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

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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

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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 )

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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

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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

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Thank you for your attention

t.koshy@iaea.org

Questions ?