Technical Report on Post Accident Monitoring

1
Overview of Activities in the Field of
Instrumentation Control At Karachi Nuclear
Power Plant
KANUPP
PRESENTED BY ZAKIA RABBANI Karachi Nuclear
Power Plant, PAKISTAN
2
Overview

• Nuclear Power in Pakistan
• IC activities at KANUPP
• Accident Monitoring Instrumentation
• Safety Parameter Display System
• Ageing Management Program

3
Nuclear Power in Pakistan

• Pakistan Atomic Energy Commission has two
• Nuclear Power Plants in operation
• 137 MW(e) PHWR Karachi Nuclear Power Plant
• 325 MW(e) PWR Chashma Nuclear Power Plant
• Third plant of 325 MW(e) is under construction
• Government of Pakistan has asked PAEC to
  increase the share of NPP in total energy
  generation to 8800MW(e) by the year 2030.

4
IC Activities at KANUPP

• KANUPP was installed in late sixties and
  started commercial operation in 1972. To ensure
  safe operation, improve performance and extend
  Plant operational life for another 15 years, PAEC
  initiated following projects to address and
  combat the aging and obsolescence problems of the
  plant, after completion of its 30 years of design
  life.

5
IC Activities at KANUPP

• Safe operation of KANUPP for safety reviews and
  upgrades (SOK)
• Technological Up-gradation (TUP) for combating
  technological obsolescence computer, control and
  instrumentation
• Balancing Modernization Rehabilitation Program
  (BMR)
• Aging Management Program (AMP) based on in
  recommendation of IAEA AMAT mission.
• Accident Monitoring Instrumentation (AMI)

6
IC Activities at KANUPP

• Activities completed under these development
  projects
• Replacement of Regulating Computers
• Process Information System (PI)
• Replacement of 155 CI loops
• Installation of Critical Parameters Display
  System
• Replacement of Fuel Handling computers
• Installation of Fire alarm system
• Replacement of Meteorological Instrumentation

7
IC Activities at KANUPP

• Future Programs
• The replacement of another 23 CI Loops is
  planned in near future
• Based on Regulatory requirements work on the
  following projects is in progress
• Post Accident Monitoring Instrumentation for
  KANUPP (PAMI).
• Safety Parameter Display System (SPDS)
• Aging Management Programmed (AMP)

8
Accident Monitoring Instrumentation
9
Accident Monitoring Instrumentation for KANUPP

• Objective
• AMI provides information to enable the operator
  to
• Monitor the plant parameters required to
  follow the effects of the accident
• Assess the post-accident conditions of the plant
  
• and determine the nature and course of the
• accident
• Determine the actions that are necessary to be
• performed and monitor the results of these
• actions, including the need to initiate the
  sector
• emergency.
• Ensure the safety-related systems have
• performed or are performing their required
  functions.

10
Accident Monitoring Instrumentation for KANUPP
Scope

• Not an independent system
• Where an available instrumentation can serve the
  purpose it is selected as AMI parameter
• Additional equipment will be provided where
  either the instrumentation is not available or
  not fulfill the design requirement
• The AMI would be provided to monitor variables
  and systems over their anticipated ranges for
  postulated accidents

11
Accident Monitoring Instrumentation for KANUPP
Design Approach

• The AMI has been designed on the basis of PAK-911
  rev.-1 (IAEA NS-R-1) and PAK/1255 (USNRC RG
  1.97), however, due to the fact that KANUPP is an
  old plant it limits retrofitting of
  instrumentation as per standards that have been
  prepared years after its design
• Foreseeing the difficulties in acquiring the
  qualified equipment the design has been optimized
  without jeopardizing the design intent

12
Accident Monitoring Instrumentation for KANUPP
Design Qualification Criteria

• Types of Variables
• Type A Variables that provide primary
  information needed to permit C/R personnel to
  take specified manual action for which no
  automatic control is provided
• Type B Variables that provide information
  regarding Safety function accomplishment
• Type C Variables that provide information to
  indicate the potential for being breached or the
  actual breach of barrier to fission products
  release

13
Accident Monitoring Instrumentation for KANUPP
Design Qualification Criteria (Contd.)

• Types of Variables (contd.)
• Type D Variable that provide information to
  indicate operation of individual safety system or
  other systems important to safety
• Type E Variable that provide information
  regarding magnitude of release of radioactive
  material

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Accident Monitoring Instrumentation for KANUPP
Design Qualification Criteria (Contd.)

• Categories of Variables
• Category 1 Provides most stringent requirements
  (fully qualified, redundant, continuous real time
  display, essential power supply) and is intended
  to be key variable
• Category 2 Provides less stringent requirements
  (essential power supply) and is generally applies
  to instrumentation designated for indicating
  systems operating status
• Category 3 High quality industrial grade
  equipment (normal power supply)

15
Accident Monitoring Instrumentation for KANUPP
Design Considerations
GOALS For design basis accidents, the following
overall safety goals are considered Sub-critical
ity of the Reactor Core Reactor Core Cooling
Primary Coolant Integrity Containment
integrity
16
Accident Monitoring Instrumentation for KANUPP
Design Considerations (Contd.)

• 16 Design Basis Events as per KFSAR
• Have been selected like
• Loss of reactivity control
• Loss of reactor power regulation
• Dual computer control failure
• Loss of PHT system pressure control
• Loss of boiler level control
• Loss of boiler pressure control
• Loss of coolant accidents

17
Accident Monitoring Instrumentation for KANUPP
Design Considerations (Contd.)

• ACCIDENT MONITORING FUNCTIONS
• 23 Accident Monitoring Functions, selected under
  PAK /1255 Regulatory Guide, would provide
  sufficient information to achieve the functional
  requirements of AMI
• Containment Controlled Depressurization
• Reactivity Control
• Core Cooling
• Maintaining Primary Coolant System Integrity

18
Accident Monitoring Instrumentation for KANUPP
Design Considerations (Contd.)
AMI has been designed to a) cover the range of
the transient with required accuracy b)   have
the required response characteristics c) cover
the postulated mission period during which the
measurement is required d) survive the
environmental conditions its associated
components must operate e)  be supplied from
appropriate qualified power supplies
19
Accident Monitoring Instrumentation for KANUPP
Design Considerations (Contd.)

• MAN-MACHINE INTRFACE
• Indicators for AMI parameters shall be
  significantly identified having no conflict with
  other instruments on the same panel. The
  identification methodology has been evolved
  consistent with the ergonomics of the existing
  Control Room.
• b)  Redundant indications shall be available in
  the close vicinity (as far as possible) for the
  purpose of comparison as far as possible.

20
Accident Monitoring Instrumentation for KANUPP
Implementation Plan
a) Identification of instrumentation as AMI
Parameters (Implemented in 2006 to meet the
Regulatory requirement) b)  Identification of
Instrumentation as temporary AMI Parameters.
These Instrumentation are either under range or
do not meet the criterion laid down in the
standards (Implemented in 2006 to meet the
Regulatory requirement)
21
Accident Monitoring Instrumentation for KANUPP
Implementation Plan

• Procurement, Installation, Commissioning and
  Identification of the new Instrumentation /
  Equipment will be done after finalization of the
  design.
• Removal of identification from temporary AMI
  Instruments.

22
Accident Monitoring Instrumentation for KANUPP
Review by IAEA
An IAEA expert mission has recently visited
KANUPP (26-30 March, 2007) to review the KANUPP
approach and the work done so far. The mission
has concluded that KANUPP approach is correct and
has also identified some areas for improvement on
which work has been initiated.
23
Safety Parameter Display System
24
Critical Functions Of SPDS System

• Primary Heat Transport Integrity
• Reactor Core Cooling
• Primary Heat Transport Inventory
• Moderator Inventory
• Secondary Cooling
• Containment Integrity
• Reactor Power Criticality
• Radiological Emission

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26
Ageing Management Program
27
Ageing Management Program

• Ageing Management of KANUPPs CI system /
  equipment need replacement after implementation
  of Technological up-gradation project covering
  the loops of following systems
• Turbine Generator its Auxiliaries
  Instrumentation
• Diesel Generator its Auxiliaries Instruments
• Fueling Machine Instrumentation
• Relays
• SOV.

28
CONCLUSION
KANUPP has timely addressed the obsolescence of
IC equipment and reactor regulation computers
besides that safety upgrades and other
improvements suggested time-to-time by regulators
and IAEA have also been or are being implemented
to provide Nuclear Power in a safe and efficient
manner. The modernization of IC has to play a
vital role now and in future in generation of
electricity using nuclear energy and this area is
to be well considered by all utilities,
regulators, IAEA and other related agencies.