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Safety Analysis Report for Decommissioning of KNPP Units 1 and 2 A. Ivanova, I. Ovcharova (ENPRO CONSULT LTD )

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Title: Safety Analysis Report for Decommissioning of KNPP Units 1 and 2 A. Ivanova, I. Ovcharova (ENPRO CONSULT LTD )


1
Safety Analysis Report for Decommissioning of
KNPP Units 1 and 2 A. Ivanova, I. Ovcharova
(ENPRO CONSULT LTD )
  • International Nuclear Forum
  • BULGARIAN NUCLEAR ENERGY NATIONAL, REGIONAL
    AND WORLD SAFETY
  • BULATOM, May 28-30, 2008, Varna, Bulgaria

2
Safety Analysis Report for Decommissioning of
KNPP Units 1 and 2
  • 1 Introduction
  • Following the Contract for joining the European
    Union, the Council of Ministers of the Republic
    of Bulgaria took a decision and shut down the
    first and second units at Kozloduy NPP (KNPP) on
    31.12.2002 in accordance with Decision ? 848 of
    19.12.2002.
  • At present units 1 and 2 possess a license for
    operation in mode ? storage of the spent fuel
    in the spent fuel pools. According to the order
    of BNSA, from the beginning of December 2006 the
    licenses for operation of KNPP units 1 and 2 have
    been modified this does not change the current
    status operation of the units in mode ?, but
    allows for dismantling of the systems and
    equipment, which are not important for safety and
    do not contain radioactive substances above the
    free release levels.
  • The next step is obtaining a licence for Stage 1
    decommissioning activities Safe enclosure (SE)
    and dismantling in Turbine hall. The development
    of Decommissioning Safety Analysis Report (DSAR)
    is one of the documents needed for this license.

3
Safety Analysis Report for Decommissioning of
KNPP Units 1 and 2
  • 2 Specific features of units 12, related to the
    decommissioning
  • Kozloduy NPP Units 1 and 2, type WWER 440, model
    B 230 have some design and structural
    peculiarities, which impact the SE. These are
  • Equipment, which is common for the whole NPP
    site
  • Buildings and systems, common for two or four
    WWER-440 units
  • Some of the consumers of the First Boilers Unit
    of Unit 1 are common for the plant site and
    others are common for Units 1 and 2.
  • During the preparation for decommissioning
    measures have been foreseen and implemented for
    all specific features, having an impact on
    decommissioning. A number of infrastructure
    projects have been realized, including the
    physical separation of Units 12 from Units 34,
    erection of buildings, etc.

4
Safety Analysis Report for Decommissioning of
KNPP Units 1 and 2
  • 3 The Option for KNPP Units 1 and 2
    Decommissioning
  • Kozloduy NPP approved an Updated Decommissioning
    Strategy for Units 14 in June 2006. According to
    this Continuous Dismantling Strategy, the
    decommissioning of Units 1 and 2 will be done in
    two stages.
  • The generalized schedule for continuous
    dismantling is the following

Period Main Events
2003-2010 Units 12 operation in ? mode
2011-2018 Stage 1 - Preparation for Safe Enclosure of Reactor Building 1, dismantling of systems and equipment outside the Safe Enclosure Area. Safe Enclosure of Reactor Building 1.
2019-2035 Stage 2 dismantling of equipment inside the Safe Enclosure Area and release of the buildings for reuse for other purposes.
5
Safety Analysis Report for Decommissioning of
KNPP Units 1 and 2
  • Safe enclosure zone of units 1  4

9
1
2
5
4
3
6
8
7
SE of Units 12 Rest of SE
1 Reactor building 1 (Units 1 2) 2 Reactor
building II (Units 3 4) 3 Auxiliary building
1 4 Auxiliary building 2 5 Sanitary and
laboratory building 1 6 Sanitary and laboratory
building 2 7 Vent tube (stack) 1 8 Vent
tube (stack) 2 9 Turbine hall
6
Safety Analysis Report for Decommissioning of
KNPP Units 1 and 2
  • 4 The scope and the structure of DSAR
  • The content of the DSAR for decommissioning of
    Unit 1 is prepared in compliance with the
    documents
  • Regulatory guide for the preparation of a safety
    analysis report for decommissioning of nuclear
    reactors, December 2006
  • Safety assessment for decommissioning of
    facilities using radioactive material, IAEA
    Guide, DS376, 2007.
  • This document is elaborated on the basis of the
  • Decommissioning Plan for KNPP Units 1 and 2,
    December 2007
  • Technical Design for decommissioning of KNPP
    Units 1 and 2, PHARE Contract BG-9809-02-03.
  • The DSAR document is prepared for Stage 1 of the
    Decommissioning, which is planned for 2011-2018
    and includes
  • The preparatory activities for the safe enclosure
    of the reactor building of Units 1 and 2
  • The dismantling of systems and equipment outside
    the Safe Enclosure Area Safe Enclosure of RB.

7
Safety Analysis Report for Decommissioning of
KNPP Units 1 and 2
  • DSAR consists of 13 chapters
  • Chapter 1 Introduction is an introductory one
    to the rest of the document. It presents the
    regulatory framework for elaboration of the
    safety analysis report for decommissioning.
  • Chapter 2 Description of the Facility gives a
    general description of the unit and of the main
    systems and activities from the viewpoint of
    decommissioning.
  • Chapter 3 Site Evaluation presents the Kozloduy
    NPP site characteristics and the assessment of
    the potential external impacts.
  • Chapter 4 Design Basis of the Decommissioning
    includes the basic safety objectives and
    principles, the classification of the systems for
    the given state of decommissioning, the
    requirements with respect to the human factor,
    the fire and physical protection of the facility.

8
Safety Analysis Report for Decommissioning of
KNPP Units 1 and 2
  • Chapter 5 Description and justification of the
    processes and the systems provides information
    about the systems, important for radiation safety
    during decommissioning and about the new systems,
    installed for the specific decommissioning
    activities.
  • Chapter 6 Safety Analysis is still not
    finalized. It defines the relevant acceptance
    criteria for normal operation and for accidents,
    the methodology for accident analysis and the
    approach which is envisaged to be applied for the
    hazard analysis at the given stage of
    decommissioning. The chapter includes a summary
    of the analysis of the external hazards.
  • Chapter 7 Decommissioning Activities provides
    information about the main activities inside and
    outside the safe enclosure zone for the
    considered stage of decommissioning. Here the
    methods for decontamination and the
    techniques/equipment for dismantling and size
    reduction are included too.

9
Safety Analysis Report for Decommissioning of
KNPP Units 1 and 2
  • Chapter 8 Safety Management describes the
    organization for management of safety, the
    package of management tools (instructions,
    regulations, etc.), qualification and training of
    personnel, safety culture, etc.
  • Chapter 9 Limiting Conditions of Operation
    describes the specifics of the operational limits
    for the systems, important for radiation safety.
  • Chapter 10 Radiation Protection describes the
    application of the principle ALARA during the
    execution of all decommissioning activities,
    including the dose budgets estimation.
  • Chapter 11 Emergency Preparedness presents the
    emergency plan of Kozloduy NPP, which remains in
    force till the final shutdown of the last unit on
    the site.

10
Safety Analysis Report for Decommissioning of
KNPP Units 1 and 2
  • Chapter 12 Radioactive Waste Management
    describes the categorization of RAW and the
    management of the radioactive waste flows at Unit
    1.
  • Chapter 13 Quality Management indicates the
    main principles, laid in the quality assurance
    program for decommissioning and for the related
    activities.

11
Safety Analysis Report for Decommissioning of
KNPP Units 1 and 2
  • 5 Design basis of the decommissioning
  • 5.1 Safety objectives and safety principles
  • The main safety objective, as defined in the
    IAEA standard SF-1 Fundamental safety
    principles, is to protect people and the
    environment from the harmful effects of ionizing
    radiation.
  • To ensure that facilities are operated and
    activities conducted so as to achieve the highest
    standards of safety that can reasonably be
    achieved, measures have to be taken
  • To control the radiation exposure of people and
    the release of radioactive material to the
    environment
  • To restrict the likelihood of events that might
    lead to a loss of control over a nuclear reactor
    core, nuclear chain reaction, radioactive source
    or any other source of radiation
  • To mitigate the consequences of such events if
    they were to occur.

12
Safety Analysis Report for Decommissioning of
KNPP Units 1 and 2
  • The fundamental safety objective applies for all
    facilities and activities and for all stages over
    the life time including decommissioning.
  • The same Standard SF-1 formulates ten safety
    principles, on the basis of which are developed
    the safety requirements and the safety measures
    to be implemented in order to achieve the
    fundamental safety objective. These principles
    are listed bellow
  • 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.
  • This aspect of the decommissioning process is
    addresses in Chapter 8 Management of safety.

13
Safety Analysis Report for Decommissioning of
KNPP Units 1 and 2
  • Principle 2 Role of government
  • An effective legal and governmental framework
    for safety, including an independent regulatory
    body, must be established and sustained.
  • In Bulgaria these matters are settled by Chapter
    II Government regulation of the Act on the safe
    use of nuclear energy. This chapter of the law
    defines the functions, structure and financing of
    the Nuclear Regulatory Agency.
  • 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.
  • The problems of organization of safety, safety
    culture, ageing management etc. are addressed in
    Chapter 8 Management of safety of DSAR.
  • Chapter 6 Safety analysis includes the
    analysis of hazards arising during
    decommissioning.

14
Safety Analysis Report for Decommissioning of
KNPP Units 1 and 2
  • Principle 4 Justification of facilities and
    activities
  • Facilities and activities that give rise to
    radiation risks must yield an overall benefit.
  • In many cases, decisions relating to benefit and
    risk are taken at the highest levels of
    government, such as a decision by a State to
    embark on a nuclear power programme. This
    evaluation has been performed at the stage of
    decision making for the construction of Kozloduy
    NPP. At the stage of decommissioning it has to be
    demonstrated that the risk is not higher than in
    the stage of operation of the nuclear facility.
    The evaluation of the radiation risk is presented
    in Chapter 10 "Radiation protection and Chapter
    6 Safety analysis.
  • Principle 5 Optimization of protection
  • Protection must be optimized to provide the
    highest level of safety that can reasonably be
    achieved.

15
Safety Analysis Report for Decommissioning of
KNPP Units 1 and 2
  • The problems of optimization of protection are
    addressed in Chapter 3 Site evaluation, Chapter
    6 Safety analysis and Chapter 10 Radiation
    protection.
  • Chapters 4 and 5 present the physical protection
    and the fire safety of decommissioning.
  • Principle 6 Limitation of risks to individuals
  • Measures for controlling radiation risks must
    ensure that no individual bears an unacceptable
    risk of harm.
  • Chapter 10 Radiation protection presents the
    application of the ALARA principle to the
    radiation risk during decommissioning. The
    application of this principle shall provide the
    highest possible margin to the fulfilment of the
    dose criteria for the workers and for the
    population, as they are defined in the Regulation
    for the basic norms of radiation protection.

16
Safety Analysis Report for Decommissioning of
KNPP Units 1 and 2
  • Principle 7 Protection of present and future
    generations
  • People and the environment, present and future,
    must be protected against radiation risks.
  • Radioactive waste management is a major
    component of the process of decommissioning.
    Chapter 12 Radioactive waste management
    addresses the topics of RAW treatment,
    minimization, etc.
  • Principle 8 Prevention of accidents
  • All practical efforts must be made to prevent
    and mitigate nuclear or radiation accidents.
  • The most adverse consequences during
    decommissioning may arise as a consequence of
    loss of radioactive source or loss of control
    over a radioactive source. The principle of
    defence in depths is incorporated in the plant
    design. The assessment of the efficiency of the
    barriers against uncontrolled release of
    radioactivity to the environment is addressed in
    Chapter 10 "Radiation protection and Chapter 6
    Accident analysis.

17
Safety Analysis Report for Decommissioning of
KNPP Units 1 and 2
  • Principle 9 Emergency preparedness and response
  • Arrangements must be made for emergency
    preparedness and response for nuclear or
    radiation incidents.
  • Emergency preparedness is addressed in Chapter
    11 of DSAR.
  • Principle 10 Protective actions to reduce
    existing or unregulated radiation risks
  • Protective actions to reduce existing or
    unregulated radiation risks must be justified and
    optimized.
  • Chapter 7 Decommissioning activities gives a
    complete review of all activities at the given
    stage of decommissioning. Both the nuclear and
    the industrial aspect of each activity is
    assessed.

18
Safety Analysis Report for Decommissioning of
KNPP Units 1 and 2
  • 5.2 Classification of structures, components and
    systems
  • 5.2.1 Safety functions and related structures,
    components and systems
  • The safety functions and the associated
    structures, systems and components (SSC) are
    defined both for the planned decommissioning
    activities, and for accident conditions. The
    safety functions required during decommissioning
    comprise a combination of safety functions that
    were needed during facility operation and
    additional functions that need to be delivered as
    a result of the specific decommissioning
    activities. During the decommissioning stage,
    which is a subject of DSAR, the following
    fundamental safety function shall be ensured
    (article 32 (2) of Regulation for Providing the
    Safety of Nuclear Power Plants)
  • Confinement of the radioactive products within
    the prescribed boundaries.

19
Safety Analysis Report for Decommissioning of
KNPP Units 1 and 2
  • In Section 5 of DSAR, the safety functions,
    specific for the different phases of Stage 1 of
    the decommissioning, are discussed in detail.
    According to the Regulation for Providing the
    Safety of Nuclear Power Plants and to the IAEA
    standard NS-R-1, the systems which remain in
    operation during both phases - preparation for
    safe enclosure and safe enclosure - of Units 1
    and 2 ensure the fulfilment of the following
    safety functions
  • To ensure integrity and tightness of the Reactor
    Building and the Auxiliary Building so that to
    avoid the exposure of the personnel and the
    environment
  • To limit the staff and population exposure in
    case of release of radioactive substances from
    sources outside of the hermetic zone of the
    reactor installation
  • To limit the release of liquid and gaseous
    radioactive substances (aerosols) within the
    licensed limits

20
Safety Analysis Report for Decommissioning of
KNPP Units 1 and 2
  • To maintain the environmental conditions
    necessary for the safety systems functioning and
    for the staff service while performing
    safety-related operations
  • To provide physical barriers to the uncontrolled
    release of radioactive materials to the
    environment
  • To ensure effective radiation monitoring of the
    environment.
  • To ensure reliable electrical power supply
  • To ensure reliable fire-alerting and fire
    extinguishing systems in order to prevent common
    cause failures of systems important to safety as
    a result of fire.
  • Since the nuclear fuel is removed from the safe
    enclosure area and is transported to the spent
    fuel storage at the beginning of Stage 1, all
    safety functions related to control of
    reactivity, maintaining the reactor in a safe
    sub-critical state and decay heat removal are not
    relevant to the process of decommissioning.

21
Safety Analysis Report for Decommissioning of
KNPP Units 1 and 2
  • The importance of a given safety function with
    respect to ensuring of safety defines the safety
    class of this function. The higher the class of a
    safety function is, the higher are the
    requirements to the SSCs that support it. The
    class of a safety function helps to define the
    level and type of testing, checks and maintenance
    of the respective SSCs.
  • The class of the safety function of a given SSC
    has an impact on the assumptions with respect to
    this SSC in the safety assessment.

22
Safety Analysis Report for Decommissioning of
KNPP Units 1 and 2
  • 5.2.2 Classification of SSCs
  • The classification of SSCs is presented in
    details in Chapter 9 of the Decommissioning plan
    for units 1 and 2 4. All existing systems are
    classified there in three categories
  • I category Systems, which are important for
    nuclear safety and radiation protection
  • II category- Systems, which are important for
    industrial safety and operation
  • III category - Not important systems, i.e. they
    can be isolated and/or dismantled.
  • After the completion of the preparation stage
    the systems ensuring nuclear safety are not
    needed, therefore their category changes from I
    to III.

23
Safety Analysis Report for Decommissioning of
KNPP Units 1 and 2
  • The use of the existing systems during the SE
    phase, as well as the use of the systems for the
    dismantling phase during and after the SE, was
    evaluated very prudently. This was done by
    answering to the following questions on all the
    systems
  • Is the system needed for SE operation?
  • Do the system lifetime and capacity meet the SE
    operational requirements?
  • Is the system needed after SE (for dismantling of
    cranes and other transportation equipment after
    the end of the SE)?
  • Is it reasonable to conserve the system?
  • A differentiation is made between categories I
    and II, since the requirements for the systems
    are different with respect to their functions.
    The systems in category III can be dismantled (or
    isolated, or conserved) after separation from the
    remaining systems.

24
Safety Analysis Report for Decommissioning of
KNPP Units 1 and 2
  • Based on the above-mentioned questions, a second
    classification is adopted, where the systems from
    the three groups (I, II and III) were classified
    according to four additional criteria
  • 1.Modification is required
  • 2.Modification is not required
  • 3.An unnecessary system
  • 3a to be isolated
  • 3b to be conserved
  • 3c to be dismantled
  • 4.New equipment.

25
Safety Analysis Report for Decommissioning of
KNPP Units 1 and 2
  • 6 The safety assessment approach
  • A graded approach has been used for the safety
    assessment. According to this approach, the scope
    and the level of the detail in the analysis are
    relevant to type of the hazards.
  • 6.1 The safety objectives for decommissioning
  • Ensuring of nuclear safety (for the phase of
    final shut down and operation in mode E, which
    are out of the scope of this document)
  • Nuclear fuel sub-criticality
  • Nuclear fuel cooling.
  • Ensuring of adequate radiation protection
  • Defence in-depth
  • Implementation of approach of optimization of
    radiation protection, which is aimed at
    controlling of the dose intake below the
    prescribed limits (ALARA)
  • Avoiding of radioactive substances discharges
    above the admitted levels

26
Safety Analysis Report for Decommissioning of
KNPP Units 1 and 2
  • Ensuring of the occupational industrial safety of
    the workers
  • Fire safety.
  • The nuclear safety requirements are not a
    subject of this document, because the stage after
    the removal of all the nuclear fuel is treated
    and the requirements are not applicable.
  • The requirements for the industrial safety of
    the personnel do not change in connection with
    the decommissioning and these are also not
    treated in details in DSAR.
  • The radiation safety is the subject of Chapter
    10 Radiation Protection under normal
    operational conditions and of Chapter 6 Safety
    Analyses in case of deviation from the normal
    operation and in case of accidents.
  • A description of the existing Fire Protection
    system is presented in Chapter 4 Design Basis of
    the Decommissioning and in Chapter 5
    Description and justification of processes and
    systems.

27
Safety Analysis Report for Decommissioning of
KNPP Units 1 and 2
  • 6.2 Safety requirements and criteria
  • The safety of nuclear power plants (NPP) is
    defined as a capability the impact of the plant
    to the population and the environment to be
    maintained within the frame of the established
    limits. This capability is based on sequentially
    positioned physical barriers that avoid the
    discharge of radioactive materials as well as on
    a great number of means that protect these
    barriers from damages.
  • Safety requirements for NPP are a set of plant
    specific indicators and respective acceptance
    criteria, allowing for an objective safety
    assessment of the plant.
  • Safety assessment of NPP is an analysis of all
    the available data by the use of modern methods,
    aiming to confirm that the respective safety
    requirements have been met.

28
Safety Analysis Report for Decommissioning of
KNPP Units 1 and 2
  • The main safety requirements and criteria during
    the considered decommissioning stage are related
    to the radiation protection.
  • The objective of the safety analysis is to
    evaluate the radiological impact of the planned
    activities and potential accidents on the
    workers, public and environment.
  • The objective of the safety analysis is
  • To support the selection of the decommissioning
    strategy, the elaboration of the decommissioning
    plan and the relevant specific decommissioning
    activities
  • To demonstrate that the radiological impact on
    the workers and public is within the prescribed
    limits, that it is as low as reasonably
    achievable (ALARA) and that the protective
    measures are optimized.

29
Safety Analysis Report for Decommissioning of
KNPP Units 1 and 2
  • The hazards for the population, workers and
    environment, related to decommissioning, are
  • Radiological e.g. external exposure from direct
    and other radiation sources, internal exposure
    through inhalation, ingestion, or cuts and
    abrasions and loss of containment leading to the
    uncontrolled release of radionuclides
  • Toxic and other dangerous e.g. asbestos,
    flammable materials, carcinogens, chemicals used
    for decontamination purposes, asphyxiants
  • Industrial e.g. dropped loads, working at
    heights, fires, high temperatures, and high
    pressures.

30
Safety Analysis Report for Decommissioning of
KNPP Units 1 and 2
  • Combined and additive effects of these hazards
    are considered to the extent to which they could
    give rise to radiological consequences to
    workers, public and environment.
  • The safety criteria, applied for all
    decommissioning activities, are derived from the
    regulatory documents in force in Bulgaria. They
    define the limits for
  • Doses for the workers
  • Doses for the public
  • Radioactive releases to the environment
  • Impacts of chemicals and other non-radioactive
    hazards.
  • The acceptance criteria for the radiological
    consequences are defined for normal operation and
    for anticipated operational occurrences.

31
Safety Analysis Report for Decommissioning of
KNPP Units 1 and 2
  • The annual effective dose per an individual of
    the public, resulting from the discharge of
    liquid and gaseous material into the environment
    for all operational states and for all nuclear
    facility at the site shall be lower than 0.15
    mSv.
  • The main objective of the safety analysis is to
    demonstrate that the acceptance criteria are met
    for all credible initiating events.
  • 6.3 Methodology for the analysis
  • The methodology, which is applied for the
    analysis of the IEs includes the following steps
  • Identification of hazards, screening and
    identification of scenarios
  • Determining of the activity inventory, relevant
    for each scenario
  • Calculation of the effective dose for the workers
    and for the public.

32
Safety Analysis Report for Decommissioning of
KNPP Units 1 and 2
  • The goal of the process of hazards
    identification is to identify all locations
    within the facility where radioactive material
    exists (intentional and inadvertent accumulations
    of radioactive materials and radioactive waste,
    surface contamination, contaminated ground,
    sources, activated components and ventilation
    system filters). The identification process
    considers also the potential new sources of
    radiological exposure of the workers as a result
    of the planned decommissioning activities
  • Internal initiating events at the facility or the
    site
  • Human induced initiating events
  • External initiating events natural and
    man-made.
  • The radiological consequences for the workers
    and for the public will be calculated for the
    identified bounding scenarios.

33
Safety Analysis Report for Decommissioning of
KNPP Units 1 and 2
  • 7 Regulatory frame and other referred documents
  • The DSAR document is developed based on the
    following Bulgarian regulations
  • Act on the Safe Use of Nuclear Energy, in force
    since 01.01.2005, State Gazette No.
    63/28.08.2002, modifications and amendments in
    State Gazette No. 70/10.08.2004
  • Environmental Protection Act, Prom. SG No 91
    dated 25 September 2002, amended SG No 98 dated
    18 October 2002
  • Regulation for the procedure for issuing licenses
    and permits for safe use of nuclear energy, prom.
    SG No 41/18.05.2004
  • Regulation for Providing the Safety of Nuclear
    Power Plants , State Gazette No. 66/ 30.07.2004,
    modifications and amendments in State Gazette No.
    46 from 2007
  • Regulation for the safety of the decommissioning
    of nuclear power plants, State Gazette
    No. 73/20.08.2004

34
Safety Analysis Report for Decommissioning of
KNPP Units 1 and 2
  1. Regulation on the conditions and procedure for
    transfer of radioactive waste to the state
    enterprise Radioactive Waste, State Gazette
    No. 64/23.07.2004
  2. Regulation for safe management of radioactive
    waste, State Gazette No. 72/18.05.2004
  3. Regulation for the procedure for assessment,
    collection, spending and control of the financial
    resources and definition of the contributions due
    to the "Nuclear Facilities Decommissioning" Fund,
    State Gazette No. 112/23.12.2003, modifications
    and amendments in State Gazette No. 78/2005, No.
    20/2006, No. 110/21.12.2007
  4. Regulation for the procedure for assessment,
    collection, spending and control of the financial
    resources and definition of the contributions due
    to the "Radioactive Waste", State Gazette
    No. 112/23.12.2003
  5. Regulation on radiation protection during
    activities with sources of ionizing radiation,
    State Gazette No. 74/24.08.2004

35
Safety Analysis Report for Decommissioning of
KNPP Units 1 and 2
  1. Regulation of the conditions and procedure for
    establishing of zones with special status around
    nuclear facilities and sites with sources of
    ionizing radiation, SG State Gazette
    No. 69/06.08.2004
  2. Regulation for emergency planning and emergency
    preparedness in case of nuclear and radiation
    accident, No 189, 30.07.2004, State Gazette
    No. 71/ 13.08.2004
  3. Regulation on Providing the Physical Security
    Assurance of Nuclear Facilities, Nuclear Material
    and Radioactive Substances State Gazette
    No. 77/03.09.2004
  4. Health Law, State Gazette No. 70/10.08.2004, last
    amendment State Gazette No. 102/19.12.06
  5. Act on the healthy and safe working condition,
    State gazette No. 124/24.12.1997, last revision
    State gazette No. 40/18.05.2007
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