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Title: I


1
IC Modernization at NPP Dukovany
  • C. Karpeta, Scientech LLC-organizational
    component
  • L. Leák, CEZ-Power Generation Division
  • J. Rosol, CEZ-Power Generation Division

IAEA Technical Meeting on Increasing Power Output
and Performance of NPPs by improved IC
Systems 29-31 May 2007, Prague, Czech Republic
2
Topics to be addressed
  • Plant IC system assessment activities.
  • Strategies of the IC modernization program.
  • Strategies for the licensing process.
  • Refurbishment of modules M1 and M2.
  • Refurbishment of modules M3, M4, and M5.
  • Resolution of the digital computer-based IC
    systems important to safety dependability issue.
  • Operational experience with the innovated modules
    M1 and M2.

3
Plant IC system assessment activities
  • Assessment performed by the French company EdF
    and the English company NNC under the EU PHARE
    program project ENE/15. It was a mutually
    independent deterministic evaluation of the plant
    IC system design, which resulted in
  • providing technical recommendations how to
    eliminate the revealed shortcomings
  • providing system level specifications for
    innovation of the individual IC systems
  • Plant internal audit, which was entirely the
    plants own effort.
  • The individual plant IC systems were evaluated
    against the following criteria
  • Impact on nuclear safety.
  • Impact on plant availability.
  • Operation and maintenance costs.
  • Lifetime, maintainability.
  • Compliance with regulatory requirements
  • PSA level 1 was applied to evaluate the impact on
    nuclear safety.
  • Simple straightforward methods were used for the
    evaluation of the remaining criteria.
  • Plant external audit, conducted by the ENAC
    consortium
  • It was focusing on safety aspects

4
Plant IC system assessment activities- cont.
  • IAEA ASSET inspections in 1993 and 1996.
  • Practically all events caused by IC failures
    were assigned level INES-0.
  • Evaluation of the IC equipment under the plant
    launched qualification program.
  • The main conclusions of the IC relating parts of
    the plant assessments were as follows
  • No major safety concerns relating to plant IC
    systems were raised, although some aspects of the
    design did not reflect the best international
    practices, such as those of the IAEA safety
    guides
  • Regarding the impact on the plant availability,
    no significant IC shortcomings were found out
  • Significant problems were identified in the
    lifetime and maintainability of the existing IC
    equipment
  • Regarding compliance with regulatory
    requirements, several areas where improvements
    were feasible were identified

5
Strategies of the IC modernization program
  • Regarding the plant operational safety aspects
  • The refurbished IC systems shall be implemented
    in order of their significance to safety, with
    the reactor protection system having the highest
    priority.
  • For practical reasons, this principle is being
    followed by having the program broken down into
    two separate projects, i.e.
  • Refurbishment of the so-called modules M1 and M2,
    where those modules encompass the reactor
    protection system, the emergency load sequencer,
    the post-accident monitoring system, the reactor
    power limitation system, the reactor power
    control system, the steam generators protection
    systems, and the plant process computer,
    including the in-core measurements processing.
  • Refurbishment of the so-called modules M3, M4,
    and M5, where those modules encompass
  • - primary circuit logic systems (i.e.
    systems providing control of component states)
  • and process control systems,
  • - turbines and generators control and
    protection systems, and the unit safeguard
  • system,
  • - secondary circuit logic systems and
    process control systems.
  • Hence, modules M1 and M2 refurbishment project
    will be implemented
    first.

6
Strategies of the IC modernization program
cont.
  • Regarding the plant availability aspects
  • Step-by-step implementation of the program at
    each unit over a specified time span.
  • Performing dismantling of the old systems and
    installation, testing, and commissioning of the
    new systems during the planned standard and
    extended refueling outages.
  • Performing, to the extent limited by plant safety
    and operational constraints, various preparatory
    activities between the outages.
  • Regarding the plant IC system concept,
    functionalities and implementation.
  • Retaining the original protection and control
    concept.
  • Retaining, as far as reasonable and practicable,
    the existing plant IC system structure.
  • Retaining all the existing functionalities.
    Modification of functions important to safety are
    allowed, provided that they are adequately
    substantiated and have been approved by the
    regulatory authority.
  • Current systems will be replaced by new systems
    on a one-by-one basis.
  • Regarding the technology platform the equipment
    of the new systems is to be built of.
  • The new systems shall be based on an up-to-date
    proven technology platform.
  • Where practicable and economical, functional
    equivalents of the current systems equipment and
    components may be used.
  • Most of the new systems should be digital
    computer-based systems.

7
Strategies for the licensing process
  • As per the provisions of the Czech Republic
    Atomic Act, reconstruction and/or implementation
    of changes in nuclear facilities that affect
    nuclear safety, radiation protection, emergency
    preparedness and security fall into the category
    of activities for which a permission (license)
    must be granted by the State Office for Nuclear
    Safety (SONS).
  • The one-step licensing process to be applied
    for implementation of reconstruction or other
    changes that affect nuclear safety, radiation
    protection, emergency preparedness and security
    of nuclear facilities, as stipulated by the
    provisions of 9, (1), f) of the Atomic Act, was
    felt to be not quite adequate for a large-scope
    several-stage IC system refurbishment projects

8
Strategies for the licensing process- cont 1
  • Project specific licensing process has been
    conceived in several rounds of discussions
    between the plant operator and the regulatory
    body. This process is copying to certain extent
    the licensing process applied to new nuclear
    power plant projects.

9
Strategies for the licensing process- cont 2
  • Project specific licensing requirements have been
    set forth by the regulatory body. They relate to
    the following areas
  • Classification of the IC functions, systems and
    equipment important to safety
  • Acceptability of the digital computer-based IC
    systems important to safety.
  • Software development process for the IC systems
    important to safety.
  • Verification and validation of the software for
    the IC safety systems.
  • Defense against common cause failures due to
    errors in the software of IC safety systems.
  • Communications between sub-systems of the digital
    computer-based IC safety systems.
  • Testability of the digital computer-based IC
    safety systems during reactor operation.
  • Compliance to the single failure criterion.
  • Equipment qualification.
  • Reliability of the innovated IC systems
    important to safety.

10
Refurbishment of modules M1 and M2Installation
and commissioning of the refurbished modules
started at unit No.3 in March 2003, and was
completed in May 2005
  • The following general technical guidelines were
    adhered to
  • Reactor trip and engineered safety features
    actuation functions are to be implemented in one
    triple redundant system, namely the reactor
    protection system.
  • Reactor power limitation functions are be
    implemented in each of the reactor protection
    system divisions, but functionally isolated from
    the trip functions.
  • Number of sensors is to be reduced.
  • Sensor sharing between the safety systems is
    allowed. Limited sensor sharing between safety
    systems and systems of lower safety grade may be
    used.
  • Some functions of the safety systems can be
    modified in correspondence with the plant
    proposed and the regulatory authority approved
    changes.
  • Post-accident monitoring is to be implemented as
    a separate system.
  • The technical level and quality of core
    monitoring should be significantly improved
    through improved processing of the measurement
    data provided by the existing reactor in-core
    instrumentation.
  • Computerized functions of operator support should
    be significantly extended, and the human-machine
    interface should be improved
  • Only limited modifications to the main and
    emergency control rooms are allowed.
  • The current structure of manual controls and
    alarm displays should be kept.
  • Extended diagnostic functions should be provided

11
Refurbishment of modules M1 and M2- cont. 1
  • The design and implementation of the refurbished
    systems is compliant with
  • the requirements for assurance of nuclear safety
    set in the Czech Republic legislation (Atomic
    Act, SONS regulations)
  • the project specific requirements set by SONS
  • the individual IC systems specific requirements
    set by the project team, which relate to the
    assurance of functionality, reliability,
    performance, environmental durability, and
    quality
  • the provisions of the applicable standards.

12
Refurbishment of modules M1 and M2- cont. 2
  • Block diagram of the refurbished modules M1 and
    M2 is depicted in Fig.1
  • Photos of the modernized main control room of
    unit No.3 and of the original and current ESFAS
    equipment are presented in Fig.2 through 4.
  • The project implementation at unit No.1 is
    nearing completion. Its implementation at units
    No.2 and 4 is in progress. The project is to be
    completed in 2009.

13
Refurbishment of the NPP Dukovany IC System
Overall architecture Fig. 1
14
Reactor protection system Fig. 2
old new
15
New MCRFig. 3
16
Sometimes it wasnt easyFig. 4
17
Refurbishment of modules M3, M4, and M5
  • The following preparatory and initial activities
    have been performed so far, or are being still in
    progress
  • The so-called Coordination Design Phase 1 has
    been elaborated. It defines the overall concept
    of the refurbished IC systems, specifies
    applicable requirements for their design and
    implementation, specifies the hardware and
    software technology platforms the refurbished IC
    systems should be built of, and specifies a
    breakdown of the project implementation into
    seven stages.
  • Coordination Design Phase 2 has been
    elaborated. It specifies the control algorithms
    to be implemented in the refurbished systems.
  • Safety classification of the IC functions in
    question has been performed to the guidance
    provided in the technical standard CSN IEC 61226.
  • Elaboration of the so-called technological
    control algorithms of the actuators.
  • Measurement of the electromagnetic environment
    and interferences pertinent to the existing
    cabling.
  • Measurement of the electromagnetic environment in
    the locations of the new IC equipment.
  • Analyses of technical characteristics of the
    interface devices, e.g. relays.
  • Analyses of the impacts of lightning and
    short-circuit currents on the existing cabling.
  • Establishing photo-documentation of the current
    state of the panels housing the IC equipment

18
Refurbishment of modules M3, M4, and M5- cont. 1
  • The main constraints imposed on the project
    implementation are as follows
  • Replacement activities shall be performed during
    the units planned outages.
  • 40 to 50 IC equipment panels will need to be
    replaced and tested during each unit outage they
    include approximately 1000 functions.
  • In contrary to the technique used during the
    project T544 implementation, off-line
    installation of the new equipment, i.e. equipment
    installation during an outage without connecting
    its outputs to the actuated devices and providing
    those connections in the next outage, is not
    possible for technical reasons.
  • The equipment cannot be refurbished on a
    straightforward one by one basis since adequate
    separation of the IC functions based on their
    safety classification needs to be accomplished.

19
Refurbishment of modules M3, M4, and M5- cont. 2
  • The refurbished portion of the plant IC system
    will consist of the following major parts
  • DIAG, RSBP, RSBS, RSBT
  • System DIAG is a new system, which will provide
  • - acquisition, time stamping processing,
    display, and archiving of the operational and
    diagnostic data generated by the refurbished
    modules M3 through M5
  • - transmission of a selected set of that
    operational and diagnostic data to the unit
    process computer system
  • - data acquisition from the unit process
    computer system and their distribution to the
    refurbished systems.

20
Refurbishment of modules M3, M4, and M5- cont. 3
  • System RSBP will
  • provide monitoring and control functions of the
    primary circuit components and processes,
    including dedicated human-machine interfaces
  • be replacing the current relay logic systems and
    control systems of the primary circuit
  • System RSBS will
  • provide monitoring and control functions of the
    secondary circuit components and processes,
    including dedicated human-machine interfaces
  • be replacing the current relay logic systems and
    control systems of the secondary circuit

21
Refurbishment of modules M3, M4, and M5- cont. 4
  • System RSBT will
  • provide monitoring and control functions of the
    units both turbine-generators, including
    dedicated human-machine interfaces
  • be replacing the unit safeguard system, the
    turbine-generators protection system, the turbine
    control systems, and the electronic hard-wired
    logic systems.
  • Refurbishment of the modules M3 through M5 is to
    be completed by the year 2015.

22
Distribution of IC functions in correspondence
with their safety classification - Fig. 5
1P10
1P11
1P12
1P15
1P13
1P16
A1
C2
C4
A5
N6
B3
The existing equipment and its safety classified
functions
Example of 6 cabinets
N2
B1
C6
A2
B4
C1
N3
N5
B2
N1
A6
A category
B category
C category Nonclassified
The new equipment
23
Original IC Fig.6NSSS part
BOP part
24
Dependability of digital computer-based IC
systems important to safety
  • To ensure adequate level of dependability of
    digital computer-based IC systems important to
    safety the following measures were taken
    regarding the hardware and software development
    and manufacture
  • Requirements common to the development and
    manufacture of computer hardware implementing IC
    functions of any of the three safety category
    functions, i.e. category A, B, or C as per the
    provisions of the standard IEC 1226, have been
    specified.
  • Specific graded requirements have been specified
    for the development and implementation of
    computer software, which provides safety category
    A functions, or safety category B functions, or
    safety category C functions.
  • Adherence to these requirements was monitored by
    conducting technical audits at the suppliers of
    digital computer-based IC systems for modules M1
    and M2.

25
Dependability of digital computer-based IC
systems important to safety cont.1
  • These measures were aimed at getting high quality
    hardware and as error free as possible
    software, commensurate with safety significance
    of the individual refurbished IC systems.
  • In parallel, measures were also taken to cope
    with those situations when in spite of all the
    efforts to avoid errors in software, common cause
    failures might occur due to some residual
    software errors. These measures consisted in
  • providing within the refurbished IC safety
    systems two diverse lines of protection against
    the so-called frequent design basis events, i.e.,
    events with the estimated frequency of occurrence
    higher than 10E-3/year
  • providing within the refurbished modules M1 and
    M2 four lines of defense-in-depth, which are
    mutually independent and to some extent diverse.
  • Detailed description of these measures is beyond
    the scope of our paper hence, also beyond the
    scope of this presentation.

26
Dependability of digital computer-based IC
systems important to safety - cont.2
  • The main requirements for the development and
    manufacture of computer hardware were as follows
  • Development of hardware shall be divided into
    formalized phases with specification of
    activities pertinent to each phase.
  • Each phase shall be terminated by verification
    and shall include generation of appropriate
    documentation.
  • Verification, quality assurance, inspection and
    test activities shall be performed to the
    provisions of appropriate plans.
  • Sub-systems, modules and components to be used in
    the computer system may be both dedicated
    hardware products as well as off-the- shelf
    products qualified for a particular application.
  • The proper working of the integrated computer
    system shall be demonstrated.

27
Dependability of digital computer-based IC
systems - SW category A
  • The main requirements for the development of
    computer software were as follows
  • Development process of software, which implements
    category A functions shall be a well structured
    and fully formalized process consisting of
    planning and development activities.
  • Planning activities shall result in establishing
    a set of planning documents, including
  • - Software quality assurance plan
  • - Software verification and validation plan
  • - Software configuration management plan
  • - Software safety plan.

28
Dependability of digital computer-based IC
systems - SW category A cont.
  • Development activities shall include
  • Requirement activities, i.e. software
    requirements specification, followed by
    performance of requirements safety
    analysis, VV tasks, and CM tasks.
  • Design activities, i.e. software design
    specification, followed by performance of design
    safety analysis, VV tasks, and CM tasks.
  • Implementation activities, i.e. coding, followed
    by performance of code safety analysis,
    VV tasks, and CM tasks.
  • Integration activities, i.e. software
    integration, followed by performance of
    safety analysis tasks, VV tasks, and CM
    tasks.
  • Validation activities, i.e. software testing,
    performance of safety analysis tasks, VV tasks,
    and CM tasks.
  • Installation activities, i.e. software
    installation into the processing units,
    performance of VV and CM tasks.
  • No third party independent VV activities need
    to be performed provided that the VV team is
    management and financial independent of the
    development team.

29
Dependability of digital computer-based IC
systems - SW category B
  • Development process of software, which implements
    category B functions shall be a well structured
    and to large extent formalized process consisting
    of planning and development activities.
  • Planning activities shall result in establishing
    a set of planning documents similar to that of
    the category A software development process but
    for the software safety plan.
  • Development activities shall be basically the
    same as those of the software category A
    development process but for the software safety
    activities.
  • Performance of the QA, VV, and CM activities
    need not be documented to the same level of rigor
    as for category A software.

30
Dependability of digital computer-based IC
systems - SW category C
  • Development process of software, which implements
    category C functions shall be a structured and to
    some extent formalized process consisting of
    planning and development activities.
  • Planning activities shall result in establishing,
    as a minimum, of the following plans
  • - Software quality assurance plan.
  • - Software verification plan.
  • Development activities shall be basically the
    same as those of the software category B
    development process but for integration and
    validation activities, which may be viewed as a
    part of the computer system integration and
    validation.
  • Performance of the QA and VV may be documented
    in a summary form.

31
HW SW development process technical audits
  • Regarding the conduct of technical audits, it was
    required that they be focusing on
  • Auditing the planning documents generation
    process.
  • Auditing the software and hardware requirements
    setting and implementation processes.
  • Auditing the software and hardware design
    processes.
  • Auditing the software and hardware manufacturing
    and testing processes.
  • Auditing the implementation of the verification,
    validation, configuration management and software
    safety processes.

32
HW SW development process technical audits
cont.
  • The performed technical audits and the process of
    audit findings and observations disposition
    contributed significantly to the verification
    that
  • The development of software and hardware
    important to safety was adequately planned for by
    the audited organizations.
  • A V-shaped model of the system, hardware and
    software lifecycle, which is depicted in Fig.8,
    was followed in the development process of
    computer hardware and software important to
    safety. The development activities as implemented
    by the audited organizations were consistent in
    all significant aspects with the above stated
    main requirements as detailed by the provisions
    of the planning documentation and by the
    provisions of the applicable standards.

33
HW SW LifecycleFig. 7
34
Implementation at Unit B3
35
Implementation and start of operation
  • Step by step implemetation in the course of four
    standard refueling outages
  • Validation in parallel operation (esp. step No.7)
  • Specific test program for reactor start - up
    (step No. 8)
  • Regulatory inspection and independent supervision
  • Trial operation (12 months)
  • Verification of guaranteed parameters
  • Guarantee period operation (ended on 20th May
    2007)

36
Lessons learned(good practice)
  • Careful preparation period
  • (started in PHARE project with English NNC Ltd)
  • Splitting in two phases M1,2 and M3-5
  • (important for implementation during standard
    refueling outages)
  • Conservative approach
  • What has not to be changed - shall not be
    changed
  • Use of the plant simulator
  • (functional specification, test design
    verification)
  • Training system (selected NPP personnel acted as
    tutors)
  • NPP staff involvement
  • (fundamental for implementation and
    commissioning)

37
Operational experience
  • Advantages of the new IC systems
  • Employment of advanced fuel due to new core
    monitoring
  • More reliable and accurate rod control (RRCS)
  • Better ex-core measurement ( fixed detectors,
    comfortable calibration, ..)
  • New functions and better HMI of the process
    computer (PCS)
  • - operators support (e.g. SPDS)
  • - separated display of alarms
  • - large and detailed screens
  • - additional dedicated displays
  • Powerful diagnostics

38
Operational experienceresume
  • The new, refurbished, IC systems
  • are compliant with regulatory authority
    requirements
  • facilitate plant service time extension
  • meet the plant operator expectations
  • The commissioning and operation in the course of
    warranty period (24 months) have proved the
    feasibility of large scale IC refurbishment
    within standard refueling outages
  • The M1,2 refurbishment project at Dukovany Unit 3
  • is viewed as a success

39
IC Modernization at NPP Dukovany
  • Thank you for your attention
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