safety Guides Contains High Level Safety Concepts T.Koshy, NPTDS/IAEA
7 Fundamental Safety Principles Principle 1: Responsibility for safety Principle 2: Role of government Principle 3: Leadership and management for safety Principle 4: Justification of facilities and activities Principle 5: Optimization of protection Principle 6: Limitations of risks to individuals Principle 7: Protection of present and future generations Principle 8: Prevention of accidents Principle 9: Emergency preparedness and response Principle 10: Protective actions to reduce existing or unregulated radiations risks must be justified and optimized Ten safety principles form the basis on which safety requirements are developed and safety measures are implemented to achieve the primary safety objective.
8 Principle 1: Responsibility for safety The prime responsibility for safety must rest with the person or organization responsible for facilities and activities that give rise to radiation risks.
9 Principle 2: Role of Government An effective legal and governmental framework for safety, including an Independent Regulatory Body, must be established and sustained.
10 Principle 3: Leadership and Management for Safety Effective leadership and management for safety must be established and sustained in organizations concerned with, and facilities and activities that give rise to, radiation risks.
11 safety culture governs attitudes and behaviours Principle 3: Leadership and Management for Safety Safety culture includes: Individual and collective commitment to safety on the part of leadership, management and personnel at all levels; Accountability of organizations and of individuals at all levels of safety; Measures to encourage a questioning and learning attitude and to discourage complacency with regard to safety.
12 Overall Plans 12 Limited Scope (1-4 plants in 2 decades) Medium Fleet (10 to 12 Plants in 2 to 3 decades) Large Fleet & Technology Development
13 Limited Scope 13 Acquire and retain knowledge to protect the health and safety of the people and environment Design / licensing bases Retain Technology developer on contract Phase in local staff (operation, maintenance, procurement etc.,) Capability for fuel reload analysis
14 Medium Fleet 14 Limited dependency on technology supplier Independent fuel supply & reload analysis Fully qualified operator training & certifying Certain level of exploratory and confirmatory research
15 Large Fleet 15 Full ownership of technology Design details of reactor and internals Test data and proprietary information on major components System specifications Capability for full design of power plants and technology development Full capability for exploratory and confirmatory research (research reactor, Hydraulic and thermo-dynamic modelling, analysis etc.,)
16 Licensing & System Engineers 16 Qualification Multi-discipline with nuclear safety training Duties (design, construction, testing & operation) Expert knowledge on safety systems (system interactions, design bases, failure modes, limitations) Information stored in retrievable manner Approves on all applicable licensing commitments & system modifications (PSAR, FSAR, etc.,) Maintains System books, PI&D, etc.,
17 Organization 17 Operations Reactor Systems Mechanical (Safety / BOP) Core cooling, HVAC, Pumps & Valves Electrical & Controls (Safety/BOP) Electrical Power System Reactor Coolant System Maintenance Planning & Scheduling Quality Assurance /Quality Control Emergency Planning & Public Relations Security
18 Interactions & Information Storage 18 Regulatory Rules / Directives Operating Experience Industry Initiatives System Description/ Specification Master Equipment List (Knowledge Repository) PSAR, FSAR, UFSAR Technical Spec. Regulatory Doc. (Knowledge Repository)
19 Information Storage 19 System & Equipment Description/Spec Master Equipment List Procurement information Tech manual & Assembly drawings Maintenance (Corrective & Preventive, Calibration, surveillance) Drawings (system & interactions) Spares Performance History Pending Actions
20 Licensing Documents 20 Preliminary Safety Analysis Report (PSAR) Construction phase Final Safety Analysis Report (FSAR) Basis for operating license Updated FSAR (UFSAR) periodic update of FASAR to document the licensing bases Technical Specification & Bases (Operational guidance endorsed by regulator part of license )
21 Chapters for Licensing Bases 21 Chapter 1 Introduction and Interfaces Chapter 2 Sites Characteristics and Site Parameters Chapter 3 Design of Structures, Components, Equipment, and Systems Chapter 4 Reactor Chapter 5 Reactor Coolant System and Connected Systems Chapter 6 Engineered Safety Features Chapter 7 Instrumentation and Controls Chapter 8 Electric Power Chapter 9 Auxiliary Systems Chapter 10 Steam and Power Conversion System
22 Chapters for Licensing Bases 22 Chapter 11 Radioactive Waste Management Chapter 12 Radiation Protection Chapter 13 Conduct of Operations Chapter 14 Initial Test Program and ITAAC-Design Certification Chapter 15 Transient and Accident Analysis Chapter 16 Technical Specifications Chapter 17 Quality Assurance Chapter 18 Human Factors Engineering Chapter 19 Severe Accidents
23 Concluding Remarks 23 Nuclear Safety can be preserved only when a conducive environment prevails (Safety Culture) Human Resource development is specific to the overall plan of the fleet For preserving corporate knowledge, a suggested age distribution is given below to facilitate knowledge management 40% above 45 yrs; yrs; years
24 Questions? 24 Thank you for your attention
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