Knowledge Management
in
Licensing & Design Bases
Thomas Koshy, Head
Nuclear Power Technology Development
Division of Nuclear Power
2
Outline of Presentation
• Purpose
• Global Nuclear Safety & Security
Framework
• Overall Plans
• Licensing & System Engineers
• Organization
• Interactions & Information Storage
• Licensing Documents
• Concluding Thoughts
Purpose
• 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
3
Nuclear Safety Lessons
11 March 2011 Fukushima Daiichi Accident
Units 1 - 4
26 April 1986 Chernobyl Accident
Unit 4
28 March 1979 Three Mile Island Accident
Unit 2
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
EXISTING SAFETY STANDARDS HIERARCHY
Safety Guides
Safety Requirements
Safety Fundamentals
Contains High Level
Safety Concepts
T.Koshy, NPTDS/IAEA
6
Fundamental Safety Principles
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.
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 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.
Principle 2: Role of Government
An effective legal and governmental framework for
safety, including an
Independent Regulatory Body, must be established and sustained.
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.
“…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.
Overall Plans
• Limited Scope
• (1-4 plants in 2 decades)
• Medium Fleet
• (10 to 12 Plants in 2 to 3 decades)
• Large Fleet & Technology
Development
12
Limited Scope
• 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
13
Medium Fleet
• Limited dependency on technology
supplier
• Independent fuel supply & reload analysis
• Fully qualified operator training &
certifying
• Certain level of exploratory and
confirmatory research
14
Large Fleet
• 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.,)
15
Licensing & System Engineers
• 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.,
16
Organization
• 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
17
Interactions & Information Storage 18
System Description/
Specification
Master Equipment List
(Knowledge Repository)
Regulatory Rules / Directives
Operating Experience
Industry Initiatives
PSAR, FSAR, UFSAR
Technical Spec.
Regulatory Doc.
(Knowledge Repository)
Information Storage
• 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
19
Licensing Documents
• 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 )
20
Chapters for Licensing Bases
• 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
21
Chapters for Licensing Bases
• 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
22
Concluding Remarks
• 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; 35% @30-45 yrs; 25% @
20-30 years
23