Transcript International Standards for NPP I&C Presented to TWG-NPPIC 2009 May 21 Vienna, Ausria Gary Johnson [email protected] +43 (1) 2600-22671 IAEA International Atomic Energy Agency.

International Standards for NPP I&C
Presented to
TWG-NPPIC
2009 May 21
Vienna, Ausria
Gary Johnson
[email protected]
+43 (1) 2600-22671
IAEA
International Atomic Energy Agency
Three organizations develop I&C standards that are used
world-wide
• IAEA
• International Electrotechnical Commission
• IEEE
• I’ll speak about the first two
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The IAEA statue establishes the agencies standards
development function
• One function of the IAEA is “to establish or adopt standards
of safety … and to provide for the application of these
standards, … at the request of a State, to any of that
State's activities in the field of atomic energy”
• These standards are to be established in consultation and, where
appropriate, in collaboration with the competent organs of the
United Nations and with the specialized agencies concerned
• IAEA statute > http://www.iaea.org/About/statute_text.html
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The purpose of IAEA Safety Guides
• Provide guidance on how to comply with the safety
requirements (In our case NS-R-1)
• Indicate international consensus that it is necessary to take
the measures recommended (or equivalent alternatives)
• Reflect best practices.
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Use of IAEA Safety Guides
• Used as the basis for IAEA design reviews, regardless of the national
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regulations
Some member states incorporate IAEA requirements (NS-R-1) and
safety guides into their regulations
Some member states incorporate IAEA requirements into their
regulations but treat safety guides as recommendations
Some member states use IAEA requirements and safety guides as
references in development of regulations or national standards. (this is
the most common)
Some member states do not use IAEA safety guides at all
IEC uses NS-G-1.3 as the source of elementary guidelines for I&C
systems important to safety.
• IEC standards provide further guidance on implementing these principles.
• NS-G-1.3 is unique in this regard
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IAEA Guidance Overview
Safety Fundamentals
Thematic standards
Facilities specific standards
Legal and governmental infrastructure
Nuclear power plants: design
Emergency preparedness and response
Nuclear power plants: operation
Management systems
Research reactors
Assessment and verification
Fuel cycle facilities
Site evaluation
Radiation related facilities and activities
Radiation protection
Waste treatment and disposal facilities
Radioactive waste management
Decommissioning
Remediation of contaminated areas
Transport of radioactive material
General safety (cross-cutting themes)
Safety of nuclear facilities
Radiation protection and safety of radiation sources
Safe management of radioactive waste
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Safe transport of radioactive material
All IAEA safety standards are
available at:
http://www-ns.iaea.org/standards/
All free!
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NS-R-1: “Safety of NPPs – Design” is the top IAEA design
requirements document
• Not legally binding
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• Adopted as regulation in some states
• Influenced regulations in other states
Not intentionally LWR specific
Responds to safety fundamentals
Prepared by engineers - little lawyer input
Outside standards are not incorporated
No public comment process
Represent a broad consensus
• All member states have the opportunity to comment
• Endorsed by the Commission for Safety Standards
• Approved by the IAEA Board of Governors
Other safety standards also relevant at a second order
• For example, GS-R-3 on management systems (including quality)
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Current safety guidance for design
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Safety of Nuclear Power Plants: Design Safety Requirements NS-R-1
• Software for Computer Based Systems Important to Safety NS-G-1.1
• Safety Assessment and Verification NS-G-1.2
• Instrumentation and Control Systems Important to Safety NS-G-1.3
• Design of Fuel Handling and Storage NS-G-1.4
• External Events Excluding Earthquakes NS-G-1.5
• Seismic Design and Qualification NS-G-1.6
• Protection Against Internal Fires and Explosions NS-G-1.7
• Design of Emergency Power Systems NS-G-1.8
• Design of the Reactor Coolant System and Associated Systems NS-G-1.9
• Design of Reactor Containment Systems NS-G-1.10
• Protection against Internal Hazards other than Fires and NS-G-1.11
• Design of the Reactor Core NS-G-1.12
• Radiation Protection Aspects of Design NS-G-1.13
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There is plan to restructure IAEA safety guides
This plan affects the design safety guides
Existing Structure
New Structure
NS-G-1.1
Software for Computer Based Systems Important to Safety
Safety Classification
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NS-G-1.2
Safety Assessment &Verification
Deterministic Safety Analyses
NS-G-1.3
I&C Systems Important to Safety
Design of I&C Systems
NS-G-1.4
Fuel Handling & Storage
NS-G-1.4
Fuel handling & storage systems
NS-G-1.5
External Events Excluding Earthquakes
Protection against Internal & External Hazards
NS-G-1.6
Seismic Design & Qualification
PSA for Design & Operations
NS-G-1.7
Protection Against Internal Fires & Explosions
Auxiliary Systems
NS-G-1.8
Design of Emergency Power Systems
Electric Power Systems
NS-G-1.9
Design of the RCS & Associated Systems
NS-G-1.8
Reactor Coolant & Associated Systems
NS-G-1.10
Design of Reactor Containment Systems
Reactor Containment Systems & Other Buildings
NS-G-1.11
Protection against Internal Hazards except Fires & Explosions
NS-G-1.12
Design of the Reactor Core
NS-G-1.12
Reactor Core
NS-G-1.13
Radiation Protection Aspects of Design
Radiation Protection &
Radioactive Waste Management
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+ - material from additional documents to be included
Completion scheduled for 2015
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Update of the I&C and electrical guides has started
• I&C Guide
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• Incorporate and replace the
software guide
• Much less detail on software
• Leave details to standards
• Update to address new topics
and new consensus, e.g.,
• Communications independence
• Soft control
• Cyber security
• Complex electronics
• Design for aging management
Electrical Guide
• Expand scope from emergency
power systems to all electrical
systems
• To some extent this is a restructuring
• Offsite power now in an annex
• Much of the emergency power
guidance is applicable to all
systems
• Check guidance for completeness
and tie to NS-R-1
• E.g., note the role of breaker
coordination in limiting the effects of
internal events, such as fire
• Integrate into new structure of safety guides
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• May involve broadening scope from NPP to Nuclear Installations
• Identify and eliminate unnecessary conflicts with national
approaches
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Work plan
• Solicit input
• Meetings to develop outline
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• About 5 experts
• About August
Develop draft (homework)
Post draft for review
Meeting to discuss draft
• About November
Revise draft (homework)
Post again for review
Meeting to review draft
• Different or larger group
• About January 2010
Finalize draft (homework)
Possibility of extra meetings if
needed
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Draft outline and current document
is available on-line
The website allows you to:
• Initiate or participate in threaded
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discussions
Post comments
Post markups
• If you post a mark-up please also
post comments explaining the
markup
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This is the first time I’ve tried a webbased process, so
• Advise me on how to improve the
site.
Be patient
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You need an account to access
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If you wish to participate
Contact me at
[email protected]
Or
Give me a business card
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International Atomic Energy Agency
IEC SC45A prepares standards applicable to electronic
and electrical functions for I&C of nuclear facilities
• By agreement between IEC and IAEA SC45A standards provide
detailed implementation guidance for IAEA safety standards.
• Thirty-one nations are members of SC45A
• Twenty-two are voting members
• About half are regular, active participants
• Currently there are 7 working groups
• Sensors & Measurements
• Digital Systems
• Special Process Measurements and Rad Monitoring
• Reliability
• I&C systems
• Modernization & Ageing Management
• Sixty-six standards issued to date
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Work in progress - I&C principles
• IEC 61513 Ed. 2.0 Nuclear power plants - Instrumentation
and control important to safety - General requirement for
systems
• IEC 61226 Ed. 3.0 Nuclear power plants - Instrumentation
and control important to safety - Classification of
instrumentation and control functions
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Work in progress - Sensors & Measurements
• IEC 60737 Ed. 2.0 Nuclear Power Plants - Instrumentation important to
safety - Temperature sensors (In-core and primary coolant circuit) :
Characteristics and test methods
• IEC 62584 Ed. 1.0 Nuclear Power Plants - Instrumentation important to
safety - Application of Gamma Thermometers (GT) for Local Power
Range Monitor (LPRM) calibration
• PNW 45A-750 Ed. 1.0 Nuclear Power Plants - Instrumentation
important to safety - Thermocouples : Characteristics and test methods
• IEC 60988 Ed. 2.0 Nuclear power plants - Instrumentation important to
safety - Acoustic monitoring systems for detection of loose parts:
Characteristics, design criteria and operational procedures
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Work in progress - Radiation Monitoring
• IEC 60951-1 Ed. 2.0 Nuclear power plants - Instrumentation important
to safety - Radiation monitoring for accident and post-accident
conditions - Part 1: General requirements
• IEC 60951-2 Ed. 2.0 Nuclear power plants - Instrumentation important
to safety - Radiation monitoring for accident and post-accident
conditions - Part 2: Equipment for continuous off-line monitoring of
radioactivity in gaseous effluents and ventilation air
• IEC 60951-3 Ed. 2.0 Nuclear power plants - Instrumentation important
to safety - Radiation monitoring for accident and post-accident
conditions - Part 3 : Equipment for continuous high range area gamma
monitoring
• IEC 60951-4 Ed. 2.0 Nuclear power plants - Instrumentation important
to safety - Radiation monitoring for accident and post-accident
conditions - Part 4: Equipment for continuous in-line or on-line
monitoring of radioactivity in process streams
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These are actually in publication
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Work in progress - Control Rooms & Human Factors
• IEC 60965 Ed. 2.0 Nuclear power plants - Control rooms Supplementary control points for reactor shutdown without
access to the main control room
• PNW 45A-748 Ed. 1.0 Nuclear Power Plants - Control
rooms - Computer based procedures
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Work in progress - Digital Systems
• IEC 61500 Ed. 2.0 Nuclear Power Plants - Instrumentation
and control important to safety - Data communication
• IEC 62566 Ed. 1.0 Nuclear Power Plants- Instrumentation
and control important to safety- Selection and use of
complex electronic components for systems performing
category A functions
• IPNW 45A-742 Ed. 1.0 Nuclear Power Plants Instrumentation and control systems important to safety Requirements for Computer Security Programmes
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Work in progress - Ageing
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IEC 62465 Ed. 1.0 Nuclear Power Plants - Instrumentation and control important to safety Management of aging of electrical cabling systems
IEC 62582-1 Ed. 1.0 Nuclear Power Plants - Instrumentation and control important to safety - Electrical
equipment condition monitoring methods - Part 1: General
IEC 62582-2 Ed. 1.0 Nuclear power plants - Instrumentation and control important to safety - Electrical
equipment condition monitoring methods - Part 2: Method descriptions - Indenter modulus
IEC 62582-3 Ed. 1.0 Nuclear power plants - Instrumentation and control important to safety - Electrical
equipment condition monitoring methods - Part 3: Method descriptions - Elongation at break
IEC 62582-4 Ed. 1.0 Nuclear power plants - Instrumentation and control important to safety - Electrical
equipment condition monitoring methods - Part 4: Method descriptions - Oxidation induction
temperature
IEC 62582-5 Ed. 1.0 Nuclear power plants - Instrumentation and control important to safety - Electrical
equipment condition monitoring methods - Part 5: Method descriptions - Optical cables
PWI 45A-1 Ed. 1.0 Management of ageing of nuclear power plant sensors
PWI 45a-3 Ed. 1.0 Management of aging of nuclear power plant connectors
PWI 45a-4 Ed. 1.0 Management of aging of nuclear power plant relays
PWI 45a-5 Ed. 1.0 Management of aging of nuclear power plant electronics
PWI 45A-6 Ed. 1.0 Obsolescence management for digital and programmable I&C in nuclear power
plant
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How to participates
• Participants must are representatives of their nation
• You must be nominated by your national committee of the IEC
• Formal correspondence goes through the national committee
• Each country has a chief delegate for SC45A
• Next meeting Yokohama, Japan
• 2009 September 10 to 18
• Much information is available at
• www.iec.ch
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